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1

Supply and Disposition of Crude Oil and Petroleum Products  

Gasoline and Diesel Fuel Update (EIA)

10,433 1,047 18,983 9,592 488 -617 17,890 3,998 19,273 10,433 1,047 18,983 9,592 488 -617 17,890 3,998 19,273 PADD 1 130 25 3,403 1,515 3,374 230 -269 3,374 264 5,307 PADD 2 1,993 892 4,464 2,094 500 -317 -225 4,240 386 5,224 PADD 3 6,249 96 7,346 4,283 -3,758 511 -211 6,723 2,976 5,239 PADD 4 887 14 643 287 -425 -18 51 615 10 713 PADD 5 1,174 20 3,127 1,413 310 82 36 2,939 362 2,789 - = No Data Reported; -- = Not Applicable; NA = Not Available; W = Withheld to avoid disclosure of individual company data. Notes: Imports at the PAD District level represent the PAD District in which the material entered the U.S. and not necessarily where the crude oil or product is processed and/or consumed. PAD District level net receipts includes implied net receipts for fuel ethanol and oxygenates (excluding fuel ethanol). Implied net receipts are calculated as the sum of stock change, refinery and blender net inputs, and exports minus the sum of renewable fuels and oxygenate plant net production, imports, and adjustments. Adjustments include an adjustment for crude oil, previously referred to as Unaccounted For Crude Oil. Also included is an adjustment for motor gasoline blending components, fuel ethanol, and distillate fuel oil. A negative stock change indicates a decrease in stocks and a positive number indicates an increase in stocks. Total stocks do not include distillate fuel oil stocks located in the Northeast Heating Oil Reserve. Total residual fuel oil stocks include stocks held at pipelines. Residual fuel oil stocks by sulfur content exclude pipeline stocks. Therefore, the sum of residual fuel oil stocks by sulfur content may not equal total residual fuel oil stocks. Exports of distillate fuel oil with sulfur greater than 15 ppm to 500 ppm may include distillate fuel oil with sulfur content 15 ppm and under due to product detail limitations in exports data received from the U.S. Census Bureau. LRG = Liquefied Refinery Gas. Data may not add to total due to independent rounding. See Definitions, Sources, and Notes link above for more information on this table.

2

Supply and Disposition of Crude Oil and Petroleum Products  

Gasoline and Diesel Fuel Update (EIA)

23,431 32,462 588,466 297,359 15,122 -19,137 554,586 123,943 23,431 32,462 588,466 297,359 15,122 -19,137 554,586 123,943 597,448 1,812,484 PADD 1 4,022 783 105,480 46,972 104,579 7,133 -8,328 104,584 8,184 164,527 145,574 PADD 2 61,781 27,645 138,371 64,904 15,509 -9,838 -6,968 131,427 11,955 161,957 273,603 PADD 3 193,724 2,967 227,728 132,784 -116,513 15,829 -6,533 208,398 92,256 162,398 1,211,066 PADD 4 27,499 433 19,935 8,906 -13,181 -544 1,567 19,066 310 22,105 38,275 PADD 5 36,406 635 96,952 43,793 9,606 2,542 1,124 91,111 11,237 86,461 143,965 - = No Data Reported; -- = Not Applicable; NA = Not Available; W = Withheld to avoid disclosure of individual company data. Notes: Imports at the PAD District level represent the PAD District in which the material entered the U.S. and not necessarily where the crude oil or product is processed and/or consumed. PAD District level net receipts includes implied net receipts for fuel ethanol and oxygenates (excluding fuel ethanol). Implied net receipts are calculated as the sum of stock change, refinery and blender net inputs, and exports minus the sum of renewable fuels and oxygenate plant net production, imports, and adjustments. Adjustments include an adjustment for crude oil, previously referred to as Unaccounted For Crude Oil. Also included is an adjustment for motor gasoline blending components, fuel ethanol, and distillate fuel oil. A negative stock change indicates a decrease in stocks and a positive number indicates an increase in stocks. Total stocks do not include distillate fuel oil stocks located in the Northeast Heating Oil Reserve. Total residual fuel oil stocks include stocks held at pipelines. Residual fuel oil stocks by sulfur content exclude pipeline stocks. Therefore, the sum of residual fuel oil stocks by sulfur content may not equal total residual fuel oil stocks. Exports of distillate fuel oil with sulfur greater than 15 ppm to 500 ppm may include distillate fuel oil with sulfur content 15 ppm and under due to product detail limitations in exports data received from the U.S. Census Bureau. LRG = Liquefied Refinery Gas. Data may not add to total due to independent rounding. See Definitions, Sources, and Notes link above for more information on this table.

3

GLASS FABRICATION AND PRODUCT CONSISTENCY TESTING OF LANTHANIDE BOROSILICATE FRIT B COMPOSITION FOR PLUTONIUM DISPOSITION  

SciTech Connect

The Department of Energy Office of Environmental Management (DOE/EM) plans to conduct the Plutonium Disposition Project at the Savannah River Site (SRS) to disposition excess weapons-usable plutonium. A plutonium glass waste form is a leading candidate for immobilization of the plutonium for subsequent disposition in a geologic repository. A reference glass composition (Lanthanide Borosilicate (LaBS) Frit B) was developed during the Plutonium Immobilization Program (PIP) to immobilize plutonium. A limited amount of performance testing was performed on this baseline composition before efforts to further pursue Pu disposition via a glass waste form ceased. Therefore, the objectives of this present task were to fabricate plutonium loaded LaBS Frit B glass and perform additional testing to provide near-term data that will increase confidence that LaBS glass product is suitable for disposal in the Yucca Mountain Repository. Specifically, testing was conducted in an effort to provide data to Yucca Mountain Project (YMP) personnel for use in performance assessment calculations. Plutonium containing LaBS glass with the Frit B composition with a 9.5 wt% PuO{sub 2} loading was prepared for testing. Glass was prepared to support Product Consistency Testing (PCT) at Savannah River National Laboratory (SRNL) and for additional performance testing at Argonne National Laboratory (ANL) and Pacific Northwest National Laboratory (PNNL). The glass was characterized using x-ray diffraction (XRD) and scanning electron microscopy coupled with energy dispersive spectroscopy (SEM/EDS) prior to performance testing. A series of PCTs were conducted at SRNL with varying exposed surface area and test durations. The leachates from these tests were analyzed to determine the dissolved concentrations of key elements. Acid stripping of leach vessels was performed to determine the concentration of the glass constituents that may have sorbed on the vessels during leach testing. Additionally, the leachate solutions were ultrafiltered to quantify colloid formation. The leached solids from select PCTs were examined in an attempt to evaluate the Pu and neutron absorber release behavior from the glass and to identify the formation of alteration phases on the glass surface. Characterization of the glass prior to testing revealed that some undissolved plutonium oxide was present in the glass. The undissolved particles had a disk-like morphology and likely formed via coarsening of particles in areas compositionally enriched in plutonium. Similar disk-like PuO{sub 2} phases were observed in previous LaBS glass testing at PNNL. In that work, researchers concluded that plutonium formed with this morphology as a result of the leaching process. It was more likely that the presence of the plutonium oxide crystals in the PNNL testing was a result of glass fabrication. A series of PCTs were conducted at 90 C in ASTM Type 1 water. The PCT-Method A (PCT-A) was conducted to compare the Pu LaBS Frit B glass durability to current requirements for High Level Waste (HLW) glass in a geologic repository. The PCT-A test has a strict protocol and is designed to specifically be used to evaluate whether the chemical durability and elemental release characteristics of a nuclear waste glass have been consistently controlled during production and, thus, meet the repository acceptance requirements. The PCT-A results on the Pu containing LaBS Frit B glass showed that the glass was very durable with a normalized elemental release value for boron of approximately 0.02 g/L. This boron release value was better than two orders of magnitude better from a boron release standpoint than the current Environmental Assessment (EA) glass used for repository acceptance. The boron release value for EA glass is 16.7 g/L.

Marra, J

2006-01-19T23:59:59.000Z

4

GLASS FABRICATION AND PRODUCT CONSISTENCY TESTING OF LANTHANIDE BOROSILICATE GLASS FOR PLUTONIUM DISPOSITION  

SciTech Connect

The Department of Energy Office of Environmental Management (DOE/EM) plans to conduct the Plutonium Disposition Project at the Savannah River Site (SRS) in Aiken, SC, to disposition excess weapons-usable plutonium. A plutonium glass waste form is a leading candidate for immobilization of the plutonium for subsequent disposition in a geologic repository. The objectives of this present task were to fabricate plutonium-loaded lanthanide borosilicate (LaBS) Frit B glass and perform testing to provide near-term data that will increase confidence that LaBS glass product is suitable for disposal in the proposed Federal Repository. Specifically, testing was conducted in an effort to provide data to Yucca Mountain Project (YMP) personnel for use in performance assessment calculations. Plutonium containing LaBS glass with the Frit B composition with a 9.5 wt% PuO{sub 2} loading was prepared for testing. Glass was prepared to support glass durability testing via the ASTM Product Consistency Testing (PCT) at Savannah River National Laboratory (SRNL). The glass was characterized with X-ray diffraction (XRD) and scanning electron microscopy coupled with energy dispersive spectroscopy (SEM/EDS) prior to performance testing. This characterization revealed some crystalline PuO{sub 2} inclusions with disk-like morphology present in the as fabricated, quench-cooled glass. A series of PCTs was conducted at SRNL with varying exposed surface area and test durations. Filtered leachates from these tests were analyzed to determine the dissolved concentrations of key elements. The leachate solutions were also ultrafiltered to quantify colloid formation. Leached solids from select PCTs were examined in an attempt to evaluate the Pu and neutron absorber release behavior from the glass and to investigate formation of alteration phases on the glass surface. A series of PCTs was conducted at 90 C in ASTM Type 1 water to compare the Pu LaBS Frit B glass durability to current requirements for High Level Waste (HLW) glass in a geologic repository. The PCT (7-day static test with powdered glass) results on the Pu-containing LaBS Frit B glass at SA/V of {approx} 2000 m{sup -1} showed that the glass was very durable with an average normalized elemental release value for boron of 0.013 g/m{sup 2}. This boron release value is {approx} 640X lower than normalized boron release from current Environmental Assessment (EA) glass used for repository acceptance. The PCT-B (7, 14, 28 and 56-day, static test with powdered glass) normalized elemental releases were similar to the normalized elemental release values from PCT-A testing, indicating that the LaBS Frit B glass is very durable as measured by the PCT. Normalized plutonium releases were essentially the same within the analytical uncertainty of the ICP-MS methods used to quantify plutonium in the 0.45 {micro}m-filtered leachates and ultra-filtered leachates, indicating that colloidal plutonium species do not form under the PCT conditions used in this study.

Crawford, C; James Marra, J; Ned Bibler, N

2007-02-12T23:59:59.000Z

5

DOE/EA-1488: Environmental Assessment for the U-233 Disposition, Medical Isotope Production, and Building 3019 Complex Shutdown at the Oak Ridge National Laboratory (12/04)  

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

88 88 FINAL Environmental Assessment for the U-233 Disposition, Medical Isotope Production, and Building 3019 Complex Shutdown at the Oak Ridge National Laboratory, Oak Ridge, Tennessee December 2004 U. S. Department of Energy Oak Ridge Operations 04-049(doc)/120204 04-049(doc)/120204 SCIENCE APPLICATIONS INTERNATIONAL CORPORATION contributed to the preparation of this document and should not be considered an eligible contractor for its review. Environmental Assessment for the U-233 Disposition, Medical Isotope Production, and Building 3019 Complex Shutdown at the Oak Ridge National Laboratory, Oak Ridge, Tennessee Date Issued-December 2004 U. S. Department of Energy Oak Ridge Operations 04-049(doc)/120204 CONTENTS

6

Records Disposition  

Directives, Delegations, and Requirements

To assign responsibilities and authorities and to prescribe policies, procedures, standards, and guidelines for the orderly disposition of records of the Department of Energy (DOE) and its management and operating contractors. Cancels DOE O 1324.2 dated 5-28-80. Chg 1 dated 4-9-92. Canceled by DOE O 1324.2B dated 1-12-95.

1988-09-13T23:59:59.000Z

7

Uranium Downblending and Disposition Project Technology Readiness...  

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

Assessment EA-1488: Environmental Assessment for the U-233 Disposition, Medical Isotope Production, and Building 3019 Complex Shutdown at the Oak Ridge National Laboratory,...

8

Records Disposition  

Directives, Delegations, and Requirements

To assign responsibilities and authorities and to prescribe policies, procedures, standards, and guidelines for the orderly disposition of records of the Department of Energy (DOE) and its operating and onsite service contractors. Cancels DOE O 1324.1 dated 7-10-78. Chg 1 dated 7-2-81. Chg 2 dated 11-9-82. Canceled by DOE O 1324.2A dated 9-13-88.

1980-05-28T23:59:59.000Z

9

Pair production in inhomogeneous fields  

SciTech Connect

We employ the recently developed worldline numerics, which combines string-inspired field theory methods with Monte Carlo techniques, to develop an algorithm for the computation of pair-production rates in scalar QED for inhomogeneous background fields. We test the algorithm with the classic Sauter potential, for which we compute the local production rate for the first time. Furthermore, we study the production rate for a superposition of a constant E field and a spatially oscillating field for various oscillation frequencies. Our results reveal that the approximation by a local derivative expansion already fails for frequencies small compared to the electron-mass scale, whereas for strongly oscillating fields a derivative expansion for the averaged field represents an acceptable approximation. The worldline picture makes the nonlocal nature of pair production transparent and facilitates a profound understanding of this important quantum phenomenon.

Gies, Holger; Klingmueller, Klaus [Institut fuer theoretische Physik, Universitaet Heidelberg, Philosophenweg 16, D-69120 Heidelberg (Germany)

2005-09-15T23:59:59.000Z

10

Pair production in inhomogeneous fields  

E-Print Network (OSTI)

We employ the recently developed worldline numerics, which combines string-inspired field theory methods with Monte-Carlo techniques, to develop an algorithm for the computation of pair-production rates in scalar QED for inhomogeneous background fields. We test the algorithm with the classic Sauter potential, for which we compute the local production rate for the first time. Furthermore, we study the production rate for a superposition of a constant E field and a spatially oscillating field for various oscillation frequencies. Our results reveal that the approximation by a local derivative expansion fails already for frequencies small compared to the electron mass scale, whereas for strongly oscillating fields a derivative expansion for the averaged field represents an acceptable approximation. The worldline picture makes the nonlocal nature of pair production transparent and facilitates a profound understanding of this important quantum phenomenon.

Holger Gies; Klaus Klingmuller

2005-05-12T23:59:59.000Z

11

disposition. prices | OpenEI  

Open Energy Info (EERE)

disposition. prices disposition. prices Dataset Summary Description This dataset comes from the Energy Information Administration (EIA), and is part of the 2011 Annual Energy Outlook Report (AEO2011). This dataset is Table 15, and contains only the reference case. The dataset uses gigawatts. The data is broken down into production, net imports, consumption by sector and price. Source EIA Date Released April 26th, 2011 (3 years ago) Date Updated Unknown Keywords 2011 AEO coal coal supply disposition. prices EIA Data application/vnd.ms-excel icon AEO2011: Coal Supply, Disposition, and Prices- Reference Case (xls, 91.7 KiB) Quality Metrics Level of Review Peer Reviewed Comment Temporal and Spatial Coverage Frequency Annually Time Period 2008-2035 License License Open Data Commons Public Domain Dedication and Licence (PDDL)

12

Disposition Schedules | Department of Energy  

Office of Environmental Management (EM)

Disposition Schedules Disposition Schedules The DOE Records Disposition Schedules provide the authority for the transfer, or disposal of records created and maintained by the...

13

Plasma Production via Field Ionization  

SciTech Connect

Plasma production via field ionization occurs when an incoming particle beam is sufficiently dense that the electric field associated with the beam ionizes a neutral vapor or gas. Experiments conducted at the Stanford Linear Accelerator Center explore the threshold conditions necessary to induce field ionization by an electron beam in a neutral lithium vapor. By independently varying the transverse beam size, number of electrons per bunch or bunch length, the radial component of the electric field is controlled to be above or below the threshold for field ionization. Additional experiments ionized neutral xenon and neutral nitric oxide by varying the incoming beam's bunch length. A self-ionized plasma is an essential step for the viability of plasma-based accelerators for future high-energy experiments.

O'Connell, C.L.; Barnes, C.D.; Decker, F.; Hogan, M.J.; Iverson, R.; Krejcik, P.; Siemann, R.; Walz, D.R.; /SLAC; Clayton, C.E.; Huang, C.; Johnson, D.K.; Joshi, C.; Lu,; Marsh, K.A.; Mori, W.; Zhou, M.; /UCLA; Deng, S.; Katsouleas, T.; Muggli, P.; Oz, E.; /Southern California U.

2007-01-02T23:59:59.000Z

14

Request For Records Disposition | Department of Energy  

Office of Environmental Management (EM)

Request For Records Disposition Request For Records Disposition Southeastern Power Administration (SEPA) Request For Records Disposition More Documents & Publications Audit...

15

EA-1488: Environmental Assessment for the U-233 Disposition,...  

Office of Environmental Management (EM)

Environmental Assessment for the U-233 Disposition, Medical Isotope Production, and Building 3019 Complex Shutdown at the Oak Ridge National Laboratory, Oak Ridge, Tennessee...

16

Evaluation of disposition scores in Bos indicus/Bos taurus cross calves at different stages of production  

E-Print Network (OSTI)

to 5. Between sires for overall disposition, calves by 297J were lowest at weaning (2.83), before slaughter (2.84), and at slaughter (2.45) and second lowest in first calf heifers (2.27). Calves by 437J were highest at weaning (4.10), before... Family Sire Dam Offspring Bulls Heifers Steers 70 297J 431H 33 0 15 18 71 297J 760H 63 2 29 32 72 432H 511G 45 1 20 24 73 432H 732H 8 0 2 6 74 437J 640H 8 0 4 4 75 437J 728H 36 1 19 16 76 551G 664J 7 0 2 5 77 551G 787G 41 1 17 23 80 551G 429H 66...

Funkhouser, Rena Rebecca

2008-10-10T23:59:59.000Z

17

DOE Records Disposition Schedule Changes | Department of Energy  

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

Records Disposition Schedule Changes DOE Records Disposition Schedule Changes Disposition Schedule Changes DOE Records Disposition Schedule Changes More Documents & Publications...

18

Disposition of uranium-233  

SciTech Connect

The US is developing a strategy for the disposition of surplus weapons-usable uranium-233 ({sup 233}U). The strategy (1) identifies the requirements for the disposition of surplus {sup 233}U; (2) identifies potential disposition options, including key issues to be resolved with each option; and (3) defines a road map that identifies future key decisions and actions. The disposition of weapons-usable fissile materials is part of a US international arms-control program for reduction of the number of nuclear weapons and the quantities of nuclear-weapons-usable materials worldwide. The disposition options ultimately lead to waste forms requiring some type of geological disposal. Major options are described herein.

Tousley, D.R. [Dept. of Energy, Washington, DC (United States). Office of Fissile Materials Disposition; Forsberg, C.W.; Krichinsky, A.M. [Oak Ridge National Lab., TN (United States)

1997-10-16T23:59:59.000Z

19

Waste and Materials Disposition Information | Department of Energy  

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

Waste and Materials Disposition Waste and Materials Disposition Information Waste and Materials Disposition Information Waste and Materials Disposition Information As the Office of Environmental Management (EM) fulfills its mission, waste and materials disposition plays a vital role in the cleanup of radioactive waste and the environmental legacy of nuclear weapons production and nuclear energy research. Disposal of waste frequently falls on the critical path of cleanup projects. Significant planning resources are spent to identify alternatives and find a path that is cost-effective and in the best interest of the Federal government. In many instances, waste disposition, (processing, treatment and disposal) is part of cleanup agreements and is of interest to stakeholders and requires the oversight of regulators.

20

Request For Records Disposition Authority: Strategic Petroleum Reserve  

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

Request For Records Disposition Authority: Strategic Petroleum Request For Records Disposition Authority: Strategic Petroleum Reserve Project Management Office Request For Records Disposition Authority: Strategic Petroleum Reserve Project Management Office Paper case files pertaining to environmental permit applications, permits and related correspondence as well as NEPA correspondence within of the Strategic Petroleum Reserve Project Management Office (SPRPMO) Request For Records Disposition Authority: Strategic Petroleum Reserve Project Management Office More Documents & Publications 2012 Annual Planning Summary for Fossil Energy, National Energy Technology Laboratory, RMOTC, and Strategic Petroleum Reserve Field Office CX-002673: Categorical Exclusion Determination CX-009794: Categorical Exclusion Determination

Note: This page contains sample records for the topic "disposition field production" 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

disposition | OpenEI  

Open Energy Info (EERE)

disposition disposition Dataset Summary Description This dataset comes from the Energy Information Administration (EIA), and is part of the 2011 Annual Energy Outlook Report (AEO2011). This dataset is table 11, and contains only the reference case. The dataset uses million barrels per day. The data is broken down into crude oil, other petroleum supply, other non petroleum supply and liquid fuel consumption. Source EIA Date Released April 26th, 2011 (3 years ago) Date Updated Unknown Keywords 2011 AEO disposition EIA liquid fuels Supply Data application/vnd.ms-excel icon AEO2011: Liquid Fuels Supply and Disposition- Reference Case (xls, 117 KiB) Quality Metrics Level of Review Peer Reviewed Comment Temporal and Spatial Coverage Frequency Annually Time Period 2008-2035

22

Request For Records Disposition | Department of Energy  

Office of Environmental Management (EM)

Request For Records Disposition Request For Records Disposition Spent Nuclear Fuels Request For Records Disposition More Documents & Publications The Report To The President And...

23

Integrated Facilities Disposition Program  

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

Facilities Facilities Disposition Program Tank Waste Corporate Board Meeting at ORNL Sharon Robinson Dirk Van Hoesen Robert Jubin Brad Patton July 29, 2009 2 Managed by UT-Battelle for the U.S. Department of Energy The Integrated Facility Disposition Program (IFDP) addresses the remaining EM Scope at both ORNL and Y-12 Cost Range: $7 - $14B Schedule: 26 Years 3 Managed by UT-Battelle for the U.S. Department of Energy Scope of work * Treatment and disposition of legacy materials and waste * D&D 327 (1.5 M ft 2 ) excess facilities generating >2 M yd 3 debris * Soil and groundwater remedial actions generating >1 M yd 3 soils * Facilities surveillance and maintenance * Reconfiguration of waste management facilities * Ongoing waste management operations * Project management

24

SRS - Programs - Liquid Waste Disposition  

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

Liquid Waste Disposition Liquid Waste Disposition This includes both the solidification of highly radioactive liquid wastes stored in SRS's tank farms and disposal of liquid low-level waste generated as a by-product of the separations process and tank farm operations. This low-level waste is treated in the Effluent Treatment Facility. High-activity liquid waste is generated at SRS as by-products from the processing of nuclear materials for national defense, research and medical programs. The waste, totaling about 36 million gallons, is currently stored in 49 underground carbon-steel waste tanks grouped into two "tank farms" at SRS. While the waste is stored in the tanks, it separates into two parts: a sludge that settles on the bottom of the tank, and a liquid supernate that resides on top of the sludge. The waste is reduced to about 30 percent of its original volume by evaporation. The condensed evaporator "overheads" are transferred to the Effluent Treatment Project for final cleanup prior to release to the environment. As the concentrate cools a portion of it crystallizes forming solid saltcake. The concentrated supernate and saltcake are less mobile and therefore less likely to escape to the environment in the event of a tank crack or leak.

25

A Study of Cattle Disposition: Exploring QTL Associated with Temperament  

E-Print Network (OSTI)

In any production setting, cattle disposition (temperament) has a great impact on handling and performance. Thus, behavior can be economically important, yielding the rationale for study. Wegenhoft (2005) previously identified several quantitative...

Boldt, Clayton Ryan

2008-05-16T23:59:59.000Z

26

PF-4 actinide disposition strategy  

SciTech Connect

The dwindling amount of Security Category I processing and storage space across the DOE Complex has driven the need for more effective storage of nuclear materials at LANL's Plutonium Facility's (PF-4's) vault. An effort was begun in 2009 to create a strategy, a roadmap, to identify all accountable nuclear material and determine their disposition paths, the PF-4 Actinide Disposition Strategy (PADS). Approximately seventy bins of nuclear materials with similar characteristics - in terms of isotope, chemical form, impurities, disposition location, etc. - were established in a database. The ultimate disposition paths include the material to remain at LANL, disposition to other DOE sites, and disposition to waste. If all the actions described in the document were taken, over half of the containers currently in the PF-4 vault would been eliminated. The actual amount of projected vault space will depend on budget and competing mission requirements, however, clearly a significant portion of the current LANL inventory can be either dispositioned or consolidated.

Marcevicius, Robert W [Los Alamos National Laboratory

2010-01-01T23:59:59.000Z

27

Used Fuel Disposition Campaign Disposal  

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

Campaign Disposal Research and Development Roadmap Prepared for U.S. Department of Energy Used Fuel Disposition Campaign September 2012 FCR&D-USED-2011-000065 REV 1 DISCLAIMER This information was prepared as an account of work sponsored by an agency of the U.S. Government. Neither the U.S. Government nor any agency thereof, nor any of their employees, makes any warranty, expressed 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. References herein to any specific commercial product, process, or service by trade name, trade mark, manufacturer, or

28

Assistant Manager for Waste Disposition  

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

The incumbent of this position is responsible for providing overall leadership and direction for oversight of assigned contractor and Federal programs and activities associated with the disposition...

29

The ultimate disposition of depleted uranium  

SciTech Connect

Depleted uranium (DU) is produced as a by-product of the uranium enrichment process. Over 340,000 MTU of DU in the form of UF{sub 6} have been accumulated at the US government gaseous diffusion plants and the stockpile continues to grow. An overview of issues and objectives associated with the inventory management and the ultimate disposition of this material is presented.

Lemons, T.R. [Uranium Enrichment Organization, Oak Ridge, TN (United States)

1991-12-31T23:59:59.000Z

30

Major Risk Factors Integrated Facility Disposition Project -...  

Office of Environmental Management (EM)

Integrated Facility Disposition Project - Oak Ridge Major Risk Factors Integrated Facility Disposition Project - Oak Ridge Full Document and Summary Versions are available for...

31

EM Waste and Materials Disposition & Transportation | Department...  

Office of Environmental Management (EM)

EM Waste and Materials Disposition & Transportation EM Waste and Materials Disposition & Transportation DOE's Radioactive Waste Management Priorities: Continue to manage waste...

32

DOE Seeks Industry Input on Nickel Disposition Strategy | Department of  

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

DOE Seeks Industry Input on Nickel Disposition Strategy DOE Seeks Industry Input on Nickel Disposition Strategy DOE Seeks Industry Input on Nickel Disposition Strategy March 23, 2012 - 12:00pm Addthis WASHINGTON, D.C. - The Energy Department's prime contractor, Fluor-B&W Portsmouth (FBP), managing the Portsmouth Gaseous Diffusion Plant (GDP), issued a request for Expressions of Interest (EOI) seeking industry input to support the development of an acquisition strategy for potential disposition of DOE nickel. The EOI requests technical, financial, and product market information to review the feasibility of technologies capable of decontaminating the nickel to a level indistinguishable from what is commercially available, such that it could be safely recycled and reused. The EOI scope is for 6,400 tons of nickel to be recovered from the uranium enrichment process

33

DOE Seeks Industry Input on Nickel Disposition Strategy | Department of  

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

Industry Input on Nickel Disposition Strategy Industry Input on Nickel Disposition Strategy DOE Seeks Industry Input on Nickel Disposition Strategy March 23, 2012 - 12:00pm Addthis WASHINGTON, D.C. - The Energy Department's prime contractor, Fluor-B&W Portsmouth (FBP), managing the Portsmouth Gaseous Diffusion Plant (GDP), issued a request for Expressions of Interest (EOI) seeking industry input to support the development of an acquisition strategy for potential disposition of DOE nickel. The EOI requests technical, financial, and product market information to review the feasibility of technologies capable of decontaminating the nickel to a level indistinguishable from what is commercially available, such that it could be safely recycled and reused. The EOI scope is for 6,400 tons of nickel to be recovered from the uranium enrichment process

34

AEO2011: Coal Supply, Disposition, and Prices | OpenEI  

Open Energy Info (EERE)

Supply, Disposition, and Prices Supply, Disposition, and Prices Dataset Summary Description This dataset comes from the Energy Information Administration (EIA), and is part of the 2011 Annual Energy Outlook Report (AEO2011). This dataset is Table 15, and contains only the reference case. The dataset uses gigawatts. The data is broken down into production, net imports, consumption by sector and price. Source EIA Date Released April 26th, 2011 (3 years ago) Date Updated Unknown Keywords 2011 AEO coal coal supply disposition. prices EIA Data application/vnd.ms-excel icon AEO2011: Coal Supply, Disposition, and Prices- Reference Case (xls, 91.7 KiB) Quality Metrics Level of Review Peer Reviewed Comment Temporal and Spatial Coverage Frequency Annually Time Period 2008-2035 License License Open Data Commons Public Domain Dedication and Licence (PDDL)

35

DOE/EA-1488: Finding of No Significant Impact U-233 Disposition, Medical Isotope Production, and Building 3019 Complex Shutdown at the Oak Ridge National Laboratory (12/10/04)  

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

FINDING OF NO SIGNIFICANT IMPACT FINDING OF NO SIGNIFICANT IMPACT U-233 DISPOSITION, MEDICAL ISOTOPE PRODUCTION, AND BUILDING 3019 COMPLEX SHUTDOWN AT THE OAK RIDGE NATIONAL LABORATORY, OAK RIDGE, TENNESSEE AGENCY: U. S. Department of Energy ACTION: Finding of No Significant Impact. SUMMARY: The U. S. Department of Energy (DOE) has completed an Environmental Assessment (EA) [DOE/EA-1488] that evaluates the processing of uranium-233 ( 233 U) stored at the Oak Ridge National Laboratory (ORNL) and other small quantities of similar material currently stored at other DOE sites in order to render it suitable for safe, long-term, economical storage. The 233 U is stored within Bldg. 3019A, which is part of the Bldg. 3019 Complex. Additionally, the proposed action would increase the availability of medical

36

REQUEST FOR RECORDS DISPOSITION AUTHORITY | Department of Energy  

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

RS-Weapons X-Rays REQUEST FOR RECORDS DISPOSITION AUTHORITY More Documents & Publications REQUEST FOR RECORDS DISPOSITION AUTHORITY REQUEST FOR RECORDS DISPOSITION AUTHORITY...

37

Facility Disposition Safety Strategy RM | Department of Energy  

Office of Environmental Management (EM)

Facility Disposition Safety Strategy RM Facility Disposition Safety Strategy RM The Facility Disposition Safety Strategy (FDSS) Review Module is a tool that assists DOE federal...

38

REQUEST FOR RECORDS DISPOSITION AUTHORITY | Department of Energy  

Office of Environmental Management (EM)

DISPOSITION AUTHORITY More Documents & Publications REQUEST FOR RECORDS DISPOSITION AUTHORITY Request For Records Disposition Autnority Records Dispostion-Coal Distribution Data...

39

REQUEST FOR RECORDS DISPOSITION AUTHORITY | Department of Energy  

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

Request for Records Disposition Authority REQUEST FOR RECORDS DISPOSITION AUTHORITY More Documents & Publications Request For Records Disposition Authority Request For Records...

40

Request For Records Disposition Authority | Department of Energy  

Office of Environmental Management (EM)

Request For Records Disposition Authority Request For Records Disposition Authority National Archives Pacific Southwest Region Request For Records Disposition Authority More...

Note: This page contains sample records for the topic "disposition field production" 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

EA-1488: Environmental Assessment for the U-233 Disposition, Medical  

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

488: Environmental Assessment for the U-233 Disposition, 488: Environmental Assessment for the U-233 Disposition, Medical Isotope Production, and Building 3019 Complex Shutdown at the Oak Ridge National Laboratory, Oak Ridge, Tennessee EA-1488: Environmental Assessment for the U-233 Disposition, Medical Isotope Production, and Building 3019 Complex Shutdown at the Oak Ridge National Laboratory, Oak Ridge, Tennessee The purpose of the proposed action evaluated in this environmental assessment (EA) is the processing of uranium-233 (233U) stored at the Oak Ridge National Laboratory (ORNL) and other small quantities of similar material currently stored at other U. S. Department of Energy (DOE) sites in order to render it suitable for safe, long-term, economical storage. The 233U is stored within Bldg. 3019A, which is part of the Bldg. 3019

42

A model of peak production in oil fields  

Science Journals Connector (OSTI)

We developed a model for oil production on the basis of simple physical considerations. The model provides a basic understanding of Hubbert’s empirical observation that the production rate for an oil-producing region reaches its maximum when approximately half the recoverable oil has been produced. According to the model the oil production rate at a large field must peak before drilling peaks. We use the model to investigate the effects of several drilling strategies on oil production. Despite the model’s simplicity predictions for the timing and magnitude of peak production match data on oil production from major oil fields throughout the world.

Daniel M. Abrams; Richard J. Wiener

2010-01-01T23:59:59.000Z

43

REQUEST FOR RECORDS DISPOSITION AUTHORITY  

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

LEAVE BLANK (NARA use only) LEAVE BLANK (NARA use only) JOB NUMBER To: NATIONAL ARCHIVES & RECORDS ADMINISTRATION 8601 ADELPHI ROAD, COLLEGE PARK, MD 20740-6001 Date Received 1. FROM (Agency or establishment) NOTIFICATION TO AGENCY In accordance with the provisions of 44 U.S.C 3303a, the disposition request, including amendments is approved except for items that may be marked "disposition not approved" or "withdrawn" in column 10. 2. MAJOR SUB DIVISION 3. MINOR SUBDIVISION 4. NAME OF PERSON WITH WHOM TO CONFER 5. TELEPHONE DATE ARCHIVIST OF THE UNITED STATES 6. AGENCY CERTIFICATION I hereby certify that I am authorized to act for this agency in matters pertaining to the disposition of its records and that the records proposed for disposal on the attached______page(s) are not needed now for the business of this agency or will not be

44

Depleted uranium disposition study -- Supplement, Revision 1  

SciTech Connect

The Department of Energy Office of Weapons and Materials Planning has requested a supplemental study to update the recent Depleted Uranium Disposition report. This supplemental study addresses new disposition alternatives and changes in status.

Becker, G.W.

1993-11-01T23:59:59.000Z

45

Gas plants, new fields spark production rise  

SciTech Connect

Gas plant construction is welcomed by operators in the Williston Basin, North Dakota. Petroleum and gas production has increased. The Montana portion of the Williston Basin shows new discoveries. Some secondary recovery efforts are in operation. Industrial officials share the same enthusiasm and optimism for rising production as they do for exploration potential in the basin. 5 tables.

Lenzini, D.

1980-04-01T23:59:59.000Z

46

Fissile Materials Disposition | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

Fissile Materials Disposition | National Nuclear Security Administration Fissile Materials Disposition | 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 Fissile Materials Disposition Home > About Us > Our Programs > Nonproliferation > Fissile Materials Disposition Fissile Materials Disposition Since the end of the Cold War, significant quantities of plutonium and

47

Remote control of off-shore oil field production equipment  

E-Print Network (OSTI)

REMOTE CONTROL OF OFF-SHORE OIL FIELD PRODUCTION EQUIPMENT A Thesis Alton W. Sissom 1949 Approve as to style and on n by Cha1rman of omm1ttee REMOTE CONTROL OF OFFSHORE OIL FIELD PRODUCTION EQUIPMENT A Thesis Alton W. Oissom 1949 REMOTE...-Carrier Channel 26 PZNOTE CONTROL OF OFF-SHORE OIL FIELD PRODUCTION K, 'UIPMENT I GENERAL IiPOPPUi TION Since the beginning of the exploitation of the under-sea oil deposits in the Gulf' of qexico, most, of the territory off the shores of Texas and Louisiana...

Sissom, Alton Wayne

2012-06-07T23:59:59.000Z

48

Plutonium Disposition Program | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

Plutonium Disposition Program Plutonium Disposition Program Home > About Us > Our Programs > Nonproliferation > Fissile Materials Disposition > Plutonium Disposition Program Plutonium Disposition Program The U.S.-Russia Plutonium Management and Disposition Agreement (PMDA), which entered into force on July 13, 2011, commits each country to dispose of at least 34 metric tons (MT) of weapon-grade plutonium withdrawn from their respective nuclear weapon programs. The U.S. remains firmly committed to its PMDA obligation to dispose of excess weapons plutonium. U.S. Plutonium Disposition The current U.S. plan to dispose of 34 MT of weapon-grade plutonium is to fabricate it into Mixed Oxide (MOX) fuel and irradiate it in existing light water reactors. This approach requires construction of new facilities

49

The Evolution of Giant Oil Field Production Behavior  

Science Journals Connector (OSTI)

The data for this study have been taken from the giant oil field database compiled by Robelius (2007...). AAPG was the main source for information about discovery year, year of first oil production, URR and cumulative

Mikael Höök; Bengt Söderbergh; Kristofer Jakobsson…

2009-03-01T23:59:59.000Z

50

Facility Disposition Safety Strategy RM  

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

Facility Disposition Safety Strategy Review Module Facility Disposition Safety Strategy Review Module March 2010 CD-0 O 0 OFFICE OF Facilit C CD-1 F ENVIRO Standard R ty Dispos Rev Critical Decis CD-2 M ONMENTAL Review Plan sition Saf view Module sion (CD) Ap CD March 2010 L MANAGE n (SRP) fety Strat e pplicability D-3 EMENT tegy CD-4 Post Ope eration Standard Review Plan, 2 nd Edition, March 2010 i FOREWORD The Standard Review Plan (SRP) 1 provides a consistent, predictable corporate review framework to ensure that issues and risks that could challenge the success of Office of Environmental Management (EM) projects are identified early and addressed proactively. The internal EM project review process encompasses key milestones established by DOE O 413.3A, Change 1, Program and Project Management for the Acquisition of Capital Assets, DOE-STD-1189-2008,

51

Savannah River Site Waste Disposition Project  

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

Terrel J. Spears Terrel J. Spears Assistant Manager Waste Disposition Project DOE Savannah River Operations Office Savannah River Site Savannah River Site Waste Disposition Project Waste Disposition Project 2 Waste Disposition Project - Mission Radioactive Liquid Waste - Tank Waste Stabilization and Disposition - Disposition 36 million gallons of radioactive liquid waste - Close 49 underground storage tanks in which the waste now resides 3 36.7 Million 33.7 Mgal (92%) 3.0 Mgal (8%) Saltcake Sludge Salt Supernate Volume Curies 397 Million Curies (MCi) 212 MCi (54%) 185 MCi (46%) Gallons (Mgal) 36.5 Million 33.5 Mgal (92%) 3.0 Mgal (8%) Liquid Waste Background Liquid Waste Background * 2 tanks closed * 49 tanks remaining to close - aging, carbon steel - 27 compliant, 22 non-compliant - 12 have known leak sites

52

Efficient solar anti-neutrino production in random magnetic fields  

E-Print Network (OSTI)

We have shown that the electron anti-neutrino appearance in the framework of the spin flavor conversion mechanism is much more efficient in the case of neutrino propagation through random than regular magnetic field. This result leads to much stronger limits on the product of the neutrino transition magnetic moment and the solar magnetic field based on the recent KamLAND data. We argue that the existence of the random magnetic fields in the solar convective zone is a natural sequence of the convective zone magnetic field evolution.

O. G. Miranda; T. I. Rashba; A. I. Rez; J. W. F. Valle

2004-05-12T23:59:59.000Z

53

Summary - Major Risk Factors Integrated Facility Disposition...  

Office of Environmental Management (EM)

& ORNL, Oak Ridge, TN EM Project: Integrated Facility Disposition Project (IFDP) ETR Report Date: August 2008 ETR-15 United States Department of Energy Office of Environmental...

54

Plutonium Disposition Program | National Nuclear Security Administrati...  

National Nuclear Security Administration (NNSA)

accumulating newly separated weapon-grade plutonium. RUSSIAN PLUTONIUM DISPOSITION Russia plans to dispose of its 34 metric tons of weapon-grade plutonium by fabricating it...

55

Used Fuel Disposition Campaign Preliminary Quality Assurance...  

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

Preliminary Quality Assurance Implementation Plan Used Fuel Disposition Campaign Preliminary Quality Assurance Implementation Plan The primary objective of this report is to...

56

Weapons Dismantlement and Disposition NNSS Capabilities  

SciTech Connect

The U.S. Department of Energy (DOE) has tasked the WDD working group to disposition the large inventory of legacy classified weapon components scattered across the complex.

Pat Arnold

2011-12-01T23:59:59.000Z

57

DISPOSITION AUTHORITIES FROZEN UNDER THE EPIDEMIOLOGICAL MORATORIUM...  

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

authorities which are under the moratorium on the destruction of health related records as of March 2008. DISPOSITION AUTHORITIES FROZEN UNDER THE EPIDEMIOLOGICAL MORATORIUM...

58

PRODUCTION ANALYSIS: CHEROKEE AND BUG FIELDS, SAN JUAN COUNTY, UTAH  

SciTech Connect

Over 400 million barrels (64 million m{sup 3}) of oil have been produced from the shallow-shelf carbonate reservoirs in the Pennsylvanian (Desmoinesian) Paradox Formation in the Paradox Basin, Utah and Colorado. With the exception of the giant Greater Aneth field, the other 100 plus oil fields in the basin typically contain 2 to 10 million barrels (0.3-1.6 million m{sup 3}) of original oil in place. Most of these fields are characterized by high initial production rates followed by a very short productive life (primary), and hence premature abandonment. Only 15 to 25 percent of the original oil in place is recoverable during primary production from conventional vertical wells. An extensive and successful horizontal drilling program has been conducted in the giant Greater Aneth field. However, to date, only two horizontal wells have been drilled in small Ismay and Desert Creek fields. The results from these wells were disappointing due to poor understanding of the carbonate facies and diagenetic fabrics that create reservoir heterogeneity. These small fields, and similar fields in the basin, are at high risk of premature abandonment. At least 200 million barrels (31.8 million m{sup 3}) of oil will be left behind in these small fields because current development practices leave compartments of the heterogeneous reservoirs undrained. Through proper geological evaluation of the reservoirs, production may be increased by 20 to 50 percent through the drilling of low-cost single or multilateral horizontal legs from existing vertical development wells. In addition, horizontal drilling from existing wells minimizes surface disturbances and costs for field development, particularly in the environmentally sensitive areas of southeastern Utah and southwestern Colorado.

Thomas C. Chidsey Jr.

2003-12-01T23:59:59.000Z

59

U.S. Crude Oil Supply & Disposition  

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

2007 2008 2009 2010 2011 2012 View 2007 2008 2009 2010 2011 2012 View History Supply Field Production (Commercial) 1,853,122 1,829,897 1,954,021 1,996,787 2,063,138 2,374,842 1859-2012 Alaskan 263,595 249,874 235,491 218,904 204,829 192,368 1981-2012 Lower 48 States 1,589,527 1,580,024 1,718,529 1,777,883 1,858,309 2,182,474 1993-2012 Imports 3,661,404 3,580,694 3,289,675 3,362,856 3,261,422 3,120,755 1910-2012 Commercial 3,658,701 3,573,581 3,269,307 3,362,856 3,261,422 3,120,755 2001-2012 Strategic Petroleum Reserve (SPR) 2,703 7,113 20,368 1977-2009 Adjustments (Commercial) 9,742 5,777 29,077 37,829 63,600 52,746 1981-2012 Disposition Stock Change -17,835 44,617 24,132 8,180 -33,345 34,134 1983-2012 Commercial -26,171 39,735 -661 8,251 -2,751 34,817 1993-2012

60

Floating oil production unit slated in small field off Gabon  

SciTech Connect

This paper reports on the first U.S. tanker converted to a floating production, storage, and offloading (FPSO) unit which takes up station in Gombe-Beta field off Gabon by Dec. 1. FPSO Ocean Producer will work under a 3 year, day rate contract let late in 1990 by Amoco-Gabon Bombe Marin co., a unit of Amoco Production Co. (OGJ, Dec. 24, 1990, p. 27). Gombe-Beta field is in the Atlantic Ocean about 70 miles south of Port Gentil, Gabon. Ocean Producer will be moored in 50 ft of water 3.7 miles off Gabon, with Bombe-Beta's unmanned production platform about 820 ft astern. The vessel will be held in position by a disconnectable, asymmetric, six point, spread mooring system, It is owned and operated by Oceaneering International Services Ltd. (OISL). Affiliate Oceaneering Production Systems (OPS) converted the 78,061 dwt oil tanker MT Baltimore Sea at a capital cost of $25 million at Gulf Copper Manufacturing Corp.'s Port Arthur, Tex., shipyard. Both companies are units of Oceaneering International Inc., Houston. OPS the Ocean Producer's use in Gombe-Beta field is the shallowest water FPSO application in the world. Amoco-Gabon chose an FPSO production system for Gombe-Beta because it expects the remote field to have a short economic life, and the oil requires extensive processing.

Not Available

1991-10-14T23:59:59.000Z

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


61

Preliminary siting characterization Salt Disposition Facility - Site B  

SciTech Connect

A siting and reconnaissance geotechnical program has been completed in S-Area at the Savannah River Site in South Carolina. This program investigated the subsurface conditions for the area known as ``Salt Disposition Facility (SDF), Site B'' located northeast of H-Area and within the S-Area. Data acquired from the Site B investigation includes both field exploration and laboratory test data.

Wyatt, D.

2000-01-04T23:59:59.000Z

62

Request For Records Disposition Authority | Department of Energy  

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

Records Schedule Contractor Checks Request For Records Disposition Authority More Documents & Publications DOE-STD-4001-2000 DOE Records Disposition Schedule Changes Audit Letter...

63

Request For Records Disposition Authority | Department of Energy  

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

Fossil Energy Equity Re-determination Records Request For Records Disposition Authority More Documents & Publications REQUEST FOR RECORDS DISPOSITION AUTHORITY Inspection Report:...

64

REQUEST FOR RECORDS DISPOSITION AUTHORITY | Department of Energy  

Office of Environmental Management (EM)

Pacific Northwest Lab: Richland Operations Office REQUEST FOR RECORDS DISPOSITION AUTHORITY More Documents & Publications REQUEST FOR RECORDS DISPOSITION AUTHORITY Request For...

65

PROCEDURE FOR PREPARING RECORDS INVENTORY AND DISPOSITION SCHEDULES...  

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

PROCEDURE FOR PREPARING RECORDS INVENTORY AND DISPOSITION SCHEDULES (RIDS) PROCEDURE FOR PREPARING RECORDS INVENTORY AND DISPOSITION SCHEDULES (RIDS) This document lists the...

66

AEO2011:Total Energy Supply, Disposition, and Price Summary | OpenEI  

Open Energy Info (EERE)

Total Energy Supply, Disposition, and Price Summary Total Energy Supply, Disposition, and Price Summary Dataset Summary Description This dataset comes from the Energy Information Administration (EIA), and is part of the 2011 Annual Energy Outlook Report (AEO2011). This dataset is table 1, and contains only the reference case. The dataset uses quadrillion Btu and the U.S. Dollar. The data is broken down into production, imports, exports, consumption and price. Source EIA Date Released April 26th, 2011 (3 years ago) Date Updated Unknown Keywords 2011 AEO consumption disposition energy exports imports Supply Data application/vnd.ms-excel icon AEO2011:Total Energy Supply, Disposition, and Price Summary- Reference Case (xls, 112.8 KiB) Quality Metrics Level of Review Peer Reviewed Comment Temporal and Spatial Coverage

67

AEO2011: Natural Gas Supply, Disposition, and Prices | OpenEI  

Open Energy Info (EERE)

Supply, Disposition, and Prices Supply, Disposition, and Prices Dataset Summary Description This dataset comes from the Energy Information Administration (EIA), and is part of the 2011 Annual Energy Outlook Report (AEO2011). This dataset is table 13, and contains only the reference case. The dataset uses gigawatts. The data is broken down into production, net imports, consumption by sector and price. Source EIA Date Released April 26th, 2011 (3 years ago) Date Updated Unknown Keywords 2011 AEO disposition EIA natural gas supply prices Data application/vnd.ms-excel icon AEO2011: Natural Gas Supply, Disposition, and Prices - Reference Case (xls, 91.8 KiB) Quality Metrics Level of Review Peer Reviewed Comment Temporal and Spatial Coverage Frequency Annually Time Period 2008-2035 License License Open Data Commons Public Domain Dedication and Licence (PDDL)

68

Nuclear Materials Disposition | Department of Energy  

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

Nuclear Materials Disposition Nuclear Materials Disposition Nuclear Materials Disposition Nuclear Materials Disposition In fulfilling its mission, EM frequently manages and completes disposition of surplus nuclear materials and spent nuclear fuel. These are not waste. They are nuclear materials no longer needed for national security or other purposes, including spent nuclear fuel, special nuclear materials (as defined by the Atomic Energy Act) and other Nuclear Materials. Spent Nuclear Fuel Spent nuclear fuel (SNF) is fuel that has been withdrawn from a nuclear reactor following irradiation, the constituent elements of which have not been separated by reprocessing. SNF may include: (1) intact, non-defective fuel assemblies or fuel rods; (2) failed fuel assemblies or fuel rods; (3) segments of fuel rods or pieces of fuel derived from spent fuel rods; and

69

I REQUEST FOR RECORDS DISPOSITION AUTHORITY  

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

REQUEST FOR RECORDS DISPOSITION AUTHORITY REQUEST FOR RECORDS DISPOSITION AUTHORITY LEAVE BL ...A (NARA use only1 JOB NUMBER TO: NATIONAL ARCHIVES & RECORDS ADMINISTRATION In accordance with the provisions of 44 U.S.C. 3303a, the Office of the Chief Information Officer disposition request, including amendments, is approved except for items that may be marked "disposition not approved" or "withdrawn" in column 10. Records Management Division N1-434-02-2 Date received 860 1 ADELPHI ROAD COLLEGE PARK, MD 20740-600 1 1. FROM (Agency or establishment) Department of Energy , ( / I 4 30 -A&&& NOTIFICATION TO AGENCY 6. AGENCY CERTIFICATION I hereby certify that I am authorized to act for this agency in matters pertaining to the disposition of its records and that the

70

REQUEST FOR RECORDS DISPOSITION AUTHORITY  

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

1nstrlrcrlons on reverts) 1nstrlrcrlons on reverts) ' 0 NATIONAL ARCMVES and RECORDS AD~~INISTRAT~ON (NIR) WASHINGTON, DC 20408 1. FROM (Agency or estabi~shment) Department of Energy Washington, DC 20585 . '2. MAJOR SUBDIVISION fn lccordance w i l h the provirions o f 4 4 DOE~NEVADA OPERATIONS OFFICE U.S.C. 3 3 0 3 r the disposition r e q u c ~ t , including rmtndments, i s approvtd n c t p l 3. MINOR SUBOlVlStON lor ilemr that mky be mrrkcd 'dir wition not approved' o r withdmwn' in c&mn lo. '4. NAME O F PERSON WITH WHOM TO CONFER 5. TELEPHONE Mary Ann Wallace -301 903 4353 6. AGENCY CERTIFICATION I hereby certify that I am authorized to a d for this to th#disposit-ion of its records and that the records roposed for disposal on the P now needed for the business of this agency or wil not be needed after the concurrence f

71

REQUEST FOR RECORDS DISPOSITION AUTHORITY  

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

m m - REQUEST FOR RECORDS DISPOSITION AUTHORITY (See Instructions on reverse) GENERAL SERVICES ADMINISTRATION N A T I O N A L ARCHIVES AND RECORDS SERVICE, WASHINGTON, DC 20408 1. F R O M ( A g e n c y o r e s t a b l i s h m e n t ) jepartment of Energy 2. MAJOR S U B D I V I S I O N Oak Ridse Operations Office 3. M I N O R S U B D I V I S I O N 4 . N A M E O F PERSON W I T H W H O M T O C O N F E R ( 5 . T E L E P H O N E E X T . L E A V E B L A N K - JOB N O . d/-d33P PO- ZJ - - - - p p D A T E R E C E I V E D p - NOTIFICATION TO AGENCY In accordance with the provisions of 44 U.S.C. 3303a the disposal request, including amendments, is approved except for items that may be marked "disposition not approved" or "withdrawn" in column 10. If no records are proposed for disposal, the signature of the Archivist is not required. - DATE ARCHIVIST

72

Processing and Disposition of Special Actinide Target Materials - 13138  

SciTech Connect

The Department of Energy (DOE) manages an inventory of materials that contains a range of long-lived radioactive isotopes that were produced from the 1960's through the 1980's by irradiating targets in high-flux reactors at the Savannah River Site (SRS) to produce special heavy isotopes for DOE programmatic use, scientific research, and industrial and medical applications. Among the products were californium-252, heavy curium (including Cm-246 through Cm-248), and plutonium-242 and -244. Many of the isotopes are still in demand today, and they can be recovered from the remaining targets previously irradiated at SRS or produced from the recovered isotopes. Should the existing target materials be discarded, the plutonium (Pu) and curium (Cm) isotopes cannot be replaced readily with existing production sources. Some of these targets are stored at SRS, while other target material is stored at Oak Ridge National Laboratory (ORNL) at several stages of processing. The materials cannot be stored in their present form indefinitely. Their long-term management involves processing items for beneficial use and/or for disposition, using storage and process facilities at SRS and ORNL. Evaluations are under way for disposition options for these materials, and demonstrations of improved flow sheets to process the materials are being conducted at ORNL and the Savannah River National Laboratory (SRNL). The disposition options and a management evaluation process have been developed. Processing demonstrations and evaluations for these unique materials are under way. (authors)

Robinson, Sharon M.; Patton, Brad D. [Oak Ridge National Laboratory, P.O. Box 2008, Oak Ridge, TN 37831 (United States)] [Oak Ridge National Laboratory, P.O. Box 2008, Oak Ridge, TN 37831 (United States); Allender, Jeffrey S. [Savannah River National Laboratory (United States)] [Savannah River National Laboratory (United States)

2013-07-01T23:59:59.000Z

73

EIS-0283: Surplus Plutonium Disposition Environmental Impact Statement  

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

This EIS analyzes the potential environmental impacts associated with alternatives for the disposition of surplus plutonium.

74

Waste Disposition Update by Christine Gelles  

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

Waste Disposition Update Waste Disposition Update Christine Gelles Associate Deputy Assistant Secretary for Waste Management (EM-30) EM SSAB Chairs Meeting Washington, DC 2 October 2012 www.em.doe.gov 2 o Waste Stream Highlights o DOE Transportation Update o Greater Than Class C (GTCC) Low Level Waste Environmental Impact Statement o Blue Ribbon Commission on America's Nuclear Future o Nuclear Regulatory Commission's LLW Regulatory Initiatives Discussion Topics www.em.doe.gov 3 Waste Stream Highlights www.em.doe.gov 4 o Within current budget outlook, it is especially critical that EM ensures safe, reliable and cost effective disposition paths exist. o The program's refocused organization and the detailed

75

Excess plutonium disposition using ALWR technology  

SciTech Connect

The Office of Nuclear Energy of the Department of Energy chartered the Plutonium Disposition Task Force in August 1992. The Task Force was created to assess the range of practicable means of disposition of excess weapons-grade plutonium. Within the Task Force, working groups were formed to consider: (1) storage, (2) disposal,and(3) fission options for this disposition,and a separate group to evaluate nonproliferation concerns of each of the alternatives. As a member of the Fission Working Group, the Savannah River Technology Center acted as a sponsor for light water reactor (LWR) technology. The information contained in this report details the submittal that was made to the Fission Working Group of the technical assessment of LWR technology for plutonium disposition. The following aspects were considered: (1) proliferation issues, (2) technical feasibility, (3) technical availability, (4) economics, (5) regulatory issues, and (6) political acceptance.

Phillips, A. (ed.); Buckner, M.R.; Radder, J.A.; Angelos, J.G.; Inhaber, H.

1993-02-01T23:59:59.000Z

76

REQUEST FOR RECORDS DISPOSITION AUTHORITY  

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

Instructions on reverse) Instructions on reverse) LEAVE BLANK - GENERAL SERVICES ADMINISTRATION NATIONAL ARCHIVES AND RECORDS SERVICE, WASHINGTON, DC 20408 I . F R O M (Agency or ertabluhmentJ D A T E RECEIVED NOTIF~CATION TO AGENCY Department of Energy 2. MAJ0.R S U B D I V I S I O N I 4 . N A M E O F PERSON W I T H W H O M T O CONFER 15. TELEPHONE E X T . \OATS l A R C H l V l S T O F T H E U N I T E D STATES In accordance with the provisions of 44 U.S.C. 3303 the dispoal request. including amendmentr, is approved . 3. M I N O R S U B D I V I S I O N except for items that may be marked "disposition not approved" or "withdrawn" in column 10. If no records are proposed for disposal, the signature of the Archivist is not required. I hereby certify that I am authorized to act for this agency in matters pertaining to the disposal of the agency's records;

77

AEO2011: Total Energy Supply, Disposition, and Price Summary | OpenEI  

Open Energy Info (EERE)

Total Energy Supply, Disposition, and Price Summary Total Energy Supply, Disposition, and Price Summary Dataset Summary Description This dataset comes from the Energy Information Administration (EIA), and is part of the 2011 Annual Energy Outlook Report (AEO2011). This dataset is table 1, and contains only the reference case. The dataset uses quadrillion BTUs, and quantifies the energy prices using U.S. dollars. The data is broken down into total production, imports, exports, consumption, and prices for energy types. Source EIA Date Released April 26th, 2011 (3 years ago) Date Updated Unknown Keywords 2011 AEO consumption EIA export import production reference case total energy Data application/vnd.ms-excel icon AEO2011: Total Energy Supply, Disposition, and Price Summary - Reference Case (xls, 112.8 KiB) Quality Metrics

78

Field Testing of Pre-Production Prototype Residential Heat Pump Water Heaters  

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

Provides and overview of field testing of 18 pre-production prototype residential heat pump water heaters

79

U.S. Natural Gas Monthly Supply and Disposition Balance  

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

Monthly Supply and Disposition Balance Monthly Supply and Disposition Balance (Billion Cubic Feet) Period: Monthly Download Series History Download Series History Definitions, Sources & Notes Definitions, Sources & Notes Data Series Apr-13 May-13 Jun-13 Jul-13 Aug-13 Sep-13 View History Gross Withdrawals 2,473 2,541 2,444 2,550 2,540 2,465 1973-2013 Marketed Production 2,086 2,166 2,097 2,188 2,188 2,105 1973-2013 NGPL Production, Gaseous Equivalent 107 110 107 113 117 116 1973-2013 Dry Production 1,979 2,056 1,990 2,076 2,071 1,989 1973-2013 Supplemental Gaseous Fuels 5 5 3 3 5 5 1973-2013 Net Imports 95 92 103 108 106 123 1973-2013 Net Storage Withdrawals -136 -418 -372 -275 -270 -355 1973-2013 Balancing Item 14 12 9 7 6 -5 2001-2013

80

Plutonium Disposition Program | National Nuclear Security Administration  

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

Home > Media Room > Fact Sheets > Plutonium Disposition Program Home > Media Room > Fact Sheets > Plutonium Disposition Program Fact Sheet Plutonium Disposition Program Jun 26, 2013 SUPPORTING NUCLEAR NONPROLIFERATION Weapon-grade plutonium and highly enriched uranium (HEU) are the critical ingredients for making a nuclear weapon. With the end of the Cold War, hundreds of tons of these materials were determined to be surplus to U.S. and Russian defense needs. Denying access to plutonium and HEU is the best way to prevent nuclear proliferation to rogue states and terrorist organizations. The most certain method to prevent these materials from falling into the wrong hands is to dispose of them. During the April 2010 Nuclear Security Summit, Secretary of State Hillary Rodham Clinton and Russian Foreign Minister Sergey Lavrov signed a protocol

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


81

U.S. and Russia Sign Plutonium Disposition Agreement | National...  

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

Our Jobs Working at NNSA Blog Home About Us Our History NNSA Timeline U.S. and Russia Sign Plutonium Disposition Agreement U.S. and Russia Sign Plutonium Disposition...

82

REQUEST FOR RECORDS DISPOSITION AUTHORITY | Department of Energy  

Office of Environmental Management (EM)

U. S. Atomic Energy Commision REQUEST FOR RECORDS DISPOSITION AUTHORITY More Documents & Publications REQUEST FOR RECORDS DISPOSITION AUTHORITY DOE-HDBK-1109-97 DOE-HDBK-1109-97...

83

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

SciTech Connect

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

Allender, J; Moore, E

2010-07-14T23:59:59.000Z

84

Surplus Highly Enriched Uranium Disposition Program plan  

SciTech Connect

The purpose of this document is to provide upper level guidance for the program that will downblend surplus highly enriched uranium for use as commercial nuclear reactor fuel or low-level radioactive waste. The intent of this document is to outline the overall mission and program objectives. The document is also intended to provide a general basis for integration of disposition efforts among all applicable sites. This plan provides background information, establishes the scope of disposition activities, provides an approach to the mission and objectives, identifies programmatic assumptions, defines major roles, provides summary level schedules and milestones, and addresses budget requirements.

NONE

1996-10-01T23:59:59.000Z

85

Wood processing wastes recovery and composted product field test  

SciTech Connect

Lumber mill waste, more than 3,000 tons per month, is one of the main waste sources in I-Lan area. Most of the lumber mill waste is sawdust which takes a large parts of organic-containing wastes in I-Lan county. Wastes from seafood plants around the Sueou Harbor causes a treatment problem because of their high nitrogen and phosphorous concentrations. Furthermore, the distiller-by products in I-Lan Winery are easy to become spoiled and result in odor. In this study, the compost method is suggested to deal with these waste problems and make energy recovery. Microorganisms incubating in the laboratory provide the stable seed needed for composting. Flowers and vegetable raising are scheduled to be used in field to verify the efficiency of the products. The optimal combination ration of wastes and operation criteria then will be concluded in this study after economic analyzing. The results show that the Zinnia elegans leaves growth is relative with organic fertilizer. It can also be illustrated from the statistical value that the F value is 19.4 and above the critical value 9.4.

Chang, C.T.; Lin, K.L. [National Inst. of I-Lan Agriculture and Technology, I-Lan City (Taiwan, Province of China)

1997-12-31T23:59:59.000Z

86

Characterizing Surplus US Plutonium for Disposition - 13199  

SciTech Connect

The United States (US) has identified 61.5 metric tons (MT) of plutonium that is permanently excess to use in nuclear weapons programs, including 47.2 MT of weapons-grade plutonium. Surplus inventories will be stored safely by the Department of Energy (DOE) and then transferred to facilities that will prepare the plutonium for permanent disposition. The Savannah River National Laboratory (SRNL) operates a Feed Characterization program for the Office of Fissile Materials Disposition (OFMD) of the National Nuclear Security Administration (NNSA) and the DOE Office of Environmental Management (DOE-EM). SRNL manages a broad program of item tracking through process history, laboratory analysis, and non-destructive assay. A combination of analytical techniques allows SRNL to predict the isotopic and chemical properties that qualify materials for disposition through the Mixed Oxide (MOX) Fuel Fabrication Facility (MFFF). The research also defines properties that are important for other disposition paths, including disposal to the Waste Isolation Pilot Plant (WIPP) as transuranic waste (TRUW) or to high-level waste (HLW) systems. (authors)

Allender, Jeffrey S. [Savannah River National Laboratory, Aiken SC 29808 (United States)] [Savannah River National Laboratory, Aiken SC 29808 (United States); Moore, Edwin N. [Moore Nuclear Energy, LLC, Savannah River Site, Aiken SC 29808 (United States)] [Moore Nuclear Energy, LLC, Savannah River Site, Aiken SC 29808 (United States)

2013-07-01T23:59:59.000Z

87

Characterizing surplus US plutonium for disposition  

SciTech Connect

The United States (US) has identified 61.5 metric tons (MT) of plutonium that is permanently excess to use in nuclear weapons programs, including 47.2 MT of weapons-grade plutonium. Surplus inventories will be stored safely by the Department of Energy (DOE) and then transferred to facilities that will prepare the plutonium for permanent disposition. The Savannah River National Laboratory (SRNL) operates a Feed Characterization program for the Office of Fissile Materials Disposition (OFMD) of the National Nuclear Security Administration (NNSA) and the DOE Office of Environmental Management (DOE-EM). SRNL manages a broad program of item tracking through process history, laboratory analysis, and non-destructive assay. A combination of analytical techniques allows SRNL to predict the isotopic and chemical properties that qualify materials for disposition through the Mixed Oxide (MOX) Fuel Fabrication Facility (MFFF). The research also defines properties that are important for other disposition paths, including disposal to the Waste Isolation Pilot Plant (WIPP) as transuranic waste (TRUW) or to high-level waste (HLW) systems.

Allender, Jeffrey S.; Moore, Edwin N.

2013-02-26T23:59:59.000Z

88

Study of fusion product effects in field-reversed mirrors  

SciTech Connect

The effect of fusion products (fps) on Field-Reversed Mirror (FRM) reactor concepts has been evaluated through the development of two new computer models. The first code (MCFRM) treats fps as test particles in a fixed background plasma, which is represented as a fluid. MCFRM includes a Monte Carlo treatment of Coulomb scattering and thus provides an accurate treatment of fp behavior even at lower energies where pitch-angle scattering becomes important. The second code (FRMOD) is a steady-state, globally averaged, two-fluid (ion and electron), point model of the FRM plasma that incorporates fp heating and ash buildup values which are consistent with the MCFRM calculations. These codes have been used extensively in the development of an advanced-fuel FRM reactor design (SAFFIRE). A Catalyzed-D version of the plant is also discussed along with an investigation of the steady-state energy distribution of fps in the FRM. User guides for the two computer codes are also included.

Driemeyer, D.E.

1980-01-01T23:59:59.000Z

89

Development of a Techno-Economic Model to Optimize DOE Spent Nuclear Fuel Disposition  

SciTech Connect

The National Spent Nuclear Fuel (NSNF) Program is evaluating final disposition of spent nuclear fuel (SNE) in the Department of Energy (DOE) complex. Final disposition of SNF may require that the fuel be treated to minimize material concerns. The treatments may range from electrometallurgical treatment (EMT) and chemical dissolution to engineering controls. Treatment options and treatment locations will depend on fuel type and location of the fuel. One of the first steps associated with selecting one or more sites for treating SNF in the DOE complex is to determine the cost of each option. An economic analysis will assist in determining which fuel treatment alternative attains the optimum disposition of SNF at the lowest possible cost to the government and the public. For this study, a set of questions was developed for the EMT process for fuels at several locations. The set of questions addresses all issues associated with design, construction, and operation of a production facility. A matrix table was developed to determine questions applicable to various fuel treatment options. A work breakdown structure (WBS) was developed to identify a treatment process and costs from initial design to shipment of treatment products to final disposition. Costs can be applied to determine the life cycle cost of each option. This technique can also be applied to other treatment techniques for treating SNF.

Ramer, R. J.; Plum, M. M.; Adams, J. P.; Dahl, C. A.

1998-02-01T23:59:59.000Z

90

Development of an Enhanced Two-Phase Production System at the Geysers Geothermal Field  

SciTech Connect

A method was developed to enhance geothermal steam production from two-phase wells at THE Geysers Geothermal Field. The beneficial result was increased geothermal production that was easily and economically delivered to the power plant.

Steven Enedy

2001-12-14T23:59:59.000Z

91

Disposition of Surplus Highly Enriched Uranium  

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

EIS-0240-S EIS-0240-S For Further Information Contact: U.S. Departmel>t of Energy Office of Fissile Materials Disposition, 1000 Independence Ave., SW, Washington, D.C. 20585 . This report has been reproduced directly from the best available copy. Available to DOE and DOE contractors from the Office of Scientific and Technical Information, P.O. Box 62, Oak Ridge, TN 37831; telephone (423) 576-8401 for prices, Available to the public from the National Technical Information Service, 5285 Port Royal Road, Springfield, VA 22161. Copies of this document are available (while supplies last) upon written request to: Office of Fissile Materials Disposition, MD-4 Forrestal Building United States Department of Energy 1000 Independence Avenue, SW Washington, DC 20585 @ Printed with soy ink on recycled paper. .__- -. @ .: Depafimmt of Energy . i i~t " Wastin@on, DC 20585 June 1996 Dear hterested

92

Disposition of Surplus Highly Enriched Uranium  

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

@ @ Printed with soy ink on recycled paper. ,, ,, This report has been reproduced directly from the best available copy. Available to DOE and DOE contractors horn the Office of Scientific and Technical Information, P.O. Box 62, Oak Ridge, TN 37831; telephone (423) 576-8401 for prices, Available to the public from the National Technical Information Service, 5285 Port Royal Road, Springfield, VA 22161. Copies of this document are available (while supplies last) upon written request to: Office of Fissile Materials Disposition, MD-4 ' Forrestal Building United States Department of Energy 1000 Independence Avenue, SW Washington, DC 20585 Department of Energy Washington, DC 20585 June 1996 Dear hterested Party: The Disposition of Surplus Highly Enriched Uranium Final Environmental Impact Statemnt is enclosed for your information. This document has been prepared in accordance

93

Disposition of Surplus Highly Enriched Uranium  

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

. . ------- .--- --. ---- DOE/EIS-0240 I United States Department of Energy I For Further Information Contact: U.S. Department of Energy Otice of Fissile Materials Disposition, 1000 Independence Ave., SW, Washington, D.C. 20585 1 I ---- I I . I I I I This report has been reproduced directly from the best available copy. Available to DOE and DOE contractors from the Office of Scientific and Technical Information, P.O. Box 62, Oak Ridge, TN 37831; telephone (423) 576-8401 for prices. Available to the public from the National Technical Information Service, 5285 Port Royal Road, Springfield, VA 22161. Copies of this document are available (while supplies last) upon written request to: I Office of Fissile Materials Disposition, MD-4 Forrestal Building United States Department of Energy 1000 Independence Avenue, SW Washington, DC 20585 , @ Printed with soy ink on recycled paper. -_. - COVERS~ET

94

SRS - Programs - H Area Nuclear Materials Disposition  

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

H Area Nuclear Materials Disposition H Area Nuclear Materials Disposition The primary mission of the H-Canyon Complex is to dissolve, purify and blend-down surplus highly enriched uranium (HEU) and aluminum-clad foreign and domestic research reactor fuel to produce a low enriched uranium (LEU) solution suitable for conversion to commercial reactor fuel. A secondary mission for H-Canyon is to dissolve excess plutonium (Pu) not suitable for MOX and transfer it for vitrification in the Defense Waste Processing Facility at SRS. H Canyon was constructed in the early 1950s and began operations in 1955. The building is called a canyon because of its long rectangular shape and two continuous trenches that contains the process vessels. It is approximately 1,000 feet long with several levels to accommodate the various stages of material stabilization, including control rooms to monitor overall equipment and operating processes, equipment and piping gallery for solution transport, storage, and disposition, and unique overhead bridge cranes to support overall process operations. All work is remotely controlled, and employees are further protected from radiation by thick concrete walls.

95

Magnetic Field Production during Preheating at the Electroweak Scale  

Science Journals Connector (OSTI)

We study the generation of magnetic fields during preheating within a scenario of hybrid inflation at the electroweak scale. We find that the nonperturbative and strongly out-of-equilibrium process of generation of magnetic fields with a nontrivial helicity occurs along the lines predicted by Vachaspati many years ago. The magnitude (?B/?EW?10-2) and correlation length of these helical magnetic fields grow linearly with time during preheating and are consistent with the possibility that these seeds gave rise to the microgauss fields observed today in galaxies and clusters of galaxies.

Andrés Díaz-Gil; Juan García-Bellido; Margarita García Pérez; Antonio González-Arroyo

2008-06-16T23:59:59.000Z

96

Update of the Used Fuel Disposition Campaign Implementation Plan |  

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

Update of the Used Fuel Disposition Campaign Implementation Plan Update of the Used Fuel Disposition Campaign Implementation Plan Update of the Used Fuel Disposition Campaign Implementation Plan The Used Fuel Disposition Campaign will identify alternatives and conduct scientific research and technology development to enable storage, transportation, and disposal of used nuclear fuel and wastes generated by existing and future nuclear fuel cycles. This Campaign Implementation Plan provides summary level detail describing how the Used Fuel Disposition Campaign supports achievement of the overarching Fuel Cycle Research and Development Program mission and objectives. Activities will be sufficiently flexible to accommodate any of the potential fuel cycle options for used fuel management. Update of the Used Fuel Disposition Campaign Implementation Plan

97

Master EM Project Definition Rating Index - Facility Disposition Definitions  

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

43 43 Master EM Project Definition Rating Index - Facility Disposition Definitions The following definitions describe the criteria required to achieve a maximum rating or maturity value of 5. It should be assumed that maturity values of 1-5 represent a subjective assessment of the quality of definition and/or the degree to which the end-state or maximum criteria have been met, or the product has been completed in accordance with the definition of maturity values. Rating Element Criteria for Maximum Rating COST A1 Cost Estimate A cost estimate has been developed and formally approved by DOE and is the basis for the cost baselines. The cost estimate is a reasonable approximation of Total Project Costs, and covers all phases of the project. The estimate is prepared in

98

Steamflood production mechanism in an edge pattern Duri field, Indonesia  

E-Print Network (OSTI)

The Duri field, located in Riau Province in Central Sumatra, Indonesia, is currently the site of the largest steamflood project in the world. Roughly half of the field is being flooded in eight project areas. Low oil rate has been encountered...

Yuwono, Ipung Punto

1999-01-01T23:59:59.000Z

99

Asymmetric neutrino production in magnetized proto-neutron stars in fully relativistic mean-field approach  

SciTech Connect

We calculate the neutrino production cross-section in the proto-neutron-star matter under a strong magnetic field in the relativistic mean-field approach. We introduce a new parameter-set which can reproduce the 1.96 solar mass neutron star. We find that the production process increases emitted neutrinos along the direction parallel to the magnetic field and decrease those along its opposite direction. It means that resultant asymmetry due to the neutrino absorption and scattering process in the magnetic field becomes larger by the addition of the neutrino production process.

Maruyama, Tomoyuki [College of Bioresource Sciences, Nihon University, Fujisawa 252-8510 (Japan); Kajino, Toshitaka; Hidaka, Jun; Takiwaki, Tomoya [National Astronomical Observatory of Japan, Mitaka, Tokyo 181-8588 (Japan); Yasutake, Nobutoshi [Department of Physics, Chiba Institute of Technology, Narashino 275-0023 (Japan); Kuroda, Takami [Department of Physics, University of Basel, CH-4056 Basel (Switzerland); Cheoun, Myung-Ki [Department of Physics, Soongsil University, Seoul, 156-743 (Korea, Republic of); Ryu, Chung-Yeol [General Education Curriculum Center, Hanyang University, Seoul, 133-791 (Korea, Republic of); Mathews, Grant J. [Center of Astrophysics, Department of Physics, University of Notre Dame, Notre Dame, IN 46556 (United States)

2014-05-02T23:59:59.000Z

100

Request For Records Disposition Authority-Nuclear Weapons | Department...  

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

For Records Disposition Authority-Nuclear Weapons This document identifies the nuclear weapon records generated by the Department of Energy's (DOE) Nuclear Weapons Complex Request...

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


101

REQUEST FOR RECORDS DISPOSITION AUTHORITY | Department of Energy  

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

Nuclear Power Plant Docket Records REQUEST FOR RECORDS DISPOSITION AUTHORITY More Documents & Publications PIA - Savannah River Remediation Accreditation Boundary (SRR AB) REQUEST...

102

Request For Records Disposition Autnority | Department of Energy  

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

Autnority Request For Records Disposition Autnority Published Posters. Posters depicting Department of Energy facilities, research projects, security awareness themes, and related...

103

Used Fuel Disposition Campaign Phase I Ring Compression Testing...  

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

Phase I Ring Compression Testing of High Burnup Cladding Used Fuel Disposition Campaign Phase I Ring Compression Testing of High Burnup Cladding The purpose of ring compression...

104

Major Risk Factors to the Integrated Facility Disposition Project  

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

The scope of the Integrated Facility Disposition Project (IFDP) needs to comprehensively address a wide range of environmental management risks atthe Oak Ridge Reservation (ORO).

105

Consent Order, Uranium Disposition Services, LLC- NCO-2010-01  

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

Issued to Uranium Disposition Services, LLC related to Construction Deficiencies at the DUF6 Conversion Buildings at the Portsmouth and Paducah Gaseous Diffusion Plants

106

Office of UNF Disposition International Program - Strategic Plan |  

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

UNF Disposition International Program - Strategic Plan UNF Disposition International Program - Strategic Plan Office of UNF Disposition International Program - Strategic Plan The Department of Energy's Office of Nuclear Energy, Used Nuclear Fuel Disposition Research and Development Office (UFD), performs the critical mission of addressing the need for an integrated strategy that combines safe storage of spent nuclear fuel with expeditious progress toward siting and licensing a disposal facility or facilities. The UFD International Program plays a key role in this effort. International collaboration provides a forum for exchanging strategies, expertise, and technologies with other nations that have also been investigating solutions to the problems of nuclear waste disposal-information that otherwise would have

107

Effective Field Theory for Higgs Plus Jet Production | Argonne...  

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

includes all possible gluon-Higgs dimension-5 and dimension-7 operators to study Higgs boson plus jet production in next-to-leading order QCD. The EFT sheds light on the effect...

108

Portugal Egypt Figure 2. Natural gas supply and disposition in the United States, 2012  

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

Portugal Egypt Figure 2. Natural gas supply and disposition in the United States, 2012 (trillion cubic feet) Natural Gas Plant Liquids Production Gross Withdrawals From Gas and Oil Wells Nonhydrocarbon Gases Removed Vented/Flared Reservoir Repressuring Production Dry Gas Imports Canada Trinidad/Tobago Natural Gas Storage Facilities Exports Japan Canada Mexico Additions Withdrawals Gas Industry Use Residential Commercial Industrial Vehicle Fuel Electric Power 29.5 0.8 0.2 3.3 2.963 0.112 0.620 0.971 0.014 24.1 1.3 2.9 2.8 2.5 2.9 7.2 0.03 9.1 0.003 Sources: Energy Information Administration (EIA), Form EIA-176, "Annual Report of Natural and Supplemental Gas Supply and Disposition"; Form EIA-895, "Annual Quantity and

109

EM Waste and Materials Disposition & Transportation  

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

On Closure Success On Closure Success 1 EM Waste and Materials Disposition & Transportation National Transportation Stakeholders Forum Chicago, Illinois May 26, 2010 Frank Marcinowski Acting Chief Technical Officer and Deputy Assistant Secretary for Technical and Regulatory Support Office of Environmental Management DOE's Radioactive Waste Management Priorities * Continue to manage waste inventories in a safe and compliant manner * Address high risk waste in a cost- ff ti effective manner * Maintain and optimize current disposal capability for future generations * Develop future disposal capacity in a complex environment * Promote the development of treatment and disposal alternatives in the 2 and disposal alternatives in the

110

NETL: News Release - DOE Project Revives Oil Production in Abandoned Fields  

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

4 , 2006 4 , 2006 DOE Project Revives Oil Production in Abandoned Fields on Osage Tribal Lands Novel Oil Recovery Technique Developed Under DOE's Native American Initiative WASHINGTON, DC - A technology developed with U.S. Department of Energy funding has revived oil production in two abandoned oilfields on Osage Indian tribal lands in northeastern Oklahoma, and demonstrated a technology that could add billions of barrels of additional domestic oil production in declining fields. Production has jumped from zero to more than 100 barrels of oil per day in the two Osage County, Okla., fields, one of which is more than 100 years old. The technology was successfully pilot-tested in the century-old field, and using the knowledge gained, the technology was applied to a neighboring field with comparable success. This suggests that such approaches could revitalize thousands of other seemingly depleted oilfields across America's Midcontinent region.

111

EIS-0287: Idaho High-Level Waste and Facilities Disposition Final...  

Office of Environmental Management (EM)

: Idaho High-Level Waste and Facilities Disposition Final Environmental Impact Statement, EIS-0287 (September 2002) EIS-0287: Idaho High-Level Waste and Facilities Disposition...

112

Surface Light Field Rendering for Virtual Product Design  

E-Print Network (OSTI)

illumination solution including accurate materials, which is stored as an outgoing Surface Light Field (SLF), as a method to improve upon this problem. In addition, suitable SLF compression and computation techniques (SLF) rendering as a suitable method for VR applications. In contrast to Radiosity solutions, SLFs

Behnke, Sven

113

Enhancing enterprise field productivity via cross platform mobile cloud apps  

Science Journals Connector (OSTI)

This paper describes the design, implementation, deployment, and ongoing management of a cross-platform native mobile application that empowers the Field (Sales, Marketing, Systems Engineers) in an Enterprise to collaborate with Customers through sharing ... Keywords: cross-platform native smartphone apps, enterprise mobile apps, hybrid (private/public) cloud services, mobile platform

T. K. Lakshman; Xander Thuijs

2011-06-01T23:59:59.000Z

114

,"Natural Gas Plant Field Production: Natural Gas Liquids "  

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

Field Production: Natural Gas Liquids " Field Production: Natural Gas Liquids " ,"Click worksheet name or tab at bottom for data" ,"Worksheet Name","Description","# Of Series","Frequency","Latest Data for" ,"Data 1","Natural Gas Plant Field Production: Natural Gas Liquids ",16,"Monthly","9/2013","1/15/1981" ,"Release Date:","11/27/2013" ,"Next Release Date:","Last Week of December 2013" ,"Excel File Name:","pet_pnp_gp_a_epl0_fpf_mbbl_m.xls" ,"Available from Web Page:","http://www.eia.gov/dnav/pet/pet_pnp_gp_a_epl0_fpf_mbbl_m.htm" ,"Source:","Energy Information Administration"

115

Field Labeling to Ensure the Electrical Safety of Production Equipment  

E-Print Network (OSTI)

not including equipment that is designed for use in hazardous locations. This publication provides compressive information on how to apply electrical components, wiring and control systems to both ensure safety of personnel and aid in the delivery..., by delivering safe products at a reasonable price a company will not be eliminated as a potential equipment supplier by being viewed in a negative light as a result of a poor safety evaluation. OSHA posts information on their website detailing the number...

Mills, Todd

2012-05-11T23:59:59.000Z

116

Natural Gas Plant Field Production: Natural Gas Liquids  

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

Product: Natural Gas Liquids Pentanes Plus Liquefied Petroleum Gases Ethane Propane Normal Butane Isobutane Period-Unit: Monthly-Thousand Barrels Monthly-Thousand Barrels per Day Annual-Thousand Barrels Annual-Thousand Barrels per Day Product: Natural Gas Liquids Pentanes Plus Liquefied Petroleum Gases Ethane Propane Normal Butane Isobutane Period-Unit: Monthly-Thousand Barrels Monthly-Thousand Barrels per Day Annual-Thousand Barrels Annual-Thousand Barrels per Day Download Series History Download Series History Definitions, Sources & Notes Definitions, Sources & Notes Show Data By: Product Area Apr-13 May-13 Jun-13 Jul-13 Aug-13 Sep-13 View History U.S. 74,056 76,732 74,938 79,040 82,376 81,196 1981-2013 PADD 1 1,525 1,439 2,394 2,918 2,821 2,687 1981-2013 East Coast 1993-2008 Appalachian No. 1 1,525 1,439 2,394 2,918 2,821 2,687 1993-2013 PADD 2 12,892 13,208 13,331 13,524 15,204 15,230 1981-2013 Ind., Ill. and Ky. 1,975 1,690 2,171 1,877 2,630 2,746 1993-2013

117

Assessment of the Integrated Facility Disposition Project at Oak Ridge  

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

Assessment of the Integrated Facility Disposition Project at Oak Assessment of the Integrated Facility Disposition Project at Oak Ridge National Laboratory & Y-12 for Transfer of Facilities & Materials to EM Assessment of the Integrated Facility Disposition Project at Oak Ridge National Laboratory & Y-12 for Transfer of Facilities & Materials to EM In December 2007, the Assistant Secretary for Environmental Management (EM-1) invited the DOE Program Secretarial Offices (PSOs) of Nuclear Energy (NE), Science (SC), and the National Nuclear Security Administration (NNSA) to propose facilities and legacy waste for transfer to Environmental Management (EM) for final disposition or deactivation and decommissioning (D&D). Assessment of the Integrated Facility Disposition Project at Oak Ridge National Laboratory & Y-12 for Transfer of Facilities & Materials to EM

118

EIS-0327: Disposition of Scrap Metals Programmatic EIS | Department of  

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

27: Disposition of Scrap Metals Programmatic EIS 27: Disposition of Scrap Metals Programmatic EIS EIS-0327: Disposition of Scrap Metals Programmatic EIS Summary This EIS will evaluate the environmental impacts of policy alternatives for the disposition of scrap metals (primarily carbon steel and stainless steel) that may have residual surface radioactivity. DOE is cancelling this EIS. Public Comment Opportunities No public comment opportunities available at this time. Documents Available for Download December 19, 2011 EA-1919: Notice of Revision to Clearance Policy Recycle of Scrap Metals Originating from Radiological Areas (December 2011) July 12, 2001 EIS-0327: Notice of Intent to Prepare a Programmatic Environmental Impact Statement and Announcement of Public Scoping Meetings Disposition of Scrap Metals

119

Properties and Dispositions: Some Metaphysical Remarks on Quantum Ontology  

Science Journals Connector (OSTI)

After some suggestions about how to clarify the confused metaphysical distinctions between dispositional and non?dispositional or categorical properties I review some of the main interpretations of QM in order to show that — with the relevant exception of Bohm’s minimalist interpretation — quantum ontology is irreducibly dispositional. Such an irreducible character of dispositions must be explained differently in different interpretations but the reducibility of the contextual properties in the case of Bohmian mechanics is guaranteed by the fact that the positions of particles play the role of the categorical basis a role that in other interpretations cannot be filled by anything else. In Bohr’s and Everett?type interpretations dispositionalism is instrumentalism in disguise.

Mauro Dorato

2006-01-01T23:59:59.000Z

120

Assessment of the Integrated Facility Disposition Project at Oak Ridge  

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

the Integrated Facility Disposition Project at Oak the Integrated Facility Disposition Project at Oak Ridge National Laboratory & Y-12 for Transfer of Facilities & Materials to EM Assessment of the Integrated Facility Disposition Project at Oak Ridge National Laboratory & Y-12 for Transfer of Facilities & Materials to EM In December 2007, the Assistant Secretary for Environmental Management (EM-1) invited the DOE Program Secretarial Offices (PSOs) of Nuclear Energy (NE), Science (SC), and the National Nuclear Security Administration (NNSA) to propose facilities and legacy waste for transfer to Environmental Management (EM) for final disposition or deactivation and decommissioning (D&D). Assessment of the Integrated Facility Disposition Project at Oak Ridge National Laboratory & Y-12 for Transfer of Facilities & Materials to EM

Note: This page contains sample records for the topic "disposition field production" 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

Used Fuel Disposition Campaign Preliminary Quality Assurance Implementation  

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

Used Fuel Disposition Campaign Preliminary Quality Assurance Used Fuel Disposition Campaign Preliminary Quality Assurance Implementation Plan Used Fuel Disposition Campaign Preliminary Quality Assurance Implementation Plan The primary objective of this report is to determine whether the existing Fuel Cycle Technologies (FCT) Quality Assurance Program Document (QAPD) is sufficient for work to be performed in the Used Fuel Disposition Campaign (UFDC), and where the existing QAPD is not sufficient, supply recommendations for changes to the QAPD to accommodate the UFDC. The FCT QAPD provides a sound and useable foundation for the implementation of QA for UFDC R&D activities, including the application of QA in a graded approach. Used Fuel Disposition Campaign Preliminary Quality Assurance Implementation Plan More Documents & Publications

122

EIS-0283-S2: Surplus Plutonium Disposition Supplemental Environmental  

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

3-S2: Surplus Plutonium Disposition Supplemental 3-S2: Surplus Plutonium Disposition Supplemental Environmental Impact Statement EIS-0283-S2: Surplus Plutonium Disposition Supplemental Environmental Impact Statement Summary This EIS analyzes the potential environmental impacts associated with changes to the surplus plutonium disposition program, including changes to the inventory of surplus plutonium and proposed new alternatives. The original EIS is available here. For more information, see: www.nnsa.energy.gov/nepa/spdsupplementaleis Public Comment Opportunities None available at this time. Documents Available for Download April 25, 2013 EIS-0283-S2: Interim Action Determination Surplus Plutonium Disposition Supplemental Environmental Impact Statement (K-Area Materials Storage (KAMS) Area Expansion at the Savannah River Site)

123

Hight-Level Waste & Facilities Disposition  

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

High-Level Waste (HLW) and Facilities Disposition Final High-Level Waste (HLW) and Facilities Disposition Final Environmental Impact Statement You are here: DOE-ID Home > Environmental Management > Idaho High-Level Waste (HLW) Table of Contents Documents are in the Adobe® PDF format and require the Adobe® Reader to access them. If you do not currently have the Acrobat Reader, you can download the Free Adobe Reader at http://get.adobe.com/reader/ Icon link to Free Adobe Acrobat Reader software * Large chapters broken down into sections Summary* Cover [ Adobe Acrobat File Size 1.48 MB] Section, 1.0 [ Adobe Acrobat File Size 612 KB] Section, 2.0 [ Adobe Acrobat File Size 251 KB] Sections, 3.0 - 3.2.1a [ Adobe Acrobat File Size 1.4 MB] Section, 3.2.1b [ Adobe Acrobat File Size 2.0 MB] Sections, 3.2.2 - 4.0 [ Adobe Acrobat File Size 1.4 MB]

124

Development of a techno-economic model to optimization DOE spent nuclear fuel disposition  

SciTech Connect

The purpose of the National Spent Nuclear Fuel (NSNF) Program conducted by Lockheed Martin Idaho Technology Co. (LMITCO) at the Idaho National Engineering and Environmental Laboratory (INEEL) is to evaluate what to do with the spent nuclear fuel (SNF) in the Department of Energy (DOE) complex. Final disposition of the SNF may require that the fuel be treated to minimize material concerns. The treatments may range from electrometallurgical treatment and chemical dissolution to engineering controls. Treatment options and treatment locations will depend on the fuel type and the current locations of the fuel. One of the first steps associated with selecting one or more sites for treating the SNF in the DOE complex is to determine the cost of each option. An economic analysis will assist in determining which fuel treatment alternative attains the optimum disposition of SNF at the lowest possible cost to the government and the public. For this study, a set of questions was developed for the electrometallurgical treatment process for fuels at several locations. The set of questions addresses all issues associated with the design, construction, and operation of a production facility. A matrix table was developed to determine questions applicable to various fuel treatment options. A work breakdown structure (WBS) was developed to identify a treatment process and costs from initial design to shipment of treatment products to final disposition. Costs will be applied to determine the life-cycle cost of each option. This technique can also be applied to other treatment techniques for treating spent nuclear fuel.

Ramer, R.J.; Plum, M.M.; Adams, J.P.; Dahl, C.A.

1997-11-01T23:59:59.000Z

125

Aboveground biomass production in an irrigation and fer-tilization field experiment with Eucalyptus globulus  

E-Print Network (OSTI)

Aboveground biomass production in an irrigation and fer- tilization field experiment). To assess optimum biomass production of Eucalyp- tus globulus in Portugal and to study the physiological in March 1986 (Pereira et al., 1988). In this paper, we present the results of aboveground biomass

Paris-Sud XI, Université de

126

HEQUEST FOR Rt43RDS DISPOSITION AUTHORITY  

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

- - HEQUEST FOR Rt43RDS DISPOSITION AUTHORITY (See ~nstructions on reverse) / GENERAL SERVICES ADMINISTRATION NATIONAL ARCHIVES AND RECORDS SERVICE, WASHINGTON, D C 20408 1 . F R O M (Agency orestablishment) U.S. Department of Energy 2 . MAJOR SUBDIVISION Oak Ridge Operations Office 3. M I N O R SUBDIVISION I hereby certify that I am authorized to act for this agency in matters pertaining to the disposal of the agency's records; that the records proposed for disposal in this Request of 4 page(s) are not now needed for the business of this agency or will not be needed after the retention periods specified; and that written concurrence from the General Accounting Office, if required under the provisions of Title 8 of the GAO Manual for Guidance of Federal Agencies, is

127

REQUEST FOR RECORDS DISPOSITION AUTHORITY S  

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

S S e e Instructions o n reverse) NATIONAL ARCHIVES and RECORDS ADMINISTRATION (NIR) WASHINGTON. DC 20408 , - - 1. FROM (Agency or establishment) Department of Energy 2. MAJOR SUBDIVISION Assistant Secretary For Fossil Energy (FE-1) I 3. MINOR SUBDIVISION Office of Naval Petroleum and Shale Oil 4 . NAME OF PERSON WITH WHOM TO CON I 1 Jerry Hinkle (FE 47) 1(202)586-43 80 I I / 6. AGENCY CERTIFICATION I NOTIFICATION TO AGENCY i I In accordance with the provisions of 44 U.S.C. 3303a the disposition request, including amendments, is ap roved except for items that may be marke! "dis osition not approved" or "withdrawn" in c o L n 10. I hereby certify that I am authorized to act for this agency in yatters pertaining to of its records and that the records roposed for disposal on the attached

128

Disposition options for {sup 233}U  

SciTech Connect

The United States is implementing a program to dispose of excess nuclear-weapons-usable materials--including {sup 233}U. A series of studies have identified multiple {sup 233}U disposition options, and these options are described herein. Most of the options involve adding depleted uranium containing {sup 238}U to the {sup 233}U. Converting the {sup 233}U into a mixture of <12 wt % {sup 233}U in {sup 238}U converts the weapons-usable {sup 233}U into nonweapons-usable {sup 233}U. For {sup 233}U that is considered waste, further isotopic dilution to <0.66 wt % {sup 233}U in {sup 238}U minimizes potential long-term repository criticality concerns and in many cases minimizes final waste volumes.

Forsberg, C.W.; Icenhour, A.S.; Krichinsky, A.M.

1998-04-27T23:59:59.000Z

129

Neutron Assay System for Confinement Vessel Disposition  

SciTech Connect

Los Alamos National Laboratory has a number of spherical confinement vessels (CVs) remaining from tests involving nuclear materials. These vessels have an inner diameter of 6 feet with 1-inch thick steel walls. The goal of the Confinement Vessel Disposition (CVD) project is to remove debris and reduce contamination inside the CVs. The Confinement Vessel Assay System (CVAS) was developed to measure the amount of special nuclear material (SNM) in CVs before and after cleanout. Prior to cleanout, the system will be used to perform a verification measurement of each vessel. After cleanout, the system will be used to perform safeguards-quality assays of {le}100-g {sup 239}Pu equivalent in a vessel for safeguards termination. The CVAS has been tested and calibrated in preparation for verification and safeguards measurements.

Frame, Katherine C. [Los Alamos National Laboratory; Bourne, Mark M. [Los Alamos National Laboratory; Crooks, William J. [Los Alamos National Laboratory; Evans, Louise [Los Alamos National Laboratory; Mayo, Douglas R. [Los Alamos National Laboratory; Miko, David K. [Los Alamos National Laboratory; Salazar, William R. [Los Alamos National Laboratory; Stange, Sy [Los Alamos National Laboratory; Valdez, Jose I. [Los Alamos National Laboratory; Vigil, Georgiana M. [Los Alamos National Laboratory

2012-07-13T23:59:59.000Z

130

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

131

Major Risk Factors to the Integrated Facility Disposition Project  

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

Oak Ridge Reservation Tennessee Major Risk Factors to the Integrated Facility Disposition Project (IFDP) Challenge The scope of the Integrated Facility Disposition Project (IFDP) needs to comprehensively address a wide range of environmental management risks at the Oak Ridge Reservation (ORO). These include: environmental remediation, regulatory compliance, deactivation and decommissioning (D&D) activities, and disposition of legacy materials and waste, along with the ongoing modernization, reindustrialization, and reconfiguration initiatives at the Oak Ridge National Laboratory and at the Y-12 National Security Complex. The balancing of the broad nature of these activities and issues at ORO are a key challenge for the IFDP especially since their interrelationship is not always obvious.

132

Offshore oil: Investigating production parameters of fields of varying size, location and water depth  

Science Journals Connector (OSTI)

Abstract This paper derives empirical estimates of field depletion level, depletion rate, decline rate and characteristic time intervals in offshore oil production based on a global field-by-field database containing 603 offshore oil fields. Statistical distributions as well as arithmetic and weighted averages of production parameters are derived for different categories of fields specified by size, location and water depth. A significant tendency of small fields having higher depletion and decline rates is found. Similarly, OECD countries generally have higher rates compared to non-OECD countries. Trends related to water depth are not clearly distinguishable and require additional investigation of time related aspects. Resulting spreads in derived parameter estimates are found to be well described by positively skewed probability distributions. Also, in line with theory, a strong correlation between depletion and decline rate is found. According to the study, the net share of global offshore production from smaller and deeper fields is increasing. A continuation of these trends would likely have implications for future aggregate offshore production behaviour, most notably, increasing global aggregate decline rates.

David Sällh; Henrik Wachtmeister; Xu Tang; Mikael Höök

2015-01-01T23:59:59.000Z

133

Geometric Origin of Pair Production by Electric Field in de Sitter Space  

E-Print Network (OSTI)

The particle production in a de Sitter space provides an interesting model to understand the curvature effect on Schwinger pair production by a constant electric field or Schwinger mechanism on the de Sitter radiation. For that purpose, we employ the recently introduced complex analysis method, in which the quantum evolution in the complex time explains the pair production via the geometric transition amplitude and gives the pair-production rate as the contour integral. We compare the result by the contour integral with that of the phase-integral method.

Sang Pyo Kim

2014-04-15T23:59:59.000Z

134

WASTE DISPOSITION PROJECT MAKES GREAT STRIDES AT THE IDAHO SITE |  

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

WASTE DISPOSITION PROJECT MAKES GREAT STRIDES AT THE IDAHO SITE WASTE DISPOSITION PROJECT MAKES GREAT STRIDES AT THE IDAHO SITE WASTE DISPOSITION PROJECT MAKES GREAT STRIDES AT THE IDAHO SITE April 1, 2010 - 12:00pm Addthis An operator uses robotic manipulators to process RH TRU. An operator uses robotic manipulators to process RH TRU. Idaho - The Waste Disposition Project Team at the Department of Energy's Idaho Site has continued to keep its commitment to remove remote handled (RH) transuranic (TRU) waste out of Idaho, protecting the Snake River Plain Aquifer and keeping the Office of Environmental Management's commitment to environmental clean up. In 2007, the first shipment of RH TRU waste left the gates of the Idaho Site, headed to the Waste Isolation Pilot Plant (WIPP) for disposal. In the three years since, devoted individuals on the CH2M-WG, Idaho's (CWI)

135

Used Fuel Disposition Campaign Preliminary Quality Assurance Implementation  

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

Preliminary Quality Assurance Preliminary Quality Assurance Implementation Plan Used Fuel Disposition Campaign Preliminary Quality Assurance Implementation Plan The primary objective of this report is to determine whether the existing Fuel Cycle Technologies (FCT) Quality Assurance Program Document (QAPD) is sufficient for work to be performed in the Used Fuel Disposition Campaign (UFDC), and where the existing QAPD is not sufficient, supply recommendations for changes to the QAPD to accommodate the UFDC. The FCT QAPD provides a sound and useable foundation for the implementation of QA for UFDC R&D activities, including the application of QA in a graded approach. Used Fuel Disposition Campaign Preliminary Quality Assurance Implementation Plan More Documents & Publications Used Fuel Disposition Campaign International Activities Implementation Plan

136

AEO2011: Liquid Fuels Supply and Disposition | OpenEI  

Open Energy Info (EERE)

Liquid Fuels Supply and Disposition Liquid Fuels Supply and Disposition Dataset Summary Description This dataset comes from the Energy Information Administration (EIA), and is part of the 2011 Annual Energy Outlook Report (AEO2011). This dataset is table 11, and contains only the reference case. The dataset uses million barrels per day. The data is broken down into crude oil, other petroleum supply, other non petroleum supply and liquid fuel consumption. Source EIA Date Released April 26th, 2011 (3 years ago) Date Updated Unknown Keywords 2011 AEO disposition EIA liquid fuels Supply Data application/vnd.ms-excel icon AEO2011: Liquid Fuels Supply and Disposition- Reference Case (xls, 117 KiB) Quality Metrics Level of Review Peer Reviewed Comment Temporal and Spatial Coverage Frequency Annually

137

Hanford Tank Waste Retrieval, Treatment and Disposition Framework |  

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

Hanford Tank Waste Retrieval, Treatment and Disposition Framework Hanford Tank Waste Retrieval, Treatment and Disposition Framework Hanford Tank Waste Retrieval, Treatment and Disposition Framework Completing the Office of River Protection (ORP) mission of stabilizing 56 million gallons of chemical and radioactive waste stored in Hanford's 177 tanks is one of the Energy Department's highest priorities. This Framework document outlines a phased approach for beginning tank waste treatment while continuing to resolve technical issues with the Pretreatment and High-Level Waste Facilities. Hanford Tank Waste Retrieval, Treatment and Disposition Framework More Documents & Publications EIS-0391: Draft Environmental Impact Statement Waste Treatment Plant and Tank Farm Program EIS-0356: Notice of Intent to Prepare an Environmental Impact Statement

138

WASTE DISPOSITION PROJECT MAKES GREAT STRIDES AT THE IDAHO SITE |  

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

WASTE DISPOSITION PROJECT MAKES GREAT STRIDES AT THE IDAHO SITE WASTE DISPOSITION PROJECT MAKES GREAT STRIDES AT THE IDAHO SITE WASTE DISPOSITION PROJECT MAKES GREAT STRIDES AT THE IDAHO SITE April 1, 2010 - 12:00pm Addthis An operator uses robotic manipulators to process RH TRU. An operator uses robotic manipulators to process RH TRU. Idaho - The Waste Disposition Project Team at the Department of Energy's Idaho Site has continued to keep its commitment to remove remote handled (RH) transuranic (TRU) waste out of Idaho, protecting the Snake River Plain Aquifer and keeping the Office of Environmental Management's commitment to environmental clean up. In 2007, the first shipment of RH TRU waste left the gates of the Idaho Site, headed to the Waste Isolation Pilot Plant (WIPP) for disposal. In the three years since, devoted individuals on the CH2M-WG, Idaho's (CWI)

139

Low Level Waste Disposition - Quantity and Inventory | Department of  

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

Low Level Waste Disposition - Quantity and Inventory Low Level Waste Disposition - Quantity and Inventory Low Level Waste Disposition - Quantity and Inventory This study has been prepared by the Used Fuel Disposition (UFD) campaign of the Fuel Cycle Research and Development (FCR&D) program. The purpose of this study is to provide an estimate of the volume of low level waste resulting from a variety of commercial fuel cycle alternatives in order to support subsequent system-level evaluations of disposal system performance. This study provides an estimate of Class A/B/C low level waste (LLW), greater than Class C (GTCC) waste, mixed LLW and mixed GTCC waste generated from the following initial set of fuel cycles and recycling processes: 1. Operations at a geologic repository based upon a once through light

140

Hanford Tank Waste Retrieval, Treatment and Disposition Framework |  

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

Hanford Tank Waste Retrieval, Treatment and Disposition Framework Hanford Tank Waste Retrieval, Treatment and Disposition Framework Hanford Tank Waste Retrieval, Treatment and Disposition Framework Completing the Office of River Protection (ORP) mission of stabilizing 56 million gallons of chemical and radioactive waste stored in Hanford's 177 tanks is one of the Energy Department's highest priorities. This Framework document outlines a phased approach for beginning tank waste treatment while continuing to resolve technical issues with the Pretreatment and High-Level Waste Facilities. Hanford Tank Waste Retrieval, Treatment and Disposition Framework More Documents & Publications EIS-0391: Draft Environmental Impact Statement Waste Treatment Plant and Tank Farm Program EIS-0356: Notice of Intent to Prepare an Environmental Impact Statement

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141

Used Fuel Disposition Campaign Disposal Research and Development Roadmap |  

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

Used Fuel Disposition Campaign Disposal Research and Development Used Fuel Disposition Campaign Disposal Research and Development Roadmap Used Fuel Disposition Campaign Disposal Research and Development Roadmap The U.S. Department of Energy Office of Nuclear Energy (DOE-NE), Office of Fuel Cycle Technology (OFCT) has established the Used Fuel Disposition Campaign (UFDC) to conduct the research and development (R&D) activities related to storage, transportation and disposal of used nuclear fuel (UNF) and high level nuclear waste (HLW). The Mission of the UFDC is To identify alternatives and conduct scientific research and technology development to enable storage, transportation and disposal of used nuclear fuel and wastes generated by existing and future nuclear fuel cycles. The U.S. has, for the past twenty-plus years, focused efforts on disposing

142

Low Level Waste Disposition - Quantity and Inventory | Department of  

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

Low Level Waste Disposition - Quantity and Inventory Low Level Waste Disposition - Quantity and Inventory Low Level Waste Disposition - Quantity and Inventory This study has been prepared by the Used Fuel Disposition (UFD) campaign of the Fuel Cycle Research and Development (FCR&D) program. The purpose of this study is to provide an estimate of the volume of low level waste resulting from a variety of commercial fuel cycle alternatives in order to support subsequent system-level evaluations of disposal system performance. This study provides an estimate of Class A/B/C low level waste (LLW), greater than Class C (GTCC) waste, mixed LLW and mixed GTCC waste generated from the following initial set of fuel cycles and recycling processes: 1. Operations at a geologic repository based upon a once through light

143

Integrated Tool Development for Used Fuel Disposition Natural System  

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

Integrated Tool Development for Used Fuel Disposition Natural Integrated Tool Development for Used Fuel Disposition Natural System Evaluation Phase I Report Integrated Tool Development for Used Fuel Disposition Natural System Evaluation Phase I Report The natural barrier system (NBS) is an integral part of a geologic nuclear waste repository. The report describes progress in development of an integrated modeling framework that can be used for systematically analyzing the performance of a natural barrier system and identifying key factors that control the performance. This framework is designed as an integrated tool for prioritization and programmatic decisions. Integrated Tool Development for Used Fuel Disposition Natural System Evaluation Phase I Report More Documents & Publications Natural System Evaluation and Tool Development FY11 Progress Report

144

Integrated Tool Development for Used Fuel Disposition Natural System  

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

Integrated Tool Development for Used Fuel Disposition Natural Integrated Tool Development for Used Fuel Disposition Natural System Evaluation Phase I Report Integrated Tool Development for Used Fuel Disposition Natural System Evaluation Phase I Report The natural barrier system (NBS) is an integral part of a geologic nuclear waste repository. The report describes progress in development of an integrated modeling framework that can be used for systematically analyzing the performance of a natural barrier system and identifying key factors that control the performance. This framework is designed as an integrated tool for prioritization and programmatic decisions. Integrated Tool Development for Used Fuel Disposition Natural System Evaluation Phase I Report More Documents & Publications Natural System Evaluation and Tool Development FY11 Progress Report

145

EA-1977: Acceptance and Disposition of Used Nuclear Fuel Containing...  

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

Fuel Containing U.S.-Origin Highly Enriched Uranium from the Federal Republic of Germany EA-1977: Acceptance and Disposition of Used Nuclear Fuel Containing U.S.-Origin...

146

Americium/Curium Disposition Life Cycle Planning Study  

SciTech Connect

At the request of the Department of Energy Savannah River Office (DOE- SR), Westinghouse Savannah River Company (WSRC) evaluated concepts to complete disposition of Americium and Curium (Am/Cm) bearing materials currently located at the Savannah River Site (SRS).

Jackson, W.N. [Westinghouse Savannah River Company, AIKEN, SC (United States); Krupa, J.; Stutts, P.; Nester, S.; Raimesch, R.

1998-04-30T23:59:59.000Z

147

EIS-0327: Disposition of Scrap Metals Programmatic EIS  

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

This EIS will evaluate the environmental impacts of policy alternatives for the disposition of scrap metals (primarily carbon steel and stainless steel) that may have residual surface radioactivity. DOE is cancelling this EIS.

148

Controls of coal fabric on coalbed gas production and compositional shift in both field production and canister desorption tests  

SciTech Connect

The production rates of coalbed gas wells commonly vary significantly, even in the same field with similar reservoir permeability and gas content. The compositional variation in produced gas is also not everywhere predictable, although in most fields produced gas becomes progressively enriched in CO, through the production life of a reservoir, such as parts of the San Juan basin. In contrast, it is generally observed that the ratio of CO{sub 2}:CH{sub 4} declines with time during field and laboratory desorption testing of coal cores. In this study, we investigate numerically the importance of coal fabric, namely cleat spacing and aperture width, on the performance of coalbed gas wells and gas compositional shifts during production. Because of the cubic relationship between fracture permeability and fracture aperture width (and thus fracture porosity) for a given cleat permeability, the production profile of coal seams varies depending on whether the permeability is distributed among closely spaced fractures (cleat) with narrower apertures or more widely spaced fractures (cleat) with wider apertures. There is a lower fracture porosity for coal with widely spaced fractures than for coal with closely spaced fractures. Therefore, the relative permeability to gas increases more rapidly for coals with more widely spaced cleats as less dewatering from fractures is required, assuming that the fractures are initially water saturated. The enrichment of CO{sub 2} in the production gas with time occurs because of the stronger adsorption of coals for CO{sub 2} than CH{sub 4}. However, during desorption of coal cores, CO{sub 2} desorbs more rapidly than methane because desorption rate is governed more by diffusion than by sorption affinity, and CO{sub 2} has much higher effective diffusivity in microporous coals than CH{sub 4}.

Cui, X.J.; Bustin, R.M. [University of British Columbia, Vancouver, BC (Canada)

2006-03-15T23:59:59.000Z

149

DISPOSITION PATHS FOR ROCKY FLATS GLOVEBOXES: EVALUATING OPTIONS  

SciTech Connect

The Kaiser-Hill Company, LLC has the responsibility for closure activities at the Rocky Flats Environmental Technology Site (RFETS). One of the challenges faced for closure is the disposition of radiologically contaminated gloveboxes. Evaluation of the disposition options for gloveboxes included a detailed analysis of available treatment capabilities, disposal facilities, and lifecycle costs. The Kaiser-Hill Company, LLC followed several processes in determining how the gloveboxes would be managed for disposition. Currently, multiple disposition paths have been chosen to accommodate the needs of the varying styles and conditions of the gloveboxes, meet the needs of the decommissioning team, and to best manage lifecycle costs. Several challenges associated with developing a disposition path that addresses both the radiological and RCRA concerns as well as offering the most cost-effective solution were encountered. These challenges included meeting the radiological waste acceptance criteria of available disposal facilities, making a RCRA determination, evaluating treatment options and costs, addressing void requirements associated with disposal, and identifying packaging and transportation options. The varying disposal facility requirements affected disposition choices. Facility conditions that impacted decisions included radiological and chemical waste acceptance criteria, physical requirements, and measurement for payment options. The facility requirements also impacted onsite activities including management strategies, decontamination activities, and life-cycle cost.

Lobdell, D.; Geimer, R.; Larsen, P.; Loveland, K.

2003-02-27T23:59:59.000Z

150

Field-induced decay of quantum vacuum: visualizing pair production in a classical photonic system  

E-Print Network (OSTI)

The phenomenon of vacuum decay, i.e. electron-positron pair production due to the instability of the quantum electrodynamics vacuum in an external field, is a remarkable prediction of Dirac theory whose experimental observation is still lacking. Here a classic wave optics analogue of vacuum decay, based on light propagation in curved waveguide superlattices, is proposed. Our photonic analogue enables a simple and experimentally-accessible visualization in space of the process of pair production as break up of an initially negative-energy Gaussian wave packet, representing an electron in the Dirac sea, under the influence of an oscillating electric field.

Stefano Longhi

2010-09-01T23:59:59.000Z

151

Matrix Product State and mean field solutions for one-dimensional systems can be found efficiently  

E-Print Network (OSTI)

We consider the problem of approximating ground states of one-dimensional quantum systems within the two most common variational ansatzes, namely the mean field ansatz and Matrix Product States. We show that both for mean field and for Matrix Product States of fixed bond dimension, the optimal solutions can be found in a way which is provably efficient (i.e., scales polynomially). This implies that the corresponding variational methods can be in principle recast in a way which scales provably polynomially. Moreover, our findings imply that ground states of one-dimensional commuting Hamiltonians can be found efficiently.

Norbert Schuch; J. Ignacio Cirac

2010-07-19T23:59:59.000Z

152

TRACKING SURPLUS PLUTONIUM FROM WEAPONS TO DISPOSITION  

SciTech Connect

Supporting nuclear nonproliferation and global security principles, beginning in 1994 the United States has withdrawn more than 50 metric tons (MT) of government-controlled plutonium from potential use in nuclear weapons. The Department of Energy (DOE), including the National Nuclear Security Administration, established protocols for the tracking of this "excess" and "surplus" plutonium, and for reconciling the current storage and utilization of the plutonium to show that its management is consistent with the withdrawal policies. Programs are underway to ensure the safe and secure disposition of the materials that formed a major part of the weapons stockpile during the Cold War, and growing quantities have been disposed as waste, after which they are not included in traditional nuclear material control and accountability (NMC&A) data systems. A combination of resources is used to perform the reconciliations that form the basis for annual reporting to DOE, to U.S. Department of State, and to international partners including the International Atomic Energy Agency.

Allender, J.; Beams, J.; Sanders, K.; Myers, L.

2013-07-16T23:59:59.000Z

153

Unallocated Off-Specification Highly Enriched Uranium: Recommendations for Disposition  

SciTech Connect

The U.S. Department of Energy (DOE) has made significant progress with regard to disposition planning for 174 metric tons (MTU) of surplus Highly Enriched Uranium (HEU). Approximately 55 MTU of this 174 MTU are ''offspec'' HEU. (''Off-spec'' signifies that the isotopic or chemical content of the material does not meet the American Society for Testing and Materials standards for commercial nuclear reactor fuel.) Approximately 33 of the 55 MTU have been allocated to off-spec commercial reactor fuel per an Interagency Agreement between DOE and the Tennessee Valley Authority (1). To determine disposition plans for the remaining {approx}22 MTU, the DOE National Nuclear Security Administration (NNSA) Office of Fissile Materials Disposition (OFMD) and the DOE Office of Environmental Management (EM) co-sponsored this technical study. This paper represents a synopsis of the formal technical report (NNSA/NN-0014). The {approx} 22 MTU of off-spec HEU inventory in this study were divided into two main groupings: one grouping with plutonium (Pu) contamination and one grouping without plutonium. This study identified and evaluated 26 potential paths for the disposition of this HEU using proven decision analysis tools. This selection process resulted in recommended and alternative disposition paths for each group of HEU. The evaluation and selection of these paths considered criteria such as technical maturity, programmatic issues, cost, schedule, and environment, safety and health compliance. The primary recommendations from the analysis are comprised of 7 different disposition paths. The study recommendations will serve as a technical basis for subsequent programmatic decisions as disposition of this HEU moves into the implementation phase.

Bridges, D. N.; Boeke, S. G.; Tousley, D. R.; Bickford, W.; Goergen, C.; Williams, W.; Hassler, M.; Nelson, T.; Keck, R.; Arbital, J.

2002-02-27T23:59:59.000Z

154

Water alternating enriched gas injection to enhance oil production and recovery from San Francisco Field, Colombia  

E-Print Network (OSTI)

The main objectives of this study are to determine the most suitable type of gas for a water-alternating-gas (WAG) injection scheme, the WAG cycle time, and gas injection rate to increase oil production rate and recovery from the San Francisco field...

Rueda Silva, Carlos Fernando

2012-06-07T23:59:59.000Z

155

Dobson Butte field, Williston basin, Stark County, North Dakota: nontypical oil production  

SciTech Connect

The Dobson Butte field (T139N, R96W), Stark County, North Dakota, was discovered in 1982 following a detailed seismic program. Production is primarily from a structural trap in the Interlake Formation of Silurian age. Three oil wells are presently producing from a dolomite reservoir at about 11,000 ft in depth. Primary recoverable reserves of these three producing wells is calculated to be about 2 million bbl of oil. Additional reserves will come from further development of the Interlake reservoir as well as from the deeper Red River (Ordovician) Formation. The Dobson Butte field is a nontypical oil field within the Williston basin as to its high pour point oil (90/sup 0/F), high production water cuts (85-95%), lack of good oil shows in samples, unpredictable noncontinuous oil-producing reservoirs throughout the entire 600-ft Interlake Formation, difficulty in log interpretations, and difficulty in determining the source bed. The interpretation of these nontypical characteristics of Interlake oil production in the Dobson Butte field compared to other Interlake oil production within the Williston basin will have a profound effect upon future Interlake exploration.

Guy, W.J.

1987-05-01T23:59:59.000Z

156

Bases, Assumptions, and Results of the Flowsheet Calculations for the Decision Phase Salt Disposition Alternatives  

SciTech Connect

The High Level Waste (HLW) Salt Disposition Systems Engineering Team was formed on March 13, 1998, and chartered to identify options, evaluate alternatives, and recommend a selected alternative(s) for processing HLW salt to a permitted wasteform. This requirement arises because the existing In-Tank Precipitation process at the Savannah River Site, as currently configured, cannot simultaneously meet the HLW production and Authorization Basis safety requirements. This engineering study was performed in four phases. This document provides the technical bases, assumptions, and results of this engineering study.

Dimenna, R.A.; Jacobs, R.A.; Taylor, G.A.; Durate, O.E.; Paul, P.K.; Elder, H.H.; Pike, J.A.; Fowler, J.R.; Rutland, P.L.; Gregory, M.V.; Smith III, F.G.; Hang, T.; Subosits, S.G.; Campbell, S.G.

2001-03-26T23:59:59.000Z

157

Supply and Disposition of Crude Oil and Petroleum Products  

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

,980 842 4,204 1,948 672 -339 187 3,995 240 4,886 ,980 842 4,204 1,948 672 -339 187 3,995 240 4,886 Crude Oil 1,472 - - - - 1,839 556 -359 17 3,416 76 0 Natural Gas Plant Liquids and Liquefied Refinery Gases 508 -17 115 63 -14 - - 75 105 71 404 Pentanes Plus 63 -17 - - 0 98 - - -18 37 53 72 Liquefied Petroleum Gases 444 - - 115 63 -112 - - 93 68 18 332 Ethane/Ethylene 163 - - - 0 -100 - - 11 - - 52 Propane/Propylene 186 - - 104 49 -22 - - 66 - 7 244 Normal Butane/Butylene 52 - - 16 5 5 - - 22 17 11 29 Isobutane/Isobutylene 43 - - -4 8 5 - - -6 50 - 7 Other Liquids - - 858 - - 12 -143 127 346 474 40 -6 Hydrogen/Oxygenates/Renewables/Other Hydrocarbons - - 858 - - 5 -547 -8 11 271 26 0 Hydrogen - - - - - - 23 - - 23 0 - -

158

Supply and Disposition of Crude Oil and Petroleum Products  

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

25,966 7,956 1,280,301 725,573 1,191,766 9,116 -19,377 1,260,324 25,966 7,956 1,280,301 725,573 1,191,766 9,116 -19,377 1,260,324 90,720 1,909,011 152,389 Crude Oil 9,418 - - - - 316,140 4,126 8,405 -1,574 336,230 3,434 0 8,328 Natural Gas Plant Liquids and Liquefied Refinery Gases 16,548 -84 14,202 18,043 26,704 - - -1,588 7,264 3,052 66,685 6,377 Pentanes Plus 2,828 -84 - - 185 -19 - - 12 63 315 2,520 43 Liquefied Petroleum Gases 13,720 - - 14,202 17,858 26,723 - - -1,600 7,201 2,737 64,165 6,334 Ethane/Ethylene 174 - - 93 - - - - 0 - - 267 - Propane/Propylene 9,223 - - 12,922 16,074 26,601 - - -793 - 1,230 64,383 5,184 Normal Butane/Butylene 2,091 - - 1,435 616 122 - - -866 3,435 1,507 188 837 Isobutane/Isobutylene 2,232 - - -248 1,168 - - - 59 3,766 - -673 313

159

Supply and Disposition of Crude Oil and Petroleum Products  

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

562 822 4,163 1,839 735 -69 52 3,955 244 4,801 562 822 4,163 1,839 735 -69 52 3,955 244 4,801 Crude Oil 1,116 - - - - 1,730 800 -87 62 3,442 55 0 Natural Gas Plant Liquids and Liquefied Refinery Gases 446 -16 121 74 -25 - - -12 105 111 395 Pentanes Plus 50 -16 - - 1 82 - - -4 31 101 -12 Liquefied Petroleum Gases 396 - - 121 73 -107 - - -8 74 11 407 Ethane/Ethylene 163 - - - 0 -108 - - -2 - - 58 Propane/Propylene 156 - - 108 59 -24 - - -3 - 2 300 Normal Butane/Butylene 48 - - 11 9 10 - - -4 29 9 45 Isobutane/Isobutylene 29 - - 2 6 14 - - 1 46 - 5 Other Liquids - - 838 - - 5 -258 -159 8 408 25 -16 Hydrogen/Oxygenates/Renewables/Other Hydrocarbons - - 838 - - 3 -565 4 1 257 21 0 Hydrogen - - - - - - 22 - - 22 0 - -

160

Supply and Disposition of Crude Oil and Petroleum Products  

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

3,707 661 107,540 52,842 98,737 3,513 -4,105 105,957 7,218 3,707 661 107,540 52,842 98,737 3,513 -4,105 105,957 7,218 157,931 153,902 Crude Oil 1,020 - - - - 26,908 20 3,378 -1,285 32,517 94 0 10,326 Natural Gas Plant Liquids and Liquefied Refinery Gases 2,687 -11 747 945 2,568 - - 471 798 453 5,214 6,541 Pentanes Plus 443 -11 - - - - - - 2 - 300 130 82 Liquefied Petroleum Gases 2,244 - - 747 945 2,568 - - 469 798 153 5,084 6,459 Ethane/Ethylene 27 - - 9 - - - - 6 - - 30 15 Propane/Propylene 1,517 - - 1,078 813 2,483 - - 724 - 126 5,041 4,442 Normal Butane/Butylene 474 - - -333 80 85 - - -246 523 27 2 1,673 Isobutane/Isobutylene 226 - - -7 52 - - - -15 275 - 11 329 Other Liquids - - 672 - - 16,653 48,432 5,798 -936 72,642 156 -307 61,003

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


161

Supply and Disposition of Crude Oil and Petroleum Products  

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

429,215 5,872 1,093,588 483,473 118,666 38,688 7,789 1,028,754 429,215 5,872 1,093,588 483,473 118,666 38,688 7,789 1,028,754 126,026 1,006,933 150,671 Crude Oil 406,791 - - - - 424,639 598 22,523 1,445 853,106 0 0 56,432 Natural Gas Plant Liquids and Liquefied Refinery Gases 22,424 -123 18,260 1,933 - - - 404 24,108 5,319 12,663 4,734 Pentanes Plus 10,215 -123 - - - - - - -20 7,565 1,094 1,453 51 Liquefied Petroleum Gases 12,209 - - 18,260 1,933 - - - 424 16,543 4,225 11,210 4,683 Ethane/Ethylene 34 - - - - - - - - - - 34 - Propane/Propylene 4,422 - - 16,669 1,593 - - - 335 - 3,714 18,635 1,915 Normal Butane/Butylene 2,360 - - 2,258 332 - - - 129 9,346 512 -5,037 2,249 Isobutane/Isobutylene 5,393 - - -667 8 - - - -40 7,197 - -2,423 519

162

Supply and Disposition of Crude Oil and Petroleum Products  

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

302,630 5,088 230,918 121,366 -164,290 -11,531 4,472 221,774 5,269 302,630 5,088 230,918 121,366 -164,290 -11,531 4,472 221,774 5,269 252,667 39,043 Crude Oil 163,870 - - - - 115,845 -53,264 -13,771 3,101 209,575 5 0 18,928 Natural Gas Plant Liquids and Liquefied Refinery Gases 138,760 -110 3,391 3,503 -119,108 - - 94 6,946 4,261 15,135 1,470 Pentanes Plus 18,508 -110 - - - -13,355 - - 14 2,156 3,795 -922 194 Liquefied Petroleum Gases 120,252 - - 3,391 3,503 -105,753 - - 80 4,790 466 16,057 1,276 Ethane/Ethylene 63,265 - - - - -61,214 - - -6 - - 2,057 400 Propane/Propylene 36,541 - - 3,406 3,155 -28,078 - - 7 - 12 15,005 363 Normal Butane/Butylene 15,114 - - 294 255 -9,019 - - 88 2,241 455 3,860 366 Isobutane/Isobutylene 5,332 - - -309 93 -7,442 - - -9 2,549 - -4,866 147

163

Supply and Disposition of Crude Oil and Petroleum Products  

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

315,006 29,943 578,101 299,380 14,453 11,088 543,388 108,925 315,006 29,943 578,101 299,380 14,453 11,088 543,388 108,925 573,483 1,831,621 Crude Oil 233,810 - - - - 237,344 8,334 7,688 468,825 2,975 0 1,067,149 Natural Gas Plant Liquids and Liquefied Refinery Gases 81,196 -552 19,023 4,020 - - 3,027 16,794 13,937 69,929 189,672 Pentanes Plus 11,167 -552 - - 772 - - -700 5,666 2,989 3,432 18,036 Liquefied Petroleum Gases 70,029 - - 19,023 3,248 - - 3,727 11,128 10,947 66,498 171,636 Ethane/Ethylene 30,015 - - 379 9 - - -414 - - 30,817 34,444 Propane/Propylene 25,545 - - 17,254 2,603 - - 2,582 - 10,040 32,780 67,782 Normal Butane/Butylene 6,893 - - 1,738 333 - - 999 4,711 907 2,347 58,942 Isobutane/Isobutylene 7,576 - - -348 303 - - 560 6,417 - 554 10,468

164

Supply and Disposition of Crude Oil and Petroleum Products  

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

8,897 964 18,564 10,598 335 158 17,505 3,205 18,490 8,897 964 18,564 10,598 335 158 17,505 3,205 18,490 Crude Oil 6,489 - - - - 8,527 144 93 14,999 67 0 Natural Gas Plant Liquids and Liquefied Refinery Gases 2,408 -18 630 170 - - 65 509 314 2,301 Pentanes Plus 317 -18 - - 29 - - -13 174 118 50 Liquefied Petroleum Gases 2,091 - - 630 141 - - 79 335 196 2,251 Ethane/Ethylene 974 - - 18 0 - - 34 - - 958 Propane/Propylene 712 - - 553 116 - - 36 - 171 1,175 Normal Butane/Butylene 179 - - 56 15 - - 5 143 26 77 Isobutane/Isobutylene 225 - - 3 9 - - 4 192 - 41 Other Liquids - - 981 - - 1,257 53 51 1,997 214 28 Hydrogen/Oxygenates/Renewables/Other Hydrocarbons - - 981 - - 40 151 5 1,050 116 0 Hydrogen - - - - - - 190 - - 190 0 - -

165

Supply and Disposition of Crude Oil and Petroleum Products  

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

71 22 3,498 1,982 3,256 25 -53 3,444 248 5,216 71 22 3,498 1,982 3,256 25 -53 3,444 248 5,216 Crude Oil 26 - - - - 864 11 23 -4 919 9 0 Natural Gas Plant Liquids and Liquefied Refinery Gases 45 0 39 49 73 - - -4 20 8 182 Pentanes Plus 8 0 - - 1 0 - - 0 0 1 7 Liquefied Petroleum Gases 37 - - 39 49 73 - - -4 20 7 175 Ethane/Ethylene 0 - - 0 - - - - 0 - - 1 Propane/Propylene 25 - - 35 44 73 - - -2 - 3 176 Normal Butane/Butylene 6 - - 4 2 0 - - -2 9 4 1 Isobutane/Isobutylene 6 - - -1 3 - - - 0 10 - -2 Other Liquids - - 22 - - 717 1,611 114 -5 2,505 10 -47 Hydrogen/Oxygenates/Renewables/Other Hydrocarbons - - 22 - - 29 291 -9 3 324 6 0 Hydrogen - - - - - - 4 - - 4 0 - - Oxygenates (excl. Fuel Ethanol) - - - - 0 - 0 0

166

Supply and Disposition of Crude Oil and Petroleum Products  

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

34,932 594 95,116 42,741 9,239 5,791 830 89,707 10,470 87,406 34,932 594 95,116 42,741 9,239 5,791 830 89,707 10,470 87,406 142,840 Crude Oil 33,114 - - - - 36,279 - 4,213 311 73,295 - 0 52,719 Natural Gas Plant Liquids and Liquefied Refinery Gases 1,818 -8 1,970 134 - - - 1,076 1,782 396 660 8,270 Pentanes Plus 794 -8 - - - - - - 163 552 92 -21 314 Liquefied Petroleum Gases 1,024 - - 1,970 134 - - - 913 1,230 304 681 7,956 Ethane/Ethylene 3 - - - - - - - - - - 3 - Propane/Propylene 420 - - 1,475 124 - - - 374 - 299 1,346 2,272 Normal Butane/Butylene 158 - - 451 10 - - - 378 556 5 -320 5,110 Isobutane/Isobutylene 443 - - 44 - - - - 161 674 - -348 574 Other Liquids - - 602 - - 3,200 7,556 2,809 -2,126 14,630 387 1,276 46,625

167

Supply and Disposition of Crude Oil and Petroleum Products  

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

3,256,148 352,785 6,794,407 3,878,852 122,574 57,691 6,406,693 3,256,148 352,785 6,794,407 3,878,852 122,574 57,691 6,406,693 1,172,965 6,767,418 1,807,777 Crude Oil 2,374,842 - - - - 3,120,755 52,746 34,134 5,489,516 24,693 0 1,060,764 Natural Gas Plant Liquids and Liquefied Refinery Gases 881,306 -6,534 230,413 62,192 - - 23,894 186,270 115,054 842,159 153,268 Pentanes Plus 116,002 -6,534 - - 10,680 - - -4,857 63,596 43,136 18,273 12,739 Liquefied Petroleum Gases 765,304 - - 230,413 51,512 - - 28,751 122,674 71,918 823,886 140,529 Ethane/Ethylene 356,592 - - 6,597 115 - - 12,504 - - 350,800 35,396 Propane/Propylene 260,704 - - 202,309 42,460 - - 13,013 - 62,490 429,970 67,991 Normal Butane/Butylene 65,555 - - 20,580 5,567 - - 1,795 52,246 9,428 28,233 28,574

168

Natural Gas Dry Production (Annual Supply & Disposition)  

Gasoline and Diesel Fuel Update (EIA)

19,266,026 20,158,602 20,623,854 21,315,507 22,901,879 24,057,609 19,266,026 20,158,602 20,623,854 21,315,507 22,901,879 24,057,609 1930-2012 Federal Offshore Gulf of Mexico 2,798,718 2,314,342 2,428,916 2,245,062 1,812,328 1,423,239 1999-2012 Alabama 250,576 240,662 218,797 203,873 178,310 208,600 1982-2012 Alaska 407,153 374,105 374,152 353,391 334,671 329,789 1982-2012 Arizona 655 523 712 183 168 117 1982-2012 Arkansas 269,724 446,318 679,784 926,426 1,071,944 1,145,744 1982-2012 California 293,639 282,497 262,853 273,597 238,082 234,067 1982-2012 Colorado 1,204,391 1,335,809 1,431,463 1,495,742 1,546,775 1,627,433 1982-2012 Florida 1,646 2,414 257 12,409 15,125 18,681 1982-2012 Illinois 1,346 1,151 1,412 1,357 1,078 2,125 1982-2012 Indiana 3,606 4,701 4,927 6,802 9,075 8,814 1982-2012

169

Natural Gas Dry Production (Annual Supply & Disposition)  

Gasoline and Diesel Fuel Update (EIA)

055,938 1,990,431 2,075,702 2,076,287 1,990,290 2,076,796 055,938 1,990,431 2,075,702 2,076,287 1,990,290 2,076,796 1997-2013 Federal Offshore Gulf of Mexico NA NA NA NA NA NA 2006-2013 Alabama NA NA NA NA NA NA 2006-2013 Alaska NA NA NA NA NA NA 2006-2013 Arizona NA NA NA NA NA NA 2006-2013 Arkansas NA NA NA NA NA NA 2006-2013 California NA NA NA NA NA NA 2006-2013 Colorado NA NA NA NA NA NA 2006-2013 Florida NA NA NA NA NA NA 2006-2013 Illinois NA NA NA NA NA NA 2006-2013 Indiana NA NA NA NA NA NA 2006-2013 Kansas NA NA NA NA NA NA 2006-2013 Kentucky NA NA NA NA NA NA 2006-2013 Louisiana NA NA NA NA NA NA 2006-2013 Maryland NA NA NA NA NA NA 2006-2013 Michigan NA NA NA NA NA NA 2006-2013 Mississippi NA NA NA NA NA NA 2006-2013 Missouri

170

Supply and Disposition of Crude Oil and Petroleum Products  

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

124 22 3,585 1,761 3,291 117 -137 3,532 241 5,264 124 22 3,585 1,761 3,291 117 -137 3,532 241 5,264 Crude Oil 34 - - - - 897 1 113 -43 1,084 3 0 Natural Gas Plant Liquids and Liquefied Refinery Gases 90 0 25 32 86 - - 16 27 15 174 Pentanes Plus 15 0 - - - - - - 0 - 10 4 Liquefied Petroleum Gases 75 - - 25 32 86 - - 16 27 5 169 Ethane/Ethylene 1 - - 0 - - - - 0 - - 1 Propane/Propylene 51 - - 36 27 83 - - 24 - 4 168 Normal Butane/Butylene 16 - - -11 3 3 - - -8 17 1 0 Isobutane/Isobutylene 8 - - 0 2 - - - -1 9 - 0 Other Liquids - - 22 - - 555 1,614 193 -31 2,421 5 -10 Hydrogen/Oxygenates/Renewables/Other Hydrocarbons - - 22 - - 25 273 -19 -35 332 5 0 Hydrogen - - - - - - 4 - - 4 0 - - Oxygenates (excl. Fuel Ethanol)

171

Supply and Disposition of Crude Oil and Petroleum Products  

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

59,397 25,268 126,131 58,449 20,168 -10,157 5,610 119,848 7,211 59,397 25,268 126,131 58,449 20,168 -10,157 5,610 119,848 7,211 146,586 280,571 Crude Oil 44,167 - - - - 55,181 16,673 -10,758 505 102,476 2,282 0 102,610 Natural Gas Plant Liquids and Liquefied Refinery Gases 15,230 -515 3,462 1,887 -432 - - 2,252 3,146 2,129 12,105 58,830 Pentanes Plus 1,896 -515 - - 6 2,928 - - -549 1,119 1,599 2,146 7,743 Liquefied Petroleum Gases 13,334 - - 3,462 1,881 -3,360 - - 2,801 2,027 530 9,959 51,087 Ethane/Ethylene 4,901 - - - 9 -3,013 - - 339 - - 1,558 4,694 Propane/Propylene 5,587 - - 3,111 1,470 -650 - - 1,991 - 199 7,328 24,444 Normal Butane/Butylene 1,561 - - 475 162 156 - - 651 514 331 858 20,078 Isobutane/Isobutylene 1,285 - - -124 240 147 - - -180 1,513 - 215 1,871

172

Supply and Disposition of Crude Oil and Petroleum Products  

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

1,164 20 3,171 1,425 308 193 28 2,990 349 2,914 1,164 20 3,171 1,425 308 193 28 2,990 349 2,914 Crude Oil 1,104 - - - - 1,209 - 140 10 2,443 - 0 Natural Gas Plant Liquids and Liquefied Refinery Gases 61 0 66 4 - - - 36 59 13 22 Pentanes Plus 26 0 - - - - - - 5 18 3 -1 Liquefied Petroleum Gases 34 - - 66 4 - - - 30 41 10 23 Ethane/Ethylene 0 - - - - - - - - - - 0 Propane/Propylene 14 - - 49 4 - - - 12 - 10 45 Normal Butane/Butylene 5 - - 15 0 - - - 13 19 0 -11 Isobutane/Isobutylene 15 - - 1 - - - - 5 22 - -12 Other Liquids - - 20 - - 107 252 94 -71 488 13 43 Hydrogen/Oxygenates/Renewables/Other Hydrocarbons - - 20 - - 19 143 37 -2 219 3 0 Hydrogen - - - - - - 47 - - 47 0 - - Oxygenates (excl. Fuel Ethanol)

173

Natural Gas Dry Production (Annual Supply & Disposition)  

Gasoline and Diesel Fuel Update (EIA)

Monthly Annual Monthly Annual Download Series History Download Series History Definitions, Sources & Notes Definitions, Sources & Notes Show Data By: Data Series Area 2007 2008 2009 2010 2011 2012 View History U.S. 19,266,026 20,158,602 20,623,854 21,315,507 22,901,879 24,057,609 1930-2012 Alabama 250,576 240,662 218,797 203,873 178,310 208,600 1982-2012 Alaska 407,153 374,105 374,152 353,391 334,671 329,789 1982-2012 Arizona 655 523 712 183 168 117 1982-2012 Arkansas 269,724 446,318 679,784 926,426 1,071,944 1,145,744 1982-2012 California 293,639 282,497 262,853 273,597 238,082 234,067 1982-2012 Colorado 1,204,391 1,335,809 1,431,463 1,495,742 1,546,775 1,627,433 1982-2012 Florida 1,646 2,414 257 12,409 15,125 18,681 1982-2012

174

Supply and Disposition of Crude Oil and Petroleum Products  

Gasoline and Diesel Fuel Update (EIA)

29,654 457 22,655 9,757 -11,830 -4,359 1,022 22,083 459 22,770 40,249 Crude Oil 19,044 - - - - 9,297 -4,312 -4,561 -451 19,787 132 0 20,405 Natural Gas Plant Liquids and Liquefied...

175

Supply and Disposition of Crude Oil and Petroleum Products  

Annual Energy Outlook 2012 (EIA)

957 15 731 315 -382 -141 33 712 15 735 Crude Oil 614 - - - - 300 -139 -147 -15 638 4 0 Natural Gas Plant Liquids and Liquefied Refinery Gases 342 0 21 11 -304 - - 14 19 9 29...

176

Supply and Disposition of Crude Oil and Petroleum Products  

Gasoline and Diesel Fuel Update (EIA)

7,134 78 8,072 4,027 -3,603 366 34 7,401 3,285 5,354 Crude Oil 5,259 - - - - 3,454 -222 227 -164 8,685 198 0 Natural Gas Plant Liquids and Liquefied Refinery Gases 1,875 0 534 1...

177

Supply and Disposition of Crude Oil and Petroleum Products  

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

2,416 250,220 124,827 -111,703 11,357 1,044 229,444 101,831 165,961 1,223,681 Crude Oil 163,028 - - - - 107,081 -6,891 7,037 -5,099 269,223 6,132 0 882,888 Natural Gas Plant...

178

Supply and Disposition of Crude Oil and Petroleum Products  

Annual Energy Outlook 2012 (EIA)

848 14 646 310 -422 -51 0 622 15 707 Crude Oil 527 - - - - 296 -183 -57 3 578 2 0 Natural Gas Plant Liquids and Liquefied Refinery Gases 320 0 11 11 -265 - - 1 17 12 48 Pentanes...

179

Supply and Disposition of Crude Oil and Petroleum Products  

Annual Energy Outlook 2012 (EIA)

6,046 98 7,569 4,450 -3,757 434 -42 6,943 2,694 5,247 Crude Oil 4,384 - - - - 3,691 -391 312 6 7,952 37 0 Natural Gas Plant Liquids and Liquefied Refinery Gases 1,663 0 411 35 165...

180

Supply and Disposition of Crude Oil and Petroleum Products  

Gasoline and Diesel Fuel Update (EIA)

200 1,135 3,879 PADD 1 348 127 739 13 -111 76 1,263 PADD 2 1,085 5 232 22 58 3 1,284 PADD 3 2,727 - -1,005 14 146 871 719 PADD 4 222 0 -4 2 27 - 194 PADD 5 630 4 38 14 81 185 420...

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


181

Supply and Disposition of Crude Oil and Petroleum Products  

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

1,173 16 2,988 1,321 324 106 21 2,811 344 2,751 1,173 16 2,988 1,321 324 106 21 2,811 344 2,751 Crude Oil 1,111 - - - - 1,160 2 62 4 2,331 0 0 Natural Gas Plant Liquids and Liquefied Refinery Gases 61 0 50 5 - - - 1 66 15 35 Pentanes Plus 28 0 - - - - - - 0 21 3 4 Liquefied Petroleum Gases 33 - - 50 5 - - - 1 45 12 31 Ethane/Ethylene 0 - - - - - - - - - - 0 Propane/Propylene 12 - - 46 4 - - - 1 - 10 51 Normal Butane/Butylene 6 - - 6 1 - - - 0 26 1 -14 Isobutane/Isobutylene 15 - - -2 0 - - - 0 20 - -7 Other Liquids - - 16 - - 74 245 103 11 414 13 1 Hydrogen/Oxygenates/Renewables/Other Hydrocarbons - - 16 - - 7 138 37 2 193 3 0 Hydrogen - - - - - - 43 - - 43 0 - - Oxygenates (excl. Fuel Ethanol) - - - - 1 1 0

182

Supply and Disposition of Crude Oil and Petroleum Products  

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

571,552 300,900 1,523,608 673,109 268,869 -25,130 18,853 1,447,490 571,552 300,900 1,523,608 673,109 268,869 -25,130 18,853 1,447,490 89,370 1,757,194 287,201 Crude Oil 408,314 - - - - 633,223 292,624 -31,767 22,602 1,259,826 19,966 0 115,743 Natural Gas Plant Liquids and Liquefied Refinery Gases 163,238 -6,037 44,417 27,019 -9,288 - - -4,496 38,476 40,729 144,640 43,693 Pentanes Plus 18,229 -6,037 - - 213 29,889 - - -1,599 11,319 36,827 -4,253 6,686 Liquefied Petroleum Gases 145,009 - - 44,417 26,806 -39,177 - - -2,897 27,157 3,902 148,893 37,007 Ethane/Ethylene 59,649 - - - 115 -39,435 - - -716 - - 21,045 3,590 Propane/Propylene 57,022 - - 39,605 21,464 -8,812 - - -1,114 - 580 109,813 22,020 Normal Butane/Butylene 17,564 - - 4,181 3,156 3,807 - - -1,354 10,449 3,322 16,291

183

Supply and Disposition of Crude Oil and Petroleum Products  

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

926,785 32,969 2,665,992 1,875,331 -1,415,011 111,431 45,954 926,785 32,969 2,665,992 1,875,331 -1,415,011 111,431 45,954 2,448,351 861,579 1,841,613 1,178,473 Crude Oil 1,386,449 - - - - 1,630,908 -244,084 67,355 8,560 2,830,779 1,288 0 861,333 Natural Gas Plant Liquids and Liquefied Refinery Gases 540,336 -180 150,143 11,694 101,692 - - 29,480 109,476 61,693 603,036 96,994 Pentanes Plus 66,222 -180 - - 10,282 -16,515 - - -3,264 42,493 1,105 19,475 5,765 Liquefied Petroleum Gases 474,114 - - 150,143 1,412 118,207 - - 32,744 66,983 60,588 583,561 91,229 Ethane/Ethylene 233,470 - - 6,504 - 100,649 - - 13,226 - - 327,397 31,406 Propane/Propylene 153,496 - - 129,707 174 10,289 - - 14,578 - 56,954 222,134 38,509 Normal Butane/Butylene 28,426 - - 12,412 1,208 5,090 - - 3,798 26,775 3,633 12,930

184

Supply and Disposition of Crude Oil and Petroleum Products  

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

10,500 998 19,270 9,979 482 370 18,113 3,631 19,116 10,500 998 19,270 9,979 482 370 18,113 3,631 19,116 Crude Oil 7,794 - - - - 7,911 278 256 15,628 99 0 Natural Gas Plant Liquids and Liquefied Refinery Gases 2,707 -18 634 134 - - 101 560 465 2,331 Pentanes Plus 372 -18 - - 26 - - -23 189 100 114 Liquefied Petroleum Gases 2,334 - - 634 108 - - 124 371 365 2,217 Ethane/Ethylene 1,001 - - 13 0 - - -14 - - 1,027 Propane/Propylene 852 - - 575 87 - - 86 - 335 1,093 Normal Butane/Butylene 230 - - 58 11 - - 33 157 30 78 Isobutane/Isobutylene 253 - - -12 10 - - 19 214 - 18 Other Liquids - - 1,015 - - 1,337 296 304 1,926 219 199 Hydrogen/Oxygenates/Renewables/Other Hydrocarbons - - 1,015 - - 75 121 -36 1,129 118 0 Hydrogen - - - - - - 208 - - 208 0 - -

185

FUEL CYCLE POTENTIAL WASTE FOR DISPOSITION  

SciTech Connect

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

Carter, J.

2011-01-03T23:59:59.000Z

186

FUEL CYCLE POTENTIAL WASTE FOR DISPOSITION  

SciTech Connect

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

Jones, R.; Carter, J.

2010-10-13T23:59:59.000Z

187

Quantum field theory in curved spacetime, the operator product expansion, and dark energy  

E-Print Network (OSTI)

To make sense of quantum field theory in an arbitrary (globally hyperbolic) curved spacetime, the theory must be formulated in a local and covariant manner in terms of locally measureable field observables. Since a generic curved spacetime does not possess symmetries or a unique notion of a vacuum state, the theory also must be formulated in a manner that does not require symmetries or a preferred notion of a ``vacuum state'' and ``particles''. We propose such a formulation of quantum field theory, wherein the operator product expansion (OPE) of the quantum fields is elevated to a fundamental status, and the quantum field theory is viewed as being defined by its OPE. Since the OPE coefficients may be better behaved than any quantities having to do with states, we suggest that it may be possible to perturbatively construct the OPE coefficients--and, thus, the quantum field theory. By contrast, ground/vacuum states--in spacetimes, such as Minkowski spacetime, where they may be defined--cannot vary analytically with the parameters of the theory. We argue that this implies that composite fields may acquire nonvanishing vacuum state expectation values due to nonperturbative effects. We speculate that this could account for the existence of a nonvanishing vacuum expectation value of the stress-energy tensor of a quantum field occurring at a scale much smaller than the natural scales of the theory.

S. Hollands; R. M. Wald

2008-05-22T23:59:59.000Z

188

EM Makes Significant Progress on Dispositioning Transuranic Waste at Idaho  

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

EM Makes Significant Progress on Dispositioning Transuranic Waste EM Makes Significant Progress on Dispositioning Transuranic Waste at Idaho Site EM Makes Significant Progress on Dispositioning Transuranic Waste at Idaho Site December 24, 2013 - 12:00pm Addthis Workers treat sludge-bearing, transuranic waste from the Advanced Mixed Waste Treatment Project. Workers treat sludge-bearing, transuranic waste from the Advanced Mixed Waste Treatment Project. A tank at the Materials and Fuels Complex containing residual sodium is moved prior to waste treatment. A tank at the Materials and Fuels Complex containing residual sodium is moved prior to waste treatment. Distillation equipment is shown prior to transport to the Idaho site. Distillation equipment is shown prior to transport to the Idaho site. In these 2010 photographs, unexploded ordnance were collected and then detonated onsite at the Mass Detonation Area.

189

EA-1290: Disposition of Russian Federation Titled Natural Uranium |  

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

290: Disposition of Russian Federation Titled Natural Uranium 290: Disposition of Russian Federation Titled Natural Uranium EA-1290: Disposition of Russian Federation Titled Natural Uranium SUMMARY This EA evaluates the potential environmental impacts of a proposal to transport up to an average of 9,000 metric tons per year of natural uranium as uranium hexafluoride (UF6) from the United States to the Russian Federation. This amount of uranium is equivalent to 13,3000 metric tons of UF6. The EA also examines the impacts of this action on the global commons. Transfer of natural UF6 to the Russian Federation is part of a joint U.S./Russian program to dispose of highly enriched uranium (HEU) from dismantled Russian nuclear weapons. PUBLIC COMMENT OPPORTUNITIES None available at this time. DOCUMENTS AVAILABLE FOR DOWNLOAD

190

EA-1599: Disposition of Radioactively Contaminated Nickel Located at the  

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

99: Disposition of Radioactively Contaminated Nickel Located 99: Disposition of Radioactively Contaminated Nickel Located at the East Tennessee Technology Park, Oak Ridge, Tennessee, and the Paducah Gaseous Diffusion Plant, Paducah, Kentucky, for Controlled Radiological Applications EA-1599: Disposition of Radioactively Contaminated Nickel Located at the East Tennessee Technology Park, Oak Ridge, Tennessee, and the Paducah Gaseous Diffusion Plant, Paducah, Kentucky, for Controlled Radiological Applications Summary This EA was being prepared to evaluate potential environmental impacts of a proposal to dispose of nickel scrap that is volumetrically contaminated with radioactive materials and that DOE recovered from equipment it had used in uranium enrichment. This EA is on hold. Public Comment Opportunities No public comment opportunities at this time.

191

Savannah River Site Achieves Transuranic Waste Disposition Goal in 2013 |  

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

Savannah River Site Achieves Transuranic Waste Disposition Goal in Savannah River Site Achieves Transuranic Waste Disposition Goal in 2013 Savannah River Site Achieves Transuranic Waste Disposition Goal in 2013 December 24, 2013 - 12:00pm Addthis Workers gather behind a “Safety and Security begins with Me” banner at the Savannah River Site. Workers gather behind a "Safety and Security begins with Me" banner at the Savannah River Site. Workers sort through transuranic waste at the Savannah River Site. Workers sort through transuranic waste at the Savannah River Site. SRR employees Glenn Kelly and Fred Merriweather pour the final amount of grout into Tank 6. SRR employees Glenn Kelly and Fred Merriweather pour the final amount of grout into Tank 6. Workers gather behind a "Safety and Security begins with Me" banner at the Savannah River Site.

192

EM Makes Significant Progress on Dispositioning Transuranic Waste at Idaho  

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

EM Makes Significant Progress on Dispositioning Transuranic Waste EM Makes Significant Progress on Dispositioning Transuranic Waste at Idaho Site EM Makes Significant Progress on Dispositioning Transuranic Waste at Idaho Site December 24, 2013 - 12:00pm Addthis Workers treat sludge-bearing, transuranic waste from the Advanced Mixed Waste Treatment Project. Workers treat sludge-bearing, transuranic waste from the Advanced Mixed Waste Treatment Project. A tank at the Materials and Fuels Complex containing residual sodium is moved prior to waste treatment. A tank at the Materials and Fuels Complex containing residual sodium is moved prior to waste treatment. Distillation equipment is shown prior to transport to the Idaho site. Distillation equipment is shown prior to transport to the Idaho site. In these 2010 photographs, unexploded ordnance were collected and then detonated onsite at the Mass Detonation Area.

193

Used Fuel Disposition Research & Development | Department of Energy  

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

Used Fuel Disposition Used Fuel Disposition Research & Development Used Fuel Disposition Research & Development A typical spent nuclear fuel cask sitting on a railcar. Since the early 1960s, the United States has safely conducted more than 3,000 shipments of used nuclear fuel without any harmful release of radioactive material. A typical spent nuclear fuel cask sitting on a railcar. Since the early 1960s, the United States has safely conducted more than 3,000 shipments of used nuclear fuel without any harmful release of radioactive material. In order to assure the development of a sustainable nuclear fuel cycle for the nation's energy future, to provide a sound technical basis for implementation of a new national policy for managing the back end of the nuclear fuel cycle, and to better understand, assess, and communicate the

194

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

195

Paducah Demolition Debris Shipped for Disposition | Department of Energy  

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

Demolition Debris Shipped for Disposition Demolition Debris Shipped for Disposition Paducah Demolition Debris Shipped for Disposition August 27, 2013 - 12:00pm Addthis The first five-car section of demolition debris from the C-340 Metals Plant leaves July 15 from the Paducah site. The first five-car section of demolition debris from the C-340 Metals Plant leaves July 15 from the Paducah site. A P&L locomotive travels near Woodville Road, south of the Paducah site, with the waste shipment in tow. A P&L locomotive travels near Woodville Road, south of the Paducah site, with the waste shipment in tow. The first five-car section of demolition debris from the C-340 Metals Plant leaves July 15 from the Paducah site. A P&L locomotive travels near Woodville Road, south of the Paducah site, with the waste shipment in tow.

196

The onset of insecticide resistance among field populations of stored-product insects  

Science Journals Connector (OSTI)

The reasons are discussed for the relatively slow onset of resistance of stored-product insects to insecticides under practical conditions. Several workers have shown by laboratory selection procedures that at least five species can develop significant levels of resistance to contact insecticides or fumigants. Recent work on field samples of beetles sent to the Pest Infestation Laboratory has revealed that 18 out of 25 so far tested have levels of resistance from ×2 to ×60. Eight species are now known to have developed some degree of resistance to nine insecticides. The standardization of test methods among workers on stored-product insects is badly needed.

E.A. Parkin

1965-01-01T23:59:59.000Z

197

Fissile material disposition program final immobilization form assessment and recommendation  

SciTech Connect

Lawrence Livermore National Laboratory (LLNL), in its role as the lead laboratory for the development of plutonium immobilization technologies for the Department of Energy`s Office of Fissile Materials Disposition (MD), has been requested by MD to recommend an immobilization technology for the disposition of surplus weapons- usable plutonium. The recommendation and supporting documentation was requested to be provided by September 1, 1997. This report addresses the choice between glass and ceramic technologies for immobilizing plutonium using the can-in-canister approach. Its purpose is to provide a comparative evaluation of the two candidate technologies and to recommend a form based on technical considerations.

Cochran, S.G.; Dunlop, W.H.; Edmunds, T.A.; MacLean, L.M.; Gould, T.H. [Westinghouse Savannah River Co., Aiken, SC (United States)

1997-10-03T23:59:59.000Z

198

Open-Source LCA Tool for Estimating Greenhouse Gas Emissions from Crude Oil Production Using Field Characteristics  

Science Journals Connector (OSTI)

Open-Source LCA Tool for Estimating Greenhouse Gas Emissions from Crude Oil Production Using Field Characteristics ... OPGEE models oil production emissions in more detail than previous transport LCA models. ... El-Houjeiri, H. and Brandt, A.Exploring the variation of GHG emissions from conventional oil production using an engineering-based LCA model. ...

Hassan M. El-Houjeiri; Adam R. Brandt; James E. Duffy

2013-05-01T23:59:59.000Z

199

NEPA Cases Filed in 2010 2010 NEPA Case Dispositions  

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

Filed in 2010 2010 NEPA Case Dispositions Filed in 2010 2010 NEPA Case Dispositions Lead Defendant Cases Filed Injunctions - Remands Judgment for defendant 46 ARMY-USACE 6 3 Dismissal w/o settlement 11 DHS-USCG 0 0 Settlement 8 DOD 1 0 Adverse dispositions: 17 DOE-Energy 0 0 TRO 0 DOE-FERC 0 0 Preliminary Injunction 5 DOE-NNSA 1 0 Permanent Injunction 4 DOI-BIA 1 0 Remand 8 DOI-BLM 17 5 DOI-BOEM 5 0 Basis for 2010 NEPA Dispositions DOI-BOR 0 0 Jurisdictional - P prevailed 0 DOI-FWS 6 1 Jurisdictional - D prevailed 12 DOI-OSM 0 1 NEPA - Not required 1 DOI-NPS 2 2 NEPA - Is required 2 DOJ 0 0 CE - Adequate 4 DOS 0 0 CE - Not Adequate 1 DOT-FAA 3 0 EA - Adequate* 11 DOT-FHWA 10 1 EA - Not Adequate* 5 DOT-FTA 2 0 EIS - Adequate* 17 EPA 1 0 EIS - Not Adequate* 5

200

MINIMIZING WASTE AND COST IN DISPOSITION OF LEGACY RESIDUES  

SciTech Connect

Research is being conducted at the Los Alamos National Laboratory (LANL) which is directed toward development of a quantitative basis for disposition of actinide-bearing process residues (both legacy residues and residues generated from ongoing programmatic operations). This research is focused in two directions: (1) identifying minimum negative consequence (waste, dose, cost) dispositions working within regulatory safeguards termination criteria, and (2) evaluating logistics/consequences of across-the-board residue discards such as authorized at Rocky Flats under a safeguards termination variance. The first approach emphasizes Laboratory commitments to environmental stewardship, worker safety, and fiscal responsibility. This approach has been described as the Plutonium Disposition Methodology (PDM) in deference to direction provided by DOE Albuquerque. The second approach is born of the need to expedite removal of residues from storage for programmatic and reasons and residue storage safety concerns. Any disposition path selected must preserve the legal distinction between residues as Special Nuclear Material (SNM) and discardable materials as waste in order to insure the continuing viability of Laboratory plutonium processing facilities for national security operations.

J. BALKEY; M. ROBINSON

2001-05-01T23:59:59.000Z

Note: This page contains sample records for the topic "disposition field production" 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

Shapiro-like resonance in ultracold molecule production via an oscillating magnetic field  

SciTech Connect

We study the process of the production of ultracold molecules from ultracold atoms using a sinusoidally oscillating magnetic-field modulation. Our study is based on a two-mode mean-field treatment of the problem. When the magnetic field is resonant roughly with the molecular binding energy, Shapiro-like resonances are observed. Their resonance profiles are well fitted by the Lorentzian functions. The linewidths depend on both the amplitude and the duration of the applied modulations and are found to be dramatically broadened by the thermal dephasing effect. The resonance centers shift due to both the many-body effect and the finite temperature effect. Our theory is consistent with a recent experiment [S. T. Thompson, E. Hodby, and C. E. Wieman, Phys. Rev. Lett. 95, 190404 (2005)]. Our model predicts a 1/3 ceiling for the molecular production yield in uncondensed ultracold atomic clouds for a long coupling time, while for condensed atoms the optimal conversion yield could be beyond the limit.

Liu Bin [Institute of Applied Physics and Computational Mathematics, Beijing 100088 (China); Graduate School, China Academy of Engineering Physics, Beijing 100088 (China); Fu Libin; Liu Jie [Institute of Applied Physics and Computational Mathematics, Beijing 100088 (China); Center for Applied Physics and Technology, Peking University, Beijing 100084 (China)

2010-01-15T23:59:59.000Z

202

Electric field induced needle-pulsed arc discharge carbon nanotube production apparatus: Circuitry and mechanical design  

SciTech Connect

A simple and low cost apparatus is reported to produce multiwall carbon nanotubes and carbon nano-onions by a low power short pulsed arc discharge reactor. The electric circuitry and the mechanical design details and a micro-filtering assembly are described. The pulsed-plasma is generated and applied between two graphite electrodes. The pulse width is 0.3 {mu}s. A strong dc electric field is established along side the electrodes. The repetitive discharges occur in less than 1 mm distance between a sharp tip graphite rod as anode, and a tubular graphite as cathode. A hydrocarbon vapor, as carbon source, is introduced through the graphite nozzle in the cathode assembly. The pressure of the chamber is controlled by a vacuum pump. A magnetic field, perpendicular to the plasma path, is provided. The results show that the synergetic use of a pulsed-current and a dc power supply enables us to synthesize carbon nanoparticles with short pulsed plasma. The simplicity and inexpensiveness of this plan is noticeable. Pulsed nature of plasma provides some extra degrees of freedom that make the production more controllable. Effects of some design parameters such as electric field, pulse frequency, and cathode shape are discussed. The products are examined using scanning probe microscopy techniques.

Kia, Kaveh Kazemi [Department of Electrical and Computer Engineering, Islamic Azad University of Bonab, Bonab (Iran, Islamic Republic of); Bonabi, Fahimeh [Department of Engineering, Islamic Azad University of Bonab, Bonab (Iran, Islamic Republic of)

2012-12-15T23:59:59.000Z

203

Draft Surplus Plutonium Disposition Supplemental Environmental...  

National Nuclear Security Administration (NNSA)

materials production activities at SRS have produced HLW that is stored on site in tanks. The function of DWPF is to vitrify the low-volume, high- activity radioactive...

204

Microsoft PowerPoint - S08-05_Leishear_Salt Disposition Initiative.ppt  

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

Blending in Nuclear Waste Tanks Blending in Nuclear Waste Tanks Bob Leishear Savannah River Remediation Salt Disposition Engineering November 17, 2010 Print Close 2 Blending in Nuclear Waste Tanks Volume 37.1 Million Gallons (Mgal) Curies 183 MCi (52%) 169 MCi (48%) 352 Million Curies (MCi) 171 MCi (49%) Sludge 34.2 Mgal (92%) 2.9 Mgal (8%) 18.4 Mgal (49%) Salt Supernate 12 MCi (3%) Saltcake 15.8 Mgal (43%) Print Close 3 Blending in Nuclear Waste Tanks Sample of Vitrified Radioactive Glass Print Close 4 Blending in Nuclear Waste Tanks SDU 3 SDU 3 SDU 2 SDU 2 SDU (Vault) 4 SDU (Vault) 4 SDU (Vault) 1 SDU (Vault) 1 Cell A Cell B Saltstone Production Facility Saltstone Production Facility Print Close 5 Blending in Nuclear Waste Tanks Print Close 6 Blending in Nuclear Waste Tanks Sludge Salt Feed Solutions Print Close 7 Experimental Strategy Scale-

205

Plutonium stabilization and disposition focus area, FY 1999 and FY 2000 multi-year program plan  

SciTech Connect

Consistent with the Environmental Management`s (EM`s) plan titled, ``Accelerating Cleanup: Paths to Closure``, and ongoing efforts within the Executive Branch and Congress, this Multi-Year Program Plan (MYPP) for the Plutonium Focus Area was written to ensure that technical gap projects are effectively managed and measured. The Plutonium Focus Area (PFA) defines and manages technology development programs that contribute to the effective stabilization of nuclear materials and their subsequent safe storage and final disposition. The scope of PFA activities includes the complete spectrum of plutonium materials, special isotopes, and other fissile materials. The PFA enables solutions to site-specific and complex-wide technology issues associated with plutonium remediation, stabilization, and preparation for disposition. The report describes the current technical activities, namely: Plutonium stabilization (9 studies); Highly enriched uranium stabilization (2 studies); Russian collaboration program (2 studies); Packaging and storage technologies (6 studies); and PFA management work package/product line (3 studies). Budget information for FY 1999 and FY 2000 is provided.

NONE

1998-03-01T23:59:59.000Z

206

Polarization Effects In The Charged Lepton Pair Production By A Neutrino (Antineutrino) In A Magnetic Field  

SciTech Connect

The probability of the process of the charged lepton pair production by a neutrino (an antineutrino) with allowance for the longitudinal and transverse polarizations of the charged leptons in a magnetic field is presented. The dependence of the probability of the process on the spin variables of the charged leptons and on the azimuthal and polar angles of the initial and final neutrinos (antineutrinos) are investigated. It is shown that the probability of the process is sensitive to the spin variables of the charged leptons and to the direction of the neutrino (antineutrino) momentum. It is determined that the neutrino (antineutrino) energy and momentum loss through the production of a charged lepton pair happens asymmetrically.

Huseynov, Vali A. [Department of General and Theoretical Physics, Nakhchivan State University, AZ 7000, Nakhchivan (Azerbaijan); Laboratory of Physical Research, Nakhchivan Division of Azerbaijan National Academy of Sciences, AZ 7000, Nakhchivan (Azerbaijan); Ahmad, Ali S. [Department of General and Theoretical Physics, Nakhchivan State University, AZ 7000, Nakhchivan (Azerbaijan)

2007-06-13T23:59:59.000Z

207

Evaluation of naturally fractured gas shale production utilizing multiwell transient tests: A field study  

SciTech Connect

A series of multiple well transient tests were conducted in a Devonian shale gas field in Meigs County, Ohio. Production parameters were quantified and it was determined that the reservoir is highly anisotropic, which is a significant factor in calculating half-fracture length from pressure transient data. Three stimulation treatments, including conventional explosive shooting, nitrogen foam frac, and high energy gas frac (HEGF), were compared on the basis of overall effectiveness and performance. Based on the evaluation of results, the nitrogen foam frac provided the most improved productivity. The study provided new type curves and analytical solutions for the mathematical representation of naturally fractured reservoirs and confirmed that the shale reservoir in Meigs County can be modeled as a dual porosity system using pseudosteady-state gas transfer from the matrix to the fracture system.

Chen, C.C.; Alam, J.; Blanton, T.L.; Vozniak, J.P.

1984-05-01T23:59:59.000Z

208

Costs and indices for domestic oil and gas field equipment and production operations, 1992--1995  

SciTech Connect

This report presents estimated costs and cost indices for domestic oil and natural gas field equipment and production operations for 1992, 1993, 1994, and 1995. The costs of all equipment and services are those in effect during June of each year. The sum (aggregates) of the costs for representative leases by region, depth, and production rate were averaged and indexed. This provides a general measure of the increased or decreased costs from year to year for lease equipment and operations. These general measured do not capture changes in industry-wide costs exactly because of annual variations in the ratio of the total number of oil wells to the total number of gas wells. The detail provided in this report is unavailable elsewhere. The body of this report contains summary tables, and the appendices contain detailed tables.

NONE

1996-08-01T23:59:59.000Z

209

Neutron production using a pyroelectric driven target coupled with a gated field ionization source  

SciTech Connect

A palm sized, portable neutron source would be useful for widespread implementation of detection systems for shielded, special nuclear material. We present progress towards the development of the components for an ultracompact neutron generator using a pulsed, meso-scale field ionization source, a deuterated (or tritiated) titanium target driven by a negative high voltage lithium tantalate crystal. Neutron production from integrated tests using an ion source with a single, biased tungsten tip and a 3 Multiplication-Sign 1 cm, vacuum insulated crystal with a plastic deuterated target are presented. Component testing of the ion source with a single tip produces up to 3 nA of current. Dielectric insulation of the lithium tantalate crystals appears to reduce flashover, which should improve the robustness. The field emission losses from a 3 cm diameter crystal with a plastic target and 6 cm diameter crystal with a metal target are compared.

Ellsworth, J. L.; Tang, V.; Falabella, S. [Lawrence Livermore National Laboratory, 7000 East Ave., Livermore, CA 94550 (United States); Naranjo, B.; Putterman, S. [University of California Los Angeles, 405 Hilgard Ave., Los Angeles, CA 90095 (United States)

2013-04-19T23:59:59.000Z

210

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

SciTech Connect

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

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

1997-12-01T23:59:59.000Z

211

Genesis field, Gulf of Mexico: Recognizing reservoir compartments on geologic and production time scales in deep-water reservoirs  

Science Journals Connector (OSTI)

...Factors for the Pleistocene Reservoirs of Genesis Field Reservoir EOD Reserves (MMBOE) Recovery Factor () Drive Mechanism Completions...49-63 Weak water drive 5 All completions are fracture packed. EOD environment of deposition. Table 2 Cumulative Production and...

Michael L. Sweet; Larry T. Sumpter

212

field  

National Nuclear Security Administration (NNSA)

9%2A en Ten-Year Site Plans (TYSP) http:nnsa.energy.govaboutusouroperationsinfopsinfopstysp

field field-type-text field-field-page-name">

213

Used Fuel Disposition Campaign Disposal Research and Development Roadmap  

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

Disposal Research and Development Disposal Research and Development Roadmap Rev. 01 Used Fuel Disposition Campaign Disposal Research and Development Roadmap Rev. 01 The U.S. Department of Energy Office of Nuclear Energy (DOE-NE), Office of Fuel Cycle Technology (OFCT) has established the Used Fuel Disposition Campaign (UFDC) to conduct the research and development (R&D) activities related to storage, transportation and disposal of used nuclear fuel (UNF) and high level nuclear waste (HLW) generated by existing and future nuclear fuel cycles. The disposal of SNF and HLW in a range of geologic media has been investigated internationally. Considerable progress has been made in the U.S and other nations, but gaps in knowledge still exist. This document provides an evaluation and prioritization of R&D opportunities

214

Used Fuel Disposition Campaign International Activities Implementation Plan  

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

International Activities International Activities Implementation Plan Used Fuel Disposition Campaign International Activities Implementation Plan The management of used nuclear fuel and nuclear waste is required for any country using nuclear energy. This includes the storage, transportation, and disposal of low and intermediate level waste (LILW), used nuclear fuel (UNF), and high level waste (HLW). The Used Fuel Disposition Campaign (UFDC), within the U.S. Department of Energy (DOE), Office of Nuclear Energy (NE), Office of Fuel Cycle Technology (FCT), is responsible for conducting research and development pertaining to the management of these materials in the U.S. Cooperation and collaboration with other countries would be beneficial to both the U.S. and other countries through

215

Used Fuel Disposition Campaign Disposal Research and Development Roadmap |  

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

Disposal Research and Development Disposal Research and Development Roadmap Used Fuel Disposition Campaign Disposal Research and Development Roadmap The U.S. Department of Energy Office of Nuclear Energy (DOE-NE), Office of Fuel Cycle Technology (OFCT) has established the Used Fuel Disposition Campaign (UFDC) to conduct the research and development (R&D) activities related to storage, transportation and disposal of used nuclear fuel (UNF) and high level nuclear waste (HLW). The Mission of the UFDC is To identify alternatives and conduct scientific research and technology development to enable storage, transportation and disposal of used nuclear fuel and wastes generated by existing and future nuclear fuel cycles. The U.S. has, for the past twenty-plus years, focused efforts on disposing

216

Microsoft PowerPoint - REVWaste_Disposition_Update.061411.pptx  

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

Materials and Disposition Update Materials and Disposition Update Environmental Management Site-Specific www.em.doe.gov 1 Environmental Management Site-Specific Advisory Board Chairs' Meeting June 15, 2011 Shirley J. Olinger EM Associate Principal Deputy for Corporate Operations DOE's Waste Management Priorities Continue to manage waste inventories in a safe and compliant manner. Address high risk waste in a cost- effective manner. Maintain and optimize current disposal capability for future generations. www.em.doe.gov 2 Develop future disposal capacity in a complex environment. Promote the development of treatment and disposal alternatives in the commercial sector. Review current policies and directives and provide needed oversight. Completed Legacy TRU Sites Teledyne-Brown ARCO Energy Technology Engineering Center

217

Update of the Used Fuel Disposition Campaign Implementation Plan  

SciTech Connect

This Campaign Implementation Plan provides summary level detail describing how the Used Fuel Disposition Campaign (UFDC) supports achievement of the overarching mission and objectives of the Department of Energy Office of Nuclear Energy Fuel Cycle Technologies Program The implementation plan begins with the assumption of target dates that are set out in the January 2013 DOE Strategy for the Management and Disposal of Used Nuclear Fuel and High-Level Radioactive Waste (http://energy.gov/downloads/strategy-management-and-disposal-used-nuclear-fuel-and-high-level-radioactive-waste). These target dates and goals are summarized in section III. This implementation plan will be maintained as a living document and will be updated as needed in response to progress in the Used Fuel Disposition Campaign and the Fuel Cycle Technologies Program.

Jens Birkholzer; Robert MacKinnon; Kevin McMahon; Sylvia Saltzstein; Ken Sorenson; Peter Swift

2014-09-01T23:59:59.000Z

218

Costs and indices for domestic oil and gas field equipment and production operations 1994 through 1997  

SciTech Connect

This report presents estimated costs and cost indices for domestic oil and natural gas field equipment and production operations for 1994, 1995, 1996, and 1997. The costs of all equipment and services are those in effect during June of each year. The sums (aggregates) of the costs for representative leases by region, depth, and production rate were averaged and indexed. This provides a general measure of the increased or decreased costs from year to year for lease equipment and operations. These general measures do not capture changes in industry-wide costs exactly because of annual variations in the ratio of the total number of oil wells to the total number of gas wells. The detail provided in this report is unavailable elsewhere. The body of this report contains summary tables, and the appendices contain detailed tables. Price changes for oil and gas, changes in taxes on oil and gas revenues, and environmental factors (compliance costs and lease availability) have a significant impact on the number and cost of oil and gas wells drilled. These changes also impact the cost of oil and gas equipment and production operations.

NONE

1998-03-01T23:59:59.000Z

219

Costs and indices for domestic oil and gas field equipment and production operations 1990 through 1993  

SciTech Connect

This report presents estimated costs and indice for domestic oil and gas field equipment and production operations for 1990, 1991, 1992, and 1993. The costs of all equipment and serives were those in effect during June of each year. The sums (aggregates) of the costs for representative leases by region, depth, and production rate were averaged and indexed. This provides a general measure of the increased or decreased costs from year to year for lease equipment and operations. These general measures do not capture changes in industry-wide costs exactly because of annual variations in the ratio of oil wells to gas wells. The body of the report contains summary tables, and the appendices contain detailed tables. Price changes for oil and gas, changes in taxes on oil and gas revenues, and environmental factors (costs and lease availability) have significant impact on the number and cost of oil and gas wells drilled. These changes also impact the cost of oil and gas production equipment and operations.

Not Available

1994-07-08T23:59:59.000Z

220

Accelerating the disposition of transuranic waste from LANL - 9495  

SciTech Connect

Los Alamos National Laboratory (LANL) was established during World War II with a single mission -- to design and build an atomic bomb. In the 65 years since, nuclear weapons physics, design and engineering have been the Laboratory's primary and sustaining mission. Experimental and process operations -- and associated cleanout and upgrade activities -- have generated a significant inventory of transuranic (TRU) waste that is stored at LANL's Technical Area 54, Material Disposal Area G (MDA G). When the Waste Isolation Pilot Plant (WIPP) opened its doors in 1999, LANL's TRU inventory totaled about 10,200 m{sup 3}, with a plutonium 239-equivalent curie (PE Ci) content of approximately 250,000 curies. By December 2008, a total of about 2,300 m3 (61,000 PE Ci) had been shipped to WIPP from LANL. This has resulted in a net reduction of about 1,000 m{sup 3} of TRU inventory over that time frame. This paper presents progress in dispositioning legacy and newly-generated transuranic waste (TRU) from ongoing missions at the LANL. The plans for, and lessons learned, in dispositioning several hundred high-activity TRU waste drums are reviewed. This waste population was one of the highest risks at LANL. Technical challenges in disposition of the high-activity drums are presented. These provide a preview of challenges to be addressed in dispositioning the remaining 6,800 m{sup 3} of TRU stored above ground and 2,400 m{sup 3} of TRU waste that is 'retrievably' stored below-grade. LANL is using subcontractors for much of this work and has formed a strong partnership with WIPP and its contractor to address this cleanup challenge.

Shepard, Mark D [Los Alamos National Laboratory; Stiger, Susan G [Los Alamos National Laboratory; Blankenhorn, James A [Los Alamos National Laboratory; Rael, George J [Los Alamos National Laboratory; Moody, David C [U.S DOE

2009-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "disposition field production" 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

Summary - Uranium233 Downblending and Disposition Project  

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

Product Product EM wa in Buil to extr from 23 downb mitigat concer dispos downb WIPP condu the "ba allowin assess techno The as Techn Techn * An * C (T * Pr * O The Ele Site: O roject: 2 P Report Date: S ited States 233 Ura Why DOE t Packaging Syste as directed to t ding 3019 at O ract 229 Th (an is 33 U. The missi blend the inven te security and rns and prepar sal. The projec blended materia or the Nevada cted to coincid ack-end" of the ng observation sment team to ology maturity p What th ssessment team ology Element ology Readine nalytical Labor oncentration p TRL=4) roduct Packag ffgas Treatmen To view the full T http://www.em.doe. objective of a Tech ements (CTEs), usin Oak Ridge/OR 233 Uranium Do Project September 20 Departmen anium D E-EM Did This em and Interfaces ake ownership Oak Ridge that sotope used in

222

Microsoft Word - Fuel Cycle Potential Waste Inventory for Disposition R5a.docx  

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

Fuel Cycle Potential Fuel Cycle Potential Waste Inventory for Disposition Prepared for U.S. Department of Energy Used Nuclear Fuel Joe T. Carter, SRNL Alan J. Luptak, INL Jason Gastelum, PNNL Christine Stockman, SNL Andrew Miller, SNL July 2012 FCR&D-USED-2010-000031 Rev 5 DISCLAIMER This information was prepared as an account of work sponsored by an agency of the U.S. Government. Neither the U.S. Government nor any agency thereof, nor any of their employees, makes any warranty, expressed 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. References herein to any specific commercial

223

Record of decision for the Storage and Disposition of Weapons- Usable  

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

14 14 Federal Register / Vol. 62, No. 13 / Tuesday, January 21, 1997 / Notices Responses: 18,620 Burden Hours: 64,310. Abstract: The LESCP is being conducted in response to the legislative requirement in P.L. 103-382, Section 1501 to assess the implementation of Title I and related education reforms. The information will be used to examine changes-over a 3-year period-that are occurring in schools and classrooms. Teachers and teacher aides will complete a mail survey, and district Title I administrators, principals, school-based staff, and parents will be interviewed during on- site field work. [FR Doc. 97-1307 Filed 1-17-97; 8:45 am] BILLING CODE 4000-01-P DEPARTMENT OF ENERGY Record of decision for the Storage and Disposition of Weapons-Usable Fissile Materials Final Programmatic

224

Update to the Fissile Materials Disposition program SST/SGT transportation estimation  

SciTech Connect

This report is an update to ``Fissile Materials Disposition Program SST/SGT Transportation Estimation,'' SAND98-8244, June 1998. The Department of Energy Office of Fissile Materials Disposition requested this update as a basis for providing the public with an updated estimation of the number of transportation loads, load miles, and costs associated with the preferred alternative in the Surplus Plutonium Disposition Final Environmental Impact Statement (EIS).

John Didlake

1999-11-15T23:59:59.000Z

225

,"U.S. Natural Gas Plant Field Production"  

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

Annual",2012,"6/30/1981" Annual",2012,"6/30/1981" ,"Release Date:","9/27/2013" ,"Next Release Date:","9/26/2014" ,"Excel File Name:","pet_pnp_gp_dc_nus_mbbl_a.xls" ,"Available from Web Page:","http://www.eia.gov/dnav/pet/pet_pnp_gp_dc_nus_mbbl_a.htm" ,"Source:","Energy Information Administration" ,"For Help, Contact:","infoctr@eia.gov" ,,"(202) 586-8800",,,"11/25/2013 11:17:57 AM" "Back to Contents","Data 1: U.S. Natural Gas Plant Field Production" "Sourcekey","MNGFPUS1","MPPFPUS1","MLPFPUS1","METFPUS1","MPRFPUS1","MBNFPUS1","MBIFPUS1"

226

,"U.S. Natural Gas Plant Field Production"  

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

Monthly","9/2013","1/15/1981" Monthly","9/2013","1/15/1981" ,"Release Date:","11/27/2013" ,"Next Release Date:","Last Week of December 2013" ,"Excel File Name:","pet_pnp_gp_dc_nus_mbbl_m.xls" ,"Available from Web Page:","http://www.eia.gov/dnav/pet/pet_pnp_gp_dc_nus_mbbl_m.htm" ,"Source:","Energy Information Administration" ,"For Help, Contact:","infoctr@eia.gov" ,,"(202) 586-8800",,,"11/25/2013 11:17:57 AM" "Back to Contents","Data 1: U.S. Natural Gas Plant Field Production" "Sourcekey","MNGFPUS1","MPPFPUS1","MLPFPUS1","METFPUS1","MPRFPUS1","MBNFPUS1","MBIFPUS1"

227

Microsoft Word - CX-MountainAvenueDispositionFY12_WEB.doc  

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

1, 2012 REPLY TO ATTN OF: KEPR-4 SUBJECT: Environmental Clearance Memorandum Joan Kendall Realty Specialist - TERR-3 Proposed Action: Disposition of Mountain Avenue Substation and...

228

The Esso Energy Award Lecture, 1998. Boosting production from low-pressure oil and gas fields: a revolution in hydrocarbon production  

Science Journals Connector (OSTI)

...Boosting production from low-pressure oil and gas fields: a revolution in hydrocarbon...major part of the future source of oil and gas supply. Full development...Caledonia Ltd (Wood Group Engineering), Marathon Oil UK Ltd, Mobil North Sea Ltd, Oil...

1999-01-01T23:59:59.000Z

229

Used fuel disposition campaign international activities implementation plan.  

SciTech Connect

The management of used nuclear fuel and nuclear waste is required for any country using nuclear energy. This includes the storage, transportation, and disposal of low and intermediate level waste (LILW), used nuclear fuel (UNF), and high level waste (HLW). The Used Fuel Disposition Campaign (UFDC), within the U.S. Department of Energy (DOE), Office of Nuclear Energy (NE), Office of Fuel Cycle Technology (FCT), is responsible for conducting research and development pertaining to the management of these materials in the U.S. Cooperation and collaboration with other countries would be beneficial to both the U.S. and other countries through information exchange and a broader participation of experts in the field. U.S. participation in international UNF and HLW exchanges leads to safe management of nuclear materials, increased security through global oversight, and protection of the environment worldwide. Such interactions offer the opportunity to develop consensus on policy, scientific, and technical approaches. Dialogue to address common technical issues helps develop an internationally recognized foundation of sound science, benefiting the U.S. and participating countries. The UNF and HLW management programs in nuclear countries are at different levels of maturity. All countries utilizing nuclear power must store UNF, mostly in wet storage, and HLW for those countries that reprocess UNF. Several countries either utilize or plan to utilize dry storage systems for UNF, perhaps for long periods of time (several decades). Geologic disposal programs are at various different states, ranging from essentially 'no progress' to selected sites and pending license applications to regulators. The table below summarizes the status of UNF and HLW management programs in several countriesa. Thus, the opportunity exists to collaborate at different levels ranging from providing expertise to those countries 'behind' the U.S. to obtaining access to information and expertise from those countries with more mature programs. The U.S. fuel cycle is a once through fuel cycle involving the direct disposal of UNF, as spent nuclear fuel, in a geologic repository (previously identified at Yucca Mountain, Nevada), following at most a few decades of storage (wet and dry). The geology at Yucca Mountain, unsaturated tuff, is unique among all countries investigating the disposal of UNF and HLW. The decision by the U.S. Department of Energy to no longer pursue the disposal of UNF at Yucca Mountain and possibly utilize very long term storage (approaching 100 years or more) while evaluating future fuel cycle alternatives for managing UNF, presents a different UNF and HLW management R&D portfolio that has been pursued in the U.S. In addition, the research and development activities managed by OCRWM have been transferred to DOE-NE. This requires a reconsideration of how the UFDC will engage in cooperative and collaborative activities with other countries. This report presents the UFDC implementation plan for international activities. The DOE Office of Civilian Radioactive Waste Management (OCRWM) has cooperated and collaborated with other countries in many different 'arenas' including the Nuclear Energy Agency (NEA) within the Organization for Economic Co-operation and Development (OECD), the International Atomic Energy Agency (IAEA), and through bilateral agreements with other countries. These international activities benefited OCRWM through the acquisition and exchange of information, database development, and peer reviews by experts from other countries. DOE-NE cooperates and collaborates with other countries in similar 'arenas' with similar objectives and realizing similar benefits. However the DOE-NE focus has not typically been in the area of UNF and HLW management. This report will first summarize these recent cooperative and collaborative activities. The manner that the UFDC will cooperate and collaborate in the future is expected to change as R&D is conducted regarding long-term storage and the potential disposal of UNF and HLW in different geolo

Nutt, W. M. (Nuclear Engineering Division)

2011-06-29T23:59:59.000Z

230

Linking Legacies: Connecting the Cold War Nuclear Weapons Production Processes to Their Environmental Consequences  

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

This report described each step in the cycle of nuclear weapons production and defined for the first time a planned disposition path for all waste streams generated prior to 1992 as a result of weapons production.

231

Disposition of excess highly enriched uranium status and update  

SciTech Connect

This paper presents the status of the US DOE program charged with the disposition of excess highly enriched uranium (HEU). Approximately 174 metric tonnes of HEU, with varying assays above 20 percent, has been declared excess from US nuclear weapons. A progress report on the identification and characterization of specific batches of excess HEU is provided, and plans for processing it into commercial nuclear fuel or low-level radioactive waste are described. The resultant quantities of low enriched fuel material expected from processing are given, as well as the estimated schedule for introducing the material into the commercial reactor fuel market. 2 figs., 3 tabs.

Williams, C.K. III; Arbital, J.G.

1997-09-01T23:59:59.000Z

232

Sound propagation in urban areas: A periodic disposition of buildings  

Science Journals Connector (OSTI)

A numerical simulation of background noise propagation is performed for a network of hexagonal buildings. The obtained results suggest that the prediction of background noise in urban spaces is possible by means of a modified diffusion equation using two parameters: the diffusion coefficient that expresses the spreading out of noise resulting from diffuse scattering and multiple reflections by buildings, and an attenuation term accounting for the wall absorption, atmospheric attenuation, and absorption by the open top. The dependence of the diffusion coefficient with geometrical shapes and the diffusive nature of the buildings are investigated in the case of a periodic disposition of hexagonal buildings.

J. Picaut; J. Hardy; L. Simon

1999-10-01T23:59:59.000Z

233

Research and development of energy-efficient appliance motor-compressors. Volume IV. Production demonstration and field test  

SciTech Connect

Two models of a high-efficiency compressor were manufactured in a pilot production run. These compressors were for low back-pressure applications. While based on a production compressor, there were many changes that required production process changes. Some changes were performed within our company and others were made by outside vendors. The compressors were used in top mount refrigerator-freezers and sold in normal distribution channels. Forty units were placed in residences for a one-year field test. Additional compressors were built so that a life test program could be performed. The results of the field test reveal a 27.0% improvement in energy consumption for the 18 ft/sup 3/ high-efficiency model and a 15.6% improvement in the 21 ft/sup 3/ improvement in the 21 ft/sup 3/ high-efficiency model as compared to the standard production unit.

Middleton, M.G.; Sauber, R.S.

1983-09-01T23:59:59.000Z

234

MUSE integral-field spectroscopy towards the Frontier Fields Cluster Abell S1063: I. Data products and redshift identifications  

E-Print Network (OSTI)

We present the first observations of the Frontier Fields Cluster Abell S1063, taken with the newly commissioned Multi Unit Spectroscopic Explorer (MUSE) integral field spectrograph. Because of the relatively large field of view (1 arcmin^2), MUSE is ideal to simultaneously target multiple galaxies in blank and cluster fields over the full optical spectrum. We analysed the four hours of data obtained in the Science Verification phase on this cluster and measured redshifts for 60 objects. We confirm the redshift of five cluster galaxies, and determine the redshift of 28 other cluster members. Behind the cluster, we find 16 galaxies at higher redshift, including three previously unknown Lyman-alpha emitters at z>3, and five multiply-lensed galaxies. We report the detection of a new z=4.113 multiply lensed galaxy, with images that are consistent with lensing model predictions derived for the Fronter Fields. We detect CIII], C IV and He II emission in a multiply lensed galaxy at z=3.116, suggesting the likely pres...

Karman, W; Grillo, C; Balestra, I; Rosati, P; Vanzella, E; Coe, D; Christensen, L; Koekemoer, A M; Kruehler, T; Lombardi, M; Mercurio, A; Nonino, M; van der Wel, A

2014-01-01T23:59:59.000Z

235

Evaluating oil quality and monitoring production from heavy oil reservoirs using geochemical methods: Application to the Boscan Field, Venezuela  

SciTech Connect

Many oil fields worldwide contain heavy oil in one or more reservoir units. The low gravity of these oils is most frequently due to biodegradation and/or low maturity. The challenge is to find ways to economically recover this oil. Methods which reduce the operating costs of producing heavy oil add significant value to such projects. Geochemical techniques which use the composition of the reservoir fluids as natural tracers offer cost effective methods to assist with reservoir management. The low viscosity and gravity of heavy oil, combined with frequent high water cuts, low flow rates, and the presence of downhole artificial lift equipment, make many conventional production logging methods difficult to apply. Therefore, monitoring production, especially if the produced oil is commingled from multiple reservoirs, can be difficult. Geochemical methods can be used to identify oil/water contacts, tubing string leaks and to allocate production to individual zones from commingled production. An example of a giant heavy oil field where geochemical methods may be applicable is the Boscan Field in Venezuela. Low maturity oil, averaging 10{degrees} API gravity, is produced from the Eocene Upper and Lower Boscan (Miosa) Sands. Geochemical, stratigraphic and engineering data have helped to better define the controls on oil quality within the field, identified new reservoir compartments and defined unique characteristics of the Upper and Lower Boscan oils. This information can be used to identify existing wells in need of workovers due to mechanical problems and to monitor production from new infill wells.

Kaufman, R.L.; Noguera, V.H.; Bantz, D.M. [Chevron Overseas Petroleum, San Ramon, CA (United States); Rodriguez, R. [Maraven, S.A., Caracas (Venezuela)

1996-08-01T23:59:59.000Z

236

A statistical analysis of well production rates from UK oil and gas fields – Implications for carbon capture and storage  

Science Journals Connector (OSTI)

Abstract The number of wells required to dispose of global CO2 emissions by injection into geological formations is of interest as a key indicator of feasible deployment rate, scale and cost. Estimates have largely been driven by forecasts of sustainable injection rate from mathematical modelling of the CO2 injection process. Recorded fluid production rates from oil and gas fields can be considered an observable analogue in this respect. The article presents statistics concerning Cumulative average Bulk fluid Production (CBP) rates per well for 104 oil and gas fields from the UK offshore region. The term bulk fluid production is used here to describe the composite volume of oil, gas and water produced at reservoir conditions. Overall, the following key findings are asserted: (1) CBP statistics for UK offshore oil and gas fields are similar to those observed for CO2 injection projects worldwide. (2) 50% probability of non-exceedance (PNE) for CBP for oil and gas fields without water flood is around 0.35 Mt/yr/well of CO2 equivalent. (3) There is negligible correlation between reservoir transmissivity and CBP. (4) Study of net and gross CBP for water flood fields suggest a 50% PNE that brine co-production during CO2 injection could lead to a 20% reduction in the number of wells required.

Simon A. Mathias; Jon G. Gluyas; Eric J. Mackay; Ward H. Goldthorpe

2013-01-01T23:59:59.000Z

237

Abstract 4241: Preclinical studies of brain/brain tumor disposition and antitumor efficacy of the aromatase inhibitor letrozole  

Science Journals Connector (OSTI)

...San Diego, CA Abstract 4241: Preclinical studies of brain/brain tumor disposition and antitumor efficacy of the aromatase...target for the treatment of CNS malignancies, as well as brain disposition and anti-tumor efficacy of letrozole, an...

Nimita Dave; Pankaj B. Desai; Gary A. Gudelsky; Kathleen LaSance; Lionel M.L. Chow; Xiaoyang Qi

2014-10-01T23:59:59.000Z

238

Increasing Heavy Oil Reserves in the Wilmington Oil Field Through Advanced Reservoir Characterization and Thermal Production Technologies, Class III  

SciTech Connect

The objective of this project was to increase the recoverable heavy oil reserves within sections of the Wilmington Oil Field, near Long Beach, California through the testing and application of advanced reservoir characterization and thermal production technologies. It was hoped that the successful application of these technologies would result in their implementation throughout the Wilmington Field and, through technology transfer, will be extended to increase the recoverable oil reserves in other slope and basin clastic (SBC) reservoirs.

City of Long Beach; Tidelands Oil Production Company; University of Southern California; David K. Davies and Associates

2002-09-30T23:59:59.000Z

239

Increasing Heavy Oil Reserves in the Wilmington Oil Field Through Advanced Reservoir Characterization and Thermal Production Technologies, Class III  

SciTech Connect

The objective of this project was to increase the recoverable heavy oil reserves within sections of the Wilmington Oil Field, near Long Beach, California through the testing and application of advanced reservoir characterization and thermal production technologies. The successful application of these technologies would result in expanding their implementation throughout the Wilmington Field and, through technology transfer, to other slope and basin clastic (SBC) reservoirs.

City of Long Beach; Tidelands Oil Production Company; University of Southern California; David K. Davies and Associates

2002-09-30T23:59:59.000Z

240

Petroleum Supply Monthly  

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

2014 Table 19. PAD District 4 - Daily Average Supply and Disposition of Crude Oil and Petroleum Products, October 2014 (Thousand Barrels per Day) Commodity Supply Disposition Field...

Note: This page contains sample records for the topic "disposition field production" 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

Implementation Guide for Surveillance and Maintenance during Facility Transition and Disposition  

Directives, Delegations, and Requirements

As DOE facilities complete mission operations and are declared excess, they pass into a transition phase that ultimately prepares them for disposition. The disposition phase of a facility's life cycle usually includes deactivation, decommissioning, and surveillance and maintenance (S&M) activities.

1999-09-29T23:59:59.000Z

242

Fisetin disposition and metabolism in mice: Identification of geraldol as an active metabolite  

E-Print Network (OSTI)

1 Fisetin disposition and metabolism in mice: Identification of geraldol as an active metabolite title: Fisetin disposition and metabolism in mice ** Corresponding author: Dr. Guy G. Chabot, Chemical-yl)-3,5-diphenyltetrazolium; PBS, phosphate buffered saline. Keywords: flavonoid, fisetin

Paris-Sud XI, Université de

243

Conformal field theories at non-zero temperature: operator product expansions, Monte Carlo, and holography  

E-Print Network (OSTI)

We compute the non-zero temperature conductivity of conserved flavor currents in conformal field theories (CFTs) in 2+1 spacetime dimensions. At frequencies much greater than the temperature, $\\hbar\\omega>> k_B T$, the $\\omega$ dependence can be computed from the operator product expansion (OPE) between the currents and operators which acquire a non-zero expectation value at T > 0. Such results are found to be in excellent agreement with quantum Monte Carlo studies of the O(2) Wilson-Fisher CFT. Results for the conductivity and other observables are also obtained in vector 1/N expansions. We match these large $\\omega$ results to the corresponding correlators of holographic representations of the CFT: the holographic approach then allows us to extrapolate to small $\\hbar \\omega/(k_B T)$. Other holographic studies implicitly only used the OPE between the currents and the energy-momentum tensor, and this yields the correct leading large $\\omega$ behavior for a large class of CFTs. However, for the Wilson-Fisher ...

Katz, Emanuel; Sorensen, Erik S; Witczak-Krempa, William

2014-01-01T23:59:59.000Z

244

Conformal field theories at non-zero temperature: operator product expansions, Monte Carlo, and holography  

E-Print Network (OSTI)

We compute the non-zero temperature conductivity of conserved flavor currents in conformal field theories (CFTs) in 2+1 spacetime dimensions. At frequencies much greater than the temperature, $\\hbar\\omega>> k_B T$, the $\\omega$ dependence can be computed from the operator product expansion (OPE) between the currents and operators which acquire a non-zero expectation value at T > 0. Such results are found to be in excellent agreement with quantum Monte Carlo studies of the O(2) Wilson-Fisher CFT. Results for the conductivity and other observables are also obtained in vector 1/N expansions. We match these large $\\omega$ results to the corresponding correlators of holographic representations of the CFT: the holographic approach then allows us to extrapolate to small $\\hbar \\omega/(k_B T)$. Other holographic studies implicitly only used the OPE between the currents and the energy-momentum tensor, and this yields the correct leading large $\\omega$ behavior for a large class of CFTs. However, for the Wilson-Fisher CFT a relevant "thermal" operator must also be considered, and then consistency with the Monte Carlo results is obtained without a previously needed ad hoc rescaling of the T value. We also establish sum rules obeyed by the conductivity of a wide class of CFTs.

Emanuel Katz; Subir Sachdev; Erik S. Sorensen; William Witczak-Krempa

2014-09-12T23:59:59.000Z

245

EIS-0287: Idaho High-Level Waste and Facilities Disposition Final  

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

Idaho High-Level Waste and Facilities Disposition Final Idaho High-Level Waste and Facilities Disposition Final Environmental Impact Statement, EIS-0287 (September 2002) EIS-0287: Idaho High-Level Waste and Facilities Disposition Final Environmental Impact Statement, EIS-0287 (September 2002) This EIS analyzes the potential environmental consequences of alternatives for managing high-level waste (HLW) calcine, mixed transuranic waste/sodium bearing waste (SBW) and newly generated liquid waste at the Idaho National Engineering and Environmental Laboratory (INEEL) in liquid and solid forms. This EIS also analyzes alternatives for the final disposition of HLW management facilities at the INEEL after their missions are completed. Idaho High-Level Waste and Facilities Disposition Final Environmental Impact Statement, DOE/EIS-0287 (September 2002)

246

EIS-0229: Storage and Disposition of Weapons-Usable Fissile Materials |  

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

29: Storage and Disposition of Weapons-Usable Fissile 29: Storage and Disposition of Weapons-Usable Fissile Materials EIS-0229: Storage and Disposition of Weapons-Usable Fissile Materials Summary The EIS will evaluate the reasonable alternatives and potential environmental impacts for the proposed siting, construction, and operation of three types of facilities for plutonium disposition. Public Comment Opportunities None available at this time. Documents Available For Download September 5, 2007 EIS-0229: Supplement Analysis (September 2007) Storage of Surplus Plutonium Materials at the Savannah River Site November 14, 2003 EIS-0229: Record of Decision (November 2003) Storage and Disposition of Weapons-Usable Fissile Materials November 7, 2003 EIS-0229-SA-03: Supplement Analysis Fabrication of Mixed Oxide Fuel Lead Assemblies in Europe

247

EIS-0287: Idaho High-Level Waste & Facilities Disposition | Department of  

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

7: Idaho High-Level Waste & Facilities Disposition 7: Idaho High-Level Waste & Facilities Disposition EIS-0287: Idaho High-Level Waste & Facilities Disposition SUMMARY This EIS analyzes the potential environmental consequences of alternatives for managing high-level waste (HLW) calcine, mixed transuranic waste/sodium bearing waste (SBW) and newly generated liquid waste at the Idaho National Engineering and Environmental Laboratory (INEEL) in liquid and solid forms. This EIS also analyzes alternatives for the final disposition of HLW management facilities at the INEEL after their missions are completed. PUBLIC COMMENT OPPORTUNITIES None available at this time. DOCUMENTS AVAILABLE FOR DOWNLOAD January 12, 2010 EIS-0287: Amended Record of Decision Idaho High-Level Waste and Facilities Disposition January 4, 2010

248

Consent Order, Uranium Disposition Services, LLC - NCO-2010-01 | Department  

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

Uranium Disposition Services, LLC - NCO-2010-01 Uranium Disposition Services, LLC - NCO-2010-01 Consent Order, Uranium Disposition Services, LLC - NCO-2010-01 March 26, 2010 Consent Order issued to Uranium Disposition Services, LLC related to Construction Deficiencies at the DUF6 Conversion Buildings at the Portsmouth and Paducah Gaseous Diffusion Plants The Office of Health, Safety and Security's Office of Enforcement has completed its investigation into the facts and circumstances associated with construction deficiencies at the DUF6 Conversion Buildings located at the Portsmouth and Paducah Gaseous Diffusion Plants. The investigation reports, dated January 22, 2009, and April 23, 2009, were provided to Uranium Disposition Services, LLC (DDS), and addressed specific areas of potential noncompliance with DOE nuclear safety requirements established in

249

Draft Environmental Assessment on the Remote-handled Waste Disposition  

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

Draft Environmental Assessment on the Remote-handled Waste Disposition Project available for public review and comment Draft Environmental Assessment on the Remote-handled Waste Disposition Project available for public review and comment The U.S. Department of Energy invites the public to review and comment on a draft environmental assessment that the Department issued today, for a proposal to process approximately 327 cubic meters of remote-handled waste currently stored at the Idaho National Laboratory. An additional five cubic meters of waste stored at the Hanford Site near Richland, Washington is also evaluated since it is reasonably foreseeable that a decision may be made in the future to send that waste to Idaho for treatment. The project is necessary to prepare the waste for legally-required disposal. Under the Department�s preferred alternative, workers would use sealed rooms called hot cells at the Idaho Nuclear Technology and Engineering Center (INTEC) to process the waste, treat it as necessary and repackage it so that it is ready for disposal. The document describes the modifications necessary to hot cells to perform the work.

250

Innovative Resin Transfer and Disposition at Indian Point Unit 1  

SciTech Connect

A number of sites have both operating and shuttered nuclear facilities. Reducing dose to the caretakers can have beneficial effects for other site personnel who may work or pass near the shuttered facility. Furthermore, disposition of waste can have a positive effect on NRC required regular reporting of, and plans for the disposition of on-site wastes. Entergy's Indian Point Energy Center recently reduced the on-site curie load by working with RWE NUKEM and WMG, Inc. to innovatively free and ship nearly 1,000 cubic feet and nearly 600 curies of 30 year old resin and sludge from Unit 1. Old drawings, operations logs, were consulted and transfer lines were remotely checked. The tank selection sequence was primarily based on dose rates. System modifications to facilitate resin transfer were made on the lowest dose tanks first to gain current operating experience. Resin transfers were performed in accordance with the procedures developed, into waiting cask with appropriate waste containers. Decomposed resin of varying consistency could clog discharge lines and operational changes were made to mitigate against flow interruptions. Hydrogen buildup in the tanks was carefully addressed while solidified resin remains a challenge to be overcome. (authors)

Posivak, E.J.; Freitag, A.A.; Miller, R.J. [WMG, Inc., Peekskill, NY (United States)

2007-07-01T23:59:59.000Z

251

Major Risk Factors Integrated Facility Disposition Project - Oak Ridge  

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

O O O f f f f i i c c e e o o f f E E n n v v i i r r o o n n m m e e n n t t a a l l M M a a n n a a g g e e m m e e n n t t ( ( E E M M ) ) E E n n g g i i n n e e e e r r i i n n g g a a n n d d T T e e c c h h n n o o l l o o g g y y External Technical Review (ETR) Report Major Risk Factors Integrated Facility Disposition Project (IFDP) Oak Ridge, TN AUGUST 1, 2008 Acknowledgement The External Technical Review of the Integrated Facility Disposition Project was conducted simultaneous to other assessments and visits. The ETR Team wishes to note the outstanding support received from all parties involved in the review, including the DOE Oak Ridge Office, the National Nuclear Security Administration Y-12 Site Office, UT-Battelle, B&W Y-12, and the Professional Project Services, Inc. (Pro2Serve). The ETR Team feels compelled to note, and

252

Generation!and!Disposition!of!Municipal!Solid!Waste! (MSW)!in!the!United!States!A!National!Survey!  

E-Print Network (OSTI)

! 1! ! Generation!and!Disposition!of!Municipal!Solid!Waste! (MSW Waste (MSW) Generation and Disposition in the U.S., in collaboration with Ms. Nora Goldstein of Bio in 2012 and in 2013 EEC and BioCycle agreed that the 2013 Survey of Waste Generation and Disposition

253

Field evaluation of cotton near-isogenic lines introgressed with QTLs for productivity and drought related traits  

E-Print Network (OSTI)

Field evaluation of cotton near-isogenic lines introgressed with QTLs for productivity and drought) between elite cultivars of the two cotton species Gossypium barbadense cv. F-177 and G. hirsutum cv. Siv, in order to (1) evaluate the potential to improve cotton drought resistance by MAS and (2) test the role

Chee, Peng W.

254

Productivity evaluation and influential factor analysis for Sarvak reservoir in South Azadegan oil field, Iran  

Science Journals Connector (OSTI)

Abstract Production pattern of oil wells and influential factors on productivity for the massive carbonate reservoir in the Middle East were researched by productivity evaluation on Sarvak and analysis of properties impact on production. Based on dynamic performance of Sarvak production test, the relationship between daily oil production, tubing pressure, cumulative oil production and choke size was analyzed and reasonable productivity prediction model was established by applying Poettman model, and the effect of physical properties and fluid parameters on productivity were analyzed further by numerical simulation. The study shows that daily oil production is linearly correlated with oil pressure under certain working regime, and daily oil production is power law correlated with choke sizes before and after working regime adjustment. The average designed single well productivity should be about 270 m3/d by depletion to ensure a three-year plateau period. Sarvak is a blocky carbonate reservoir, when developed with horizontal wells, interbeds distributed between layers and permeability property have the strongest impact on production of horizontal wells. So, highly deviated wells should be used to reduce the effect of interbeds and acidizing should be considered to improve the reservoir physical properties.

Hui LIU; Rui GUO; Junchang DONG; Li LIU; Yang LIU; Yingjie YI

2013-01-01T23:59:59.000Z

255

Microsoft Word - BingenSwitchDisposition_CXMemo.doc  

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

7, 2012 7, 2012 REPLY TO ATTN OF: KEC-4 SUBJECT: Environmental Clearance Memorandum Joan Kendall Realty Specialist - TERR-3 Proposed Action: Bingen Substation Sectionalizing Switches Disposition Categorical Exclusion Applied (from Subpart D, 10 C.F.R. Part 1021): B1.24 Property Transfers Location: Klickitat County, Washington Proposed by: Bonneville Power Administration (BPA) Description of the Proposed Action: BPA proposes to sell two sectionalizing switches owned by BPA but located on PacifiCorp's Condit-Powerdale 69-kilovolt (kV) line in and adjacent to the Bingen Substation. BPA sold the Bingen substation to Klickitat County PUD in 1997 but retained ownership rights to inspect, maintain, repair, and replace its remaining revenue meters,

256

Microsoft Word - DOE Records Disposition Schedule Changes3.doc  

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

6 6 Changes-to-Schedules REV 3 DOE Administrative Records Schedules Changes Last revised: 12/14/2009 Date DOE Admin Schedule Item(s) Change Authorizing Document 3/02/07 1 10b, 24, 27, 42a-c Added items for Form I-9 (GRS 1, Item 10b), reasonable accommodation records (GRS 1, Item 24), alternative dispute resolution records (GRS 1, item 27), and alternative worksite records (GRS 1, Item 42). Added item numbers for N1 citations. GRS Transmittal No. 11, 12/31/03; GRS Transmittal No. 12, 7/14/04; GRS 1 Item 42 6/14/07 1 11 Second sentence in NOTE deleted. 6/14/07 1 12 Moved the NOTE for 12a to the series title. GRS 1, item 12 6/14/07 1 21 Inserted the "see note" and the disposition authority for the series title. N1-343-98-4, item 21 and GRS

257

Topic Index to the DOE Administrative Records Disposition Schedules  

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

5/21/07 TOPICINDEXTODOEADMINSCHEDULES 5/21/07 TOPICINDEXTODOEADMINSCHEDULES Topic Index to the DOE Administrative Records Disposition Schedules (excluding the GRS Schedules) Topic Schedule Item [A] [B] [C] [D] [E] [F] [G] [H] [I] [J] [K] [L] [M] [N] [O] [P] [Q] [R] [S] [T] [U] [V] [W] [X] [Y] [Z] A Academic/Outreach Program 1 44 Access Request Files 18 6 Accountable Officers' Files 6 1 Accounting Administrative Files 6 5 Administrative Claims Files 6 10 Administrative Training Records 1 29.2 Administrative Issuances 16 1 Administrative - All Other copies of Administrative Issuances 16 1.6 Administrative Grievance, Disciplinary, and Adverse Action Files 1 30 Americans with Disabilities Act 1 42 Apprenticeship Program Files 1 45 Architectural Models 17 7

258

Storage and Disposition of Weapons-Usable Fissile Materials  

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

86 86 Federal Register / Vol. 63, No. 156 / Thursday, August 13, 1998 / Notices 1 SRS has been identified by DOE as the preferred site for the immobilization disposition facility. responsibilities are to (1) evaluate the standards of accreditation applied to applicant foreign medical schools; and (2) determine the comparability of those standards to standards for accreditation applied to United States medical schools. For Further Information Contact: Bonnie LeBold, Executive Director, National Committee on Foreign Medical Education and Accreditation, 7th and D Streets, S.W., Room 3082, ROB #3, Washington, D.C. 20202-7563. Telephone: (202) 260-3636. Beginning September 28, 1998, you may call to obtain the identity of the countries whose standards are to be evaluated during this

259

ABSTRACT REQUESTER CONTRACT SCOPE OF WORK RATIONAL FOR DECISION DISPOSITION  

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

WAIVER ACTION - WAIVER ACTION - ABSTRACT REQUESTER CONTRACT SCOPE OF WORK RATIONAL FOR DECISION DISPOSITION General Motors Conduct research, development and Cost Sharing 20 percent Recommended Corporation testing of 30 KW proton-exchange- membrane (PEM) fuel cell propulsion systems 0 STATEMENT OF CONSIDERATIONS REQUEST BY GENERAL MOTORS CORPORATION FOR AN ADVANCE WAIVER OF DOMESTIC AND FOREIGN RIGHTS UNDER CONTRACT NO. DE-AC02-90CH10435, W(A)-90- 056, CH-0663 The Allison Gas Turbine Division of the General Motors Corporation (hereafter GM), a large business, has petitioned for an advance waiver of patent rights under DOE Contract No. DE-AC02- 90CH10435. The contract, yet to be definitized, resulted from an RFP issued in January 1990. As set out in the attached waiver petition, GM has requested that domestic and foreign title to

260

Radiation Damage Effects in Candidate Titanates for Pu Disposition: Zirconolite  

SciTech Connect

Specimens of titanate ceramics containing approximately 10 mass% 238Pu were tested to determine the long-term effects of radiation-induced damage from the ? decay of 239Pu that would have been disposed of in the nuclear-waste repository at Yucca Mountain. These tests provided information on the changes in bulk properties such as dimensions, densities, and chemical durability. Although these materials become amorphous at low doses, the specimens remained physically strong. Even after the radiation-induced swelling saturated, the specimens remained physically intact with no evidence for microcracking. Thus, in combination with results reported previously on similar materials, the material remains a physically viable material for the disposition of surplus weapons-grade Pu.

Strachan, Denis M.; Scheele, Randall D.; Buck, Edgar C.; Kozelisky, Anne E.; Sell, Rachel L.; Elovich, Robert J.; Buchmiller, William C.

2008-01-15T23:59:59.000Z

Note: This page contains sample records for the topic "disposition field production" 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

Status of nuclear weapons material disposition in Russia  

SciTech Connect

The security of nuclear weapons and fissile material in Russia, the disposition of weapons-usable fissile material in Russia, the Clinton administration`s policies and programs for assisting Russia in improving its security over nuclear weapons and fissile material, and the disposal of Russian weapons-usable fissile materials are discussed in this paper. There are {approximately}30,000 nuclear warheads in the former Soviet Union, {approximately}1000 t of weapon-usable high-enriched uranium (HEU), {approximately} 160 t of separated plutonium in weapons or available for weapons, and {approximately}30 t of separated civil plutonium stored in Russia. Most, if not all, of these inventories are stored under inadequate conditions of physical security and of material control and accounting.

Cochran, T.B.

1994-12-31T23:59:59.000Z

262

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

SciTech Connect

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

Greene, S.R.

1999-07-17T23:59:59.000Z

263

Radiation Damage Effects in Candidate Titanates for Pu Disposition: Zirconolite  

SciTech Connect

This is the second of two papers on the results of radiation-induced damage accumulation in titanate ceramics that potentially could be used for weapons grade plutonium disposition. In the first paper we discussed the results from pyrochlore (betafite) based ceramics. In this paper, we discuss the effects of radiation-induced damage on the density and crystal structure of a nominally phase-pure zirconolite and two other zirconolite-bearing ceramics from the alpha decay of 238Pu. Macro (bulk) and micro (X-ray diffraction) swelling were found to be temperature independent, whereas the density determined with He gas pycnometry was temperature dependent. It took approximately 740 days (2.6?1018 ?/g) for the specimens to become X-ray amorphous—longer for the swelling to saturate. Unlike what we observed for the pyrochlore-based ceramics, we did not observe any phase changes associated with storage temperature and damage ingrowth. The forward dissolution rate at a pH value of 2 for material containing essentially all zirconolite is 1.7(4)?10-3 g/(m2?d). Very little pH dependence was observed for zirconolite specimens and, like we observed for the pyrochlore-bearing ceramics in this study, there was no dependence on the amount of radiation-induced damage. As with the pyrochlore, these materials did not become substantially friable with increasing radiation-induced damage. Even after the radiation-induced swelling saturated, the specimens remained physically intact with no evidence for microcracking. Thus, the material remains physically a viable material for the disposition of surplus weapons-grade Pu.

Strachan, Denis M.; Scheele, Randall D.; Buck, Edgar C.; Kozelisky, Anne E.; Sell, Rachel L.; Elovich, Robert J.; Buchmiller, William C.

2008-01-15T23:59:59.000Z

264

Seismic response to fluid injection and production in two Salton Trough geothermal fields, southern California  

E-Print Network (OSTI)

D I P IPPO , R. (2012). Geothermal Power Plants: Principles,in the vicinity of geothermal power plants worldwide, it isregional effects of geothermal power production. This study

Lajoie, Lia Joyce

2012-01-01T23:59:59.000Z

265

,"U.S. Natural Gas Monthly Supply and Disposition Balance"  

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

Monthly Supply and Disposition Balance" Monthly Supply and Disposition Balance" ,"Click worksheet name or tab at bottom for data" ,"Worksheet Name","Description","# Of Series","Frequency","Latest Data for" ,"Data 1","U.S. Natural Gas Monthly Supply and Disposition Balance",9,"Monthly","9/2013","1/15/1973" ,"Release Date:","12/12/2013" ,"Next Release Date:","1/7/2014" ,"Excel File Name:","ng_sum_sndm_s1_m.xls" ,"Available from Web Page:","http://www.eia.gov/dnav/ng/ng_sum_sndm_s1_m.htm" ,"Source:","Energy Information Administration" ,"For Help, Contact:","infoctr@eia.gov"

266

,"U.S. Natural Gas Annual Supply and Disposition Balance"  

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

Annual Supply and Disposition Balance" Annual Supply and Disposition Balance" ,"Click worksheet name or tab at bottom for data" ,"Worksheet Name","Description","# Of Series","Frequency","Latest Data for" ,"Data 1","Supply",5,"Annual",2012,"6/30/1930" ,"Data 2","Disposition",5,"Annual",2012,"6/30/1930" ,"Release Date:","12/12/2013" ,"Next Release Date:","1/7/2014" ,"Excel File Name:","ng_sum_snd_dcu_nus_a.xls" ,"Available from Web Page:","http://www.eia.gov/dnav/ng/ng_sum_snd_dcu_nus_a.htm" ,"Source:","Energy Information Administration" ,"For Help, Contact:","infoctr@eia.gov"

267

Seismic response to fluid injection and production in two Salton Trough geothermal fields, southern California  

E-Print Network (OSTI)

geothermal field, Imperial Valley, California. GSA Bulletin,2011). Worldwide Projects: Imperial Valley (United States).2012 Brawley earthquake, Imperial Valley. Bulletin of the

Lajoie, Lia Joyce

2012-01-01T23:59:59.000Z

268

Neutrino absorption by W production in the presence of a magnetic field  

E-Print Network (OSTI)

In this work we calculate the decay rate of the electron type neutrinos into $W$ bosons and electrons in presence of an external uniform magnetic field. The decay rate is calculated from the imaginary part of the $W$ exchange neutrino self-energy diagram but in the weak field limit and compare our result with the existing one.

Kaushik Bhattacharya; Sarira Sahu

2008-11-11T23:59:59.000Z

269

Production  

Science Journals Connector (OSTI)

Production is obtained from proved reserves but the determinants of the scale of production in the industry and country components of the world total are many and complex with some unique to the individual com...

D. C. Ion

1980-01-01T23:59:59.000Z

270

DOE/EIS-0283; Surplus Plutonium Disposition Final Environmental Impact Statement (11/1999)  

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

3 of 5 3 of 5 Volume II Final Environmental Impact Statement November 1999 DOE/EIS-0283 Surplus Plutonium Disposition Final Environmental Impact Statement Volume II United States Department of Energy Office of Fissile Materials Disposition November 1999 Cover Sheet Responsible Agency: United States Department of Energy (DOE) Title: Surplus Plutonium Disposition Final Environmental Impact Statement (SPD EIS) (DOE/EIS-0283) Locations of Candidate Sites: California, Idaho, New Mexico, North Carolina, South Carolina, Tennessee, Texas, Virginia, and Washington Contacts: For further information on the SPD Final EIS contact: For information on the DOE National Environmental Policy Act (NEPA) process contact: Mr. G. Bert Stevenson, NEPA Compliance Officer Ms. Carol Borgstrom, Director Office of Fissile Materials Disposition

271

Used Fuel Disposition R&D Documents | Department of Energy  

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

Used Fuel Disposition Used Fuel Disposition Research & Development » Used Fuel Disposition R&D Documents Used Fuel Disposition R&D Documents December 4, 2013 Preliminary Report on Dual-Purpose Canister Disposal Alternatives (FY13) This report documents the first phase of a multi-year project to understand the technical feasibility and logistical implications of direct disposal of spent nuclear fuel in existing dual-purpose canisters (DPCs) and other types of storage casks. October 25, 2013 Deep Borehole Disposal Research: Demonstration Site Selection Guidelines, Borehole Seals Design, and RD&D Needs Deep borehole disposal is one alternative for the disposal of spent nuclear fuel and other radioactive waste forms; identifying a site or areas with favorable geological, hydrogeological, and geochemical conditions is one of

272

EIS-0475: Disposition of the Bannister Federal Complex, Kansas City, MO |  

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

EIS-0475: Disposition of the Bannister Federal Complex, Kansas EIS-0475: Disposition of the Bannister Federal Complex, Kansas City, MO EIS-0475: Disposition of the Bannister Federal Complex, Kansas City, MO Summary NNSA/DOE announces its intent to prepare an EIS for the disposition of the Bannister Federal Complex, Kansas City, MO. NNSA previously decided in a separate NEPA review (EA-1592) to relocate its operations from the Bannister Federal Complex to a newly constructed industrial campus eight miles from the current location. NOTE: On November 30, 2012, DOE announced the cancellation of this EIS and its intent to prepare an Environmental Assessment (EA-1947). Public Comment Opportunities None available at this time. Documents Available for Download November 30, 2012 EA-1947: Notice of Intent to Prepare an Environmental Assessment and

273

Fuel Cycle Potential Waste Inventory for Disposition Rev 5 | Department of  

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

Fuel Cycle Potential Waste Inventory for Disposition Rev 5 Fuel Cycle Potential Waste Inventory for Disposition Rev 5 Fuel Cycle Potential Waste Inventory for Disposition Rev 5 The United States currently utilizes a once-through fuel cycle where used nuclear fuel is stored onsite in either wet pools or in dry storage systems with ultimate disposal envisioned in a deep mined geologic repository. This report provides an estimate of potential waste inventory and waste form characteristics for the DOE used nuclear fuel and high-level radioactive waste and a variety of commercial fuel cycle alternatives in order to support subsequent system-level evaluations of disposal system performance. Fuel Cycle Potential Waste Inventory for Disposition R5a.docx More Documents & Publications Repository Reference Disposal Concepts and Thermal Load Management Analysis

274

EA-1410: Proposed Disposition of the Omega West Facility at Los Alamos  

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

10: Proposed Disposition of the Omega West Facility at Los 10: Proposed Disposition of the Omega West Facility at Los Alamos National Laboratory, Los Alamos, New Mexico EA-1410: Proposed Disposition of the Omega West Facility at Los Alamos National Laboratory, Los Alamos, New Mexico SUMMARY This EA evaluates the environmental impacts for the proposal to remove the Omega West Facility and the remaining support structures from Los Alamos Canyon at the U.S. Department of Energy Los Alamos National Laboratory in Los Alamos, New Mexico. PUBLIC COMMENT OPPORTUNITIES None available at this time. DOCUMENTS AVAILABLE FOR DOWNLOAD March 28, 2002 EA-1410: Finding of No Significant Impact Proposed Disposition of the Omega West Facility at Los Alamos National Laboratory, Los Alamos, New Mexico March 28, 2002 EA-1410: Final Environmental Assessment

275

On Solar Energy Disposition:A Perspective from Observation and Modeling  

Science Journals Connector (OSTI)

Solar energy disposition (SED) concerns the amount of solar radiation reflected to space, absorbed in the atmosphere, and absorbed at the surface. The state of knowledge on SED is examined by comparing eight datasets from surface and satellite ...

Zhanqing Li; Louis Moreau; Albert Arking

1997-01-01T23:59:59.000Z

276

Magnetic Field Effect on Charmonium Production in High Energy Nuclear Collisions  

E-Print Network (OSTI)

It is important to understand the strong external magnetic field generated at the very beginning of high energy nuclear collisions. We study the effect of the magnetic field on the charmonium yield and anisotropic distribution in Pb+Pb collisions at the LHC energy. The time dependent Schr\\"odinger equation is employed to describe the motion of $c\\bar{c}$ pairs. We compare our model prediction of non- collective anisotropic parameter $v_2$ of $J/\\psi$s with CMS data at high transverse momentum. This is the first attempt to measure the magnetic field in high energy nuclear collisions.

Guo, Xingyu; Xu, Nu; Xu, Zhe; Zhuang, Pengfei

2015-01-01T23:59:59.000Z

277

Predicted and actual productions of horizontal wells in heavy-oil fields  

Science Journals Connector (OSTI)

This paper discusses the comparison of predicted and actual cumulative and daily oil production. The predicted results were obtained from the use of Joshi's equation, wherein, the effects of anisotropy and eccentricity were included. The cumulative production obtained from the use of equations developed by Borisov, Giger, Renard and Dupuy resulted in errors in excess of 100%, thus, they were not considered applicable for predicting cumulative and daily flows of heavy oils in horizontal wells. The wells considered in this analysis varied from 537 to 1201 metres with corresponding well bores of 0.089 to. 0.110 m. Using Joshi's equation, the predicted cumulative oil-production was within a 20% difference for up to 12 months of production for long wells and up to 24 months for short wells. Short wells were defined as those being under 1000 m.

Peter Catania

2000-01-01T23:59:59.000Z

278

Identification and selection of a stable gel polymer to control or reduce water production in gas condensate fields  

Science Journals Connector (OSTI)

Abstract The existence of water in hydrocarbon reservoirs damages the wells. In many cases, it leads to shut off the wells and decreases the gas production efficiency. For example, one of the problems of fractured gas wells is unwanted water invasion to gas production areas through the existing fracture in the reservoirs. This would increase the water production and decrease the gas production efficiency. As well, increasing of water/gas production ratio will increase the total operational costs due to water separation from the gas flow, corrosion of inside and outside well facilities and hydrate formation. Hence, prevention of water production in gas wells can boost the gas production economy. Generally, some mechanical and chemical methods exist to control unwanted water. One of the most effective methods to control and prevent of water production in hydrocarbon reservoirs is gel polymer method. The gel polymer is a chemical method with high efficiency and low cost. This work is concerned with producing a stable and suitable gel polymer (HPAM–Cr (III) gel system) to control and remove water in the gas condensate fields. The important parameters in the gel construction such as the polymer and cross-linker concentrations, pH of solution and also the effect of different additives have been examined and optimized at four temperatures of 30, 60, 80 and 100 °C. The effect of gel polymer on the absolute and relative permeabilities of two different cores for water and gas condensate fluids has been investigated. The results show that prepared gel polymer results in decreasing the water relative permeability, while increases the gas condensate relative permeability.

Shahram Karimi; Feridun Esmaeilzadeh; Dariush Mowla

2014-01-01T23:59:59.000Z

279

Environmental Assessment Addendum Disposition of Additional Waste at the Paducah Site  

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

9-A 9-A Environmental Assessment Addendum Disposition of Additional Waste at the Paducah Site December 2003 U. S. Department of Energy Oak Ridge Operations Oak Ridge, Tennessee DOE/EA-1339-A Disposition of Additional Waste at the Paducah Site Environmental Assessment Addendum December 2003 U. S. Department of Energy Oak Ridge Operations U.S. Department of Energy Paducah Site DOE/EA-1339A Table of Contents Table of Contents............................................................................................................................ v Acronyms.......................................................................................................................................

280

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

E-Print Network (OSTI)

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

Gonzalez, Vanessa L

2012-06-07T23:59:59.000Z

Note: This page contains sample records for the topic "disposition field production" 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

Production of field-reversed mirror plasma with a coaxial plasma gun  

DOE Patents (OSTI)

The use of a coaxial plasma gun to produce a plasma ring which is directed into a magnetic field so as to form a field-reversed plasma confined in a magnetic mirror. Plasma thus produced may be used as a target for subsequent neutral beam injection or other similarly produced and projected plasma rings or for direct fusion energy release in a pulsed mode.

Hartman, Charles W. (Alamo, CA); Shearer, James W. (Livermore, CA)

1982-01-01T23:59:59.000Z

282

The Impact of Farmer-Field-Schools on Knowledge and Productivity: A Study of Potato Farmers in the Peruvian Andes1  

E-Print Network (OSTI)

1 The Impact of Farmer-Field-Schools on Knowledge and Productivity: A Study of Potato Farmers-school (FFS) program on farmers' knowledge of integrated pest management (IPM) practices related to potato practices has the potential to significantly improve productivity in potato production. U.S. General

Sadoulet, Elisabeth

283

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

SciTech Connect

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

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

1998-08-01T23:59:59.000Z

284

Process modeling of plutonium conversion and MOX fabrication for plutonium disposition  

SciTech Connect

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

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

1998-10-01T23:59:59.000Z

285

Metabolism and disposition of 1-bromopropane in rats and mice following inhalation or intravenous administration  

Science Journals Connector (OSTI)

Workplace exposure to 1-bromopropane (1-BrP) can potentially occur during its use in spray adhesives, fats, waxes, and resins. 1-BrP may be used to replace ozone depleting solvents, resulting in an increase in its annual production in the US, which currently exceeds 1 million pounds. The potential for human exposure to 1-BrP and the reports of adverse effects associated with potential occupational exposure to high levels of 1-BrP have increased the need for the development of biomarkers of exposure and an improved understanding of 1-BrP metabolism and disposition. In this study, the factors influencing the disposition and biotransformation of 1-BrP were examined in male F344 rats and B6C3F1 mice following inhalation exposure (800 ppm) or intravenous administration (5, 20, and 100 mg/kg). [1,2,3-13C]1-BrP and [1-14C]1-BrP were administered to enable characterization of urinary metabolites using NMR spectroscopy, LC–MS/MS, and HPLC coupled radiochromatography. Exhaled breath volatile organic chemicals (VOC), exhaled CO2, urine, feces, and tissues were collected for up to 48 h post-administration for determination of radioactivity distribution. Rats and mice exhaled a majority of the administered dose as either VOC (40–72%) or 14CO2 (10–30%). For rats, but not mice, the percentage of the dose exhaled as VOC increased between the mid (? 50%) and high (? 71%) dose groups; while the percentage of the dose exhaled as 14CO2 decreased (19 to 10%). The molar ratio of exhaled 14CO2 to total released bromide, which decreased as dose increased, demonstrated that the proportion of 1-BrP metabolized via oxidation relative to pathways dependent on glutathione conjugation is inversely proportional to dose in the rat. [14C]1-BrP equivalents were recovered in urine (13–17%, rats; 14–23% mice), feces (rats and mice administered i.v. 5 to 100 mg/kg [14C]1-BrP. Metabolites characterized in urine of rats and mice include N-acetyl-S-propylcysteine, N-acetyl-3-(propylsulfinyl)alanine, N-acetyl-S-(2-hydroxypropyl)cysteine, 1-bromo-2-hydroxypropane-O-glucuronide, N-acetyl-S-(2-oxopropyl)cysteine, and N-acetyl-3-[(2-oxopropyl)sulfinyl]alanine. These metabolites may be formed following oxidation of 1-bromopropane to 1-bromo-2-propanol and bromoacetone and following subsequent glutathione conjugation with either of these compounds. Rats pretreated with 1-aminobenzotriazole (ABT), a potent inhibitor of P450 excreted less in urine (?30%), exhaled as 14CO2 (?80%), or retained in liver (?90%), with a concomitant increase in radioactivity expired as VOC (?52%). Following ABT pretreatment, rat urinary metabolites were reduced in number from 10 to 1, N-acetyl-S-propylcysteine, which accounted for > 90% of the total urinary radioactivity in ABT pretreated rats. Together, these data demonstrate a role for cytochrome P450 and glutathione in the dose-dependent metabolism and disposition of 1-BrP in the rat.

C.E. Garner; S.C.J. Sumner; J.G. Davis; J.P. Burgess; Y. Yueh; J. Demeter; Q. Zhan; J. Valentine; A.R. Jeffcoat; L.T. Burka; J.M. Mathews

2006-01-01T23:59:59.000Z

286

Metabolism and disposition of 1-bromopropane in rats and mice following inhalation or intravenous administration  

SciTech Connect

Workplace exposure to 1-bromopropane (1-BrP) can potentially occur during its use in spray adhesives, fats, waxes, and resins. 1-BrP may be used to replace ozone depleting solvents, resulting in an increase in its annual production in the US, which currently exceeds 1 million pounds. The potential for human exposure to 1-BrP and the reports of adverse effects associated with potential occupational exposure to high levels of 1-BrP have increased the need for the development of biomarkers of exposure and an improved understanding of 1-BrP metabolism and disposition. In this study, the factors influencing the disposition and biotransformation of 1-BrP were examined in male F344 rats and B6C3F1 mice following inhalation exposure (800 ppm) or intravenous administration (5, 20, and 100 mg/kg). [1,2,3-{sup 13}C]1-BrP and [1-{sup 14}C]1-BrP were administered to enable characterization of urinary metabolites using NMR spectroscopy, LC-MS/MS, and HPLC coupled radiochromatography. Exhaled breath volatile organic chemicals (VOC), exhaled CO{sub 2}, urine, feces, and tissues were collected for up to 48 h post-administration for determination of radioactivity distribution. Rats and mice exhaled a majority of the administered dose as either VOC (40-72%) or {sup 14}CO{sub 2} (10-30%). For rats, but not mice, the percentage of the dose exhaled as VOC increased between the mid ({approx} 50%) and high ({approx} 71%) dose groups; while the percentage of the dose exhaled as {sup 14}CO{sub 2} decreased (19 to 10%). The molar ratio of exhaled {sup 14}CO{sub 2} to total released bromide, which decreased as dose increased, demonstrated that the proportion of 1-BrP metabolized via oxidation relative to pathways dependent on glutathione conjugation is inversely proportional to dose in the rat. [{sup 14}C]1-BrP equivalents were recovered in urine (13-17%, rats; 14-23% mice), feces (< 2%), or retained in the tissues and carcass (< 6%) of rats and mice administered i.v. 5 to 100 mg/kg [{sup 14}C]1-BrP. Metabolites characterized in urine of rats and mice include N-acetyl-S-propylcysteine, N-acetyl-3-(propylsulfinyl)alanine, N-acetyl-S-(2-hydroxypropyl)cysteine, 1-bromo-2-hydroxypropane-O-glucuronide, N-acetyl-S-(2-oxopropyl)cysteine, and N-acetyl-3-[(2-oxopropyl)sulfinyl]alanine. These metabolites may be formed following oxidation of 1-bromopropane to 1-bromo-2-propanol and bromoacetone and following subsequent glutathione conjugation with either of these compounds. Rats pretreated with 1-aminobenzotriazole (ABT), a potent inhibitor of P450 excreted less in urine ({down_arrow}30%), exhaled as {sup 14}CO2 ({down_arrow}80%), or retained in liver ({down_arrow}90%), with a concomitant increase in radioactivity expired as VOC ({up_arrow}52%). Following ABT pretreatment, rat urinary metabolites were reduced in number from 10 to 1, N-acetyl-S-propylcysteine, which accounted for > 90% of the total urinary radioactivity in ABT pretreated rats. Together, these data demonstrate a role for cytochrome P450 and glutathione in the dose-dependent metabolism and disposition of 1-BrP in the rat.

Garner, C.E. [Department of Drug Metabolism and Disposition, RTI International, Research Triangle Park, NC 27709 (United States)]. E-mail: cegarner@rti.org; Sumner, S.C.J. [Department of Drug Metabolism and Disposition, RTI International, Research Triangle Park, NC 27709 (United States); Davis, J.G. [Department of Drug Metabolism and Disposition, RTI International, Research Triangle Park, NC 27709 (United States); Burgess, J.P. [Department of Drug Metabolism and Disposition, RTI International, Research Triangle Park, NC 27709 (United States); Yueh, Y. [Department of Drug Metabolism and Disposition, RTI International, Research Triangle Park, NC 27709 (United States); Demeter, J. [Department of Drug Metabolism and Disposition, RTI International, Research Triangle Park, NC 27709 (United States); Zhan, Q. [Department of Drug Metabolism and Disposition, RTI International, Research Triangle Park, NC 27709 (United States); Valentine, J. [Department of Drug Metabolism and Disposition, RTI International, Research Triangle Park, NC 27709 (United States); Jeffcoat, A.R. [Department of Drug Metabolism and Disposition, RTI International, Research Triangle Park, NC 27709 (United States); Burka, L.T. [National Institute of Environmental Health Sciences, Research Triangle Park, NC 27709 (United States); Mathews, J.M. [Department of Drug Metabolism and Disposition, RTI International, Research Triangle Park, NC 27709 (United States)

2006-08-15T23:59:59.000Z

287

Field-project designs for carbon dioxide sequestration and enhanced coalbed methane production  

SciTech Connect

Worldwide concerns about global warming and possible contributions to it from anthropogenic carbon dioxide have become important during the past several years. Coal seams may make excellent candidates for CO{sub 2} sequestration; coal-seam sequestration could enhance methane production and improve sequestration economics. Reservoir-simulation computations are an important component of any engineering design before carbon dioxide is injected underground. We have performed such simulations for a hypothetical pilot-scale project in representative coal seams. In these simulations we assume four horizontal production wells that form a square, that is, two wells drilled at right angles to each other forming two sides of a square, with another pair of horizontal wells similarly drilled to form the other two sides. Four shorter horizontal wells are drilled from a vertical well at the center of the square, forming two straight lines orthogonal to each other. By modifying coal properties, especially sorption rate, we have approximated different types of coals. By varying operational parameters, such as injector length, injection well pressure, time to injection, and production well pressure, we can evaluate different production schemes to determine an optimum for each coal type. Any optimization requires considering a tradeoff between total CO{sub 2} sequestered and the rate of methane production. Values of total CO{sub 2} sequestered and methane produced are presented for multiple coal types and different operational designs. 30 refs., 11 figs., 1 tab.

W. Neal Sams; Grant Bromhal; Sinisha Jikich; Turgay Ertekin; Duane H. Smith [EG& amp; G Technical Services, Morgantown, WV (United States). National Energy Technology Laboratory

2005-12-01T23:59:59.000Z

288

Production  

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

Algae production R&D focuses on exploring resource use and availability, algal biomass development and improvements, characterizing algal biomass components, and the ecology and engineering of...

289

Photo-production of scalar particles in the field of a circularly polarized laser beam  

E-Print Network (OSTI)

The photo-production of a pair of scalar particles in the presence of an intense, circularly polarized laser beam is investigated. Using the optical theorem within the framework of scalar quantum electrodynamics, explicit expressions are given for the pair production probability in terms of the imaginary part of the vacuum polarization tensor. Its leading asymptotic behavior is determined for various limits of interest. The influence of the absence of internal spin degrees of freedom is analyzed via a comparison with the corresponding probabilities for production of spin-1/2 particles; the lack of spin is shown to suppress the pair creation rate, as compared to the predictions from Dirac theory. Potential applications of our results for the search of minicharged particles are indicated.

Selym Villalba-Chávez; Carsten Müller

2012-08-17T23:59:59.000Z

290

From Fields to Fuels: Recent Advances in the Microbial Production of Biofuels  

Science Journals Connector (OSTI)

In a move toward consolidated bioprocessing (engineering a microorganism that is capable of both digesting biomass and converting the resulting sugars into biofuels), the group engineered the biofuel-producing strain to express and secrete xylanases that break down xylan into xylose, a pentose that is readily catabolized by E. coli. ... Another use of the ?-oxidation pathway in biofuel production is the production of methyl ketone biofuels in E. coli. ... With improvements in both biofuel synthesis pathways and biomass digestion capabilities, our approach could provide an economical route to prodn. of advanced biofuels. ...

Yan Kung; Weerawat Runguphan; Jay D. Keasling

2012-11-05T23:59:59.000Z

291

INCREASING HEAVY OIL RESERVES IN THE WILMINGTON OIL FIELD THROUGH ADVANCED RESERVOIR CHARACTERIZATION AND THERMAL PRODUCTION TECHNOLOGIES  

SciTech Connect

The project involves using advanced reservoir characterization and thermal production technologies to improve thermal recovery techniques and lower operating and capital costs in a slope and basin clastic (SBC) reservoir in the Wilmington field, Los Angeles Co., Calif. Through September 2001, project work has been completed on the following activities: data preparation; basic reservoir engineering; developing a deterministic three dimensional (3-D) geologic model, a 3-D deterministic reservoir simulation model and a rock-log model; well drilling and completions; and surface facilities on the Fault Block II-A Tar Zone (Tar II-A). Work is continuing on research to understand the geochemistry and process regarding the sand consolidation well completion technique, final reservoir tracer work, operational work and research studies to prevent thermal-related formation compaction in the Tar II-A steamflood area, and operational work on the Tar V steamflood pilot and Tar II-A post-steamflood projects. The project team spent the Fourth Quarter 2001 performing routine well work and reservoir surveillance on the Tar II-A post-steamflood and Tar V pilot steamflood projects. The Tar II-A post-steamflood operation started in February 1999 and steam chest fillup occurred in September-October 1999. The targeted reservoir pressures in the ''T'' and ''D'' sands are maintained at 90 {+-} 5% hydrostatic levels by controlling water injection and gross fluid production and through the bimonthly pressure monitoring program enacted at the start of the post-steamflood phase. The project team ramped up well work activity from October 2000 through November 2001 to increase production and injection. In December, water injection well FW-88 was plug and abandoned and replaced by new well FW-295 into the ''D'' sands to accommodate the Port of Long Beach at their expense. Well workovers are planned for 2002 as described in the Operational Management section. Expanding thermal recovery operations to other sections of the Wilmington Oil Field, including the Tar V horizontal well pilot steamflood project, is a critical part of the City of Long Beach and Tidelands Oil Production Company's development strategy for the field. The steamflood operation in the Tar V pilot project is mature and profitable. Recent production performance is below projections because of wellbore mechanical limitations that were being addressed in 2001. As the fluid production is hot, the pilot steamflood was converted to a hot waterflood project in June 2001.

Scott Hara

2002-01-31T23:59:59.000Z

292

Radiation damage effects in candidate titanates for Pu disposition: Zirconolite  

Science Journals Connector (OSTI)

Results from studies of radiation-induced damage from the alpha decay of 238Pu on the density and crystal structure of a nominally phase-pure zirconolite and two other zirconolite-bearing ceramics are discussed. Macro and micro swelling were found to be temperature independent, whereas the density determined with He gas pycnometry was temperature dependent. Approximately 2.6 × 1018 ?/g were needed to render the specimens X-ray amorphous– more to saturate the swelling. Unlike pyrochlore-based ceramics, we did not observe any phase changes associated with storage temperature and damage ingrowth. The forward dissolution rate at a pH value of 2 for material containing essentially all zirconolite is 1.7(4) × 10?3 g/(m2 d) with very little pH dependence and no dependence on the amount of radiation-induced damage. Even after the radiation-induced swelling saturated, the specimens remained physically intact with no evidence for microcracking. Thus, the material remains physically a viable material for the disposition of surplus weapons-grade Pu.

D.M. Strachan; R.D. Scheele; E.C. Buck; A.E. Kozelisky; R.L. Sell; R.J. Elovich; W.C. Buchmiller

2008-01-01T23:59:59.000Z

293

Potential role of ABC-assisted repositories in U.S. plutonium and high-level waste disposition  

SciTech Connect

This paper characterizes the issues involving deep geologic disposal of LWR spent fuel rods, then presents results of an investigation to quantify the potential role of Accelerator-Based Conversion (ABC) in an integrated national nuclear materials and high level waste disposition strategy. The investigation used the deep geological repository envisioned for Yucca Mt., Nevada as a baseline and considered complementary roles for integrated ABC transmutation systems. The results indicate that although a U.S. geologic waste repository will continue to be required, waste partitioning and accelerator transmutation of plutonium, the minor actinides, and selected long-lived fission products can result in the following substantial benefits: plutonium burndown to near zero levels, a dramatic reduction of the long term hazard associated with geologic repositories, an ability to place several-fold more high level nuclear waste in a single repository, electricity sales to compensate for capital and operating costs.

Berwald, David; Favale, Anthony; Myers, Timothy; McDaniel, Jerry [Grumman Aerospace Corporation, Bethpage New York 11714 (United States); Bechtel Corporation, 50 Beal St., San Francisco, California 94105 (United States)

1995-09-15T23:59:59.000Z

294

DOE/EIS-0240-SA-1: Supplement Analysis for the Disposition of Surplus Highly Enriched Uranium (October 2007)  

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

0-SA1 0-SA1 SUPPLEMENT ANALYSIS DISPOSITION OF SURPLUS HIGHLY ENRICHED URANIUM October 2007 U.S. Department of Energy National Nuclear Security Administration Office of Fissile Materials Disposition Washington, D.C. i TABLE OF CONTENTS 1.0 Introduction and Purpose .................................................................................................................1 2.0 Background......................................................................................................................................1 2.1 Scope of the HEU EIS............................................................................................................ 2 2.2 Status of Surplus HEU Disposition Activities .......................................................................

295

PRODUCTION OF LARGE VOLUME CYLINDRICAL RF PLASMA USING CIRCULAR MAGNETIC LINE CUSP FIELD  

Science Journals Connector (OSTI)

A large volume cylindrical rf (radio frequency) plasma source using a circular magnetic line cusp field has been developed for various large scale plasma processings. In this type of plasma source, a capacitively coupled 13.56 \\{MHz\\} rf plasma is produced in a circular magnetic line cusp field. Two versions of the plasma source have been constructed and tasted. The first version has a pair of peripheral rf electrodes placed outside the ionization chamber and is suitable for preparing a large volume uniform plasma. This plasma source can attain uniformity within 107 cm?3 over a 30 cm diameter region. The other which is provided with parallel doughnut plate electrodes forming part of the chamber wall serves as a high current plasma source, where the electron density is proportional to the rf power and equal to 7 × 109 cm?3 for 500 W.

K. YAMAUCHI; M. SHIBAGAKI; A. KONO; K. TAKAHASHI; T. SHEBUYA; E. YABE; K. TAKAYAMA

1993-01-01T23:59:59.000Z

296

Production  

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

Algae production R&D focuses on exploring resource use and availability, algal biomass development and improvements, characterizing algal biomass components, and the ecology and engineering of cultivation systems.

297

Barriers and Issues Related to Achieving Final Disposition of Depleted Uranium  

SciTech Connect

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

298

Methods to estimate on-field nitrogen emissions from crop production as an input to LCA studies in the agricultural sector  

Science Journals Connector (OSTI)

Nitrogen compounds emitted from the field are usually considered in Life Cycle Assessments (LCA) of agricultural products or processes. The environmentally most important of these N emissions are ammonia (NH3), n...

Frank Brentrup; Jürgen Küsters…

2000-11-01T23:59:59.000Z

299

INCREASING HEAVY OIL RESERVES IN THE WILMINGTON OIL FIELD THROUGH ADVANCED RESERVOIR CHARACTERIZATION AND THERMAL PRODUCTION TECHNOLOGIES  

SciTech Connect

The objective of this project is to increase the recoverable heavy oil reserves within sections of the Wilmington Oil Field, near Long Beach, California through the testing and application of advanced reservoir characterization and thermal production technologies. The successful application of these technologies will result in expanding their implementation throughout the Wilmington Field and, through technology transfer, to other slope and basin clastic (SBC) reservoirs. The existing steamflood in the Tar zone of Fault Block II-A (Tar II-A) has been relatively inefficient because of several producibility problems which are common in SBC reservoirs: inadequate characterization of the heterogeneous turbidite sands, high permeability thief zones, low gravity oil and non-uniform distribution of the remaining oil. This has resulted in poor sweep efficiency, high steam-oil ratios, and early steam breakthrough. Operational problems related to steam breakthrough, high reservoir pressure, and unconsolidated sands have caused premature well and downhole equipment failures. In aggregate, these reservoir and operational constraints have resulted in increased operating costs and decreased recoverable reserves. A suite of advanced reservoir characterization and thermal production technologies are being applied during the project to improve oil recovery and reduce operating costs.

Scott Hara

2001-06-27T23:59:59.000Z

300

INCREASING HEAVY OIL RESERVES IN THE WILMINGTON OIL FIELD THROUGH ADVANCED RESERVOIR CHARACTERIZATION AND THERMAL PRODUCTION TECHNOLOGIES  

SciTech Connect

The project involves using advanced reservoir characterization and thermal production technologies to improve thermal recovery techniques and lower operating and capital costs in a slope and basin clastic (SBC) reservoir in the Wilmington field, Los Angeles Co., Calif. Through June 2001, project work has been completed on the following activities: data preparation; basic reservoir engineering; developing a deterministic three dimensional (3-D) geologic model, a 3-D deterministic reservoir simulation model and a rock-log model; well drilling and completions; and surface facilities on the Fault Block II-A Tar Zone (Tar II-A). Work is continuing on research to understand the geochemistry and process regarding the sand consolidation well completion technique, final reservoir tracer work, operational work and research studies to prevent thermal-related formation compaction in the Tar II-A steamflood area, and operational work on the Tar V steamflood pilot and Tar II-A post-steamflood projects. The project team spent the Third Quarter 2001 performing well work and reservoir surveillance on the Tar II-A post-steamflood project. The Tar II-A post-steamflood operation started in February 1999 and steam chest fillup occurred in September-October 1999. The targeted reservoir pressures in the ''T'' and ''D'' sands are maintained at 90 {+-} 5% hydrostatic levels by controlling water injection and gross fluid production and through the bimonthly pressure monitoring program enacted at the start of the post-steamflood phase. The project team ramped up well work activity from October 2000 to September 2001 to increase production and injection. This work will continue through 2001 as described in the Operational Management section. Expanding thermal recovery operations to other sections of the Wilmington Oil Field, including the Tar V horizontal well pilot steamflood project, is a critical part of the City of Long Beach and Tidelands Oil Production Company's development strategy for the field. The current steamflood operations in the Tar V pilot are economical, but recent performance is below projections because of wellbore mechanical limitations that are being addressed in 2001.

Scott Hara

2001-11-01T23:59:59.000Z

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301

INCREASING HEAVY OIL RESERVES IN THE WILMINGTON OIL FIELD THROUGH ADVANCED RESERVOIR CHARACTERIZATION AND THERMAL PRODUCTION TECHNOLOGIES  

SciTech Connect

The project involves using advanced reservoir characterization and thermal production technologies to improve thermal recovery techniques and lower operating and capital costs in a slope and basin clastic (SBC) reservoir in the Wilmington field, Los Angeles Co., CA. Through September 2000, project work has been completed on the following activities: data preparation; basic reservoir engineering; developing a deterministic three dimensional (3-D) geologic model, a 3-D deterministic reservoir simulation model and a rock-log model; well drilling and completions; and surface facilities on the Fault Block II-A Tar Zone (Tar II-A). Work is continuing on improving core analysis techniques, final reservoir tracer work, operational work and research studies to prevent thermal-related formation compaction in the Tar II-A steamflood area, and operational work on the Tar V steamflood pilot and Tar II-A post steamflood projects. Work was discontinued on the stochastic geologic model and developing a 3-D stochastic thermal reservoir simulation model of the Tar II-A Zone so the project team could use the 3-D deterministic reservoir simulation model to provide alternatives for the Tar II-A post steamflood operations and shale compaction studies. The project team spent the fourth quarter 2000 performing well work and reservoir surveillance on the Tar II-A post-steamflood project and the Tar V horizontal well steamflood pilot. Expanding thermal recovery operations to other sections of the Wilmington Oil Field, including the Tar V horizontal well pilot steamflood project, is a critical part of the City of Long Beach and Tidelands Oil Production Company's development strategy for the field. The current steamflood operations in the Tar V pilot are economical, but recent performance is below projections because of wellbore mechanical limitations that are being evaluated.

Scott Hara

2001-05-07T23:59:59.000Z

302

INCREASING HEAVY OIL RESERVES IN THE WILMINGTON OIL FIELD THROUGH ADVANCED RESERVOIR CHARACTERIZATION AND THERMAL PRODUCTION TECHNOLOGIES  

SciTech Connect

The objective of this project is to increase the recoverable heavy oil reserves within sections of the Wilmington Oil Field, near Long Beach, California, through the testing and application of advanced reservoir characterization and thermal production technologies. The hope is that successful application of these technologies will result in their implementation throughout the Wilmington Field and, through technology transfer, will be extended to increase the recoverable oil reserves in other slope and basin clastic (SBC) reservoirs. The existing steamflood in the Tar zone of Fault Block II-A (Tar II-A) has been relatively inefficient because of several producibility problems which are common in SBC reservoirs: inadequate characterization of the heterogeneous turbidite sands, high permeability thief zones, low gravity oil and non-uniform distribution of the remaining oil. This has resulted in poor sweep efficiency, high steam-oil ratios, and early steam breakthrough. Operational problems related to steam breakthrough, high reservoir pressure, and unconsolidated sands have caused premature well and downhole equipment failures. In aggregate, these reservoir and operational constraints have resulted in increased operating costs and decreased recoverable reserves. A suite of advanced reservoir characterization and thermal production technologies are being applied during the project to improve oil recovery and reduce operating costs, including: (1) Development of three-dimensional (3-D) deterministic and stochastic reservoir simulation models--thermal or otherwise--to aid in reservoir management of the steamflood and post-steamflood phases and subsequent development work. (2) Development of computerized 3-D visualizations of the geologic and reservoir simulation models to aid reservoir surveillance and operations. (3) Perform detailed studies of the geochemical interactions between the steam and the formation rock and fluids. (4) Testing and proposed application of a novel alkaline-steam well completion technique for the containment of the unconsolidated formation sands and control of fluid entry and injection profiles. (5) Installation of a 2100 ft, 14 inch insulated, steam line beneath a harbor channel to supply steam to an island location. (6) Testing and proposed application of thermal recovery technologies to increase oil production and reserves: (a) Performing pilot tests of cyclic steam injection and production on new horizontal wells. (b) Performing pilot tests of hot water-alternating-steam (WAS) drive in the existing steam drive area to improve thermal efficiency. (7) Perform a pilot steamflood with the four horizontal injectors and producers using a pseudo steam-assisted gravity-drainage (SAGD) process. (8) Advanced reservoir management, through computer-aided access to production and geologic data to integrate reservoir characterization, engineering, monitoring and evaluation.

Unknown

2001-08-08T23:59:59.000Z

303

Alternative technical summary report for direct disposition in deep boreholes: Direct disposal of plutonium metal/plutonium dioxide in compound canisters, Version 4.0. Fissile Materials Disposition Program  

SciTech Connect

This report summarizes and compares the Immobilized and Direct Beep Borehole Disposition Alternatives. The important design concepts, facility features and operational procedures are briefly described, and a discussion of the issues that affect the evaluation of each alternative against the programmatic assessment criteria that have been established for selecting the preferred alternatives for plutonium disposition.

Wijesinghe, A.M.

1996-08-23T23:59:59.000Z

304

Water issues associated with heavy oil production.  

SciTech Connect

Crude oil occurs in many different forms throughout the world. An important characteristic of crude oil that affects the ease with which it can be produced is its density and viscosity. Lighter crude oil typically can be produced more easily and at lower cost than heavier crude oil. Historically, much of the nation's oil supply came from domestic or international light or medium crude oil sources. California's extensive heavy oil production for more than a century is a notable exception. Oil and gas companies are actively looking toward heavier crude oil sources to help meet demands and to take advantage of large heavy oil reserves located in North and South America. Heavy oil includes very viscous oil resources like those found in some fields in California and Venezuela, oil shale, and tar sands (called oil sands in Canada). These are described in more detail in the next chapter. Water is integrally associated with conventional oil production. Produced water is the largest byproduct associated with oil production. The cost of managing large volumes of produced water is an important component of the overall cost of producing oil. Most mature oil fields rely on injected water to maintain formation pressure during production. The processes involved with heavy oil production often require external water supplies for steam generation, washing, and other steps. While some heavy oil processes generate produced water, others generate different types of industrial wastewater. Management and disposition of the wastewater presents challenges and costs for the operators. This report describes water requirements relating to heavy oil production and potential sources for that water. The report also describes how water is used and the resulting water quality impacts associated with heavy oil production.

Veil, J. A.; Quinn, J. J.; Environmental Science Division

2008-11-28T23:59:59.000Z

305

DOE/EIS-0283; Surplus Plutonium Disposition Final Environmental Impact Statement (11/1999)  

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

2 of 5 2 of 5 Volume I - Part B Final Environmental Impact Statement November 1999 DOE/EIS-0283 Surplus Plutonium Disposition Final Environmental Impact Statement Volume I - Part B United States Department of Energy Office of Fissile Materials Disposition November 1999 Cover Sheet Responsible Agency: United States Department of Energy (DOE) Title: Surplus Plutonium Disposition Final Environmental Impact Statement (SPD EIS) (DOE/EIS-0283) Locations of Candidate Sites: California, Idaho, New Mexico, North Carolina, South Carolina, Tennessee, Texas, Virginia, and Washington Contacts: For further information on the SPD Final EIS contact: For information on the DOE National Environmental Policy Act (NEPA) process contact: Mr. G. Bert Stevenson, NEPA Compliance Officer Ms. Carol Borgstrom, Director

306

DOE Chooses Idaho Treatment Group, LLC to Disposition Waste at the Advanced  

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

Chooses Idaho Treatment Group, LLC to Disposition Waste at the Chooses Idaho Treatment Group, LLC to Disposition Waste at the Advanced Mixed Waste Treatment Project: Contract will continue cleanup and waste operations at the Idaho Site DOE Chooses Idaho Treatment Group, LLC to Disposition Waste at the Advanced Mixed Waste Treatment Project: Contract will continue cleanup and waste operations at the Idaho Site May 27, 2011 - 12:00pm Addthis Media Contact Brad Bugger (208) 526-0833 Idaho Falls - In order to further meet the U.S. Department of Energy's commitments to the citizens of the state of Idaho, the DOE today announced that it has selected Idaho Treatment Group, LLC (ITG) to perform waste processing at the Advanced Mixed Waste Treatment Project (AMWTP) at DOE's Idaho Site near Idaho Falls. The contract is estimated at approximately

307

U.S. and Russia Sign Plan for Russian Plutonium Disposition | Department of  

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

Sign Plan for Russian Plutonium Disposition Sign Plan for Russian Plutonium Disposition U.S. and Russia Sign Plan for Russian Plutonium Disposition November 19, 2007 - 4:31pm Addthis Will Eliminate Enough Russian Plutonium for Thousands of Nuclear Weapons WASHINGTON, DC -U.S. Secretary of Energy Samuel W. Bodman and Russian Federal Atomic Energy Agency Director Sergey Kiriyenko have signed a joint statement outlining a plan to dispose of 34 metric tons of surplus plutonium from Russia's weapons program. Under the new plan, the United States will cooperate with Russia to convert Russian weapon-grade plutonium into mixed oxide fuel (MOX) and irradiate the MOX fuel in the BN-600 fast reactor, currently operating at the Beloyarsk nuclear power plant, and in the BN-800 fast reactor, currently under construction at the same site. The United States and Russia also

308

DOE 2010 Safety and Security Reform Project - HSS Directives Disposition and Status (December 4, 2012)  

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

10 Safety and Security Reform Project - HSS Directives Disposition and Status (December 4, 2012) 10 Safety and Security Reform Project - HSS Directives Disposition and Status (December 4, 2012) Page 1 of 3 2010 HSS Directives Disposition Status Secretary of Energy Notice SEN-35-91, Nuclear Safety Policy Revise Complete - see Policy 420.1. Order 5400.5, Radiation Protection of the Public and the Environment Revise Complete - see Order 458.1. Order 5480.19, Conduct of Operations Requirements for DOE Facilities Revise Complete - see Order 422.1. Order 5480.20A, Personnel Selection, Training, Qualification, and Certification Requirements Revise Complete - see Order 426.2. Order 5480.30, Nuclear Reactor Design Criteria Re-certify Complete - re-certified. Manual 140.1-1B, Interface with the Defense Nuclear Facilities Safety Board Re-certify Complete - re-certified.

309

EIS-0283-S1: Supplement to the Surplus Plutonium Disposition Environmental  

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

3-S1: Supplement to the Surplus Plutonium Disposition 3-S1: Supplement to the Surplus Plutonium Disposition Environmental Impact Statement EIS-0283-S1: Supplement to the Surplus Plutonium Disposition Environmental Impact Statement SUMMARY The Supplement evaluates the potential environmental impacts of using MOX fuel in these six specific reactors named in the DCS proposal as well as other program changes made since the SPD Draft EIS was published. PUBLIC COMMENT OPPORTUNITIES None available at this time. DOCUMENTS AVAILABLE FOR DOWNLOAD November 5, 1999 EIS-0236-S1: DOE Notice of Availability of the Draft Environmental Impact Statement National Ignition Facility Draft Environmental Impact Statement to the Stockpile Stewardship and Management November 5, 1999 EIS-0236-S1: Notice of Availability for the Draft Supplemental Programmatic

310

Used Fuel Disposition R&D Documents | Department of Energy  

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

March 31, 2011 March 31, 2011 Used Fuel Disposition Campaign Disposal Research and Development Roadmap The U.S. Department of Energy Office of Nuclear Energy (DOE-NE), Office of Fuel Cycle Technology (OFCT) has established the Used Fuel Disposition Campaign (UFDC) to conduct the research and development (R&D) activities related to storage, transportation and disposal of used nuclear fuel (UNF) and high level nuclear waste (HLW). The Mission of the UFDC is March 30, 2011 Basis for Identification of Disposal Options for R and D for Spent Nuclear Fuel and High-Level Waste The Used Fuel Disposition campaign (UFD) is selecting a set of geologic media for further study including variations on the design of the repository, the engineered barrier, and the waste. Salt, clay/shale, and

311

Superfund Policy Statements and Guidance Regarding Disposition of Radioactive Waste in Non-NRC Licensed Disposal Facilities - 13407  

SciTech Connect

This talk will discuss EPA congressional testimony and follow-up letters, as well as letters to other stakeholders on EPA's perspectives on the disposition of radioactive waste outside of the NRC licensed disposal facility system. This will also look at Superfund's historical practices, and emerging trends in the NRC and agreement states on waste disposition. (author)

Walker, Stuart [U.S. Environmental Protection Agency (United States)] [U.S. Environmental Protection Agency (United States)

2013-07-01T23:59:59.000Z

312

The impact of personal dispositions on information sensitivity, privacy concern and trust in disclosing health information online  

Science Journals Connector (OSTI)

Reluctance to provide personal health information could impede the success of web-based healthcare services. This paper focuses on the role of personal dispositions in disclosing health information online. The conceptual model argues that individuals' ... Keywords: Health status, Information privacy concern, Information sensitivity, Intrinsic and extrinsic perspectives of trust, Intrinsic factors, Personal dispositions, Personality, Trust, Utility Theory

Gaurav Bansal; Fatemeh "Mariam" Zahedi; David Gefen

2010-05-01T23:59:59.000Z

313

Generation!and!Disposition!of!Municipal!Solid!Waste! (MSW)!in!the!United!States!A!National!Survey!  

E-Print Network (OSTI)

! 1! ! Generation!and!Disposition!of!Municipal!Solid!Waste! (MSW on Municipal Solid Waste (MSW) Generation and Disposition in the U.S., in collaboration with Ms. Nora Goldstein was not carried out in 2012 and in 2013 EEC and BioCycle agreed that the 2013 Survey of Waste Generation

Columbia University

314

INCREASING HEAVY OIL RESERVES IN THE WILMINGTON OIL FIELD THROUGH ADVANCED RESERVOIR CHARACTERIZATION AND THERMAL PRODUCTION TECHNOLOGIES  

SciTech Connect

The project involves using advanced reservoir characterization and thermal production technologies to improve thermal recovery techniques and lower operating and capital costs in a slope and basin clastic (SBC) reservoir in the Wilmington field, Los Angeles Co., CA. Through March 1999, project work has been completed related to data preparation, basic reservoir engineering, developing a deterministic three dimensional (3-D) geologic model, a 3-D deterministic reservoir simulation model, and a rock-log model, well drilling and completions, and surface facilities. Work is continuing on the stochastic geologic model, developing a 3-D stochastic thermal reservoir simulation model of the Fault Block IIA Tar (Tar II-A) Zone, and operational work and research studies to prevent thermal-related formation compaction. Thermal-related formation compaction is a concern of the project team due to observed surface subsidence in the local area above the steamflood project. Last quarter on January 12, the steamflood project lost its inexpensive steam source from the Harbor Cogeneration Plant as a result of the recent deregulation of electrical power rates in California. An operational plan was developed and implemented to mitigate the effects of the two situations. Seven water injection wells were placed in service in November and December 1998 on the flanks of the Phase 1 steamflood area to pressure up the reservoir to fill up the existing steam chest. Intensive reservoir engineering and geomechanics studies are continuing to determine the best ways to shut down the steamflood operations in Fault Block II while minimizing any future surface subsidence. The new 3-D deterministic thermal reservoir simulator model is being used to provide sensitivity cases to optimize production, steam injection, future flank cold water injection and reservoir temperature and pressure. According to the model, reservoir fill up of the steam chest at the current injection rate of 28,000 BPD and gross and net oil production rates of 7,700 BPD and 750 BOPD (injection to production ratio of 4) will occur in October 1999. At that time, the reservoir should act more like a waterflood and production and cold water injection can be operated at lower net injection rates to be determined. Modeling runs developed this quarter found that varying individual well injection rates to meet added production and local pressure problems by sub-zone could reduce steam chest fill-up by up to one month.

Scott Hara

2000-02-18T23:59:59.000Z

315

INCREASING HEAVY OIL RESERVES IN THE WILMINGTON OIL FIELD THROUGH ADVANCED RESERVOIR CHARACTERIZATION AND THERMAL PRODUCTION TECHNOLOGIES  

SciTech Connect

The project involves using advanced reservoir characterization and thermal production technologies to improve thermal recovery techniques and lower operating and capital costs in a slope and basin clastic (SBC) reservoir in the Wilmington field, Los Angeles Co., CA. Through March 2001, project work has been completed on the following activities: data preparation; basic reservoir engineering; developing a deterministic three dimensional (3-D) geologic model, a 3-D deterministic reservoir simulation model and a rock-log model; well drilling and completions; and surface facilities on the Fault Block II-A Tar Zone (Tar II-A). Work is continuing on research to understand the geochemistry and process regarding the sand consolidation well completion technique, final reservoir tracer work, operational work and research studies to prevent thermal-related formation compaction in the Tar II-A steamflood area, and operational work on the Tar V steamflood pilot and Tar II-A post-steamflood projects. The project team spent the Second Quarter 2001 performing well work and reservoir surveillance on the Tar II-A post-steamflood project. The Tar II-A steamflood reservoirs have been operated over fifteen months at relatively stable pressures, due in large part to the bimonthly pressure monitoring program enacted at the start of the post-steamflood phase in January 1999. Starting in the Fourth Quarter 2000, the project team has ramped up activity to increase production and injection. This work will continue through 2001 as described in the Operational Management section. Expanding thermal recovery operations to other sections of the Wilmington Oil Field, including the Tar V horizontal well pilot steamflood project, is a critical part of the City of Long Beach and Tidelands Oil Production Company's development strategy for the field. The current steamflood operations in the Tar V pilot are economical, but recent performance is below projections because of wellbore mechanical limitations that are being addressed in 2001. Much of the second quarter was spent writing DOE annual and quarterly reports to stay current with contract requirements.

Scott Hara

2001-05-08T23:59:59.000Z

316

Preliminary Technology Readiness Assessment (TRA) for the Calcine Disposition Project Volume 1 (CDP)  

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

TECHNOLOGY READINESS ASSESSMENT TECHNOLOGY READINESS ASSESSMENT OF THE CALCINE DISPOSITION PROJECT VOLUME ONE Anthony F. Kluk Hoyt C. Johnson Clyde Phillip McGinnis Michael Rinker Steven L. Ross Herbert G. Sutter John Vienna February 2011 Prepared by the U.S. Department of Energy Washington, DC February 2011 ii This page intentionally left blank. Review of Calcine Disposition Project Self-Assessment of Technology Maturation iii SIGNATURES ____________________________________ ____________________________________ Anthony F. Kluk, Team Lead Date ____________________________________ ____________________________________ Hoyt C. Johnson Date ____________________________________ ____________________________________ Clyde Phillip McGinnis Date ____________________________________ ____________________________________

317

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

SciTech Connect

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

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

1997-08-01T23:59:59.000Z

318

DOE/EIS-0283; Surplus Plutonium Disposition Final Environmental Impact Statement (11/1999)  

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

Summary Final Environmental Impact Statement November 1999 Summary DOE/EIS-0283 Surplus Plutonium Disposition Final Environmental Impact Statement Summary United States Department of Energy Office of Fissile Materials Disposition November 1999 Summary i Table of Contents S.1 Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . S-1 Purpose of and Need for the Proposed Action . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . S-3 Issues Identified During the Scoping Period . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . S-4 Issues Already Intended for Inclusion in the SPD EIS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . S-4 Additional Issues That Need to Be Addressed in the SPD EIS . . . . . . . . . . . . . . . . . . . . . . . . S-5 Issues That Need to Be or Are Already Addressed Elsewhere . . . . . . . . . . . . . . . .

319

INCREASING HEAVY OIL RESERVES IN THE WILMINGTON OIL FIELD THROUGH ADVANCED RESERVOIR CHARACTERIZATION AND THERMAL PRODUCTION TECHNOLOGIES  

SciTech Connect

The project involves using advanced reservoir characterization and thermal production technologies to improve thermal recovery techniques and lower operating and capital costs in a slope and basin clastic (SBC) reservoir in the Wilmington field, Los Angeles Co., Calif. Through December 2001, project work has been completed on the following activities: data preparation; basic reservoir engineering; developing a deterministic three dimensional (3-D) geologic model, a 3-D deterministic reservoir simulation model and a rock-log model; well drilling and completions; and surface facilities on the Fault Block II-A Tar Zone (Tar II-A). Work is continuing on research to understand the geochemistry and process regarding the sand consolidation well completion technique, final reservoir tracer work, operational work and research studies to prevent thermal-related formation compaction in the Tar II-A steamflood area, and operational work on the Tar V steamflood pilot and Tar II-A post-steamflood projects. During the First Quarter 2002, the project team developed an accelerated oil recovery and reservoir cooling plan for the Tar II-A post-steamflood project and began implementing the associated well work in March. The Tar V pilot steamflood project will be converted to post-steamflood cold water injection in April 2002. The Tar II-A post-steamflood operation started in February 1999 and steam chest fillup occurred in September-October 1999. The targeted reservoir pressures in the ''T'' and ''D'' sands are maintained at 90 {+-} 5% hydrostatic levels by controlling water injection and gross fluid production and through the bimonthly pressure monitoring program enacted at the start of the post-steamflood phase. Most of the 2001 well work resulted in maintaining oil and gross fluid production and water injection rates. Reservoir pressures in the ''T'' and ''D'' sands are at 88% and 91% hydrostatic levels, respectively. Well work during the first quarter and plans for 2002 are described in the Reservoir Management section. The steamflood operation in the Tar V pilot project is mature and profitable. Recent production performance has been below projections because of wellbore mechanical limitations that have been addressed during this quarter. As the fluid production temperatures were beginning to exceed 350 F, our self-imposed temperature limit, the pilot steamflood was converted to a hot waterflood project in June 2001 and will be converted to cold water injection next quarter.

Scott Hara

2002-04-30T23:59:59.000Z

320

Increasing heavy oil reserves in the Wilmington oil field through advanced reservoir characterization and thermal production technologies. Technical progress report  

SciTech Connect

The project involves improving thermal recovery techniques in a slope and basin clastic (SBC) reservoir in the Wilmington field, Los Angeles Co., California using advanced reservoir characterization and thermal production technologies. This is the third quarterly technical progress report for the project. Significant technical achievements accomplished include the drilling of four horizontal wells (two producers and two steam injectors) utilizing a new and lower cost drilling program, the drilling of five observation wells to monitor the horizontal steamflood pilot, the installation of a subsurface harbor channel crossing for delivering steam to an island location, and a geochemical study of the scale minerals being created in the wellbore. Cyclic steam injection into the two horizontal injection wells began in mid-December 1995 utilizing the new 2400 ft steam line under the Cerritos channel and the wells will be placed on production in May. Cyclic steam injection into the two horizontal producers will start in May. Work on the basic reservoir engineering is expected to be completed in March 1996. The deterministic geologic model was improved to add eight layers to the previous ten.

Hara, S.

1996-05-06T23:59:59.000Z

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321

Increasing Heavy Oil Reserves in the Wilmington Oil Field Through Advanced Reservoir Characterization and Thermal Production Technologies  

SciTech Connect

The project involves improving thermal recovery techniques in a slope and basin clastic (SBC) reservoir in the Wilmington field, Los Angeles Co., Calif. using advanced reservoir characterization and thermal production technologies. The existing steamflood in the Tar zone of Fault Block (FB) II-A has been relatively inefficient because of several producibility problems which are common in SBC reservoirs. Inadequate characterization of the heterogeneous turbidite sands, high permeability thief zones, low gravity oil, and nonuniform distribution of remaining oil have all contributed to poor sweep efficiency, high steam-oil ratios, and early steam breakthrough. Operational problems related to steam breakthrough, high reservoir pressure, and unconsolidated formation sands have caused premature well and downhole equipment failures. In aggregate, these reservoir and operational constraints have resulted in increased operating costs and decreased recoverable reserves. The advanced technologies to be applied include: (1) Develop three-dimensional (3-D) deterministic and stochastic geologic models. (2) Develop 3-D deterministic and stochastic thermal reservoir simulation models to aid in reservoir management and subsequent development work. (3) Develop computerized 3-D visualizations of the geologic and reservoir simulation models to aid in analysis. (4) Perform detailed study on the geochemical interactions between the steam and the formation rock and fluids. (5) Pilot steam injection and production via four new horizontal wells (2 producers and 2 injectors). (6) Hot water alternating steam (WAS) drive pilot in the existing steam drive area to improve thermal efficiency. (7) Installing a 2100 foot insulated, subsurface harbor channel crossing to supply steam to an island location. (8) Test a novel alkaline steam completion technique to control well sanding problems and fluid entry profiles. (9) Advanced reservoir management through computer-aided access to production and geologic data to integrate reservoir characterization, engineering, monitoring, and evaluation. Summary of Technical Progress

Scott Hara

1997-08-08T23:59:59.000Z

322

Increasing Heavy Oil Reserves in the Wilmington Oil Field Through Advanced Reservoir Characterization and Thermal Production Technologies  

SciTech Connect

The project involves improving thermal recovery techniques in a slope and basin clastic (SBC) reservoir in the Wilmington field, Los Angeles Co., Calif. using advanced reservoir characterization and thermal production technologies. The existing steamflood in the Tar zone of Fault Block (FB) II-A has been relatively inefficient because of several producibility problems which are common in SBC reservoirs. Inadequate characterization of the heterogeneous turbidite sands, high permeability thief zones, low gravity oil, and nonuniform distribution of remaining oil have all contributed to poor sweep efficiency, high steam-oil ratios, and early steam breakthrough. Operational problems related to steam breakthrough, high reservoir pressure, and unconsolidated formation sands have caused premature well and downhole equipment failures. In aggregate, these reservoir and operational constraints have resulted in increased operating costs and decreased recoverable reserves. The advanced technologies to be applied include: (1) Develop three-dimensional (3-D) deterministic and stochastic geologic models. (2) Develop 3-D deterministic and stochastic thermal reservoir simulation models to aid in reservoir management and subsequent development work. (3) Develop computerized 3-D visualizations of the geologic and reservoir simulation models to aid in analysis. (4) Perform detailed study on the geochemical interactions between the steam and the formation rock and fluids. (5) Pilot steam injection and production via four new horizontal wells (2 producers and 2 injectors). (6) Hot water alternating steam (WAS) drive pilot in the existing steam drive area to improve thermal efficiency. (7) Installing a 2100 foot insulated, subsurface harbor channel crossing to supply steam to an island location. (8) Test a novel alkaline steam completion technique to control well sanding problems and fluid entry profiles. (9) Advanced reservoir management through computer-aided access to production and geologic data to integrate reservoir characterization, engineering, monitoring, and evaluation.

Scott Hara

1998-03-03T23:59:59.000Z

323

Increasing Heavy Oil Reservers in the Wilmington Oil field Through Advanced Reservoir Characterization and Thermal Production Technologies  

SciTech Connect

The project involves improving thermal recovery techniques in a slope and basin clastic (SBC) reservoir in the Wilmington field, Los Angeles Co., Calif. using advanced reservoir characterization and thermal production technologies. The existing steamflood in the Tar zone of Fault Block (FB) 11-A has been relatively inefficient because of several producibility problems which are common in SBC reservoirs. Inadequate characterization of the heterogeneous turbidite sands, high permeability thief zones, low gravity oil, and nonuniform distribution of remaining oil have all contributed to poor sweep efficiency, high steam-oil ratios, and early steam breakthrough. Operational problems related to steam breakthrough, high reservoir pressure, and unconsolidated formation sands have caused premature well and downhole equipment failures. In aggregate, these reservoir and operational constraints have resulted in increased operating costs and decreased recoverable reserves. The advanced technologies to be applied include: (1) Develop three-dimensional (3-D) deterministic and stochastic geologic models. (2) Develop 3-D deterministic and stochastic thermal reservoir simulation models to aid in reservoir management and subsequent development work. (3) Develop computerized 3-D visualizations of the geologic and reservoir simulation models to aid in analysis. (4) Perform detailed study on the geochemical interactions between the steam and the formation rock and fluids. (5) Pilot steam injection and production via four new horizontal wells (2 producers and 2 injectors). (6) Hot water alternating steam (WAS) drive pilot in the existing steam drive area to improve thermal efficiency. (7) Installing a 2100 foot insulated, subsurface harbor channel crossing to supply steam to an island location. (8) Test a novel alkaline steam completion technique to control well sanding problems and fluid entry profiles. (9) Advanced reservoir management through computer-aided access to production and geologic data to integrate reservoir characterization, engineering, monitoring, and evaluation.

Hara, Scott [Tidelands Oil Production Co., Long Beach, CA (United States)

1997-05-05T23:59:59.000Z

324

INCREASING HEAVY OIL RESERVES IN THE WILMINGTON OIL FIELD THROUGH ADVANCED RESERVOIR CHARACTERIZATION AND THERMAL PRODUCTION TECHNOLOGIES  

SciTech Connect

The overall objective of this project is to increase heavy oil reserves in slope and basin clastic (SBC) reservoirs through the application of advanced reservoir characterization and thermal production technologies. The project involves improving thermal recovery techniques in the Tar Zone of Fault Blocks II-A and V (Tar II-A and Tar V) of the Wilmington Field in Los Angeles County, near Long Beach, California. A primary objective is to transfer technology which can be applied in other heavy oil formations of the Wilmington Field and other SBC reservoirs, including those under waterflood. The thermal recovery operations in the Tar II-A and Tar V have been relatively inefficient because of several producibility problems which are common in SBC reservoirs. Inadequate characterization of the heterogeneous turbidite sands, high permeability thief zones, low gravity oil, and nonuniform distribution of remaining oil have all contributed to poor sweep efficiency, high steam-oil ratios, and early steam breakthrough. Operational problems related to steam breakthrough, high reservoir pressure, and unconsolidated formation sands have caused premature well and downhole equipment failures. In aggregate, these reservoir and operational constraints have resulted in increased operating costs and decreased recoverable reserves. The advanced technologies to be applied include: (1) Develop three-dimensional (3-D) deterministic and stochastic geologic models. (2) Develop 3-D deterministic and stochastic thermal reservoir simulation models to aid in reservoir management and subsequent development work. (3) Develop computerized 3-D visualizations of the geologic and reservoir simulation models to aid in analysis. (4) Perform detailed study on the geochemical interactions between the steam and the formation rock and fluids. (5) Pilot steam injection and production via four new horizontal wells (2 producers and 2 injectors). (6) Hot water alternating steam (WAS) drive pilot in the existing steam drive area to improve thermal efficiency. (7) Installing an 2400 foot insulated, subsurface harbor channel crossing to supply steam to an island location. (8) Test a novel alkaline steam completion technique to control well sanding problems and fluid entry profiles. (9) Advanced reservoir management through computer-aided access to production and geologic data to integrate reservoir characterization, engineering, monitoring, and evaluation.

Scott Hara

2004-03-05T23:59:59.000Z

325

INCREASING HEAVY OIL RESERVES IN THE WILMINGTON OIL FIELD THROUGH ADVANCED RESERVOIR CHARACTERIZATION AND THERMAL PRODUCTION TECHNOLOGIES  

SciTech Connect

The overall objective of this project is to increase heavy oil reserves in slope and basin clastic (SBC) reservoirs through the application of advanced reservoir characterization and thermal production technologies. The project involves improving thermal recovery techniques in the Tar Zone of Fault Blocks II-A and V (Tar II-A and Tar V) of the Wilmington Field in Los Angeles County, near Long Beach, California. A primary objective is to transfer technology which can be applied in other heavy oil formations of the Wilmington Field and other SBC reservoirs, including those under waterflood. The thermal recovery operations in the Tar II-A and Tar V have been relatively inefficient because of several producibility problems which are common in SBC reservoirs. Inadequate characterization of the heterogeneous turbidite sands, high permeability thief zones, low gravity oil, and nonuniform distribution of remaining oil have all contributed to poor sweep efficiency, high steam-oil ratios, and early steam breakthrough. Operational problems related to steam breakthrough, high reservoir pressure, and unconsolidated formation sands have caused premature well and downhole equipment failures. In aggregate, these reservoir and operational constraints have resulted in increased operating costs and decreased recoverable reserves. The advanced technologies to be applied include: (1) Develop three-dimensional (3-D) deterministic and stochastic geologic models. (2) Develop 3-D deterministic and stochastic thermal reservoir simulation models to aid in reservoir management and subsequent development work. (3) Develop computerized 3-D visualizations of the geologic and reservoir simulation models to aid in analysis. (4) Perform detailed study on the geochemical interactions between the steam and the formation rock and fluids. (5) Pilot steam injection and production via four new horizontal wells (2 producers and 2 injectors). (6) Hot water alternating steam (WAS) drive pilot in the existing steam drive area to improve thermal efficiency. (7) Installing an 2400 foot insulated, subsurface harbor channel crossing to supply steam to an island location. (8) Test a novel alkaline steam completion technique to control well sanding problems and fluid entry profiles. (9) Advanced reservoir management through computer-aided access to production and geologic data to integrate reservoir characterization, engineering, monitoring, and evaluation.

Scott Hara

2003-09-04T23:59:59.000Z

326

INCREASING HEAVY OIL RESERVES IN THE WILMINGTON OIL FIELD THROUGH ADVANCED RESERVOIR CHARACTERIZATION AND THERMAL PRODUCTION TECHNOLOGIES  

SciTech Connect

The overall objective of this project is to increase heavy oil reserves in slope and basin clastic (SBC) reservoirs through the application of advanced reservoir characterization and thermal production technologies. The project involves improving thermal recovery techniques in the Tar Zone of Fault Blocks II-A and V (Tar II-A and Tar V) of the Wilmington Field in Los Angeles County, near Long Beach, California. A primary objective is to transfer technology which can be applied in other heavy oil formations of the Wilmington Field and other SBC reservoirs, including those under waterflood. The thermal recovery operations in the Tar II-A and Tar V have been relatively inefficient because of several producibility problems which are common in SBC reservoirs. Inadequate characterization of the heterogeneous turbidite sands, high permeability thief zones, low gravity oil, and nonuniform distribution of remaining oil have all contributed to poor sweep efficiency, high steam-oil ratios, and early steam breakthrough. Operational problems related to steam breakthrough, high reservoir pressure, and unconsolidated formation sands have caused premature well and downhole equipment failures. In aggregate, these reservoir and operational constraints have resulted in increased operating costs and decreased recoverable reserves. The advanced technologies to be applied include: (1) Develop three-dimensional (3-D) deterministic and stochastic geologic models. (2) Develop 3-D deterministic and stochastic thermal reservoir simulation models to aid in reservoir management and subsequent development work. (3) Develop computerized 3-D visualizations of the geologic and reservoir simulation models to aid in analysis. (4) Perform detailed study on the geochemical interactions between the steam and the formation rock and fluids. (5) Pilot steam injection and production via four new horizontal wells (2 producers and 2 injectors). (6) Hot water alternating steam (WAS) drive pilot in the existing steam drive area to improve thermal efficiency. (7) Installing an 2400 foot insulated, subsurface harbor channel crossing to supply steam to an island location. (8) Test a novel alkaline steam completion technique to control well sanding problems and fluid entry profiles. (9) Advanced reservoir management through computer-aided access to production and geologic data to integrate reservoir characterization, engineering, monitoring, and evaluation.

Scott Hara

2003-06-04T23:59:59.000Z

327

DRAFT EM SSAB Chairs Meeting Waste Disposition Strategies...  

Office of Environmental Management (EM)

Management Accomplishments * Portsmouth: Reached full production rate of the DUF6 Conversion facility * Paducah: 50,000 cubic feet of PCB debris from C-340 disposed offsite *...

328

EIS-0283-S2: Surplus Plutonium Disposition Supplemental Environmental Impact Statement  

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

This EIS analyzes the potential environmental impacts associated with changes to the surplus plutonium disposition program, including changes to the inventory of surplus plutonium and proposed new alternatives. The original EIS is available at http://energy.gov/nepa/downloads/eis-0283-final-environmental-impact-sta....

329

Plutonium-bearing materials feed report for the DOE Fissile Materials Disposition Program alternatives  

SciTech Connect

This report has identified all plutonium currently excess to DOE Defense Programs under current planning assumptions. A number of material categories win clearly fan within the scope of the MD (Materials Disposition) program, but the fate of the other categories are unknown at the present time. MD planning requires that estimates be made of those materials likely to be considered for disposition actions so that bounding cases for the PEIS (Programmatic Environmental Impact Statement) can be determined and so that processing which may be required can be identified in considering the various alternatives. A systematic analysis of the various alternatives in reachmg the preferred alternative requires an understanding of the possible range of values which may be taken by the various categories of feed materials. One table identifies the current total inventories excess to Defense Program planning needs and represents the bounding total of Pu which may become part of the MD disposition effort for all materials, except site return weapons. The other categories, principally irradiated fuel, rich scrap, and lean scrap, are discussed. Another table summarizes the ranges and expected quantities of Pu which could become the responsibility of the MD program. These values are to be used for assessing the impact of the various alternatives and for scaling operations to assess PEIS impact. Determination of the actual materials to be included in the disposition program will be done later.

Brough, W.G. [Lawrence Livermore National Lab., CA (United States); Boerigter, S.T. [Los Alamos National Lab., NM (United States)

1995-04-06T23:59:59.000Z

330

Coherence and Conservatism in the Dynamics of Belief II: Iterated Belief Change without Dispositional Coherence  

Science Journals Connector (OSTI)

......University Press 2003 Original Article Coherence and Conservatism in the Dynamics of Belief...Iterated Belief Change without Dispositional Coherence Hans Rott 1 1 Department of Philosophy...based on the conclusions of Rott, Coherence and Conservatism in the Dynamics of Belief......

Hans Rott

2003-02-01T23:59:59.000Z

331

SUPERGLASS. Engineering field tests - Phase 3. Production, market planning, and product evaluation for a high-thermal-performance insulating glass design utilizing HEAT MIRROR transparent insulation. Final report  

SciTech Connect

HEAT MIRROR transparent window insulation consists of a clear polyester film two mils (.002'') thick with a thin, clear low-emissivity (.15) coating deposited on one side by state-of-the-art vacuum deposition processes. This neutral-colored invisible coating reflects long-wave infrared energy (heat). When mounted by being stretched with a 1/2'' air-gap on each side of the film, the resulting unit reduces heat loss by 60% compared to dual insulating glass. Southwall Corporation produces HEAT MIRROR transparent insulation and markets it to manufacturers of sealed insulating glass (I.G.) units and window and building manufacturers who make their own I.G. These companies build and sell the SUPERGLASS sealed glazing units. Units made and installed in buildings by six customers were visited. These units were located in many geographic regions, including the Pacific Northwest, Rocky Mountains, New England, Southeast, and West Coast. As much as could be obtained of their history was recorded, as was their current condition and performance. These units had been in place from two weeks to over a year. All of the units were performing thermally very well, as measured by taking temperature profiles through them and through adjacent conventional I.G. units. Some units had minor visual defects (attributed to I.G. assembly techniques) which are discussed in detail. Overall occupant acceptance was enthusiastically positive. In addition to saving energy, without compromise of optical quality or appearance, the product makes rooms with large glazing areas comfortable to be in in cold weather. All defects observed were present when built; there appears to be no in-field degradation of quality at this time.

Tilford, C L

1982-11-01T23:59:59.000Z

332

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

SciTech Connect

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

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

1998-08-01T23:59:59.000Z

333

Injections of Natural Gas into Storage (Annual Supply & Disposition)  

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

Citygate Price Residential Price Commercial Price Industrial Price Electric Power Price Gross Withdrawals Gross Withdrawals From Gas Wells Gross Withdrawals From Oil Wells Gross Withdrawals From Shale Gas Wells Gross Withdrawals From Coalbed Wells Repressuring Nonhydrocarbon Gases Removed Vented and Flared Marketed Production NGPL Production, Gaseous Equivalent Dry Production Imports By Pipeline LNG Imports Exports Exports By Pipeline LNG Exports Underground Storage Capacity Gas in Underground Storage Base Gas in Underground Storage Working Gas in Underground Storage Underground Storage Injections Underground Storage Withdrawals Underground Storage Net Withdrawals Total Consumption Lease and Plant Fuel Consumption Pipeline & Distribution Use Delivered to Consumers Residential Commercial Industrial Vehicle Fuel Electric Power Period: Monthly Annual

334

A study of production/injection data from slim holes and large-diameter wells at the Takigami Geothermal Field, Kyushu, Japan  

SciTech Connect

Production and injection data from nine slim holes and sixteen large-diameter wells at the Takigami Geothermal Field, Kyushu, Japan were analyzed in order to establish relationships (1) between injectivity and productivity indices, (2) between productivity/injectivity index and borehole diameter, and (3) between discharge capacity of slim holes and large-diameter wells. Results are compared with those from the Oguni and Sumikawa fields. A numerical simulator (WELBOR) was used to model the available discharge rate from Takigami boreholes. The results of numerical modeling indicate that the flow rate of large-diameter geothermal production wells with liquid feedzones can be predicted using data from slim holes. These results also indicate the importance of proper well design.

Garg, S.K. [Maxwell Federal Div., Inc., San Diego, CA (United States)] [Maxwell Federal Div., Inc., San Diego, CA (United States); Combs, J. [Geo-Hills Associates, Los Altos Hills, CA (United States)] [Geo-Hills Associates, Los Altos Hills, CA (United States); Azawa, Fumio [Idemitsu Kosan Co. Ltd., Tokyo (Japan)] [Idemitsu Kosan Co. Ltd., Tokyo (Japan); Gotoh, Hiroki [Idemitsu Oita Geothermal Co. Ltd., Oita (Japan)] [Idemitsu Oita Geothermal Co. Ltd., Oita (Japan)

1996-11-01T23:59:59.000Z

335

DRAFT EM SSAB Chair's Meeting Waste Disposition Strategies...  

Energy Savers (EERE)

of lessons learned and equipment for use of TRUPACT-III at other sites * Closed Tanks 5 and 6, which are the 5 th and 6 th tanks to be closed * Continuing production of HLW...

336

INCREASING HEAVY OIL RESERVES IN THE WILMINGTON OIL FIELD THROUGH ADVANCED RESERVOIR CHARACTERIZATION AND THERMAL PRODUCTION TECHNOLOGIES  

SciTech Connect

The project involves using advanced reservoir characterization and thermal production technologies to improve thermal recovery techniques and lower operating and capital costs in a slope and basin clastic (SBC) reservoir in the Wilmington field, Los Angeles Co., CA. Through June 2002, project work has been completed on the following activities: data preparation; basic reservoir engineering; developing a deterministic three dimensional (3-D) geologic model, a 3-D deterministic reservoir simulation model and a rock-log model; well drilling and completions; and surface facilities on the Fault Block II-A Tar Zone (Tar II-A). Work is continuing on research to understand the geochemistry and process regarding the sand consolidation well completion technique, final reservoir tracer work, operational work and research studies to prevent thermal-related formation compaction in the Tar II-A steamflood area, and operational work on the Tar V post-steamflood pilot and Tar II-A post-steamflood projects. During the Third Quarter 2002, the project team essentially completed implementing the accelerated oil recovery and reservoir cooling plan for the Tar II-A post-steamflood project developed in March 2002 and is proceeding with additional related work. The project team has completed developing laboratory research procedures to analyze the sand consolidation well completion technique and will initiate work in the fourth quarter. The Tar V pilot steamflood project terminated hot water injection and converted to post-steamflood cold water injection on April 19, 2002. Proposals have been approved to repair two sand consolidated horizontal wells that sanded up, Tar II-A well UP-955 and Tar V well J-205, with gravel-packed inner liner jobs to be performed next quarter. Other well work to be performed next quarter is to convert well L-337 to a Tar V water injector and to recomplete vertical well A-194 as a Tar V interior steamflood pattern producer. Plans have been approved to drill and complete well A-605 in Tar V in the first quarter 2003. Plans have been approved to update the Tar II-A 3-D deterministic reservoir simulation model and run sensitivity cases to evaluate the accelerated oil recovery and reservoir cooling plan. The Tar II-A post-steamflood operation started in February 1999 and steam chest fillup occurred in September-October 1999. The targeted reservoir pressures in the ''T'' and ''D'' sands are maintained at 90 {+-} 5% hydrostatic levels by controlling water injection and gross fluid production and through the bimonthly pressure monitoring program enacted at the start of the post-steamflood phase. Well work related to the Tar II-A accelerated oil recovery and reservoir cooling plan began in March 2002 with oil production increasing from 1009 BOPD in the first quarter to 1145 BOPD in the third quarter. Reservoir pressures have been increased during the quarter from 88% to 91% hydrostatic levels in the ''T'' sands and from 91% to 94% hydrostatic levels in the ''D'' sands. Well work during the quarter is described in the Reservoir Management section. The post-steamflood production performance in the Tar V pilot project has been below projections because of wellbore mechanical limitations and the loss of a horizontal producer a second time to sand inflow that are being addressed in the fourth quarter. As the fluid production temperatures exceeded 350 F, our self-imposed temperature limit, the pilot steamflood was converted to a hot waterflood project in June 2001 and converted to cold water injection on April 19, 2002.

Scott Hara

2002-11-08T23:59:59.000Z

337

Used fuel disposition research and development roadmap - FY10 status.  

SciTech Connect

Since 1987 the U.S. has focused research and development activities relevant to the disposal of commercial used nuclear fuel and U.S. Department of Energy (DOE) owned spent nuclear fuel and high level waste on the proposed repository at Yucca Mountain, Nevada. At the same time, the U.S. successfully deployed a deep geologic disposal facility for defense-related transuranic waste in bedded salt at the Waste Isolation Pilot Plant. In 2009 the DOE established the Used Fuel Disposition Campaign (UFDC) within the Office of Nuclear Energy. The Mission of the UFDC is to identify alternatives and conduct scientific research and technology development to enable storage, transportation and disposal of used nuclear fuel and wastes generated by existing and future nuclear fuel cycles. The U.S. national laboratories have participated on these programs and has conducted research and development related to these issues to a limited extent. However, a comprehensive research and development (R&D) program investigating a variety of geologic media has not been a part of the U.S. waste management program since the mid 1980s. Such a comprehensive R&D program is being developed in the UFDC with a goal of meeting the UFDC Grand Challenge to provide a sound technical basis for absolute confidence in the safety and security of long-term storage, transportation, and disposal of used nuclear fuel and wastes from the nuclear energy enterprise. The DOE has decided to no longer pursue the development of a repository at Yucca Mountain, Nevada. Since a repository site will ultimately have to be selected, sited, characterized, designed, and licensed, other disposal options must now be considered. In addition to the unsaturated volcanic tuff evaluated at Yucca Mountain, several different geologic media are under investigation internationally and preliminary assessments indicate that disposal of used nuclear fuel and high level waste in these media is feasible. Considerable progress has been made in the U.S. and other nations in understanding disposal concepts in different geologic media, but gaps in knowledge still exist. A principal aspect of concern to the UFDC as it considers the broad issues of siting a repository in different geologic media are the marked differences in the regulatory bases for assessing suitability and safety of a repository between the U.S. and other nations. Because the probability based - risked informed nature of the current U.S. regulations for high-level radioactive waste and spent nuclear fuel is sufficiently different from other regulations, information gained in previous studies, while useful, likely need to be supplemented to enable more convincing communication with the public, better defense of the numerical models, and stronger safety cases. Thus, it was recognized when the UFDC was established that there were readily identified disposal-related R&D opportunities to address knowledge gaps. An effort to document these research opportunities was a key component of Fiscal Year (FY) 2010 engineered system, natural system, and system-level modeling activities for a range of disposal environments. A principal contribution to identifying these gaps was a workshop held to gather perspectives from experts both within and external to the UFDC regarding R&D opportunities. In the planning for FY2010 it was expected that these activities would culminate with a UFDC research and development roadmap that would identify the knowledge gaps, discuss the R&D needed to fill these gaps, and prioritize the proposed R&D over both the near- and long-term. A number of knowledge gaps and needed R&D were identified and are discussed in this report. However, these preliminary R&D topics have not been evaluated in detail nor have they been prioritized to support future planning efforts. This will be completed in FY11 and the final UFDC Research and Development Roadmap will be completed. This report discusses proposed R&D topics in three areas related to repository siting, design, and performance: natural systems

Nutt, W. M. (Nuclear Engineering Division)

2010-10-01T23:59:59.000Z

338

Abandoned oil fields in Oklahoma  

SciTech Connect

Data are presented for approximately 165 abandoned oil fields in Oklahoma that have produced 10,000 or more barrels of oil prior to abandonment. The following information is provided for each field: county; DOE field code; field name; AAPG geologic province code; discovery date of field; year of last production, if known; discovery well operator; proven acreage; formation thickness; depth of field; gravity of oil production; calendar year; yearly field oil production; yearly field gas production; cumulative oil production; cumulative gas production; number abandoned fields in county; cumulative production of oil from fields; and cumulative production of gas from fields. (ATT)

Chism, J.

1983-08-01T23:59:59.000Z

339

USING CABLE SUSPENDED SUBMERSIBLE PUMPS TO REDUCE PRODUCTION COSTS TO INCREASE ULTIMATE RECOVERY IN THE RED MOUNTAIN FIELD OF THE SAN JUAN BASIN REGION  

SciTech Connect

This report discusses: (1) being able to resume marginal oil production operations in the Red Mountain Oil Field, located in McKinley County, New Mexico by installing a cable suspended electric submersible pumping system (HDESP); (2) determining if this system can reduce life costs making it a more cost effective production system for similar oil fields within the region, and if warranted, drill additional wells to improve the economics. In April 2003, a cooperative 50% cost share agreement between Enerdyne and the DOE was executed to investigate the feasibility of using cable suspended electric submersible pumps to reduce the life costs and increase the ultimate oil recovery of the Red Mountain Oil Field, located on the Chaco Slope of the San Juan Basin, New Mexico. The field was discovered in 1934 and has produced approximately 55,650 cubic meters (m{sup 3}), (350,000 barrels, 42 gallons) of oil. Prior to April 2003, the field was producing only a few cubic meters of oil each month; however, the reservoir characteristics suggest that the field retains ample oil to be economic. This field is unique, in that, the oil accumulations, above fresh water, occur at depths from 88-305 meters, (290 feet to 1000 feet), and serves as a relatively good test area for this experiment.

Don L. Hanosh

2004-11-01T23:59:59.000Z

340

Alternative technical summary report for immobilized disposition in deep boreholes: Immobilized disposal of plutonium in coated ceramic pellets in grout without canisters, Version 4.0. Fissile materials disposition program  

SciTech Connect

This paper summarizes and compares the immobilized and direct borehole disposition alternatives previously presented in the alternative technical summary. The important design concepts, facility features and operational procedures are first briefly described. This is followed by a discussion of the issues that affect the evaluation of each alternative against the programmatic assessment criteria that have been established for selecting the preferred alternatives for plutonium disposition.

Wijesinghe, A.M.

1996-08-23T23:59:59.000Z

Note: This page contains sample records for the topic "disposition field production" 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

Increased oil production and reserves from improved completion techniques in the Bluebell Field, Uinta Basin, Utah. Annual report, October 1, 1994--September 30, 1995  

SciTech Connect

The Bluebell field produces from the Tertiary lower Green River and Wasatch Formations of the Uinta Basin, Utah. The productive interval consists of thousands of feet of interbedded fractured clastic and carbonate beds deposited in a fluvial-dominated deltaic lacustrine environment. Wells in the Bluebell field are typically completed by perforating 40 or more beds over 1,000 to 3,000 vertical feet (300-900 m), then applying an acid-fracture stimulation treatment to the entire interval. This completion technique is believed to leave many potentially productive beds damaged and/or untreated, while allowing water-bearing and low-pressure (thief) zones to communicate with the wellbore. Geologic and engineering characterization has been used to define improved completion techniques. The study identified reservoir characteristics of beds that have the greatest long-term production potential.

Allison, M.L.; Morgan, C.D.

1996-05-01T23:59:59.000Z

342

DRAFT EM SSAB Chairs Meeting Waste Disposition Strategies Update  

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

EM HQ Updates Waste Disposition Overview Christine Gelles Associate Deputy Assistant Secretary for Waste Management Office of Environmental Management EM SSAB Chairs Meeting 5 November 2013 www.energy.gov/EM 2 * Waste Management Accomplishments and Priorities * National TRU Program Update * LLW/MLLW Disposal Update * Other Programmatic Updates * Disposition Maps - Current Tools Discussion Outline www.energy.gov/EM 3 FY13 Waste Management Accomplishments * WIPP: Emplaced 5,065 cubic meters of TRU with 89 percent of shipments departed from TRU waste sites as planned * Los Alamos: Met Framework Agreement goal for FY 13 ahead of schedule, disposing of over 1,800 cubic meters of legacy managed TRU waste * Oak Ridge: Partnered with regulators to develop strategy for

343

Preliminary Technology Readiness Assessment (TRA) for the Calcine Disposition Project Volume 2 (CDP)  

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

PRELIMINARY TECHNOLOGY PRELIMINARY TECHNOLOGY OF THE CALCINE Prepared by the U.S. Department of Energy ECHNOLOGY READINESS ASSESSMENT ALCINE DISPOSITION PROJECT VOLUME TWO Anthony F. Kluk Hoyt C. Johnson Clyde Phillip McGinnis Michael Rinker Steven L. Ross Herbert G. Sutter John Vienna February 2011 Prepared by the U.S. Department of Energy Washington, DC SSESSMENT ROJECT 412.09 (06/03/2009 - Rev. 11) CALCINE DISPOSITION PROJECT TECHNOLOGY MATURATION PLAN Identifier: Revision*: Page: PLN-1482 2 C-1 of C-317 Appendix C Appendix C Checklists for Critical Technology Elements and Technology Readiness Levels This appendix provides the CTE and TRL checklists for the CTEs. For the TRL questions that receive a "Y" (yes) response, the supporting documentation is provided with a complete reference at the

344

DOE/EIS-0283; Surplus Plutonium Disposition Final Environmental Impact Statement (11/1999)  

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

5 of 5 5 of 5 Final Environmental Impact Statement November 1999 Comment Response Document Volume III - Part B Cover Sheet Responsible Agency: United States Department of Energy (DOE) Title: Surplus Plutonium Disposition Final Environmental Impact Statement (SPD EIS) (DOE/EIS-0283) Locations of Candidate Sites: California, Idaho, New Mexico, North Carolina, South Carolina, Tennessee, Texas, Virginia, and Washington Contacts: For further information on the SPD Final EIS contact: For information on the DOE National Environmental Policy Act (NEPA) process contact: Mr. G. Bert Stevenson, NEPA Compliance Officer Ms. Carol Borgstrom, Director Office of Fissile Materials Disposition Office of NEPA Policy and Assistance U.S. Department of Energy Office of Environment, Safety and Health

345

Environmental Assessment Addendum Disposition of Additional Waste at the Paducah Site  

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

FINDING OF NO SIGNIFICANT IMPACT FINDING OF NO SIGNIFICANT IMPACT WASTE DISPOSITION ACTIVITIES AT THE PADUCAH SITE PADUCAH, KENTUCKY AGENCY: U.S. DEPARTMENT OF ENERGY ACTION: FINDING OF NO SIGNIFICANT IMPACT SUMMARY: The U.S. Department of Energy (DOE) has completed an environmental assessment addendum (DOE/EA-1339-A), which is incorporated herein by reference, for proposed disposition of 17,600 m 3 of waste from the Paducah Site in Paducah, Kentucky. It is anticipated that most of the waste would be transported for disposal at various locations in the United States. Based on the results of the impact analysis reported in the EA, DOE has determined that the proposed action is not a major federal action that would significantly affect the quality of the human environment within the context of the

346

EIS-0283DS Supplement to the Surplus Plutonium Disposition Draft Environmental Impact Statement, April 1999  

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

Sheet Sheet Responsible Agency: United States Department of Energy (DOE) Title: Supplement to the Surplus Plutonium Disposition Draft Environmental Impact Statement (Supplement) (DOE/EIS-0283-DS) Locations of Candidate Sites: Idaho, North Carolina, South Carolina, Texas, Virginia, and Washington Contacts: For further information on the Supplement contact: For further information on the DOE National Environmental Policy Act (NEPA) process contact: Mr. G. Bert Stevenson, NEPA Compliance Officer Office of Fissile Materials Disposition U.S. Department of Energy P.O. Box 23786 Washington, DC 20026-3786 Voice: (202) 586-5368 Ms. Carol Borgstrom, Director Office of NEPA Policy and Assistance Office of Environment, Safety and Health U.S. Department of Energy 1000 Independence Ave., SW

347

Final Environmental Assessment for Waste Disposition Activities at the Paducah Site Paducah, Kentucky  

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

0-347(doc)/093002 0-347(doc)/093002 1 FINDING OF NO SIGNIFICANT IMPACT WASTE DISPOSITION ACTIVITIES AT THE PADUCAH SITE PADUCAH, KENTUCKY AGENCY: U.S. DEPARTMENT OF ENERGY ACTION: FINDING OF NO SIGNIFICANT IMPACT SUMMARY: The U.S. Department of Energy (DOE) has completed an environmental assessment (DOE/EA-1339), which is incorporated herein by reference, for proposed disposition of polychlorinated biphenyl (PCB) wastes, low-level radioactive waste (LLW), mixed low- level radioactive waste (MLLW), and transuranic (TRU) waste from the Paducah Gaseous Diffusion Plant Site (Paducah Site) in Paducah, Kentucky. All of the wastes would be transported for disposal at various locations in the United States. Based on the results of the impact analysis reported in the EA, DOE has determined that the proposed action is

348

DOE/EIS-0283; Surplus Plutonium Disposition Final Environmental Impact Statement (11/1999)  

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

4 of 5 4 of 5 Final Environmental Impact Statement November 1999 Comment Response Document Volume III - Part A Cover Sheet Responsible Agency: United States Department of Energy (DOE) Title: Surplus Plutonium Disposition Final Environmental Impact Statement (SPD EIS) (DOE/EIS-0283) Locations of Candidate Sites: California, Idaho, New Mexico, North Carolina, South Carolina, Tennessee, Texas, Virginia, and Washington Contacts: For further information on the SPD Final EIS contact: For information on the DOE National Environmental Policy Act (NEPA) process contact: Mr. G. Bert Stevenson, NEPA Compliance Officer Ms. Carol Borgstrom, Director Office of Fissile Materials Disposition Office of NEPA Policy and Assistance U.S. Department of Energy Office of Environment, Safety and Health

349

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

SciTech Connect

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

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

1998-10-01T23:59:59.000Z

350

production | OpenEI  

Open Energy Info (EERE)

production production Dataset Summary Description This dataset comes from the Energy Information Administration (EIA), and is part of the 2011 Annual Energy Outlook Report (AEO2011). This dataset is table 1, and contains only the reference case. The dataset uses quadrillion BTUs, and quantifies the energy prices using U.S. dollars. The data is broken down into total production, imports, exports, consumption, and prices for energy types. Source EIA Date Released April 26th, 2011 (3 years ago) Date Updated Unknown Keywords 2011 AEO consumption EIA export import production reference case total energy Data application/vnd.ms-excel icon AEO2011: Total Energy Supply, Disposition, and Price Summary - Reference Case (xls, 112.8 KiB) Quality Metrics Level of Review Peer Reviewed

351

Low-level Waste Safely Dispositioned Under Runoff Cover at SRS | Department  

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

Low-level Waste Safely Dispositioned Under Runoff Cover at SRS Low-level Waste Safely Dispositioned Under Runoff Cover at SRS Low-level Waste Safely Dispositioned Under Runoff Cover at SRS April 26, 2011 - 12:00pm Addthis The liner installer heat-welds a sand anchor closed. The sand anchors are installed under the liner and across the length of the slit trench to keep the liner in place and minimize the effects of wind lift. The liner installer heat-welds a sand anchor closed. The sand anchors are installed under the liner and across the length of the slit trench to keep the liner in place and minimize the effects of wind lift. A view of the Slit Trenches 1-4 operational cover in E Area. A view of the Slit Trenches 1-4 operational cover in E Area. The liner installer heat-welds a sand anchor closed. The sand anchors are installed under the liner and across the length of the slit trench to keep the liner in place and minimize the effects of wind lift.

352

Microsoft PowerPoint - FY09_11 Disposition Plan_090804  

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

to 2011 FIMS Disposition to 2011 FIMS Disposition Plan Phil Dalby, P.E., LEED AP Facilities Engineer Office of Engineering and Construction Management U. S. Department of Energy August 4, 2009 2 FY 2009 to FY 2011 Disposition Plan RPV # Of Assets GSF RPV # Of Assets Gross Sq Feet FY 02 N/A N/A N/A $322,545,118 379 1,533,715 - $2,914,059 $322,545,118 FY 03 N/A N/A N/A $313,800,817 420 1,140,524 - $2,166,996 $636,345,935 FY 04 N/A N/A N/A $678,724,838 536 2,878,328 - $5,468,823 $1,315,070,773 FY 05 $1,029,311,442 473 4,111,764 $1,047,538,247 488 4,101,396 102% $7,792,652 $2,362,609,020 FY 06 $788,456,532 270 1,773,232 $1,352,580,138 625 2,800,679 172% $5,321,290 $3,715,189,158 FY 07 $550,347,778 208 1,414,961 $595,332,143 243 1,568,969 108% $2,981,041 $4,310,521,301 FY 08 $312,272,791 114 782,388 $1,029,579,616 219 1,418,007 330%

353

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

SciTech Connect

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

Williams, K.A.

1999-10-01T23:59:59.000Z

354

Transportation requirements for the disposition of excess weapon plutonium by burning in fission reactors  

SciTech Connect

Both the US and Russia are planning to dispose of about 50 Mg of excess weapon plutonium over a 25-year period. One option is to transfer the plutonium to Advanced Light Water (power) Reactors (ALWRs) for use as fuel. Subsequent disposal would then be considered commercial spent fuel. This disposition option, like others, involves the transportation of plutonium in various material forms as it proceeds through various points in the recovery operation. This paper examines both the disposition option and the issues surrounding the transportation of 50 Mg of excess plutonium within the US under current regulatory and infrastructure constraints. Transportation issues include criticality control, shielding, and containment of the contents. Allowable limits on each of these issues are specified by the applicable (or selected) regulation. The composition and form of the radioactive materials to be transported will determine, in part, the applicable portions of the regulations as well as the packaging design. The regulations and the packaging design, along with safeguard and security issues, will determine the quantity of plutonium or fuel assemblies per package as well as the number of packages per shipment and the type of highway carrier. For the disposition of 50 Mg of weapon plutonium using ALWRs in a 25-year campaign, the annual shipment rates are determined for the various types of carriers.

Hovingh, J.; Walter, C.E.

1996-01-01T23:59:59.000Z

355

Study of plutonium disposition using existing GE advanced Boiling Water Reactors  

SciTech Connect

The end of the cold war and the resulting dismantlement of nuclear weapons has resulted in the need for the US to dispose of 50 to 100 metric tons of excess of plutonium in a safe and proliferation resistant manner. A number of studies, including the recently released National Academy of Sciences (NAS) study, have recommended conversion of plutonium into spent nuclear fuel with its high radiation barrier as the best means of providing permanent conversion and long-term diversion resistance to this material. The NAS study ``Management and Disposition of Excess Weapons Plutonium identified Light Water Reactor spent fuel as the most readily achievable and proven form for the disposition of excess weapons plutonium. The study also stressed the need for a US disposition program which would enhance the prospects for a timely reciprocal program agreement with Russia. This summary provides the key findings of a GE study where plutonium is converted into Mixed Oxide (MOX) fuel and a typical 1155 MWe GE Boiling Water Reactor (BWR) is utilized to convert the plutonium to spent fuel. A companion study of the Advanced BWR has recently been submitted. The MOX core design work that was conducted for the ABWR enabled GE to apply comparable fuel design concepts and consequently achieve full MOX core loading which optimize plutonium throughput for existing BWRs.

Not Available

1994-06-01T23:59:59.000Z

356

Assessment of the Integrated Facility Disposition Project at Oak Ridge National Laboratory & Y-12 for Transfer of Facilities & Materials to EM  

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

Integrated Facilities Disposition Project Integrated Facilities Disposition Project Technical Assistance Page 1 of 2 Oak Ridge National Laboratory Y-12 National Security Complex Tennessee Tennessee Assessment of the Integrated Facility Disposition Project at ORNL & Y-12 for Transfer of Facilities & Materials to EM Challenge In December 2007, the Assistant Secretary for Environmental Management (EM-1) invited the DOE Program Secretarial Offices (PSOs) of Nuclear Energy (NE), Science (SC), and the National Nuclear Security Administration (NNSA) to propose facilities and legacy waste for transfer to Environmental Management (EM) for final disposition or deactivation and decommissioning (D&D). In parallel with the EM-1 initiative, the Oak Ridge Reservation was conducting a Critical

357

USING CABLE SUSPENDED SUBMERSIBLE PUMPS TO REDUCE PRODUCTION COSTS TO INCREASE ULTIMATE RECOVERY IN THE RED MOUNTAIN FIELD IN SAM JUAN BASIN REGION  

SciTech Connect

A joint venture between Enerdyne LLC, a small independent oil and gas producer, and Pumping Solutions Inc., developer of a low volume electric submersible pump, suspended from a cable, both based in Albuquerque, New Mexico, has re-established marginal oil production from the Red Mountain Oil Field, located in the San Juan Basin, New Mexico by working over 17 existing wells and installing submersible pumps.

Don L. Hanosh

2004-08-01T23:59:59.000Z

358

3D slicing of radiogenic heat production in Bahariya Formation, Tut oil field, North-Western Desert, Egypt  

Science Journals Connector (OSTI)

A 3D block of radiogenic heat production was constructed from the subsurface total gamma ray logs of Bahariya Formation, Western Desert, Egypt. The studied rocks possess a range of radiogenic heat production varying from 0.21 ?Wm?3 to 2.2 ?Wm?3. Sandstone rocks of Bahariya Formation have higher radiogenic heat production than the average for crustal sedimentary rocks. The high values of density log of Bahariya Formation indicate the presence of iron oxides which contribute the uranium radioactive ores that increase the radiogenic heat production of these rocks. The average radiogenic heat production produced from the study area is calculated as 6.3 kW. The histogram and cumulative frequency analyses illustrate that the range from 0.8 to 1.2 ?Wm?3 is about 45.3% of radiogenic heat production values. The 3D slicing of the reservoir shows that the southeastern and northeastern parts of the study area have higher radiogenic heat production than other parts.

I.M. Al-Alfy; M.A. Nabih

2013-01-01T23:59:59.000Z

359

Increasing heavy oil reserves in the Wilmington oil field through advanced reservoir characterization and thermal production technologies. Quarterly report, July 1 - September 30, 1996  

SciTech Connect

The project involves improving thermal recovery techniques in a slope and basin clastic (SBC) reservoir in the Wilmington field, Los Angeles Co., Calif. using advanced reservoir characterization and thermal production technologies. This is the sixth quarterly technical progress report for the project. Through September 1996, the project continues to make good progress but is slightly behind schedule. Estimated costs are on budget for the work performed to date. Technical achievements accomplished during the quarter include placing the first two horizontal wells on production following cyclic steam stimulation, completing several draft technical reports and preparing presentations on the deterministic geologic model, steam channel crossing and horizontal well drilling for technical transfer. Cyclic steam injection into the first two horizontal wells was completed in June 1996 and initial oil production from the project began the same month. Work has commenced on the stochastic geologic and reservoir simulation models. High temperature core work and reservoir tracer work will commence in the First Quarter 1997.

Hara, S. [Tidelands Oil Production Co., Long Beach, CA (United States)

1996-12-01T23:59:59.000Z

360

A comparison of GHG emissions from UK field crop production under selected arable systems with reference to disease control  

Science Journals Connector (OSTI)

Crop disease not only threatens global food security by reducing crop production at a time of growing demand, but also contributes to greenhouse gas (GHG) emissions by reducing efficiency of N fertiliser ... oper...

Robert R. Carlton; Jon S. West; Pete Smith…

2012-05-01T23:59:59.000Z

Note: This page contains sample records for the topic "disposition field production" 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

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

SciTech Connect

The purpose of this document is to support the US Department of Energy (DOE) Fissile Materials Disposition Program`s preparation of the draft surplus plutonium disposition environmental impact statement (EIS). This is one of several responses to data call requests for background information on activities associated with the operation of the lead assembly (LA) mixed-oxide (MOX) fuel fabrication facility. The DOE Office of fissile Materials Disposition (DOE-MD) has developed a dual-path strategy for disposition of surplus weapons-grade plutonium. One of the paths is to disposition surplus plutonium through irradiation of MOX fuel in commercial nuclear reactors. MOX fuel consists of plutonium and uranium oxides (PuO{sub 2} and UO{sub 2}), typically containing 95% or more UO{sub 2}. DOE-MD requested that the DOE Site Operations Offices nominate DOE sites that meet established minimum requirements that could produce MOX LAs. The paper describes the following: Site map and the LA facility; process descriptions; resource needs; employment requirements; wastes, emissions, and exposures; accident analysis; transportation; qualitative decontamination and decommissioning; post-irradiation examination; LA fuel bundle fabrication; LA EIS data report assumptions; and LA EIS data report supplement.

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

1997-08-01T23:59:59.000Z

362

Trap types vs productivity of significant Wilcox gas fields in the south Texas, listric growth fault trend, and the divergent origin of its two largest producers  

SciTech Connect

Detailed mapping and analysis of 23 Wilcox fields in the subject trend indicates that gas production is related to trap type. Of total cumulative production of 3.4 TCFG, 65% is from upthrown fault blocks implying very effective fault seals due to differential pressure and/or shale smears. NE Thompsonville and Bob West fields have produced 650 and 200 BCFG, respectively, with 400 BCFG remaining reserves in the latter. The field structures are not attributed to listric growth faulting, as is suggested by their trend location. NE Thompsonville is a 9-mile-long turtle structure that originated through depositional loading of an upper slope basin, followed by tilting, and then eventual collapse of a sediment squeeze-up mound due to gravitational instability. These events provide an excellent example of basin evolution through sediment loading accompanied by withdrawal of a salt-shale substrate; the basin flanks are defined by basin-dipping listric faulting that accommodated subsidence and merge beneath its floor. Bob West Field lies along the edge of the Laramide fold belt. The 1-1/2 x 4 mile field anticline adjoins a deep-seated fault that slices over and across a buried structural ridge of probable Cretaceous age. Uplift of the latter, immediately following deposition of 20+ stacked, shelf-bar producing sands, upwarped the fault and resulted in rollover growth of the Wilcox anticline. The fault shows no downward decrease in dip typical of listric faults. NE Thompsonville and Bob West fields both produce upthrown along crestal faults. This analysis indicates that {open_quotes}high-side{close_quotes} closures, irrespective of diverse origins, have achieved head-of-the-class stature as Wilcox gas producers.

Stricklin, F.L. Jr. [Wilcox Exploration Enterprises, Woodlands, TX (United States)

1996-09-01T23:59:59.000Z

363

Plan and schedule for disposition and regulatory compliance for miscellaneous streams. Revision 1  

SciTech Connect

On December 23, 1991, the U.S. Department of Energy, Richland Operations Office (RL) and the Washington State Department of Ecology (Ecology) agreed to adhere to the provisions of Department of Ecology Consent Order No. DE 91NM-177 (Consent Order). The Consent Order lists regulatory milestones for liquid effluent streams at the Hanford Site to comply with the permitting requirements of Washington Administrative Code (WAC) 173-216 (State Waste Discharge Permit Program) or WAC 173-218 (Washington Underground Injection Control Program) where applicable. Hanford Site liquid effluent streams discharging to the soil column have been categorized in the Consent Order as follows: Phase I Streams Phase II Streams Miscellaneous Streams. Phase I and Phase II Streams are addressed in two RL reports: {open_quotes}Plan and Schedule to Discontinue Disposal of Contaminated Liquids into the Soil Column at the Hanford Site{close_quotes} (DOE-RL 1987), and {open_quotes}Annual Status of the Report of the Plan and Schedule to Discontinue Disposal of Contaminated Liquids into the Soil Column at the Hanford Site{close_quotes}. Miscellaneous Streams are those liquid effluent streams discharged to the ground that are not categorized as Phase I or Phase II Streams. Miscellaneous Streams discharging to the soil column at the Hanford Site are subject to the requirements of several milestones identified in the Consent Order. This document provides a plan and schedule for the disposition of Miscellaneous Streams. The disposition process for the Miscellaneous Streams is facilitated using a decision tree format. The decision tree and corresponding analysis for determining appropriate disposition of these streams is presented in this document.

NONE

1994-12-01T23:59:59.000Z

364

Disposition of toxic PCB congeners in snapping turtle eggs: expressed as toxic equivalents of TCDD  

SciTech Connect

Studies of snapping turtles, taken from the region of the Upper Hudson River, in New York State, revealed exceedingly high levels of PCBs in the adipose tissue. There is evidence to suggest that large reserves of fat provide protection against chlorinated hydrocarbon toxicity. Such storage may protect snapping turtle eggs from disposition of toxic PCB congeners and account for the apparent absence of reports regarding detrimental effects on the hatchability of eggs from turtles living in the vicinity of the upper Hudson River. The present study was undertaken to determine if indeed these eggs are protected against disposition of toxic PCB congeners by the presence of large reserves of fat. Although tissue volumes play an important role in determining the initial site of disposition, the major factor controlling the elimination of these compounds involves metabolism. For simple halogenated benzenes as well as for more complex halogenated biphenyls, oxidative metabolism catalyzed by P-448, occurs primarily at the site of two adjacent unsubstituted carbon atoms via arene oxide formation leading to the formation of water soluble metabolites. Toxicological studies have demonstrated that the most toxic PCB congeners, isosteriomers of tetrachlorodibenzo-p-dioxin (TCDD), require no metabolic activation. These compounds have chlorine atoms in the meta and para positions of both rings. It may be concluded that the structures of PCB congeners and isomers which favor induction of cytochrome P-448 are also those which are toxic and resist metabolism. It is the objective of the present study to determine if the heavy fat bodies of the female turtle provide a sufficiently large sink to retain the toxic congeners and prevent their incorporation into the eggs.

Bryan, A.M.; Stone, W.B.; Olafsson, P.G.

1987-11-01T23:59:59.000Z

365

DOE plutonium disposition study: Pu consumption in ALWRs. Volume 2, Final report  

SciTech Connect

The Department of Energy (DOE) has contracted with Asea Brown Boveri-Combustion Engineering (ABB-CE) to provide information on the capability of ABB-CE`s System 80 + Advanced Light Water Reactor (ALWR) to transform, through reactor burnup, 100 metric tonnes (MT) of weapons grade plutonium (Pu) into a form which is not readily useable in weapons. This information is being developed as part of DOE`s Plutonium Disposition Study, initiated by DOE in response to Congressional action. This document Volume 2, provides a discussion of: Plutonium Fuel Cycle; Technology Needs; Regulatory Considerations; Cost and Schedule Estimates; and Deployment Strategy.

Not Available

1993-05-15T23:59:59.000Z

366

DOE/EIS-0283-SA1: Supplement Analysis and Amended Record of Decision for Changes Needed To the Surplus Plutonium Disposition Program (4/24/03)  

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

3-SA1 3-SA1 April 2003 Changes Needed To The Surplus Plutonium Disposition Program SUPPLEMENT ANALYSIS AND AMENDED RECORD OF DECISION U.S. Department of Energy National Nuclear Security Administration Office of Fissile Materials Disposition Washington, D.C. Table of Contents i Table of Contents List of Figures ................................................................................................................................. ii List of Tables .................................................................................................................................. ii List of Acronyms ...........................................................................................................................

367

Optimization and implementation study of plutonium disposition using existing CANDU Reactors. Final report  

SciTech Connect

Since early 1994, the Department of Energy has been sponsoring studies aimed at evaluating the merits of disposing of surplus US weapons plutonium as Mixed Oxide (MOX) fuel in existing commercial Canadian Pressurized Heavy Water reactors, known as CANDU`s. The first report, submitted to DOE in July, 1994 (the 1994 Executive Summary is attached), identified practical and safe options for the consumption of 50 to 100 tons of plutonium in 25 years in some of the existing CANDU reactors operating the Bruce A generating station, on Lake Huron, about 300 km north east of Detroit. By designing the fuel and nuclear performance to operate within existing experience and operating/performance envelope, and by utilizing existing fuel fabrication and transportation facilities and methods, a low cost, low risk method for long term plutonium disposition was developed. In December, 1995, in response to evolving Mission Requirements, the DOE requested a further study of the CANDU option with emphasis on more rapid disposition of the plutonium, and retaining the early start and low risk features of the earlier work. This report is the result of that additional work.

NONE

1996-09-01T23:59:59.000Z

368

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

SciTech Connect

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

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

1997-05-01T23:59:59.000Z

369

SAMPLE RESULTS FROM THE INTEGRATED SALT DISPOSITION PROGRAM MACROBATCH 4 TANK 21H QUALIFICATION SAMPLES  

SciTech Connect

Savannah River National Laboratory (SRNL) analyzed samples from Tank 21H to qualify them for use in the Integrated Salt Disposition Program (ISDP) Batch 4 processing. All sample results agree with expectations based on prior analyses where available. No issues with the projected Salt Batch 4 strategy are identified. This revision includes additional data points that were not available in the original issue of the document, such as additional plutonium results, the results of the monosodium titanate (MST) sorption test and the extraction, scrub strip (ESS) test. This report covers the revision to the Tank 21H qualification sample results for Macrobatch (Salt Batch) 4 of the Integrated Salt Disposition Program (ISDP). A previous document covers initial characterization which includes results for a number of non-radiological analytes. These results were used to perform aluminum solubility modeling to determine the hydroxide needs for Salt Batch 4 to prevent the precipitation of solids. Sodium hydroxide was then added to Tank 21 and additional samples were pulled for the analyses discussed in this report. This work was specified by Task Technical Request and by Task Technical and Quality Assurance Plan (TTQAP).

Peters, T.; Fink, S.

2011-06-22T23:59:59.000Z

370

Disposition of plutonium from dismantled nuclear weapons: Fission options and comparisons  

SciTech Connect

Over the next decade, the United States expects to recover about 50 Mg of excess weapon plutonium and the Republic of Russia expects to recover a similar amount. Ensuring that these large quantities of high-grade material are not reused in nuclear weapons has drawn considerable attention. In response to this problem, the US Department of Energy (DOE) chartered the Plutonium Disposition Task Force (PDTF), in the summer of 1992, to assess a range of practical means for disposition of excess US plutonium. This report summarizes and compares the Fission Options'' provided to the Fission Working Group Review Committee (the committee) of the PDTF. The review by the committee was based on preliminary information received as of December 4, 1992, and as such the results summarized in this report should also be considered preliminary. The committee concluded that irradiation of excess weapon plutonium in fission reactors in conjunction with the generation of electricity and storing the spent fuel is a fast, cost-effective, and environmentally acceptable method of addressing the safeguards (diversion) issue. When applied appropriately, this method is consistent with current nonproliferation policy. The principal effect of implementing the fission options is at most a moderate addition of plutonium to that existing in commercial spent fuel. The amount of plutonium in commercial spent fuel by the year 2000 is estimated to be 300 Mg. The addition of 50 Mg of excess weapon plutonium, in this context, is not a determining factor, moreover, several of the fission options achieve substantial annihilation of plutonium.

Omberg, R.P. (Westinghouse Hanford Co., Richland, WA (United States)); Walter, C.E. (Lawrence Livermore National Lab., CA (United States))

1993-02-05T23:59:59.000Z

371

Disposition of plutonium from dismantled nuclear weapons: Fission options and comparisons  

SciTech Connect

Over the next decade, the United States expects to recover about 50 Mg of excess weapon plutonium and the Republic of Russia expects to recover a similar amount. Ensuring that these large quantities of high-grade material are not reused in nuclear weapons has drawn considerable attention. In response to this problem, the US Department of Energy (DOE) chartered the Plutonium Disposition Task Force (PDTF), in the summer of 1992, to assess a range of practical means for disposition of excess US plutonium. This report summarizes and compares the ``Fission Options`` provided to the Fission Working Group Review Committee (the committee) of the PDTF. The review by the committee was based on preliminary information received as of December 4, 1992, and as such the results summarized in this report should also be considered preliminary. The committee concluded that irradiation of excess weapon plutonium in fission reactors in conjunction with the generation of electricity and storing the spent fuel is a fast, cost-effective, and environmentally acceptable method of addressing the safeguards (diversion) issue. When applied appropriately, this method is consistent with current nonproliferation policy. The principal effect of implementing the fission options is at most a moderate addition of plutonium to that existing in commercial spent fuel. The amount of plutonium in commercial spent fuel by the year 2000 is estimated to be 300 Mg. The addition of 50 Mg of excess weapon plutonium, in this context, is not a determining factor, moreover, several of the fission options achieve substantial annihilation of plutonium.

Omberg, R.P. [Westinghouse Hanford Co., Richland, WA (United States); Walter, C.E. [Lawrence Livermore National Lab., CA (United States)

1993-02-05T23:59:59.000Z

372

Disposition of fuel elements from the Aberdeen and Sandia pulse reactor (SPR-II) assemblies  

SciTech Connect

We describe the disposition of fuel from the Aberdeen (APR) and the Sandia Pulse Reactors (SPR-II) which were used to provide intense neutron bursts for radiation effects testing. The enriched Uranium - 10% Molybdenum fuel from these reactors was shipped to the Los Alamos National Laboratory (LANL) for size reduction prior to shipment to the Savannah River Site (SRS) for final disposition in the H Canyon facility. The Shipper/Receiver Agreements (SRA), intra-DOE interfaces, criticality safety evaluations, safety and quality requirements and key materials management issues required for the successful completion of this project will be presented. This work is in support of the DOE Consolidation and Disposition program. Sandia National Laboratories (SNL) has operated pulse nuclear reactor research facilities for the Department of Energy since 1961. The Sandia Pulse Reactor (SPR-II) was a bare metal Godiva-type reactor. The reactor facilities have been used for research and development of nuclear and non-nuclear weapon systems, advanced nuclear reactors, reactor safety, simulation sources and energy related programs. The SPR-II was a fast burst reactor, designed and constructed by SNL that became operational in 1967. The SPR-ll core was a solid-metal fuel enriched to 93% {sup 235}U. The uranium was alloyed with 10 weight percent molybdenum to ensure the phase stabilization of the fuel. The core consisted of six fuel plates divided into two assemblies of three plates each. Figure 1 shows a cutaway diagram of the SPR-II Reactor with its decoupling shroud. NNSA charged Sandia with removing its category 1 and 2 special nuclear material by the end of 2008. The main impetus for this activity was based on NNSA Administrator Tom D'Agostino's six focus areas to reenergize NNSA's nuclear material consolidation and disposition efforts. For example, the removal of SPR-II from SNL to DAF was part of this undertaking. This project was in support of NNSA's efforts to consolidate the locations of special nuclear material (SNM) to reduce the cost of securing many SNM facilities. The removal of SPR-II from SNL was a significant accomplishment in SNL's de-inventory efforts and played a key role in reducing the number of locations requiring the expensive security measures required for category 1 and 2 SNM facilities. A similar pulse reactor was fabricated at the Y-12 National Security Complex beginning in the late 1960's. This Aberdeen Pulse Reactor (APR) was operated at the Army Pulse Radiation Facility (APRF) located at the Aberdeen Test Center (ATC) in Maryland. When the APRF was shut down in 2003, a portion of the DOE-owned Special Nuclear Material (SNM) was shipped to an interim facility for storage. Subsequently, the DOE determined that the material from both the SPR-II and the APR would be processed in the H-Canyon at the Savannah River Site (SRS). Because of the SRS receipt requirements some of the material was sent to the Los Alamos National Laboratory (LANL) for size-reduction prior to shipment to the SRS for final disposition.

Mckerley, Bill [Los Alamos National Laboratory; Bustamante, Jacqueline M [Los Alamos National Laboratory; Costa, David A [Los Alamos National Laboratory; Drypolcher, Anthony F [Los Alamos National Laboratory; Hickey, Joseph [Los Alamos National Laboratory

2010-01-01T23:59:59.000Z

373

Applications of advanced petroleum production technology and water alternating gas injection for enhanced oil recovery - Mattoon Oil Field, Illinois. Final report  

SciTech Connect

Phase I results of a C0{sub 2}-assisted oil recovery demonstration project in selected Cypress Sandstone reservoirs at Mattoon Field, Illinois are reported. The design and scope of this project included C0{sub 2} injectvity testing in the Pinnell and Sawyer units, well stimulaton treatments with C0{sub 2} in the Strong unit and infill well drilling, completion and oil production. The field activities were supported by extensive C0{sub 2}-oil-water coreflood experiments, CO{sub 2} oil-phase interaction experiments, and integrated geologic modeling and reservoir simulations. The progress of the project was made public through presentations at an industry meeting and a DOEs contractors` symposium, through quarterly reports and one-to-one consultations with interested operators. Phase II of this project was not implemented. It would have been a water-alternating-gas (WAG) project of longer duration.

Baroni, M. [American Oil Recovery, Inc., Decatur, IL (United States)

1995-09-01T23:59:59.000Z

374

Verification and Validation Strategy for Implementation of Hybrid Potts-Phase Field Hydride Modeling Capability in MBM  

SciTech Connect

The Used Fuel Disposition (UFD) program has initiated a project to develop a hydride formation modeling tool using a hybrid Potts­phase field approach. The Potts model is incorporated in the SPPARKS code from Sandia National Laboratories. The phase field model is provided through MARMOT from Idaho National Laboratory.

Jason D. Hales; Veena Tikare

2014-04-01T23:59:59.000Z

375

End of FY10 report - used fuel disposition technical bases and lessons learned : legal and regulatory framework for high-level waste disposition in the United States.  

SciTech Connect

This report examines the current policy, legal, and regulatory framework pertaining to used nuclear fuel and high level waste management in the United States. The goal is to identify potential changes that if made could add flexibility and possibly improve the chances of successfully implementing technical aspects of a nuclear waste policy. Experience suggests that the regulatory framework should be established prior to initiating future repository development. Concerning specifics of the regulatory framework, reasonable expectation as the standard of proof was successfully implemented and could be retained in the future; yet, the current classification system for radioactive waste, including hazardous constituents, warrants reexamination. Whether or not consideration of multiple sites are considered simultaneously in the future, inclusion of mechanisms such as deliberate use of performance assessment to manage site characterization would be wise. Because of experience gained here and abroad, diversity of geologic media is not particularly necessary as a criterion in site selection guidelines for multiple sites. Stepwise development of the repository program that includes flexibility also warrants serious consideration. Furthermore, integration of the waste management system from storage, transportation, and disposition, should be examined and would be facilitated by integration of the legal and regulatory framework. Finally, in order to enhance acceptability of future repository development, the national policy should be cognizant of those policy and technical attributes that enhance initial acceptance, and those policy and technical attributes that maintain and broaden credibility.

Weiner, Ruth F.; Blink, James A. (Lawrence Livermore National Laboratory, Livermore, CA); Rechard, Robert Paul; Perry, Frank (Los Alamos National Laboratory, Los Alamos, NM); Jenkins-Smith, Hank C. (University of Oklahoma, Norman, OK); Carter, Joe (Savannah River Nuclear Solutions, Aiken, SC); Nutt, Mark (Argonne National Laboratory, Argonne, IL); Cotton, Tom (Complex Systems Group, Washington DC)

2010-09-01T23:59:59.000Z

376

Review of the Facility Centered Assessment of the Los Alamos National Laboratory Waste Disposition Project, September 2011  

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

Facility Centered Assessment of the Facility Centered Assessment of the Los Alamos National Laboratory Waste Disposition Project September 2011 Office of Safety and Emergency Management Evaluations Office of Health, Safety and Security U.S. Department of Energy Table of Contents 1.0 Introduction ............................................................................................................................ 1 2.0 Background ............................................................................................................................ 1 3.0 Results .................................................................................................................................... 2 4.0 Conclusions ............................................................................................................................ 7

377

Review of the Facility Centered Assessment of the Los Alamos National Laboratory Waste Disposition Project, September 2011  

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

Facility Centered Assessment of the Facility Centered Assessment of the Los Alamos National Laboratory Waste Disposition Project September 2011 Office of Safety and Emergency Management Evaluations Office of Health, Safety and Security U.S. Department of Energy Table of Contents 1.0 Introduction ............................................................................................................................ 1 2.0 Background ............................................................................................................................ 1 3.0 Results .................................................................................................................................... 2 4.0 Conclusions ............................................................................................................................ 7

378

Sample results from the integrated salt disposition program macrobatch 6 tank 21H qualifications MST solids sample  

SciTech Connect

Savannah River National Laboratory (SRNL) performed experiments on qualification material for use in the Integrated Salt Disposition Program (ISDP) Batch 6 processing. As part of this qualification work, SRNL performed an Actinide Removal Process (ARP) test. From this test, the residual monosodium titanate (MST) was analyzed for radionuclide uptake. The results of these analyses are reported and are within historical precedent.

Peters, T. B.

2013-02-26T23:59:59.000Z

379

Green River Locks and Dams 3, 4, 5, 6 and Barren River Lock and Dam 1 Disposition, Kentucky  

E-Print Network (OSTI)

Green River Locks and Dams 3, 4, 5, 6 and Barren River Lock and Dam 1 Disposition, Kentucky 16 September 2014 ABSTRACT: Green River Locks and Dams 3 through 6 and Barren River Lock and Dam 1 were. The Green River Locks and Dams 5 and 6 ceased operations in 1951 due to a marked decline in navigation

US Army Corps of Engineers

380

Process Guide for the Identification and Disposition of S/CI or Defective Items at Department of Energy Facilities  

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

The Process Guide for the Identification and Disposition of S/CI or Defective Items was developed to help DOE facilities to collect, screen, communicate information, and dispose of S/CI or defective items that could potentially impact operations at DOE facilities.

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


381

A Roadmap and Discussion of Issues for Physics Analyses Required to Support Plutonium Disposition in VVER-1000 Reactors  

SciTech Connect

The purpose of this report is to document the physics analyses that must be performed to successfully disposition weapons-usable plutonium in VVER-1000 reactors in the Russian Federation. The report is a document to support programmatic and financial planning. It does not include documentation of the technical procedures by which physics analyses are performed, nor are the results of any analyses included.

Primm, R.T.; Drischler, J.D.; Pavlovichev, A.M. Styrine, Y.A.

2000-06-01T23:59:59.000Z

382

Analysis and section of processes for the disposition of excess fissile material from nuclear weapon dismantlement in the United States  

SciTech Connect

The end of the cold war and the acceleration of nuclear disarmament efforts by the United States (US) and Russia are generating large quantities of surplus fissile nuclear materials that are no longer needed for military purposes. The safe and secure disposition of this surplus material to prevent theft or reuse in weapons has become a high priority for the US Department of Energy (USDOE). Many options exist for storage and disposition (use or disposal) of these surplus materials. The criteria, which have been developed from the basis for a preliminary ``screening`` of options, to eliminate from further consideration those options that do not meet minimal requirements. Factors, or attributes, contained in the screening and selection criteria include: (1) resistance to theft and diversion by unauthorized parties, (2) resistance to retrieval, extraction, and reuse by the host nation, (3) technical viability, (4) environmental, safety, and health impacts, (5) cost effectiveness, (6) timeliness, (7) fostering of progress and cooperation with Russia and others, (8) public and institutional acceptance, and (9) additional benefits. The evaluation of environmental impacts, in accordance with the US National Environmental Policy Ac (NEPA) process, is an integral part of the overall evaluation process. Because of the variety of physical and chemical forms of the nuclear material inventory, and because of the large number of possible disposition technologies and final forms, several hundred possible pathways to disposition have been defined and have undergone a systematic selection process. Also, because nuclear material disposition will have far ranging impacts, extensive public, in the form of public and stakeholder, input was integral to the selection process.

Myers, B.R.; Armantrout, G.A. [Lawrence Livermore National Lab., CA (United States); Erickson, R. [Los Alamos National Lab., NM (United States)

1995-02-01T23:59:59.000Z

383

Using Cable Suspended Submersible Pumps to Reduce Production Costs to Increase Ultimate Recovery in the Red Mountain Field of the San Juan Basin Region  

SciTech Connect

A joint venture between Enerdyne LLC, a small independent oil and gas producer, and Pumping Solutions Inc., developer of a low volume electric submersible pump, suspended from a cable, both based in Albuquerque, New Mexico, has re-established marginal oil production from Red Mountain Oil Field, located in the San Juan Basin, New Mexico by working over 17 existing wells, installing cable suspended submersible pumps ( Phase I ) and operating the oil field for approximately one year ( Phase II ). Upon the completion of Phases I and II ( Budget Period I ), Enerdyne LLC commenced work on Phase III which required additional drilling in an attempt to improve field economics ( Budget Period II ). The project was funded through a cooperative 50% cost sharing agreement between Enerdyne LLC and the National Energy Technology Laboratory (NETL), United States Department of Energy, executed on April 16, 2003. The total estimated cost for the two Budget Periods, of the Agreement, was $1,205,008.00 as detailed in Phase I, II & III Authorization for Expenditures (AFE). This report describes tasks performed and results experienced by Enerdyne LLC during the three phases of the cooperative agreement.

Don L. Hanosh

2006-08-15T23:59:59.000Z

384

DOE-STD-1120-2005; Integration of Environment Safety and Health into Facility Disposition Activities  

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

20-2005 20-2005 Volume 1 of 2 April 2005 DOE STANDARD INTEGRATION OF ENVIRONMENT, SAFETY, AND HEALTH INTO FACILITY DISPOSITION ACTIVITIES Volume 1 of 2: Documented Safety Analysis for Decommissioning and Environmental Restoration Projects U.S. Department of Energy AREA SAFT Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. NOT MEASUREMENT SENSITIVE TS i This document has been reproduced directly from the best available copy. Available to DOE and DOE contractors from the Office of Scientific and Technical Information, P.O. Box 62, Oak Ridge, TN 37831; (423) 576-8401. Available to the public from the U.S. Department of Commerce, Technology Administration, National Technical Information Service, Springfield, VA 22161; (703) 605-6000.

385

DOE/EA-1607 FINAL ENVIRONMENTAL ASSESSMENT DISPOSITION OF DOE EXCESS  

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

µCi/cc microcuries per cubic centimeter µCi/cc microcuries per cubic centimeter MAP mitigation action plan MEI maximally exposed individual mg/kg milligrams per kilogram mrem millirem mSv millisievert MT metric ton MTCA Model Toxics Control Act MTU metric tons of uranium N/A not applicable Final Environmental Assessment: Disposition of DOE Excess Depleted Uranium, Natural Uranium, and Low-Enriched Uranium vi NAAQS National Ambient Air Quality Standards NEF National Enrichment Facility NEPA National Environmental Policy Act NRC U.S. Nuclear Regulatory Commission NU natural uranium NUF 6 natural uranium hexafluoride pCi/g picocuries per gram PEIS programmatic environmental impact statement PM 2.5 particulate matter with a diameter of 2.5 microns or less PM 10 particulate matter with a diameter of 10 microns or less

386

Used Fuel Disposition Campaign Phase I Ring Compression Testing of High  

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

Phase I Ring Compression Testing of Phase I Ring Compression Testing of High Burnup Cladding Used Fuel Disposition Campaign Phase I Ring Compression Testing of High Burnup Cladding The purpose of ring compression testing is to generate data to support the development of the technical basis for extended storage and transportation of high-burnup fuel. This report highlights the results of completed Phase I testing of high-burnup M5® cladding and the revised three-year test plan. The goal of the ring compression testing is to identify process conditions that would minimize radial-hydride formation and the corresponding DBTT of high-burnup fuel cladding and to generate data and models to support the development of the technical basis for extended storage and transportation of high-burnup fuel.

387

May Also Be Used U.S. DEPARTMENT OF ENERGY REQUEST FOR RECORDS DISPOSITION AUTHORIZATION  

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

5 5 (06-93) 05-90 Edition May Also Be Used U.S. DEPARTMENT OF ENERGY REQUEST FOR RECORDS DISPOSITION AUTHORIZATION OMB Control No. 1910-1700 OMB Burden Disclosure Statement on Back 1. Control Number 2a. Organizational Unit and Routing Symbol 2b. Departmental Organization Contractor Organization 3a. Volume On Hand (Cu. Ft.) 3b. Volume Accumulated Annually (Estimate Cu. Ft.) 4. Record Dates (From/To) 5. Identification of Filing Unit (Include type of record, function performed, security classification (or other restrictions), and other descriptive facts) 6. Appraisal (Include justification for retention period. Indicate relationship of filing unit to any other related filing unit in the same or other organizations. Also, indicate retention period in U.S. Department of Energy (DOE), if subsequent transfer to National Archives

388

Abandoned oil fields in Kansas and Nebraska  

SciTech Connect

Data on approximately 400 abandoned oil fields in Kansas and 90 abandoned oil fields in Nebraska are presented. The following information is obtained on each field: county; DOE field code; field name; AAPG geologic province code; discovery date; year of last production; discovery well operator; proven acreage; formation thickness; depth of field; API gravity; calendar year; yearly field oil production; yearly field gas production; cumulative oil production; cumulative gas production; number abandoned fields in county; cumulative production of oil from fields; and cumulative production of gas from fields. (DMC)

Not Available

1982-12-01T23:59:59.000Z

389

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

SciTech Connect

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

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

1998-08-01T23:59:59.000Z

390

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

SciTech Connect

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

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

1998-08-01T23:59:59.000Z

391

Engineering evaluation of alternatives for the disposition of Niagara Falls Storage Site, its residues and wastes  

SciTech Connect

The final disposition scenarios selected by DOE for assessment in this document are consistent with those stated in the Notice of Intent to prepare an Environmental Impact Statement (EIS) for the Niagara Falls Storage Site (NFSS) (DOE, 1983d) and the modifications to the alternatives resulting from the public scoping process. The scenarios are: take no action beyond interim remedial measures other than maintenance and surveillance of the NFSS; retain and manage the NFSS as a long-term waste management facility for the wastes and residues on the site; decontaminate, certify, and release the NFSS for other use, with long-term management of the wastes and residues at other DOE sites; and partially decontaminate the NFSS by removal and transport off site of only the more radioactive residues, and upgrade containment of the remaining wastes and residues on site. The objective of this document is to present to DOE the conceptual engineering, occupational radiation exposure, construction schedule, maintenance and surveillance requirements, and cost information relevant to design and implementation of each of the four scenarios. The specific alternatives within each scenario used as the basis for discussion in this document were evaluated on the bases of engineering considerations, technical feasibility, and regulatory requirements. Selected alternatives determined to be acceptable for each of the four final disposition scenarios for the NFSS were approved by DOE to be assessed and costed in this document. These alternatives are also the subject of the EIS for the NFSS currently being prepared by Argonne National Laboratory (ANL). 40 figures, 38 tables.

Not Available

1984-01-01T23:59:59.000Z

392

DOE/EA-1651: Final Environmental Assessment for U-233 Material Downblending and Disposition Project at the Oak Ridge National Laboratory Oak Ridge, Tennessee (January 2010)  

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

51 51 Final Environmental Assessment for U-233 Material Downblending and Disposition Project at the Oak Ridge National Laboratory Oak Ridge, Tennessee U. S. Department of Energy Oak Ridge Office Oak Ridge, Tennessee January 2010 FINDING OF NO SIGNIFICANT IMPACT URANIUM-233 MATERIAL DOWNBLENDING AND DISPOSITION PROJECT AT THE OAK RIDGE NATIONAL LABORATORY, OAK RIDGE, TENNESSEE AGENCY: U.S. Department of Energy (DOE) ACTION: Finding of No Significant Impact (FONSI) SUMMARY: DOE has completed the Final Environmental Assessment for U-233 Material Downblending and Disposition Project at the Oak Ridge National Laboratory [DOE/EA-1651]. This environmental assessment (EA) evaluates the impacts of planned activities to modify selected

393

DOE plutonium disposition study: Analysis of existing ABB-CE Light Water Reactors for the disposition of weapons-grade plutonium. Final report  

SciTech Connect

Core reactivity and basic fuel management calculations were conducted on the selected reactors (with emphasis on the System 80 units as being the most desirable choice). Methods used were identical to those reported in the Evolutionary Reactor Report. From these calculations, the basic mission capability was assessed. The selected reactors were studied for modification, such as the addition of control rod nozzles to increase rod worth, and internals and control system modifications that might also be needed. Other system modifications studied included the use of enriched boric acid as soluble poison, and examination of the fuel pool capacities. The basic geometry and mechanical characteristics, materials and fabrication techniques of the fuel assemblies for the selected existing reactors are the same as for System 80+. There will be some differences in plutonium loading, according to the ability of the reactors to load MOX fuel. These differences are not expected to affect licensability or EPA requirements. Therefore, the fuel technology and fuel qualification sections provided in the Evolutionary Reactor Report apply to the existing reactors. An additional factor, in that the existing reactor availability presupposes the use of that reactor for the irradiation of Lead Test Assemblies, is discussed. The reactor operating and facility licenses for the operating plants were reviewed. Licensing strategies for each selected reactor were identified. The spent fuel pool for the selected reactors (Palo Verde) was reviewed for capacity and upgrade requirements. Reactor waste streams were identified and assessed in comparison to uranium fuel operations. Cost assessments and schedules for converting to plutonium disposition were estimated for some of the major modification items. Economic factors (incremental costs associated with using weapons plutonium) were listed and where possible under the scope of work, estimates were made.

Not Available

1994-06-01T23:59:59.000Z

394

Class III Mid-Term Project, "Increasing Heavy Oil Reserves in the Wilmington Oil Field Through Advanced Reservoir Characterization and Thermal Production Technologies"  

SciTech Connect

The overall objective of this project was to increase heavy oil reserves in slope and basin clastic (SBC) reservoirs through the application of advanced reservoir characterization and thermal production technologies. The project involved improving thermal recovery techniques in the Tar Zone of Fault Blocks II-A and V (Tar II-A and Tar V) of the Wilmington Field in Los Angeles County, near Long Beach, California. A primary objective has been to transfer technology that can be applied in other heavy oil formations of the Wilmington Field and other SBC reservoirs, including those under waterflood. The first budget period addressed several producibility problems in the Tar II-A and Tar V thermal recovery operations that are common in SBC reservoirs. A few of the advanced technologies developed include a three-dimensional (3-D) deterministic geologic model, a 3-D deterministic thermal reservoir simulation model to aid in reservoir management and subsequent post-steamflood development work, and a detailed study on the geochemical interactions between the steam and the formation rocks and fluids. State of the art operational work included drilling and performing a pilot steam injection and production project via four new horizontal wells (2 producers and 2 injectors), implementing a hot water alternating steam (WAS) drive pilot in the existing steamflood area to improve thermal efficiency, installing a 2400-foot insulated, subsurface harbor channel crossing to supply steam to an island location, testing a novel alkaline steam completion technique to control well sanding problems, and starting on an advanced reservoir management system through computer-aided access to production and geologic data to integrate reservoir characterization, engineering, monitoring, and evaluation. The second budget period phase (BP2) continued to implement state-of-the-art operational work to optimize thermal recovery processes, improve well drilling and completion practices, and evaluate the geomechanical characteristics of the producing formations. The objectives were to further improve reservoir characterization of the heterogeneous turbidite sands, test the proficiency of the three-dimensional geologic and thermal reservoir simulation models, identify the high permeability thief zones to reduce water breakthrough and cycling, and analyze the nonuniform distribution of the remaining oil in place. This work resulted in the redevelopment of the Tar II-A and Tar V post-steamflood projects by drilling several new wells and converting idle wells to improve injection sweep efficiency and more effectively drain the remaining oil reserves. Reservoir management work included reducing water cuts, maintaining or increasing oil production, and evaluating and minimizing further thermal-related formation compaction. The BP2 project utilized all the tools and knowledge gained throughout the DOE project to maximize recovery of the oil in place.

Scott Hara

2007-03-31T23:59:59.000Z

395

A Study of Production/Injection Data from Slim Holes and Large-Diameter Wells at the Okuaizu Geothermal Field, Tohoku, Japan  

SciTech Connect

Discharge from the Okuaizu boreholes is accompanied by in situ boiling. Analysis of cold-water injection and discharge data from the Okuaizu boreholes indicates that the two-phase productivity index is about an order of magnitude smaller than the injectivity index. The latter conclusion is in agreement with analyses of similar data from Oguni, Sumikawa, and Kirishima geothermal fields. A wellbore simulator was used to examine the effect of borehole diameter on the discharge capacity of geothermal boreholes with two-phase feedzones. Based on these analyses, it appears that it should be possible to deduce the discharge characteristics of largediameter wells using test data from slim holes with two-phase feeds.

Renner, Joel Lawrence; Garg, Sabodh K.; Combs, Jim

2002-06-01T23:59:59.000Z

396

RMOTC - Production  

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

Production Production RMOTC Pumpjack in action During the process of the sale of NPR-3, RMOTC will focus on maximizing the value of the NPR-3 site and will continue with its Production Optimization Projects. NPR-3 includes 9,481 acres with more than 400 oil-producing wells. Current oil production is at approximately 240 barrels of oil per day. In July 2013, RMOTC began working on a number of Production Optimization Projects within the NPR-3 field, with the goal to optimize and improve flow and efficiency. Production Optimization Projects include repairing and replacing existing infrastructure with new infrastructure in order to optimize current wells and bring additional wells online. These Production Optimization Projects will continue throughout 2013 and are focused on improving current production and creating revenue for the America tax payer.

397

Increasing heavy oil reservers in the Wilmington oil Field through advanced reservoir characterization and thermal production technologies, technical progress report, October 1, 1996--December 31, 1996  

SciTech Connect

The project involves improving thermal recovery techniques in a slope and basin clastic (SBC) reservoir in the Wilmington field, Los Angeles Co., Calif. using advanced reservoir characterization and thermal production technologies. The existing steamflood in the Tar zone of Fault Block (FB) 11-A has been relatively inefficient because of several producibility problems which are common in SBC reservoirs. Inadequate characterization of the heterogeneous turbidite sands, high permeability thief zones, low gravity oil, and nonuniform distribution of remaining oil have all contributed to poor sweep efficiency, high steam-oil ratios, and early steam breakthrough. Operational problems related to steam breakthrough, high reservoir pressure, and unconsolidated formation sands have caused premature well and downhole equipment failures. In aggregate, these reservoir and operational constraints have resulted in increased operating costs and decreased recoverable reserves. The advanced technologies to be applied include: (1) Develop three-dimensional (3-D) deterministic and stochastic geologic models. (2) Develop 3-D deterministic and stochastic thermal reservoir simulation models to aid in reservoir management and subsequent development work. (3) Develop computerized 3-D visualizations of the geologic and reservoir simulation models to aid in analysis. (4) Perform detailed study on the geochemical interactions between the steam and the formation rock and fluids. (5) Pilot steam injection and production via four new horizontal wells (2 producers and 2 injectors). (6) Hot water alternating steam (WAS) drive pilot in the existing steam drive area to improve thermal efficiency. (7) Installing a 2100 foot insulated, subsurface harbor channel crossing to supply steam to an island location. (8) Test a novel alkaline steam completion technique to control well sanding problems and fluid entry profiles. (9) Advanced reservoir management through computer-aided access to production and geologic data to integrate reservoir characterization, engineering, monitoring, and evaluation.

Hara, S. [Tidelands Oil Production Co., Long Beach, CA (United States)], Casteel, J. [USDOE Bartlesville Project Office, OK (United States)

1997-05-11T23:59:59.000Z

398

Increasing heavy oil reserves in the Wilmington Oil field through advanced reservoir characterization and thermal production technologies. Quarterly report, April 1, 1996--June 30, 1996  

SciTech Connect

The project involves improving thermal recovery techniques in a slope and basin clastic (SBC) reservoir in the Wilmington field, Los Angeles Co., California using advanced reservoir characterization and thermal production technologies. Inadequate characterization of the heterogeneous turbidite sands, high permeability thief zones, low gravity oil, and nonuniform distribution of remaining oil have all contributed to poor sweep efficiency, high steam-oil ratios, and early steam breakthrough. Operational problems related to steam breakthrough, high reservoir pressure, and unconsolidated formation sands have caused premature well and downhole equipment failures. In aggregate, these reservoir and operational constraints have resulted in increased operating costs and decreased recoverable reserves. The technologies include: (1) Develop three-dimensional (3-D) deterministic and stochastic geologic models. (2) Develop 3-D deterministic and stochastic thermal reservoir simulation models to aid in reservoir management and subsequent development work. (3) Develop computerized 3-D visualizations of the geologic and reservoir simulation models to aid in analysis. (4) Perform detailed study on the geochemical interactions between the steam and the formation rock and fluids. (5) Pilot steam injection and production via four new horizontal wells (2 producers and 2 injectors). (6) Hot water alternating steam (WAS) drive pilot in the existing steam drive area to improve thermal efficiency. (7) Installing an 2400 foot insulated, subsurface harbor channel crossing to supply steam to an island location. (8) Test a novel alkaline steam completion technique to control well sanding problems and fluid entry profiles. (9) Advanced reservoir management through computer-aided access to production and geologic data to integrate reservoir characterization, engineering, monitoring, and evaluation.

Hara, S.

1996-08-05T23:59:59.000Z

399

SAMPLE RESULTS FROM THE INTEGRATED SALT DISPOSITION PROGRAM MACROBATCH 5 TANK 21H QUALIFICATION MST, ESS AND PODD SAMPLES  

SciTech Connect

Savannah River National Laboratory (SRNL) performed experiments on qualification material for use in the Integrated Salt Disposition Program (ISDP) Batch 5 processing. This qualification material was a composite created from recent samples from Tank 21H and archived samples from Tank 49H to match the projected blend from these two tanks. Additionally, samples of the composite were used in the Actinide Removal Process (ARP) and extraction-scrub-strip (ESS) tests. ARP and ESS test results met expectations. A sample from Tank 21H was also analyzed for the Performance Objectives Demonstration Document (PODD) requirements. SRNL was able to meet all of the requirements, including the desired detection limits for all the PODD analytes. This report details the results of the Actinide Removal Process (ARP), Extraction-Scrub-Strip (ESS) and Performance Objectives Demonstration Document (PODD) samples of Macrobatch (Salt Batch) 5 of the Integrated Salt Disposition Program (ISDP).

Peters, T.; Fink, S.

2012-04-24T23:59:59.000Z

400

Nonproliferation and arms control assessment of weapons-usable fissile material storage and excess plutonium disposition alternatives  

SciTech Connect

This report has been prepared by the Department of Energy`s Office of Arms Control and Nonproliferation (DOE-NN) with support from the Office of Fissile Materials Disposition (DOE-MD). Its purpose is to analyze the nonproliferation and arms reduction implications of the alternatives for storage of plutonium and HEU, and disposition of excess plutonium, to aid policymakers and the public in making final decisions. While this assessment describes the benefits and risks associated with each option, it does not attempt to rank order the options or choose which ones are best. It does, however, identify steps which could maximize the benefits and mitigate any vulnerabilities of the various alternatives under consideration.

NONE

1997-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "disposition field production" 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

The Effects of Music-Mathematics Integrated Curriculum and Instruction on Elementary Students’ Mathematics Achievement and Dispositions  

E-Print Network (OSTI)

THE EFFECTS OF MUSIC-MATHEMATICS INTEGRATED CURRICULUM AND INSTRUCTION ON ELEMENTARY STUDENTS? MATHEMATICS ACHIEVEMENT AND DISPOSITIONS A Dissertation by SONG AN Submitted to the Office of Graduate Studies of Texas A...&M University in partial fulfillment of the requirements for the degree of DOCTOR OF PHILOSOPHY May 2012 Major Subject: Curriculum and Instruction THE EFFECTS OF MUSIC-MATHEMATICS INTEGRATED CURRICULUM AND INSTRUCTION ON ELEMENTARY STUDENTS...

An, Song

2012-07-16T23:59:59.000Z

402

Evaluation of Udder Conformation, Weight, Body Condition, Reproduction, Disposition, and Calf Growth in Bos indicus – Bos taurus Cows  

E-Print Network (OSTI)

Condition, Reproduction, Disposition, and Calf Growth in Bos indicus ? Bos taurus Cows. (August 2011) Aaron Jay Cooper, B.S., Texas A&M University; M.S., University of Nebraska-Lincoln Chair of Advisory Committee: Dr. James O. Sanders Data were... of Texas A&M University in partial fulfillment of the requirements for the degree of DOCTOR OF PHILOSOPHY August 2011 Major Subject: Animal Breeding Evaluation of Udder Conformation, Weight, Body...

Cooper, Aaron Jay

2011-10-21T23:59:59.000Z

403

Transfer of excess nuclear material from Los Alamos to Savannah River site for long-term disposition  

SciTech Connect

Los Alamos National Laboratory is preparing excess nuclear material for shipment to Savannah River Site (SRS) for final disposition. Prior to shipment the nuclear material will be stabilized and packaged to meet strict criteria. The criterion that must be met include: (1) the DOE stabilization, packaging and storage requirements for plutonium bearing materials, DOE-STD-3013, (2) shipping container packaging requirements, (3) SRS packaging and storage criteria, and (4) DOE Material Disposition criteria for either immobilization or MOX reactor fuel. Another issue in preparing for this transfer is the DOE certification of shipping containers and the availability of shipping containers. This transfer of the nuclear material is fully supported by the EM, DP and NN Sections of the DOE, as well as, by LANL and SRS, yet a strong collaboration is needed to meet all established requirements relating to stabilization, packaging, shipment, storage and final disposition. This paper will present the overall objectives, the issues and the planned strategy to accomplish this nuclear material transfer.

Hoth, C. W. (Carl W.); Yarbro, T. F. (Tresa F.); Foster, Lynn A.

2001-06-01T23:59:59.000Z

404

Transportable Vitrification System RCRA Closure Practical Waste Disposition Saves Time And Money  

SciTech Connect

The Transportable Vitrification System (TVS) was a large-scale vitrification system for the treatment of mixed wastes. The wastes contained both hazardous and radioactive materials in the form of sludge, soil, and ash. The TVS was developed to be moved to various United States Department of Energy (DOE) facilities to vitrify mixed waste as needed. The TVS consists of four primary modules: (1) Waste and Additive Materials Processing Module; (2) Melter Module; (3) Emissions Control Module; and (4) Control and Services Module. The TVS was demonstrated at the East Tennessee Technology Park (ETTP) during September and October of 1997. During this period, approximately 16,000 pounds of actual mixed waste was processed, producing over 17,000 pounds of glass. After the demonstration was complete it was determined that it was more expensive to use the TVS unit to treat and dispose of mixed waste than to direct bury this waste in Utah permitted facility. Thus, DOE had to perform a Resource Conservation and Recovery Act (RCRA) closure of the facility and find a reuse for as much of the equipment as possible. This paper will focus on the following items associated with this successful RCRA closure project: TVS site closure design and implementation; characterization activities focused on waste disposition; pollution prevention through reuse; waste minimization efforts to reduce mixed waste to be disposed; and lessons learned that would be integrated in future projects of this magnitude.

Brill, Angie; Boles, Roger; Byars, Woody

2003-02-26T23:59:59.000Z

405

Lessons Learned from Three Mile Island Packaging, Transportation and Disposition that Apply to Fukushima Daiichi Recovery  

SciTech Connect

Following the massive earthquake and resulting tsunami damage in March of 2011 at the Fukushima Daiichi nuclear power plant in Japan, interest was amplified for what was done for recovery at the Three Mile Island Unit 2 (TMI-2) in the United States following its meltdown in 1979. Many parallels could be drawn between to two accidents. This paper presents the results of research done into the TMI-2 recovery effort and its applicability to the Fukushima Daiichi cleanup. This research focused on three topics: packaging, transportation, and disposition. This research work was performed as a collaboration between Japan’s Central Research Institute of Electric Power Industry (CRIEPI) and the Idaho National Laboratory (INL). Hundreds of TMI-2 related documents were searched and pertinent information was gleaned from these documents. Other important information was also obtained by interviewing employees who were involved first hand in various aspects of the TMI-2 cleanup effort. This paper is organized into three main sections: (1) Transport from Three Mile Island to Central Facilities Area at INL, (2) Transport from INL Central Receiving Facility to INL Test Area North (TAN) and wet storage at TAN, and (3) Transport from TAN to INL Idaho Nuclear Technology and Engineering Center (INTEC) and Dry Storage at INTEC. Within each of these sections, lessons learned from performing recovery activities are presented and their applicability to the Fukushima Daiichi nuclear power plant cleanup are outlined.

Layne Pincock; Wendell Hintze; Dr. Koji Shirai

2012-07-01T23:59:59.000Z

406

Increasing heavy oil reserves in the Wilmington oil field through advanced reservoir characterization and thermal production technologies. [Quarterly report], October 1, 1995--December 31, 1995  

SciTech Connect

The project involves improving thermal recovery techniques in a slope and basin clastic (SBC) reservoir in the Wilmington field, Los Angeles Co., California using advanced reservoir characterization and thermal production technologies. This is the third quarterly technical progress report for the project. Through December 1995, the project is on schedule and on budget. Several significant technical achievements have already been successfully accomplished including the drilling of four horizontal wells (two producers and two steam injectors) utilizing a new and lower cost drilling program, the drilling of five observation wells to monitor the horizontal steamflood pilot, the installation of a subsurface harbor channel crossing for delivering steam to an island location, and a geochemical study of the scale minerals being created in the wellbore. Steam injection into the two horizontal injection wells began in mid-December 1995 utilizing the new 2400 ft steam line under the Cerritos Channel. Work on the basic reservoir engineering is expected to be completed in March 1996. A working deterministic geologic model was completed which allowed work to commence on the stochastic geologic and reservoir simulation models.

Hara, S. [Tidelands Oil Production Co., Long Beach, CA (United States)

1996-01-31T23:59:59.000Z

407

Sample Results From The Interim Salt Disposition Program Macrobatch 7 Tank 21H Qualification Samples  

SciTech Connect

Savannah River National Laboratory (SRNL) analyzed samples from Tank 21H in support of qualification of Macrobatch (Salt Batch) 7 for the Interim Salt Disposition Program (ISDP). An ARP and several ESS tests were also performed. This document reports characterization data on the samples of Tank 21H as well as simulated performance of ARP/MCU. No issues with the projected Salt Batch 7 strategy are identified, other than the presence of visible quantities of dark colored solids. A demonstration of the monosodium titanate (0.2 g/L) removal of strontium and actinides provided acceptable 4 hour average decontamination factors for Pu and Sr of 3.22 and 18.4, respectively. The Four ESS tests also showed acceptable behavior with distribution ratios (D(Cs)) values of 15.96, 57.1, 58.6, and 65.6 for the MCU, cold blend, hot blend, and Next Generation Solvent (NGS), respectively. The predicted value for the MCU solvent was 13.2. Currently, there are no models that would allow a prediction of extraction behavior for the other three solvents. SRNL recommends that a model for predicting extraction behavior for cesium removal for the blended solvent and NGS be developed. While no outstanding issues were noted, the presence of solids in the samples should be investigated in future work. It is possible that the solids may represent a potential reservoir of material (such as potassium) that could have an impact on MCU performance if they were to dissolve back into the feed solution. This salt batch is intended to be the first batch to be processed through MCU entirely using the new NGS-MCU solvent.

Peters, T. B.; Washington, A. L. II

2013-08-08T23:59:59.000Z

408

Lab Scale Production of NpO2  

SciTech Connect

The Savannah River Site (SRS) plans to disposition its legacy H-Canyon neptunium to Oak Ridge National Laboratory after converting it to oxide in HB-Line. Neptunium oxide, (NpO{sub 2}) was produced at the Savannah River Technology Center using the anticipated HB-Line flowsheet conditions. The oxide was produced from a neptunium nitrate solution via anion exchange, oxalate precipitation, and calcination at either 600 C or 650 C. The 98 grams of NpO{sub 2} produced in the laboratory should be representative of material produced in HB-Line and is to be used for gas generation testing to support radioactive material transportation safety analysis as part of the neptunium stabilization and disposition program at SRS. Results of each step of the oxide production will be presented.

Duffey, J

2003-08-29T23:59:59.000Z

409

Relationships between soil CO2 concentration and CO2 production, temperature, water content, and gas diffusivity: implications for field studies through sensitivity analyses  

Science Journals Connector (OSTI)

Soil CO2 levels reflect CO2 production and transport in soil and provide valuable information about soil CO2 dynamics. However, extracting information from soil CO2 profiles is often difficult because of the comp...

Shoji Hashimoto; Hikaru Komatsu

2006-02-01T23:59:59.000Z

410

Le Rglement des tudes, la Dclaration des droits des tudiants et des tudiantes, les Dispositions relatives l'application de la politique sur l'usage du franais  

E-Print Network (OSTI)

Dispositions relatives à l'application de la politique sur l'usage du français à l'Université Laval, la Politique sur l'usage du français à l'Université Laval ainsi que le Règlement disciplinaire à l

Laval, Université

411

PSI # Date Time Location Incident Description Disposition 4341 9/2/2011 8:00 Blue Ridge Bicycle Theft Norco Mountain bike BPD notified  

E-Print Network (OSTI)

PSI # Date Time Location Incident Description Disposition 4341 9/2/2011 8:00 Blue Ridge Bicycle Four or more citations received Fine issued 4353 9/8/2011 16:00 Elizabeth Rogers Bicycle Theft Bluish Green bicycle BPD notified 4354 9/9/2011 13:49 Short St Hair Salon Criminal Damage Graffiti on the rear

Baltisberger, Jay H.

412

Final Demolition and Disposition of 209-E Critical Mass Laboratory - 12267  

SciTech Connect

The 209-E Critical Mass Laboratory was constructed in 1960 to provide a heavy shielded reactor room where quantities of plutonium or uranium in solution could be brought to near-critical configurations under carefully controlled and monitored conditions. In the late 1980's, the responsible contractor, Pacific Northwest National Laboratory (PNNL), was directed by the Department of Energy (DOE) to prepare the facility for unoccupied status. The facility was demolished under a Removal Action Work Plan pursuant to the Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA). The funding for this project was provided by the American Recovery and Reinvestment Act (ARRA). The primary rooms of concern with regards to contamination in 209-E facility, which is over 9,000 square feet, are the criticality assembly room (CAR), the mix room, and the change room. The CAR contained two reactor hoods (HO-140 and HO-170), which each had a high efficiency particulate air (HEPA) filter system. The CAR contained 13 tanks ranging from 38 L (10 gal) to 401 L (106 gal). Tanks TK-109 and TK-110 are below grade, and were removed as part of this demolition and disposition remedy. Nonradiological and radiological hazardous substances were removed, decontaminated, or fixed in place, prior to demolition. Except for the removal of below grade tanks TK-109 and TK-110, the facility was demolished to slab-on-grade. PNNL performed stabilization and deactivation activities that included removal of bulk fissile material and chemicals, flushing tanks, stabilizing contamination within gloveboxes and hoods, and packaging and removing waste. The removal of the contaminated plutonium equipment and materials from the 209E facility presented a number of challenges similar in nature to those associated with the inventory reduction and cleanup activities at the Plutonium Finishing Plant. Although there were no bulk fissile materials or chemicals within the facility, there were residual radiological materials (isotopes of plutonium and americium) in the tanks and hoods. The complexity of the remedy was present because of the various configurations of the tanks and hoods, combined with the residual contaminants. Because of the weight and dimensional configuration, size reduction of the slab tanks, as well as removal and disposal of the different material used for moderation and absorption, were two examples of challenges that were resolved to complete the remedy. One of the key methods developed and implemented at the facility was the design and construction of a shroud to allow the cutting of the Pu contaminated tanks. The shroud design, development and implementation at the 209E Project was an example of enhanced work planning and task hazards analysis with worker involvement. This paper will present the lessons learned from the 209E facility inventory reduction activities including the shroud and other methodologies used. The initial Lessons Learned discussion for this project was scheduled for late January 2012. This facility is the first open-air demolition of a highly contaminated plutonium-contaminated facility accomplished by CH2M Hill under the Plateau Remediation Contract. The demolition was completed without spread of contamination to the workers and the surrounding area. As with any project of this complexity, there are significant accomplishments, as well as experience that can be applied to future demolition of plutonium-contaminated facilities on the Hanford Site. These experiences will be documented at a later date. (authors)

Woolery, Wade [US Department of Energy, Richland WA (United States); Dodd, Edwin III [CH2M Hill Plateau Remediation Company, Richland WA (United States)

2012-07-01T23:59:59.000Z

413

Peluchi : product development of a programmable robotic toy to stimulate interest in the fields of science and technology amongst young girls  

E-Print Network (OSTI)

Statistically speaking, science, technology, and engineering are male dominated fields. Peluchi is a second-generation prototype of a programmable robotic toy targeted towards young girls in hope of promoting more interest ...

Vu, My (My H.)

2011-01-01T23:59:59.000Z

414

Health Care Professionals vs Other Professionals: Do They Have Different Perceptions about Health Care Waste and Dangerous Products Pictograms? Some Findings Using a Digital Device in Field Survey  

Science Journals Connector (OSTI)

This paper presents a part of a wider research about GHS symbols comprehensibility. Here, a field survey was conducted using a digital device, instead of traditional platform – printed paper. Participants were...

Cláudia Renata Mont’Alvão

2014-01-01T23:59:59.000Z

415

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

SciTech Connect

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

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

1995-12-31T23:59:59.000Z

416

Sample Results From The Interim Salt Disposition Program Macrobatch 7 Tank 21H Qualification MST Solids Sample  

SciTech Connect

Savannah River National Laboratory (SRNL) performed experiments on qualification material for use in the Interim Salt Disposition Program (ISDP) Batch 7 processing. The Marcrobatch 7 material was received with visible fine particulate solids, atypical for these samples. The as received material was allowed to settle for a period greater than 24 hours. The supernatant was then decanted and utilized as our clarified feed material. As part of this qualification work, SRNL performed an Actinide Removal Process (ARP) test using the clarified feed material. From this test, the residual monosodium titanate (MST) was analyzed for radionuclide uptake after filtration from H-Tank Farm (HTF) feed salt solution. The results of these analyses are reported and are within historical precedent.

Washington, A. L. II; Peters, T. B.

2013-09-19T23:59:59.000Z

417

Pre-industrial charcoal production in Lower Lusatia (Brandenburg, Germany): Detection and evaluation of a large charcoal-burning field by combining archaeological studies, GIS-based analyses of shaded-relief maps and dendrochronological age determination  

Science Journals Connector (OSTI)

Abstract In pre-industrial times, charcoal burning was a common source of energy across Europe. Charcoal production and its related consequences for the upland environment are well known due to historical and palaeoenvironmental research. In recent years, awareness has grown regarding the use of woods in the lowlands for charcoal production. In the last 20 years, a large charcoal-burning field in Lower Lusatia (Brandenburg, North German Lowlands) was discovered by systematic archaeological excavations of the opencast mine of Jänschwalde. However, the excavations are limited to the mine, which only covers a portion of the Jänschwalder Heide and the surrounding forests. In this paper, we present the results of our study regarding the spatial extension and timing of charcoal production in the Jänschwalder Heide and its surrounding areas. We applied a combined approach using archaeological research results, GIS-analyses of shaded-relief maps (SRMs) and tree-ring dating of selected charcoal kiln remains. Approximately 900 excavated charcoal kiln ground plans were analysed, which provided a solid data basis for our GIS analyses. For an extensive evaluation, we enlarged our study area beyond the limits of the lignite mine. We identified and digitised the remains of the charcoal kilns by creating \\{SRMs\\} from digital elevation models (DEMs) that were based on high-resolution airborne laser scanning data (ALS). The data from the excavated and digitised charcoal kiln remains were analysed in terms of their sizes and spatial distributions. In addition, the dendrochronological ages of 16 selected charcoal kiln remains were determined. This study shows that charcoal production was more extensive than initially proven by archaeological excavations. The remains of more than 5000 charcoal kilns were detected on the \\{SRMs\\} across an area that was twice as large as the excavated charcoal-burning field. In the Jänschwalder Heide, considerably more charcoal kiln relicts exist compared with the surrounding communal areas. Furthermore, the charcoal kiln remains in the Jänschwalder Heide have larger diameters, suggesting large-scale charcoal production for supplying energy to the nearby ironworks at Peitz. However, the charcoal production on the communal land was most likely for local crafts. The ages of the charcoal kiln remains indicated that charcoal production occurred between the 17th and 19th centuries, corresponding with the main period of charcoal burning. Overall, our study suggested that charcoal production sites are underestimated in the modern landscapes of the North German Lowlands.

A. Raab; M. Takla; T. Raab; A. Nicolay; A. Schneider; H. Rösler; K.-U. Heußner; E. Bönisch

2014-01-01T23:59:59.000Z

418

Field-to-Fuel Performance Testing of Various Biomass Feedstocks: Production and Catalytic Upgrading of Bio-Oil to Refinery Blendstocks (Presentation)  

SciTech Connect

Large-scale, cost-competitive deployment of thermochemical technologies to replace petroleum oil with domestic biofuels will require inclusion of high volumes of low-cost, diverse biomass types into the supply chain. However, a comprehensive understanding of the impacts of feedstock thermo-physical and chemical variability, particularly inorganic matter (ash), on the yield and product distribution

Carpenter, D.; Westover, T.; Howe, D.; Evans, R.; French, R.; Kutnyakov, I.

2014-09-01T23:59:59.000Z

419

DOE - Office of Legacy Management -- Sperry Products Inc - CT 07  

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

Sperry Products Inc - CT 07 Sperry Products Inc - CT 07 FUSRAP Considered Sites Site: SPERRY PRODUCTS, INC. (CT.07) Eliminated from consideration under FUSRAP Designated Name: Not Designated Alternate Name: None Location: Danbury , Connecticut CT.07-1 Evaluation Year: 1994 CT.07-2 Site Operations: Performed tests involving non-destructive inspection techniques in the 1950s. CT.07-3 Site Disposition: Eliminated - Potential for contamination considered remote based on the limited scope of activities performed at the site CT.07-2 Radioactive Materials Handled: Yes Primary Radioactive Materials Handled: Uranium CT.07-3 Radiological Survey(s): No Site Status: Eliminated from consideration under FUSRAP Also see Documents Related to SPERRY PRODUCTS, INC. CT.07-1 - Sperry Products Letter; VanValkenburg to DeRenzis;

420

Petroleum Supply Annual 2005, Volume 1  

Annual Energy Outlook 2012 (EIA)

Table 2. U.S. Daily Average Supply and Disposition of Crude Oil and Petroleum Products, 2005 (Thousand Barrels per Day) Field Production Refinery and Blender Net Production Imports...

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


421

MODIS Land Products Subsets  

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

Data for Selected Field Sites (n=1147) Data for Selected Field Sites (n=1147) Obtain MODIS data for areas centered on selected field sites or flux towers from around the world. The goal of the MODIS Subsets for Selected Field Sites is to prepare summaries of selected MODIS Land Products for the community to use for validation of models and remote sensing products and to characterize field sites. Search for data: By Site from a Map Server from Google Earth (Install Google Earth) From FTP site (ASCII) Methods Data products were first subsetted from one or more 1200x1200-km MODIS tiles to 25 x 25-km arrays by the MODIS Science Data Support Team (MODAPS). These products were further subsetted (7x7) and reformatted from their native HDF-EOS to ASCII using version 2.2 of the MODIS Reprojection Tool (MRT) in combination with code developed at the ORNL DAAC.

422

Abandoned oil fields in Alaska, California, Colorado, Montana, North Dakota, Utah and Wyoming  

SciTech Connect

This publication lists approximately 250 abandoned oil fields in Alaska, California, Colorado, Montana, North Dakota, Utah and Wyoming that have produced 10,000 or more barrels of oil before abandonment. The following information is provided for each field: county; DOE field code; field name; AAPG geologic province code; discovery data of field; year of last production; discovery well operator; proven acreage; formation thickness; depth of field; gravity of oil production; calendar year; yearly field oil production; yearly field gas production; cumulative oil production; cumulative gas production; number abandoned fields in county; cumulative production of oil from fields; cumulative production of gas from fields. (ATT)

Not Available

1983-04-01T23:59:59.000Z

423

Field of Expertise Biotechnology  

E-Print Network (OSTI)

Field of Expertise Human- & Biotechnology #12;Human- and biotechnology is one of the key possible by research in human- and biotechnology is not just restricted to medicine and pharmacy, but also laboratory to support introduction of medical products to the market. In the field of biotechnology, Graz

424

Amended Record of Decision: Idaho High-Level Waste and Facilities Disposition Final Environmental Impact Statement (DOE/EIS-0287) (11/28/06)  

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

811 Federal Register 811 Federal Register / Vol. 71, No. 228 / Tuesday, November 28, 2006 / Notices Information Relay Service (FIRS) at 1-800-877-8339. [FR Doc. E6-20124 Filed 11-27-06; 8:45 am] BILLING CODE 4000-01-P DEPARTMENT OF ENERGY Amended Record of Decision: Idaho High-Level Waste and Facilities Disposition Final Environmental Impact Statement AGENCY: Department of Energy. ACTION: Amended Record of Decision. SUMMARY: The U.S. Department of Energy (DOE) is amending its Record of Decision (ROD) published December 19, 2005 (70 Federal Register [FR] 75165), pursuant to the Idaho High-Level Waste and Facilities Disposition Final Environmental Impact Statement (Final EIS) (DOE/EIS-0287, September 2002). The Final EIS analyzed two sets of alternatives for accomplishing DOE's

425

EIA - Analysis of Natural Gas Production  

Gasoline and Diesel Fuel Update (EIA)

Production Production 2010 Natural Gas Year-In-Review 2009 This is a special report that provides an overview of the natural gas industry and markets in 2009 with special focus on the first complete set of supply and disposition data for 2009 from the Energy Information Administration. Topics discussed include natural gas end-use consumption trends, offshore and onshore production, imports and exports of pipeline and liquefied natural gas, and above-average storage inventories. Categories: Prices, Production, Consumption, Imports/Exports & Pipelines, Storage (Released, 7/9/2010, Html format) Natural Gas Data Collection and Estimation This presentation to the Oklahoma Independent Petroleum Association gives an overview of the EIA natural gas data collection system, Oklahoma natural gas statistics, recent changes in monthly natural gas production statistics, and the May 2010 short-term natural gas forecast. The presentation focuses on the EIA-914, the "Monthly Natural Gas Production Report," and recent changes to this survey's estimation methodology. Categories: Production (Released, 6/9/2010, ppt format)

426

Supplement to report on boron disposition from fused salts. Final report  

SciTech Connect

The goal of this project was to develop a process to fabricate pure, dense, coherent boron coatings 1 mm thick on graphite or copper substrates. Electrodeposition from molten fluoride salts was the technique chosen for development. The investigation was begun by making a thorough search of the relevant literature and consulting with workers active in the field or related fields. As a result of this search, the technique selected from the literature was a process whereby boron is electrodeposited from a molten equimolal mixture of potassium and lithium fluorides containing dissolved boron trifluoride gas. Initial tests at Bendix consisted of a material evaluation study of 0.02-mm-thick, boron-coated copper specimens. The properties of the boron deposit determined from this material evaluation study were such that an apparatus was designed, constructed, and tested at Bendix Kansas City.

Smith, M.L.

1980-10-01T23:59:59.000Z

427

Fissile Material Disposition Program: Deep Borehole Disposal Facility PEIS data input report for direct disposal. Direct disposal of plutonium metal/plutonium dioxide in compound metal canisters. Version 3.0  

SciTech Connect

The US Department of Energy (DOE) is examining options for disposing of excess weapons-usable nuclear materials [principally plutonium (Pu) and highly enriched uranium (HEU)] in a form or condition that is substantially and inherently more difficult to recover and reuse in weapons production. This report is the data input report for the Programmatic Environmental Impact Statement (PEIS). The PEIS examines the environmental, safety, and health impacts of implementing each disposition alternative on land use, facility operations, and site infrastructure; air quality and noise; water, geology, and soils; biotic, cultural, and paleontological resources; socioeconomics; human health; normal operations and facility accidents; waste management; and transportation. This data report is prepared to assist in estimating the environmental effects associated with the construction and operation of a Deep Borehole Disposal Facility, an alternative currently included in the PEIS. The facility projects under consideration are, not site specific. This report therefore concentrates on environmental, safety, and health impacts at a generic site appropriate for siting a Deep Borehole Disposal Facility.

Wijesinghe, A.M.; Shaffer, R.J.

1996-01-15T23:59:59.000Z

428

EA-1977: Acceptance and Disposition of Used Nuclear Fuel Containing U.S.-Origin Highly Enriched Uranium from the Federal Republic of Germany  

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

This environmental assessment (EA) will evaluate the potential environmental impacts of a DOE proposal to accept used nuclear fuel from the Federal Republic of Germany at DOE’s Savannah River Site (SRS) for processing and disposition. This used nuclear fuel is composed of kernels containing thorium and U.S.-origin highly enriched uranium (HEU) embedded in small graphite spheres that were irradiated in nuclear reactors used for research and development purposes.

429

221-U Facility concrete and reinforcing steel evaluations specification for the canyon disposition initiative (CDI)  

SciTech Connect

This describes a test program to establish the in-situ material properties of the reinforced concrete in Building 221-U for comparison to the original design specifications. Field sampling and laboratory testing of concrete and reinforcing steel structural materials in Building 221-U for design verification will be undertaken. Forty seven samples are to be taken from radiologically clean exterior walls of the canyon. Laboratory testing program includes unconfined compressive strength of concrete cores, tensile strength of reinforcing steel, and petrographic examinations of concrete cores taken from walls below existing grade.

Baxter, J.T.

1998-05-28T23:59:59.000Z

430

Interim salt disposition program macrobatch 6 tank 21H qualification monosodium titanate and cesium mass transfer tests  

SciTech Connect

Savannah River National Laboratory (SRNL) performed experiments on qualification material for use in the Interim Salt Disposition Program (ISDP) Batch 6 processing. This qualification material was a set of six samples from Tank 21H in October 2012. This sample was used as a real waste demonstration of the Actinide Removal Process (ARP) and the Extraction-Scrub-Strip (ESS) tests process. The Tank 21H sample was contacted with a reduced amount (0.2 g/L) of MST and characterized for strontium and actinide removal at 0 and 8 hour time intervals in this salt batch. {sup 237}Np and {sup 243}Am were both observed to be below detection limits in the source material, and so these results are not reported in this report. The plutonium and uranium samples had decontamination factor (DF) values that were on par or slightly better than we expected from Batch 5. The strontium DF values are slightly lower than expected but still in an acceptable range. The Extraction, Scrub, and Strip (ESS) testing demonstrated cesium removal, stripping and scrubbing within the acceptable range. Overall, the testing indicated that cesium removal is comparable to prior batches at MCU.

Washington, A. L. II; Peters, T. B.; Fink, S. D.

2013-02-25T23:59:59.000Z

431

Practice Field Practice Field  

E-Print Network (OSTI)

Courts Soccer Field Swimming pool Bandeen Hall Mountain House # 3 # 2 Golf Course Security Patterson Hall.B. Scott Arena Library Centennial Theater Mc Greer Hall Pollack Hall New Johnson Science Building Dewhurst Dining Hall Champlain Regional College # 4 Mackinnon Hall Residence # 6 Memorial House Retired Faculty

432

Alternative dispositioning methods for HEU spent nuclear fuel at the Savannah River Site  

SciTech Connect

The United States has a strong policy on prevention of the international spread of nuclear weapons. This policy was announced in Presidential Directive PDD-13 and summarized in a White House press release September 27, 1993. Two cornerstones of this policy are: seek to eliminate where possible the accumulation of stockpiles of highly- enriched uranium or plutonium; propose{hor_ellipsis}prohibiting the production of highly-enriched uranium (HEU) or plutonium for nuclear explosives purposes or outside international safeguards. The Department of Energy is currently struggling to devise techniques that safely and efficiently dispose of spent nuclear fuel (SNF) while satisfying national non-proliferation policies. SRS plans and proposals for disposing of their SNF are safe and cost effective, and fully satisfy non-proliferation objectives.

Krupa, J.F.; McKibben, J.M.; Parks, P.B.; DuPont, M.E.

1995-11-01T23:59:59.000Z

433

Strategies for the disposition of high explosives resulting from dismantlement of nuclear weapons  

SciTech Connect

Many thousands of pounds of high quality main-charge explosives will result as surplus from the dismantlement of returns from the US nuclear weapons stockpile. The method most often employed for dealing with this surplus explosive is destruction by open burning. However, open burning as a means of treating excess explosives is losing favor because of environmental concerns associated with such an uncontrolled thermal destruction process. Thus, alternative processes for treatment of excess explosives from weapon dismantlement is discussed. These alternatives include: reformulation, crystalline component recovery, chemical conversion of the crystalline component to higher value products which may have civilian or military applications and, when necessary, treatment as waste in an environmentally benign fashion.

Pruneda, C.; Humphrey, J.

1993-03-01T23:59:59.000Z

434

MODIS Land Product Subsets  

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

Validation > MODIS Land Subsets Validation > MODIS Land Subsets MODIS Land Product Subsets Overview Earth, Western Hemisphere The goal of the MODIS Land Product Subsets project is to provide summaries of selected MODIS Land Products for the community to use for validation of models and remote-sensing products and to characterize field sites. Output files contain pixel values of MODIS land products in text format and in GeoTIFF format. In addition, data visualizations (time series plots and grids showing single composite periods) are available. MODIS Land Product Subsets Resources The following MODIS Land Product Subsets resources are maintained by the ORNL DAAC: MODIS Land Products Offered Background Citation Policy Methods and formats MODIS Sinusoidal Grid - Google Earth KMZ Classroom Exercises

435

A Comprehensive Solution for Managing TRU and LLW From Generation to Final Disposition - 13205  

SciTech Connect

A LANL multi-disciplinary team faced the challenge of building and delivering a waste information system capable of managing radioactive, hazardous, and industrial waste from cradle to grave. The result is the Waste Compliance and Tracking System (WCATS) a flexible, adaptive system that has allowed LANL to consolidate its legacy applications into one system, and leverage the advantages of managing all waste types within a single scalable enterprise application. Key functionality required for robust waste operations, include: waste characterization, waste identification, transportation, inventory management, waste processing, and disposal. In order to maintain data quality, field operations such as waste identification, surveillance checklists, wall-to-wall inventory assessments, waste transfers, shipment pickup and receipt, and simple consolidation operations are captured by the operator or technician using mobile computers. Work flow is managed via end-user defined work paths, to ensure that unit operations are performed in the correct order. Regulatory compliance reports and algorithms are provided to support typical U.S. EPA, DOT, NRC, and DOE requirements, including the EPA hazardous waste manifest, NRC LLW manifest, DOE nuclear material at risk, RCRA TSDF inventory rules, and so forth. The WCATS application has allowed LANL to migrate and consolidate its disparate legacy applications. The design and implementation is generalized so that facility owners can customize the user interface, setup facilities and unit operations (i.e., treatment, storage, disposal, characterization, and administrative), define inventory compliance rules, and establish custom work flow requirements. (authors)

Tozer, Justin C.; Sanchez, Edwina G.; Dorries, Alison M. [Los Alamos National Laboratory, Los Alamos, NM 87544 (United States)] [Los Alamos National Laboratory, Los Alamos, NM 87544 (United States)

2013-07-01T23:59:59.000Z

436

MODIS Land Products Subsets  

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

Introduction Introduction The goal of the MODIS Land Product Subsets project is to provide summaries of selected MODIS Land Products for the community to use for validation of models and remote-sensing products, and to characterize field sites. The MODIS Land Product Subsets are derived from MODIS products that were generated with Collection 4 or later algorithms. Please be advised that these products are subject to continual review and revision. The MODIS land product subsets are provided in ASCII and GeoTIFF format. The subsets are stored as individual text(ASCII) files, each file represents one field site and one MODIS product.The ASCII data covers 7x7 km of the field site. These ASCII files contain comma-delimited rows of parameter values (image bands) for each pixel in the selected area. Each row in the file will contain data from one 8-day, 16-day, or annual period (depending on the temporal frequency of the data product represented).

437

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

SciTech Connect

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

Blink, J A

2011-03-23T23:59:59.000Z

438

SRS vitrification studies in support of the U.S. program for disposition of excess plutonium  

SciTech Connect

Many thousands of nuclear weapons are being retired in the U.S. and Russian as a result of nuclear disarmament activities. These efforts are expected to produce a surplus of about 50 MT of weapons grade plutonium (Pu) in each country. In addition to this inventory, the U.S. Department of Energy (DOE) has more than 20 MT of Pu scrap, residue, etc., and Russian is also believed to have at least as much of this type of material. The entire surplus Pu inventories in the U.S. and Russian present a clear and immediate danger to national and international security. It is important that a solution be found to secure and manage this material effectively and that such an effort be implemented as quickly as possible. One option under consideration is vitrification of Pu into a safe, durable, accountable and proliferation-resistant form. As a result of decades to experience within the DOE community involving vitrification of a variety of hazardous and radioactive wastes, this existing technology can now be expanded to include mobilization of large amounts of Pu. This technology can then be implemented rapidly using the many existing resources currently available. An overall strategy to vitrify many different types of Pu will be already developed throughout the waste management community can be used in a staged Pu vitrification effort. This approach uses the flexible vitrification technology already available and can even be made portable so that it may be brought to the source and ultimately, used to produce a consistent and common borosilicate glass composition for the vitrified Pu. The final composition of this product can be made similar to nationally and internationally accepted HLW glasses.

Wicks, G.G.; McKibben, J.M.; Plodinec, M.J.; Ramsey, W.G.

1995-09-01T23:59:59.000Z

439

DOE/EIS-0287-SA-01: Supplement Analysis for the Idaho High-Level Waste and Facilities Disposition Final Environmental Impact Statement (June 2005)  

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

7 7 -SA-Ol SUPPLEMENT ANALYSIS For The Idaho High-Level Waste and Facilities Disposition Final Environmental Impact Statement June 2005 United States Department of Energy Idaho Operations Office 1.0 2.0 3.0 4.0 5.0 6.0 DOEÆIS-0287 -SA-O 1 TABLE OF CONTENTS Introduction......................................................................................................................... 4 Background......................................................................................................................... 4 Areas of Review.................................................................................................................. 6 3.1 3.2 3.3 3.4 Proposed Waste Treatment Technology.......... .......................................................

440

Identification and evaluation of alternatives for the disposition of fluoride fuel and flush salts from the molten salt reactor experiment at Oak Ridge National Laboratory, Oak Ridge, Tennessee  

SciTech Connect

This document presents an initial identification and evaluation of the alternatives for disposition of the fluoride fuel and flush salts stored in the drain tanks at the Molten Salt Reactor Experiment (MSRE) at Oak Ridge National Laboratory (ORNL). It will serve as a resource for the U.S. Department of Energy contractor preparing the feasibility study for this activity under the Comprehensive Environmental Response, Compensation and Liability Act (CERCLA). This document will also facilitate further discussion on the range of credible alternatives, and the relative merits of alternatives, throughout the time that a final alternative is selected under the CERCLA process.

NONE

1996-08-15T23:59:59.000Z

Note: This page contains sample records for the topic "disposition field production" 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

Product Efficiency Cases  

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

product-efficiency-cases Office of Hearings and product-efficiency-cases Office of Hearings and Appeals 1000 Independence Ave., SW Washington, DC, 20585 202-287-1566 en EXC-13-0004 - In the Matter of Liebherr Canada Ltd. http://energy.gov/oha/downloads/exc-13-0004-matter-liebherr-canada-ltd EXC-13-0004 - In the Matter of Liebherr Canada Ltd.

442

DOE - Office of Legacy Management -- Floyd Bennett Field - NY 0-11  

Office of Legacy Management (LM)

Floyd Bennett Field - NY 0-11 Floyd Bennett Field - NY 0-11 FUSRAP Considered Sites Site: Floyd Bennett Field (NY.0-11 ) Eliminated from consideration under FUSRAP Designated Name: Not Designated Alternate Name: Naval Air Station NY.0-11-1 Location: Buildings 67 and 69 , Brooklyn , New York NY.0-11-1 Evaluation Year: 1987 NY.0-11-1 Site Operations: The Air station was considered by the AEC but was not used. NY.0-11-1 Site Disposition: Eliminated - No involvement with MED/AEC operations NY.0-11-1 Radioactive Materials Handled: No Primary Radioactive Materials Handled: None Radiological Survey(s): No Site Status: Eliminated from consideration under FUSRAP Also see Documents Related to Floyd Bennett Field NY.0-11-1 - Memorandum/Checklist; Wallo to the File; Subject: Elimination of Floyd Bennett Field; December 7, 1987

443

DOE/EA-1651: FINDING OF NO SIGNIFICANT IMPACT Uranium-233 Material Downblending and Disposition Project at the Oak Ridge National Laboratory, Oak Ridge, Tennessee (01/13/10)  

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

URANIUM-233 MATERIAL DOWNBLENDING AND DISPOSITION PROJECT URANIUM-233 MATERIAL DOWNBLENDING AND DISPOSITION PROJECT AT THE OAK RIDGE NATIONAL LABORATORY, OAK RIDGE, TENNESSEE AGENCY: U.S. Department of Energy (DOE) ACTION: Finding of No Significant Impact (FONSI) SUMMARY: DOE has completed the Final Environmental Assessment for U-233 Material Downblending and Disposition Project at the Oak Ridge National Laboratory [DOE/EA-1651]. This environmental assessment (EA) evaluates the impacts of planned activities to modify selected Oak Ridge National Laboratory (ORNL) facilities; process the ORNL inventory of uranium-233 (U-233); and transport the processed material to a long-term disposal facility. Small quantities of similar material currently stored at other DOE sites may also be included in this initiative. The

444

Fissile Material Disposition Program: Deep borehole disposal Facility PEIS date input report for immobilized disposal. Immobilized disposal of plutonium in coated ceramic pellets in grout with canisters. Version 3.0  

SciTech Connect

Following President Clinton`s Non-Proliferation Initiative, launched in September, 1993, an Interagency Working Group (IWG) was established to conduct a comprehensive review of the options for the disposition of weapons-usable fissile materials from nuclear weapons dismantlement activities in the United States and the former Soviet Union. The IWG review process will consider technical, nonproliferation, environmental budgetary, and economic considerations in the disposal of plutonium. The IWG is co-chaired by the White House Office of Science and Technology Policy and the National Security Council. The Department of Energy (DOE) is directly responsible for the management, storage, and disposition of all weapons-usable fissile material. The Department of Energy has been directed to prepare a comprehensive review of long-term options for Surplus Fissile Material (SFM) disposition, taking into account technical, nonproliferation, environmental, budgetary, and economic considerations.

Wijesinghe, A.M.; Shaffer, R.J.

1996-01-15T23:59:59.000Z

445

Department of Energy National Nuclear Security Administration Finding of No Significant Impact for the Proposed Disposition of the Omega West Facility at Los Alamos National Laboratory, Los Alamos, New Mexico  

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

Finding of No Significant Impact for the Proposed Disposition of the Omega West Facility at Los Alamos National Laboratory, Los Alamos, New Mexico U. S. Department of Energy National Nuclear Security Administration Office of Los Alamos Site Operations 528 35th Street Los Alamos, NM 87544 DEPARTMENT OF ENERGY, NATIONAL NUCLEAR SECUIRTY ADMINISTRATION FINDING OF NO SIGNIFICANT IMPACT Proposed Disposition of the Omega West Facility at Los Alamos National Laboratory FINAL ENVIRONMENTAL ASSESSMENT: The Environmental Assessment (EA) for the Proposed Disposition of the Omega West Facility at Los Alamos National Laboratory [DOE/EA- 74 IO) (attached) provides sufficient evidence and analysis to determine that a Finding Of No Significant Impact is appropriate for the Proposed Action (Complete

446

The Disposition of Cocaine and Opiate Analytes in Hair and Fingernails of Humans Following Cocaine and Codeine Administration  

Science Journals Connector (OSTI)

......ofhair specimens to identify long-term drug exposure has made...separate glass vessels for storage at -30~ (storage length...lipids, inorganic salts, waste products, and drug to...allowing nu- trients, waste products, and exogenous......

Jeri D. Ropero-Miller; Bruce A. Goldberger; Edward J. Cone; Robert E. Joseph; Jr.

2000-10-01T23:59:59.000Z

447

EIS-0402: Remediation of Area IV of the Santa Susana Field Laboratory, California  

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

DOE is preparing an EIS for cleanup of Area IV, including the Energy Technology Engineering Center (ETEC), as well as the Northern Buffer Zone of the Santa Susana Field Laboratory (SSFL) in eastern Ventura County, California, approximately 29 miles north of downtown Los Angeles. (DOE’s operations bordered the Northern Buffer Zone. DOE is responsible for soil cleanup in Area IV and the Northern Buffer Zone.) In the EIS, DOE will evaluate reasonable alternatives for disposition of radiological facilities and support buildings, remediation of contaminated soil and groundwater, and disposal of all resulting waste at permitted facilities.

448

National High Magnetic Field Laboratory - Science Starts Here...  

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

a better and much more productive scientist. I had the opportunity to learn unique high magnetic field experimental techniques from the top researchers in the field, in a...

449

Facility Disposition Projects  

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

Score Maturity Value Target Score Maturity Value Target Score A1 Cost Estimate H 7.5 1 7.5 5 37.5 5 37.5 A2 Cost Risk/Contingency Analysis P 3.0 1 3.0 5 15.0 5 15.0 A3 Funding Requirements/Profile H 7.5 1 7.5 4 30.0 5 37.5 A4 Independent Cost Estimate/Schedule Review P 3.0 N/A 0.0 5 15.0 5 15.0 A5 Life Cycle Cost P 3.0 1 3.0 4 12.0 5 15.0 A6 Forecast of Cost at Completion P 3.0 N/A 0.0 3 9.0 5 15.0 A7 Cost Estimate for Next Phase Work Scope P 3.0 5 15.0 5 15.0 5 15.0 Subtotal Cost 36.0 133.5 150.0 B1 Project Schedule H 7.5 1 7.5 4 30.0 5 37.5 B2 Major Milestones P 3.0 1 3.0 5 15.0 5 15.0 B3 Resource Loading P 3.0 1 3.0 4 12.0 5 15.0 B4 Critical Path Management H 7.5 1 7.5 4 30.0 5 37.5 B5 Schedule Risk/Contingency Analysis P 3.0 1 3.0 5 15.0 5 15.0 B6 Forecast of Schedule Completion P 3.0 N/A 0.0 3 9.0 5 15.0 B7 Schedule for Next Phase Work Scope P 3.0 5 15.0 5 15.0 5 15.0 Subtotal Schedule

450

EIS-0402: Santa Susana Field Laboratory Area IV, California | Department of  

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

2: Santa Susana Field Laboratory Area IV, California 2: Santa Susana Field Laboratory Area IV, California EIS-0402: Santa Susana Field Laboratory Area IV, California Summary This EIS evaluates the environmental impacts of remediation of Area IV of the Santa Susana Field Laboratory (SSFL Area IV). SSFL Area IV, occupying approximately 290 acres of the total 2,852-acre SSFL site is located in the hills between Chatsworth and Simi Valley, CA, and was developed as a remote site to test rocket engines and conduct nuclear research. This EIS will evaluate alternatives for disposition of radiological facilities and support buildings, remediation of the affected environment, and disposal of all resulting waste at existing, approved sites. Public Comment Opportunities No public comment opportunities available at this time.

451

DOE - Office of Legacy Management -- Burris Park Field Station - CA 10  

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

Burris Park Field Station - CA 10 Burris Park Field Station - CA 10 FUSRAP Considered Sites Site: Burris Park Field Station (CA.10 ) Eliminated from consideration under FUSRAP Designated Name: Not Designated Alternate Name: None Location: Kingsburg , California CA.10-1 Evaluation Year: 1987 CA.10-2 Site Operations: Site owned and operated by Univ. o