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1

Health Risks Associated with Conversion of Depleted UF6  

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

2

Depleted UF6 Conversion facility EIS Topics  

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

3

Production and Handling Slide 35: UF6 Cylinder Data Summary  

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UF6 Cylinder Data Summary UF6 Cylinder Data Summary Skip Presentation Navigation First Slide Previous Slide Next Slide Last Presentation Table of Contents UF6 Cylinder Data Summary Cylinder Model Nominal Diam. (in.) Material of Construction Minimum Volume Approximate Tare Weight Without Valve Protector Maximum Enrichment Uranium-235 Shipping Limit Maximum, a UF6 ft3 liters lb kg Weight % lb kg 1S 1.5 Nickel 0.0053 0.15 1.75 0.79 100.00 1.0 0.45 2S .5 Nickel 0.026 0.74 4.2 1.91 100.00 4.9 2.22 5A 5 Monel 0.284 8.04 55 25 100.00 55 24.95 5B 5 Nickel 0.284 8.04 55 25 100.00 55 24.95 8A 8 Monel 1.319 37.35 120 54 12.5 255 115.67 12A 12 Nickel 2.38 67.4 185 84 5.0 460 208.7 12B 12 Monel 2.38 67.4 185 84 5.0 460 208.7 308c 30 Steel 26.0 736.0 1,400 635 5.0b 5,020 2,277 48A 48 Steel 108.9 3,.84 4,500 2,041 4.5b 21,030 9,539 48Xd 48 Steel 108.9 3,084 4,500 2,041 4.5b,g 21,030 9,539 48F 48 Steel

4

Environmental Risks Associated with Conversion of Depleted UF6  

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

5

Onsite Gaseous Centrifuge Enrichment Plant UF6 Cylinder Destructive Analysis  

SciTech Connect

The IAEA safeguards approach for gaseous centrifuge enrichment plants (GCEPs) includes measurements of gross, partial, and bias defects in a statistical sampling plan. These safeguard methods consist principally of mass and enrichment nondestructive assay (NDA) verification. Destructive assay (DA) samples are collected from a limited number of cylinders for high precision offsite mass spectrometer analysis. DA is typically used to quantify bias defects in the GCEP material balance. Under current safeguards measures, the operator collects a DA sample from a sample tap following homogenization. The sample is collected in a small UF6 sample bottle, then sealed and shipped under IAEA chain of custody to an offsite analytical laboratory. Current practice is expensive and resource intensive. We propose a new and novel approach for performing onsite gaseous UF6 DA analysis that provides rapid and accurate assessment of enrichment bias defects. DA samples are collected using a custom sampling device attached to a conventional sample tap. A few micrograms of gaseous UF6 is chemically adsorbed onto a sampling coupon in a matter of minutes. The collected DA sample is then analyzed onsite using Laser Ablation Absorption Ratio Spectrometry-Destructive Assay (LAARS-DA). DA results are determined in a matter of minutes at sufficient accuracy to support reliable bias defect conclusions, while greatly reducing DA sample volume, analysis time, and cost.

Anheier, Norman C.; Cannon, Bret D.; Qiao, Hong (Amy) [Amy; Carter, Jennifer C.; McNamara, Bruce K.; O'Hara, Matthew J.; Phillips, Jon R.; Curtis, Michael M.

2012-07-17T23:59:59.000Z

6

Conceptual Ideas for New Nondestructive UF6 Cylinder Assay Techniques  

SciTech Connect

Nondestructive assay (NDA) measurements of uranium cylinders play an important role in helping the International Atomic Energy Agency (IAEA) safeguard uranium enrichment plants. Traditionally, these measurements have consisted of a scale or load cell to determine the mass of UF{sub 6} in the cylinder combined with a gamma-ray measurement of the 186 keV peak from {sup 235}U to determine enrichment. More recently, Los Alamos National Laboratory (LANL) and Pacific Northwest National Laboratory (PNNL) have developed systems that exploit the passive neutron signal from UF{sub 6} to determine uranium mass and/or enrichment. These include the Uranium Cylinder Assay System (UCAS), the Passive Neutron Enrichment Meter (PNEM), and the Hybrid Enrichment Verification Array (HEVA). The purpose of this report is to provide the IAEA with new ideas on technologies that may or may not be under active development but could be useful for UF{sub 6} cylinder assay. To begin, we have included two feasibility studies of active interrogation techniques. There is a long history of active interrogation in the field of nuclear safeguards, especially for uranium assay. Both of the active techniques provide a direct measure of {sup 235}U content. The first is an active neutron method based on the existing PNEM design that uses a correlated {sup 252}Cf interrogation source. This technique shows great promise for UF{sub 6} cylinder assay and is based on advanced technology that could be implemented in the field in the near term. The second active technique is nuclear resonance fluorescence (NRF). In the NRF technique, a bremsstrahlung photon beam could be used to illuminate the cylinder, and high-resolution gamma-ray detectors would detect the characteristic de-excitation photons. The results of the feasibility study show that under certain measurement geometries, NRF is impractical for UF6 cylinder assay, but the 'grazing transmission' and 'secant transmission' geometries have more potential for this application and should be assessed quantitatively. The next set of techniques leverage scintillator detectors that are sensitive to both neutron and gamma radiation. The first is the BC-523A capture-gated organic liquid scintillator. The detector response from several different neutron energies has been characterized and is included in the study. The BC-523A has not yet been tested with UF{sub 6} cylinders, but the application appears to be well suited for this technology. The second detector type is a relatively new inorganic scintillator called CLYC. CLYC provides a complementary detection approach to the HEVA and PNEM systems that could be used to determine uranium enrichment in UF{sub 6} cylinders. In this section, the conceptual idea for an integrated CLYC-HEVA/PNEM system is explored that could yield more precision and robustness against systemic uncertainties than any one of the systems by itself. This is followed by a feasibility study on using alpha-particle-induced reaction gamma-rays as a way to estimate {sup 234}U abundance in UF{sub 6}. Until now, there has been no readily available estimate of the strength of these reaction gamma-rays. Thick target yields of the chief reaction gammas are computed and show that they are too weak for practical safeguards applications. In special circumstances where long count times are permissible, the 1,275 keV F({alpha},x{gamma}) is observable. Its strength could help verify an operator declaration provided other knowledge is available (especially the age). The other F({alpha},x{gamma}) lines are concealed by the dominant uranium line spectrum and associated continuum. Finally, the last section provides several ideas for electromagnetic and acoustic nondestructive evaluation (NDE) techniques. These can be used to measure cylinder wall thickness, which is a source of systematic uncertainty for gamma-ray-based NDA techniques; characterize the UF{sub 6} filling profile inside the cylinder, which is a source of systematic uncertainty for neutron-based NDA techniques; locate hidden objects inside the cylinder; a

Miller, Karen A. [Los Alamos National Laboratory

2012-05-02T23:59:59.000Z

7

Hybrid Enrichment Assay Methods for a UF6 Cylinder Verification Station: FY10 Progress Report  

SciTech Connect

Pacific Northwest National Laboratory (PNNL) is developing the concept of an automated UF6 cylinder verification station that would be located at key measurement points to positively identify each cylinder, measure its mass and enrichment, store the collected data in a secure database, and maintain continuity of knowledge on measured cylinders until the arrival of International Atomic Energy Agency (IAEA) inspectors. At the center of this unattended system is a hybrid enrichment assay technique that combines the traditional enrichment-meter method (based on the 186 keV peak from 235U) with non-traditional neutron-induced high-energy gamma-ray signatures (spawned primarily by 234U alpha emissions and 19F(alpha, neutron) reactions). Previous work by PNNL provided proof-of-principle for the non-traditional signatures to support accurate, full-volume interrogation of the cylinder enrichment, thereby reducing the systematic uncertainties in enrichment assay due to UF6 heterogeneity and providing greater sensitivity to material substitution scenarios. The work described here builds on that preliminary evaluation of the non-traditional signatures, but focuses on a prototype field system utilizing NaI(Tl) and LaBr3(Ce) spectrometers, and enrichment analysis algorithms that integrate the traditional and non-traditional signatures. Results for the assay of Type-30B cylinders ranging from 0.2 to 4.95 wt% 235U, at an AREVA fuel fabrication plant in Richland, WA, are described for the following enrichment analysis methods: 1) traditional enrichment meter signature (186 keV peak) as calculated using a square-wave convolute (SWC) algorithm; 2) non-traditional high-energy gamma-ray signature that provides neutron detection without neutron detectors and 3) hybrid algorithm that merges the traditional and non-traditional signatures. Uncertainties for each method, relative to the declared enrichment for each cylinder, are calculated and compared to the uncertainties from an attended HPGe verification station at AREVA, and the IAEA’s uncertainty target values for feed, tail and product cylinders. A summary of the major findings from the field measurements and subsequent analysis follows: • Traditional enrichment-meter assay using specially collimated NaI spectrometers and a Square-Wave-Convolute algorithm can achieve uncertainties comparable to HPGe and LaBr for product, natural and depleted cylinders. • Non-traditional signatures measured using NaI spectrometers enable interrogation of the entire cylinder volume and accurate measurement of absolute 235U mass in product, natural and depleted cylinders. • A hybrid enrichment assay method can achieve lower uncertainties than either the traditional or non-traditional methods acting independently because there is a low degree of correlation in the systematic errors of the two individual methods (wall thickness variation and 234U/235U variation, respectively). This work has indicated that the hybrid NDA method has the potential to serve as the foundation for an unattended cylinder verification station. When compared to today’s handheld cylinder-verification approach, such a station would have the following advantages: 1) improved enrichment assay accuracy for product, tail and feed cylinders; 2) full-volume assay of absolute 235U mass; 3) assay of minor isotopes (234U and 232U) important to verification of feedstock origin; single instrumentation design for both Type 30B and Type 48 cylinders; and 4) substantial reduction in the inspector manpower associated with cylinder verification.

Smith, Leon E.; Jordan, David V.; Orton, Christopher R.; Misner, Alex C.; Mace, Emily K.

2010-08-01T23:59:59.000Z

8

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

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

9

Automated UF6 Cylinder Enrichment Assay: Status of the Hybrid Enrichment Verification Array (HEVA) Project: POTAS Phase II  

SciTech Connect

Pacific Northwest National Laboratory (PNNL) intends to automate the UF6 cylinder nondestructive assay (NDA) verification currently performed by the International Atomic Energy Agency (IAEA) at enrichment plants. PNNL is proposing the installation of a portal monitor at a key measurement point to positively identify each cylinder, measure its mass and enrichment, store the data along with operator inputs in a secure database, and maintain continuity of knowledge on measured cylinders until inspector arrival. This report summarizes the status of the research and development of an enrichment assay methodology supporting the cylinder verification concept. The enrichment assay approach exploits a hybrid of two passively-detected ionizing-radiation signatures: the traditional enrichment meter signature (186-keV photon peak area) and a non-traditional signature, manifested in the high-energy (3 to 8 MeV) gamma-ray continuum, generated by neutron emission from UF6. PNNL has designed, fabricated, and field-tested several prototype assay sensor packages in an effort to demonstrate proof-of-principle for the hybrid assay approach, quantify the expected assay precision for various categories of cylinder contents, and assess the potential for unsupervised deployment of the technology in a portal-monitor form factor. We refer to recent sensor-package prototypes as the Hybrid Enrichment Verification Array (HEVA). The report provides an overview of the assay signatures and summarizes the results of several HEVA field measurement campaigns on populations of Type 30B UF6 cylinders containing low-enriched uranium (LEU), natural uranium (NU), and depleted uranium (DU). Approaches to performance optimization of the assay technique via radiation transport modeling are briefly described, as are spectroscopic and data-analysis algorithms.

Jordan, David V.; Orton, Christopher R.; Mace, Emily K.; McDonald, Benjamin S.; Kulisek, Jonathan A.; Smith, Leon E.

2012-06-01T23:59:59.000Z

10

Supplemental Systems for Unattended UF6 Cylinder Monitoring  

SciTech Connect

Cylinder assay and mass measurements, the mainstay of enrichment plant verification efforts have historically been performed by International Atomic Energy Agency (IAEA) inspectors using portable equipment. For the sake of efficiency, accuracy, and timeliness, such equipment is being supplanted by unattended measurement stations. Ancillary systems must be employed with such stations to ensure that measured parameters are properly recorded, cylinders are positively identified, operations occur according to procedure, and no tampering takes place in the inspectors’ absence. Depending on the facility, it may prove feasible to track cylinders from the measurement vicinity to their storage locations using surveillance. This paper will provide a cursory description of the various subsystems associated with Pacific Northwest National Laboratory’s Integrated Cylinder Verification Station and how inattention to the requirements of such systems could seriously diminish the capability of the integrated whole.

Curtis, Michael M.

2010-08-11T23:59:59.000Z

11

Automated Nondestructive Assay of UF6 Cylinders: Detector Characterization and Initial Measurements  

SciTech Connect

International Atomic Energy Agency (IAEA) inspectors currently perform periodic inspections at uranium enrichment plants to verify UF6 cylinder enrichment declarations. Measurements are typically performed with handheld high-resolution sensors on a sampling of cylinders assumed to be representative of the facility's entire cylinder inventory. These measurements are time-consuming and assay only a small fraction of the total cylinder volume. An automated nondestructive assay system capable of providing enrichment measurements over the full volume of the cylinder could improve upon current verification practices in terms of manpower and assay accuracy. Pacific Northwest National Laboratory is developing an Integrated Cylinder Verification System (ICVS) intended for this purpose and has developed a field prototype of the nondestructive assay (NDA) components of an ICVS. The nondestructive assay methods would combine the 'traditional' enrichment-meter signature (i.e. 186-keV emission from 235U) as well as 'non-traditional' high-energy photon signatures derived from neutrons produced primarily by 19F({alpha},n) reactions. This paper describes the design, calibration and characterization of the NaI(Tl) and LaBr3(Ce) spectrometers utilized in the field prototype. An overview of a recent field measurement campaign is then provided, supported by example gamma-ray pulse-height spectra collected on cylinders of known enrichment.

Mace, Emily K.; Smith, Leon E.

2011-10-01T23:59:59.000Z

12

Technology Assessment for Proof-of-Concept UF6 Cylinder Unique Identification Task 3.1.2 Report – Survey and Assessment of Technologies  

SciTech Connect

The National Nuclear Security Administration (NNSA) Office of Nonproliferation and International Security’s (NA-24) Next Generation Safeguards Initiative (NGSI) and the nuclear industry have begun to develop approaches to identify and monitor uranium hexafluoride (UF6) cylinders. The NA-24 interest in a global monitoring system for UF6 cylinders relates to its interest in supporting the International Atomic Energy Agency (IAEA) in deterring and detecting diversion of UF6 (e.g., loss of cylinder in transit) and undeclared excess production at conversion and enrichment facilities. The industry interest in a global monitoring system for UF6 cylinders relates to the improvements in operational efficiencies that such a system would provide. This task is part of an effort to survey and assess technologies for a UF6 cylinder to identify candidate technologies for a proof-of-concept demonstration and evaluation for the Cylinder Identification System (CIS).

Wylie, Joann; Hockert, John

2014-04-24T23:59:59.000Z

13

Portsmouth DUF6 Conversion Final EIS - Appendix D: Environmental Synopsis for the Depleted UF6 Conversion Project  

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Portsmouth DUF Portsmouth DUF 6 Conversion Final EIS APPENDIX D: ENVIRONMENTAL SYNOPSIS FOR THE DEPLETED UF 6 CONVERSION PROJECT Environmental Synopsis D-2 Portsmouth DUF 6 Conversion Final EIS ENVIRONMENTAL SYNOPSIS FOR THE DEPLETED UF 6 CONVERSION PROJECT (Solicitation No. DE-RP05-01OR22717) October 2002 Environmental Assessment Division Argonne National Laboratory Argonne, Illinois Prepared for Office of Site Closure - Oak Ridge Office (EM-32) Office of Environmental Management U.S. Department of Energy Washington, D.C. October 2002 iii CONTENTS 1 INTRODUCTION........................................................................................................... 1 2 BACKGROUND.............................................................................................................

14

Paducah DUF6 Conversion Final EIS - Appendix D: Environmental Synopsis for the Depleted UF6 Conversion Project  

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Paducah DUF Paducah DUF 6 Conversion Final EIS APPENDIX D: ENVIRONMENTAL SYNOPSIS FOR THE DEPLETED UF 6 CONVERSION PROJECT Environmental Synopsis D-2 Paducah DUF 6 Conversion Final EIS ENVIRONMENTAL SYNOPSIS FOR THE DEPLETED UF 6 CONVERSION PROJECT (Solicitation No. DE-RP05-01OR22717) October 2002 Environmental Assessment Division Argonne National Laboratory Argonne, Illinois Prepared for Office of Site Closure - Oak Ridge Office (EM-32) Office of Environmental Management U.S. Department of Energy Washington, D.C. October 2002 iii CONTENTS 1 INTRODUCTION........................................................................................................... 1 2 BACKGROUND............................................................................................................. 3 3

15

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

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

16

RESULTS FROM A DEMONSTRATION OF RF-BASED UF6 CYLINDER ACCOUNTING AND TRACKING SYSTEM INSTALLED AT A USEC FACILITY  

SciTech Connect

Approved industry-standard cylinders are used globally for storing and transporting uranium hexafluoride (UF{sub 6}) at uranium enrichment plants and processing facilities. To verify that no diversion or undeclared production of nuclear material involving UF{sub 6} cylinders at the facility has occurred, the International Atomic Energy Agency (IAEA) conducts periodic, labor-intensive physical inspections to validate facility records, cylinder identities, and cylinder weights. A reliable cylinder monitoring system that would improve overall inspector effectiveness would be a significant improvement to the current international safeguards inspection regime. Such a system could include real-time unattended monitoring of cylinder movements, situation-specific rules-based event detection algorithms, and the capability to integrate with other types of safeguards technologies. This type of system could provide timely detection of abnormal operational activities that may be used to ensure more appropriate and efficient responses by the IAEA. A system of this type can reduce the reliance on paper records and have the additional benefit of facilitating domestic safeguards at the facilities at which it is installed. A radio-frequency (RF)-based system designed to track uranium hexafluoride (UF{sub 6}) cylinders during processing operations was designed, assembled, and tested at the United States Enrichment Corporation (USEC) facility in Portsmouth, Ohio, to determine the operational feasibility and durability of RF technology. The overall objective of the effort was to validate the robustness of RF technology for potential use as a future international safeguards tool for tracking UF6 cylinders at uranium-processing facilities. The results to date indicate that RF tags represent a feasible technique for tracking UF{sub 6} cylinders in operating facilities. Additional work will be needed to improve the operational robustness of the tags for repeated autoclave processing and to add tamper-indicating and data authentication features to some of the pertinent system components. Future efforts will focus on these needs along with implementing protocols relevant to IAEA safeguards. The work detailed in this report demonstrates the feasibility of constructing RF devices that can survive the operational rigors associated with the transportation, storage, and processing of UF6 cylinders. The system software specially designed for this project is called Cylinder Accounting and Tracking System (CATS). This report details the elements of the CATS rules-based architecture and its use in safeguards-monitoring and asset-tracking applications. Information is also provided on improvements needed to make the technology ready, as well as options for improving the safeguards aspects of the technology. The report also includes feedback from personnel involved in the testing, as well as individuals who could utilize an RF-based system in supporting the performance of their work. The system software was set up to support a Mailbox declaration, where a declaration can be made either before or after cylinder movements take place. When the declaration is made before cylinders move, the operators must enter this information into CATS. If the IAEA then shows up unexpectedly at the facility, they can see how closely the operational condition matches the declaration. If the declaration is made after the cylinders move, this provides greater operational flexibility when schedules are interrupted or are changed, by allowing operators to declare what moves have been completed. The IAEA can then compare where cylinders are with where CATS or the system says they are located. The ability of CATS to automatically generate Mailbox declarations is seen by the authors as a desirable feature. The Mailbox approach is accepted by the IAEA but has not been widely implemented (and never in enrichment facilities). During the course of this project, we have incorporated alternative methods for implementation.

Pickett, Chris A [ORNL; Kovacic, Donald N [ORNL; Morgan, Jim [Innovative Solutions; Younkin, James R [ORNL; Carrick, Bernie [USEC; Ken, Whittle [USEC; Johns, R E [Pacific Northwest National Laboratory (PNNL)

2008-09-01T23:59:59.000Z

17

Next Generation Safeguards Initiative: Overview and Policy Context of UF6 Cylinder Tracking Program  

SciTech Connect

Thousands of cylinders containing uranium hexafluoride (UF{sub 6}) move around the world from conversion plants to enrichment plants to fuel fabrication plants, and their contents could be very useful to a country intent on diverting uranium for clandestine use. Each of these large cylinders can contain close to a significant quantity of natural uranium (48Y cylinder) or low-enriched uranium (LEU) (30B cylinder) defined as 75 kg {sup 235}U which can be further clandestinely enriched to produce 1.5 to 2 significant quantities of high enriched uranium (HEU) within weeks or months depending on the scale of the clandestine facility. The National Nuclear Security Administration (NNSA) Next Generation Safeguards Initiative (NGSI) kicked off a 5-year plan in April 2011 to investigate the concept of a unique identification system for UF{sub 6} cylinders and potentially to develop a cylinder tracking system that could be used by facility operators and the International Atomic Energy Agency (IAEA). The goal is to design an integrated solution beneficial to both industry and inspectorates that would improve cylinder operations at the facilities and provide enhanced capabilities to deter and detect both diversion of low-enriched uranium and undeclared enriched uranium production. The 5-year plan consists of six separate incremental tasks: (1) define the problem and establish the requirements for a unique identification (UID) and monitoring system; (2) develop a concept of operations for the identification and monitoring system; (3) determine cylinder monitoring devices and technology; (4) develop a registry database to support proof-of-concept demonstration; (5) integrate that system for the demonstration; and (6) demonstrate proof-of-concept. Throughout NNSA's performance of the tasks outlined in this program, the multi-laboratory team emphasizes that extensive engagement with industry stakeholders, regulatory authorities and inspectorates is essential to its success.

Boyer, Brian D [Los Alamos National Laboratory; Whitaker, J. Michael [ORNL; White-Horton, Jessica L. [ORNL; Durbin, Karyn R. [NNSA

2012-07-12T23:59:59.000Z

18

Status Report on the Passive Neutron Enrichment Meter (PNEM) for UF6 Cylinder Assay  

SciTech Connect

The Passive Neutron Enrichment Meter (PNEM) is a nondestructive assay (NDA) system being developed at Los Alamos National Laboratory (LANL). It was designed to determine {sup 235}U mass and enrichment of uranium hexafluoride (UF{sub 6}) in product, feed, and tails cylinders (i.e., 30B and 48Y cylinders). These cylinders are found in the nuclear fuel cycle at uranium conversion, enrichment, and fuel fabrication facilities. The PNEM is a {sup 3}He-based neutron detection system that consists of two briefcase-sized detector pods. A photograph of the system during characterization at LANL is shown in Fig. 1. Several signatures are currently being studied to determine the most effective measurement and data reduction technique for unfolding {sup 235}U mass and enrichment. The system collects total neutron and coincidence data for both bare and cadmium-covered detector pods. The measurement concept grew out of the success of the Uranium Cylinder Assay System (UCAS), which is an operator system at Rokkasho Enrichment Plant (REP) that uses total neutron counting to determine {sup 235}U mass in UF{sub 6} cylinders. The PNEM system was designed with higher efficiency than the UCAS in order to add coincidence counting functionality for the enrichment determination. A photograph of the UCAS with a 48Y cylinder at REP is shown in Fig. 2, and the calibration measurement data for 30B product and 48Y feed and tails cylinders is shown in Fig. 3. The data was collected in a low-background environment, meaning there is very little scatter in the data. The PNEM measurement concept was first presented at the 2010 Institute of Nuclear Materials Management (INMM) Annual Meeting. The physics design and uncertainty analysis were presented at the 2010 International Atomic Energy Agency (IAEA) Safeguards Symposium, and the mechanical and electrical designs and characterization measurements were published in the ESARDA Bulletin in 2011.

Miller, Karen A. [Los Alamos National Laboratory; Swinhoe, Martyn T. [Los Alamos National Laboratory; Menlove, Howard O. [Los Alamos National Laboratory; Marlow, Johnna B. [Los Alamos National Laboratory

2012-05-02T23:59:59.000Z

19

Uranium Hexafluoride (UF6)  

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Hexafluoride (UF6) Hexafluoride (UF6) Uranium Hexafluoride (UF6) line line Properties of UF6 UF6 Health Effects Uranium Hexafluoride (UF6) Physical and chemical properties of UF6, and its use in uranium processing. Uranium Hexafluoride and Its Properties Uranium hexafluoride is a chemical compound consisting of one atom of uranium combined with six atoms of fluorine. It is the chemical form of uranium that is used during the uranium enrichment process. Within a reasonable range of temperature and pressure, it can be a solid, liquid, or gas. Solid UF6 is a white, dense, crystalline material that resembles rock salt. UF6 crystals in a glass vial image UF6 crystals in a glass vial. Uranium hexafluoride does not react with oxygen, nitrogen, carbon dioxide, or dry air, but it does react with water or water vapor. For this reason,

20

Thermo-mechanical study of bare 48Y UF6 containers exposed to the regulatory fire environment.  

SciTech Connect

Most of the regulatory agencies world-wide require that containers used for the transportation of natural UF6 and depleted UF6 must survive a fully-engulfing fire environment for 30 minutes as described in 10CFR71 and in TS-R-1. The primary objective of this project is to examine the thermo-mechanical performance of 48Y transportation cylinders when exposed to the regulatory hypothetical fire environment without the thermal protection that is currently used for shipments in those countries where required. Several studies have been performed in which UF6 cylinders have been analyzed to determine if the thermal protection currently used on UF6 cylinders of type 48Y is necessary for transport. However, none of them could clearly confirm neither the survival nor the failure of the 48Y cylinder when exposed to the regulatory fire environment without the additional thermal protection. A consortium of five companies that move UF6 is interested in determining if 48Y cylinders can be shipped without the thermal protection that is currently used. Sandia National Laboratories has outlined a comprehensive testing and analysis project to determine if these shipping cylinders are capable of withstanding the regulatory thermal environment without additional thermal protection. Sandia-developed coupled physics codes will be used for the analyses that are planned. A series of destructive and non-destructive tests will be performed to acquire the necessary material and behavior information to benchmark the models and to answer the question about the ability of these containers to survive the fire environment. Both the testing and the analysis phases of this project will consider the state of UF6 under thermal and pressure loads as well as the weakening of the steel container due to the thermal load. Experiments with UF6 are also planned to collect temperature- and pressure-dependent thermophysical properties of this material.

Ammerman, Douglas James; Lopez, Carlos; Morrow, Charles; Korbmacher, Tim (Urenco Enrichment Co. Ltd., Gronau, Germany); Charette, Marc-Andre (Cameco Corporation, Port Hope, ON, Canada)

2010-11-01T23:59:59.000Z

Note: This page contains sample records for the topic "depleted uf6 cylinder" 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

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

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

22

Video: Part of the 'Hole' Story (of Uranium Hexafluoride Cylinders)  

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Hole Story Hole Story Part of the "Hole" Story (of Uranium Hexafluoride Cylinders) Holes in the depleted Uranium Hexafluoride storage cylinders are investigated. It is shown that corrosion products cause the openings to be self-healing. View this Video in Real Player format Download free RealPlayer SP Highlights of the Video: Video 00:00 Part of the 'Hole' Story Video 00:05 One of the depleted UF6 cylinder storage lots at Portsmouth Video 00:28 48G cylinders, each containing 14 tons of depleted UF6, in storage Video 00:52 Stacked 48G cylinders Video 01:35 UF6 sealed in glass tube Video 02:01 A lifting lug of one cylinder damaging a neighboring cylinder Video 02:37 Damage to small hole cylinder from impact with a lifting lub of an adjoining cylinder

23

Next Generations Safeguards Initiative: The Life of a Cylinder  

SciTech Connect

The U.S. Department of Energy/National Nuclear Security Administration Office of Nonproliferation and International Security's Next Generation Safeguards Initiative (NGSI) has begun a program based on a five-year plan to investigate the concept of a global monitoring scheme that uniquely identifies uranium hexafluoride (UF6) cylinders and their locations throughout the life cycle. A key initial activity in the NGSI program is to understand and document the 'life of a UF6 cylinder' from cradle to grave. This document describes the life of a UF6 cylinder and includes cylinder manufacture and procurement processes as well as cylinder-handling and operational practices at conversion, enrichment, fuel fabrication, and depleted UF6 conversion facilities. The NGSI multiple-laboratory team is using this document as a building block for subsequent tasks in the five-year plan, including development of the functional requirements for cylinder-tagging and tracking devices.

Morgan, James B [ORNL; White-Horton, Jessica L [ORNL

2012-01-01T23:59:59.000Z

24

Results from a "Proof-of-Concept" Demonstration of RF-Based Tracking of UF6 Cylinders during a Processing Operation at a Uranium Enrichment Plant  

SciTech Connect

Approved industry-standard cylinders are used globally for processing, storing, and transporting uranium hexafluoride (UF{sub 6}) at uranium enrichment plants. To ensure that cylinder movements at enrichment facilities occur as declared, the International Atomic Energy Agency (IAEA) must conduct time-consuming periodic physical inspections to validate facility records, cylinder identity, and containment. By using a robust system design that includes the capability for real-time unattended monitoring (of cylinder movements), site-specific rules-based event detection algorithms, and the capability to integrate with other types of monitoring technologies, one can build a system that will improve overall inspector effectiveness. This type of monitoring system can provide timely detection of safeguard events that could be used to ensure more timely and appropriate responses by the IAEA. It also could reduce reliance on facility records and have the additional benefit of enhancing domestic safeguards at the installed facilities. This paper will discuss the installation and evaluation of a radio-frequency- (RF-) based cylinder tracking system that was installed at a United States Enrichment Corporation Centrifuge Facility. This system was installed primarily to evaluate the feasibility of using RF technology at a site and the operational durability of the components under harsh processing conditions. The installation included a basic system that is designed to support layering with other safeguard system technologies and that applies fundamental rules-based event processing methodologies. This paper will discuss the fundamental elements of the system design, the results from this site installation, and future efforts needed to make this technology ready for IAEA consideration.

Pickett, Chris A [ORNL] [ORNL; Kovacic, Donald N [ORNL] [ORNL; Whitaker, J Michael [ORNL] [ORNL; Younkin, James R [ORNL] [ORNL; Hines, Jairus B [ORNL] [ORNL; Laughter, Mark D [ORNL] [ORNL; Morgan, Jim [Innovative Solutions] [Innovative Solutions; Carrick, Bernie [USEC] [USEC; Boyer, Brian [Los Alamos National Laboratory (LANL)] [Los Alamos National Laboratory (LANL); Whittle, K. [USEC] [USEC

2008-01-01T23:59:59.000Z

25

Investigation of breached depleted UF{sub 6} cylinders  

SciTech Connect

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

DeVan, J.H. [Martin Marietta Energy Systems, Inc., Oak Ridge, TN (United States)

1991-12-31T23:59:59.000Z

26

Investigation of breached depleted UF{sub 6} cylinders  

SciTech Connect

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

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

1991-09-01T23:59:59.000Z

27

Investigation of breached depleted UF sub 6 cylinders  

SciTech Connect

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

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

1991-09-01T23:59:59.000Z

28

Depleted Uranium Uses Research and Development  

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

29

FAQ 8-What is uranium hexafluoride (UF6)?  

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is uranium hexafluoride (UF6)? is uranium hexafluoride (UF6)? What is uranium hexafluoride (UF6)? Uranium hexafluoride is a chemical compound consisting of one atom of uranium combined with six atoms of fluorine. It is the chemical form of uranium that is used during the uranium enrichment process. Within a reasonable range of temperature and pressure, it can be a solid, liquid, or gas. Solid UF6 is a white, dense, crystalline material that resembles rock salt. Liquid UF6 is formed only at temperatures greater than 147° F (64° C) and at pressures greater than 1.5 times atmospheric pressure (22 psia). At atmospheric pressure, solid UF6 will transform directly to UF6 gas (sublimation) when the temperature is raised to 134° F (57° C), without going through a liquid phase.

30

Overview of Depleted Uranium Hexafluoride Management Program  

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

31

Refurbishment of uranium hexafluoride cylinder storage yards C-745-K, L, M, N, and P and construction of a new uranium hexafluoride cylinder storage yard (C-745-T) at the Paducah Gaseous Diffusion Plant, Paducah, Kentucky  

SciTech Connect

The Paducah Gaseous Diffusion Plant (PGDP) is a uranium enrichment facility owned by the US Department of Energy (DOE). A residual of the uranium enrichment process is depleted uranium hexafluoride (UF6). Depleted UF6, a solid at ambient temperature, is stored in 32,200 steel cylinders that hold a maximum of 14 tons each. Storage conditions are suboptimal and have resulted in accelerated corrosion of cylinders, increasing the potential for a release of hazardous substances. Consequently, the DOE is proposing refurbishment of certain existing yards and construction of a new storage yard. This environmental assessment (EA) evaluates the impacts of the proposed action and no action and considers alternate sites for the proposed new storage yard. The proposed action includes (1) renovating five existing cylinder yards; (2) constructing a new UF6 storage yard; handling and onsite transport of cylinders among existing yards to accommodate construction; and (4) after refurbishment and construction, restacking of cylinders to meet spacing and inspection requirements. Based on the results of the 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 National Environmental Policy Act of 1969. Therefore, DOE is issuing a Finding of No Significant Impact. Additionally, it is reported in this EA that the loss of less than one acre of wetlands at the proposed project site would not be a significant adverse impact.

NONE

1996-07-01T23:59:59.000Z

32

Methods and results for stress analyses on 14-ton, thin-wall depleted UF{sub 6} cylinders  

SciTech Connect

Uranium enrichment operations at the three US gaseous diffusion plants produce depleted uranium hexafluoride (DUF{sub 6}) as a residential product. At the present time, the inventory of DUF{sub 6} in this country is more than half a million tons. The inventory of DUF{sub 6} is contained in metal storage cylinders, most of which are located at the gaseous diffusion plants. The principal objective of the project is to ensure the integrity of the cylinders to prevent causing an environmental hazard by releasing the contents of the cylinders into the atmosphere. Another objective is to maintain the cylinders in such a manner that the DUF{sub 6} may eventually be converted to a less hazardous material for final disposition. An important task in the DUF{sub 6} cylinders management project is determining how much corrosion of the walls can be tolerated before the cylinders are in danger of being damaged during routine handling and shipping operations. Another task is determining how to handle cylinders that have already been damaged in a manner that will minimize the chance that a breach will occur or that the size of an existing breach will be significantly increased. A number of finite element stress analysis (FESA) calculations have been done to analyze the stresses for three conditions: (1) while the cylinder is being lifted, (2) when a cylinder is resting on two cylinders under it in the customary two-tier stacking array, and (3) when a cylinder is resting on tis chocks on the ground. Various documents describe some of the results and discuss some of the methods whereby they have been obtained. The objective of the present report is to document as many of the FESA cases done at Oak Ridge for 14-ton thin-wall cylinders as possible, giving results and a description of the calculations in some detail.

Kirkpatrick, J.R.; Chung, C.K.; Frazier, J.L.; Kelley, D.K.

1996-10-01T23:59:59.000Z

33

FAQ 7-How is depleted uranium produced?  

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

34

UF6 overfilling prevention at Eurodif production Georges Besse plant  

SciTech Connect

Risk of overfilling exists on different equipments of Georges BESSE Plant: cylinders, desublimers and intermediate tanks. The preventive measures are composed of technical devices: desublimers weighing, load monitoring alarms, automatic controls ... and procedures, training, safety organization. In thirteen years of operation, some incidents have occurred but none of them has caused any personal injuries. They are related and discussed. The main factors involved in the Sequoyah fuel facility accident on 1/4/1986 have been analyzed and taken into account.

Reneaud, J.M. [Eurodif Production, Pierrelatte (France)

1991-12-31T23:59:59.000Z

35

Photoelectron Spectroscopy and Theoretical Studies of UF5 ? and UF6 ?  

SciTech Connect

The UF5 ? and UF6 ? anions are produced using electrospray ionization and investigated by photoelectron spectroscopy and relativistic quantum chemistry. An extensive vibrational progression is observed in the spectra of UF5 ?, indicating significant geometry changes between the anion and neutral ground state. Franck-Condon factor simulations of the observed vibrational progression yield an adiabatic electron detachment energy of 3.82 ± 0.05 eV for UF5 ?. Relativistic quantum calculations using density functional and ab initio theories are performed on UF5 ? and UF6 ? and their neutrals. The ground states of UF5 ? and UF5 are found to have C4v symmetry, but with a large U?F bond length change. The ground state of UF5 ? is a triplet state (3B2) with the two 5f electrons occupying a 5fz3-based 8a1 highest occupied molecular orbital (HOMO) and the 5fxyz-based 2b2 HOMO-1 orbital. The detachment cross section from the 5fxyz orbital is observed to be extremely small and the detachment transition from the 2b2 orbital is more than ten times weaker than that from the 8a1 orbital at the photon energies available. The UF6 ? anion is found to be octahedral, similar to neutral UF6 with the extra electron occupying the 5fxyz-based a2u orbital. Surprisingly, no photoelectron spectrum could be observed for UF6 ? due to the extremely low detachment cross section from the 5fxyz-based HOMO of UF6 ?.

Dau, Phuong D.; Su, Jing; Liu, Hong-Tao; Huang, Dao-Ling; Wei, Fan; Li, Jun; Wang, Lai S.

2012-05-17T23:59:59.000Z

36

E-Print Network 3.0 - activities uf6 cylinder Sample Search Results  

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Science; Ohta, Shigemi - Theory Group, Institute of Particle and Nuclear Studies, High Energy Accelerator Research Organization (KEK) Collection: Environmental Sciences and Ecology...

37

High temperature experiments on a 4 tons UF6 container TENERIFE program  

SciTech Connect

The paper presents an experimental program (called TENERIFE) whose aim is to investigate the behaviour of a cylinder containing UF{sub 6} when exposed to a high temperature fire for model validation. Taking into account the experiments performed in the past, the modelization needs further information in order to be able to predict the behaviour of a real size cylinder when engulfed in a 800{degrees}C fire, as specified in the regulation. The main unknowns are related to (1) the UF{sub 6} behaviour beyond the critical point, (2) the relationship between temperature field and internal pressure and (3) the equivalent conductivity of the solid UF{sub 6}. In order to investigate these phenomena in a representative way it is foreseen to perform experiments with a cylinder of real diameter, but reduced length, containing 4 tons of UF{sub 6}. This cylinder will be placed in an electrically heated furnace. A confinement vessel prevents any dispersion of UF{sub 6}. The heat flux delivered by the furnace will be calibrated by specific tests. The cylinder will be changed for each test.

Casselman, C.; Duret, B.; Seiler, J.M.; Ringot, C.; Warniez, P.

1991-12-31T23:59:59.000Z

38

Standard test method for determination of bromine and chlorine in UF6 and uranyl nitrate by X-Ray fluorescence (XRF) spectroscopy  

E-Print Network (OSTI)

1.1 This method covers the determination of bromine (Br) and chlorine (Cl) in uranium hexafluoride (UF6) and uranyl nitrate solution. The method as written covers the determination of bromine in UF6 over the concentration range of 0.2 to 8 ?g/g, uranium basis. The chlorine in UF6 can be determined over the range of 4 to 160 ?g/g, uranium basis. Higher concentrations may be covered by appropriate dilutions. The detection limit for Br is 0.2 ?g/g uranium basis and for Cl is 4 ?g/g uranium basis. 1.2 This standard may involve hazardous materials, operations and equipment. This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use.

American Society for Testing and Materials. Philadelphia

2001-01-01T23:59:59.000Z

39

Preliminary Concept of Operations for a Global Cylinder Identification and Monitoring System  

SciTech Connect

This report describes a preliminary concept of operations for a Global Cylinder Identification and Monitoring System that could improve the efficiency of the International Atomic Energy Agency (IAEA) in conducting its current inspection activities and could provide a capability to substantially increase its ability to detect credible diversion scenarios and undeclared production pathways involving UF6 cylinders. There exist concerns that a proliferant State with access to enrichment technology could obtain a cylinder containing natural or low-enriched uranium hexafluoride (UF6) and produce a significant quantity (SQ)1 of highly enriched uranium in as little as 30 days. The National Nuclear Security Administration (NNSA) through the Next Generation Safeguards Initiative sponsored a multi-laboratory team to develop an integrated system that provides for detecting scenarios involving 1) diverting an entire declared cylinder for enrichment at a clandestine facility, 2) misusing a declared cylinder at a safeguarded facility, and 3) using an undeclared cylinder at a safeguarded facility. An important objective in developing this integrated system was to improve the timeliness for detecting the cylinder diversion and undeclared production scenarios. Developing this preliminary concept required in-depth analyses of current operational and safeguards practices at conversion, enrichment, and fuel fabrication facilities. The analyses evaluated the processing, movement, and storage of cylinders at the facilities; the movement of cylinders between facilities (including cylinder fabrication); and the misuse of safeguarded facilities.

Whitaker, J. M. [ORNL; White-Horton, J. L. [ORNL; Morgan, J. B. [InSolves Associates

2013-08-01T23:59:59.000Z

40

Storage  

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Environmental Risks » Storage Environmental Risks » Storage Depleted UF6 Environmental Risks line line Storage Conversion Manufacturing Disposal Environmental Risks of Depleted UF6 Storage Discussion of the potential environmental impacts from storage of depleted UF6 at the three current storage sites, as well as potential impacts from the storage of depleted uranium after conversion to an oxide form. Impacts Analyzed in the PEIS The PEIS included an analysis of the potential environmental impacts from continuing to store depleted UF6 cylinders at the three current storage sites, as well as potential impacts from the storage of depleted uranium after conversion to an oxide form. Impacts from Continued Storage of UF6 Cylinders Continued storage of the UF6 cylinders would require extending the use of a

Note: This page contains sample records for the topic "depleted uf6 cylinder" from the National Library of EnergyBeta (NLEBeta).
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41

Cylinder monitoring program  

SciTech Connect

Cylinders containing depleted uranium hexafluoride (UF{sub 6}) in storage at the Department of Energy (DOE) gaseous diffusion plants, managed by Martin Marietta Energy Systems, Inc., are being evaluated to determine their expected storage life. Cylinders evaluated recently have been in storage service for 30 to 40 years. In the present environment, the remaining life for these storage cylinders is estimated to be 30 years or greater. The group of cylinders involved in recent tests will continue to be monitored on a periodic basis, and other storage cylinders will be observed as on a statistical sample population. The program has been extended to all types of large capacity UF{sub 6} cylinders.

Alderson, J.H. [Martin Marietta Energy Systems, Inc., Paducah, KY (United States)

1991-12-31T23:59:59.000Z

42

Transportation  

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Transportation Transportation Transportation of Depleted Uranium Materials in Support of the Depleted Uranium Hexafluoride Conversion Program Issues associated with transport of depleted UF6 cylinders and conversion products. Conversion Plan Transportation Requirements The DOE has prepared two Environmental Impact Statements (EISs) for the proposal to build and operate depleted uranium hexafluoride (UF6) conversion facilities at its Portsmouth and Paducah gaseous diffusion plant sites, pursuant to the National Environmental Policy Act (NEPA). The proposed action calls for transporting the cylinder at ETTP to Portsmouth for conversion. The transportation of depleted UF6 cylinders and of the depleted uranium conversion products following conversion was addressed in the EISs.

43

Enrichment Assay Methods Development for the Integrated Cylinder Verification System  

SciTech Connect

International Atomic Energy Agency (IAEA) inspectors currently perform periodic inspections at uranium enrichment plants to verify UF6 cylinder enrichment declarations. Measurements are typically performed with handheld high-resolution sensors on a sampling of cylinders taken to be representative of the facility's entire product-cylinder inventory. Pacific Northwest National Laboratory (PNNL) is developing a concept to automate the verification of enrichment plant cylinders to enable 100 percent product-cylinder verification and potentially, mass-balance calculations on the facility as a whole (by also measuring feed and tails cylinders). The Integrated Cylinder Verification System (ICVS) could be located at key measurement points to positively identify each cylinder, measure its mass and enrichment, store the collected data in a secure database, and maintain continuity of knowledge on measured cylinders until IAEA inspector arrival. The three main objectives of this FY09 project are summarized here and described in more detail in the report: (1) Develop a preliminary design for a prototype NDA system, (2) Refine PNNL's MCNP models of the NDA system, and (3) Procure and test key pulse-processing components. Progress against these tasks to date, and next steps, are discussed.

Smith, Leon E.; Misner, Alex C.; Hatchell, Brian K.; Curtis, Michael M.

2009-10-22T23:59:59.000Z

44

Final DUF6 PEIS: Volume 2: Appendix J; Transportation  

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Transportation Transportation Depleted UF 6 PEIS J-i APPENDIX J: ENVIRONMENTAL IMPACTS OF TRANSPORTATION OF UF 6 CYLINDERS, URANIUM OXIDE, URANIUM METAL, AND ASSOCIATED MATERIALS Transportation Depleted UF 6 PEIS J-ii Transportation Depleted UF 6 PEIS J-iii CONTENTS (APPENDIX J) NOTATION . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . J-vi J.1 SUMMARY OF TRANSPORTATION OPTION IMPACTS . . . . . . . . . . . . . . . . . . J-3 J.2 TRANSPORTATION MODES . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . J-8 J.2.1 Truck Transportation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . J-8 J.2.2 Rail Transportation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . J-9 J.2.3 Transportation Options Considered But Not Analyzed in Detail . . . . . . . . . . J-9 J.3 IMPACTS OF OPTIONS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . J-10 J.3.1

45

Depleted uranium plasma reduction system study  

SciTech Connect

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

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

1994-12-01T23:59:59.000Z

46

Thermal Reactions of Uranium Metal, UO2, U3O8, UF4, and UO2F2 with NF3 to Produce UF6  

SciTech Connect

he objective of this paper is to demonstrate that NF3 fluorinates uranium metal, UO2, UF4, UO3, U3O8, and UO2F2•2H2O to produce the volatile UF6 at temperatures between 100 and 500?C. Thermogravimetric reaction profiles are described that reflect changes in the uranium oxidation state and discrete chemical speciation. Differences in the onset temperatures for each system indicate that NF3-substrate interactions are important for the temperature at which NF3 reacts: U metal > UO3 > UO2 > UO2F2 > UF4 and in fact may indicate different fluorination mechanisms for these various substrates. These studies demonstrate that NF3 is a potential replacement fluorinating agent in the existing nuclear fuel cycle and in oft-proposed actinide volatility reprocessing.

McNamara, Bruce K.; Scheele, Randall D.; Kozelisky, Anne E.; Edwards, Matthew K.

2009-11-01T23:59:59.000Z

47

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

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

48

Draft Environmental Impact Statement for Construction and Operation of a Depleted Uranium Hexafluoride Conversion Facility at the Portsmouth, Ohio, Site  

SciTech Connect

This document is a site-specific environmental impact statement (EIS) for construction and operation of a proposed depleted uranium hexafluoride (DUF{sub 6}) conversion facility at the U.S. Department of Energy (DOE) Portsmouth site in Ohio (Figure S-1). The proposed facility would convert the DUF{sub 6} stored at Portsmouth to a more stable chemical form suitable for use or disposal. The facility would also convert the DUF{sub 6} from the East Tennessee Technology Park (ETTP) site near Oak Ridge, Tennessee. In a Notice of Intent (NOI) published in the Federal Register on September 18, 2001 (Federal Register, Volume 66, page 48123 [66 FR 48123]), DOE announced its intention to prepare a single EIS for a proposal to construct, operate, maintain, and decontaminate and decommission two DUF{sub 6} conversion facilities at Portsmouth, Ohio, and Paducah, Kentucky, in accordance with the National Environmental Policy Act of 1969 (NEPA) (United States Code, Title 42, Section 4321 et seq. [42 USC 4321 et seq.]) and DOE's NEPA implementing procedures (Code of Federal Regulations, Title 10, Part 1021 [10 CFR Part 1021]). Subsequent to award of a contract to Uranium Disposition Services, LLC (hereafter referred to as UDS), Oak Ridge, Tennessee, on August 29, 2002, for design, construction, and operation of DUF{sub 6} conversion facilities at Portsmouth and Paducah, DOE reevaluated its approach to the NEPA process and decided to prepare separate site-specific EISs. This change was announced in a Federal Register Notice of Change in NEPA Compliance Approach published on April 28, 2003 (68 FR 22368); the Notice is included as Attachment B to Appendix C of this EIS. This EIS addresses the potential environmental impacts from the construction, operation, maintenance, and decontamination and decommissioning (D&D) of the proposed conversion facility at three alternative locations within the Portsmouth site; from the transportation of all ETTP cylinders (DUF{sub 6}, low-enriched UF6 [LEU-UF{sub 6}], and empty) to Portsmouth; from the transportation of depleted uranium conversion products to a disposal facility; and from the transportation, sale, use, or disposal of the fluoride-containing conversion products (hydrogen fluoride [HF] or calcium fluoride [CaF{sub 2}]). An option of shipping the ETTP cylinders to Paducah is also considered. In addition, this EIS evaluates a no action alternative, which assumes continued storage of DUF{sub 6} in cylinders at the Portsmouth and ETTP sites. A separate EIS (DOE/EIS-0359) evaluates potential environmental impacts for the proposed Paducah conversion facility.

N /A

2003-11-28T23:59:59.000Z

49

Breached cylinder incident at the Portsmouth gaseous diffusion plant  

SciTech Connect

On June 16, 1990, during an inspection of valves on partially depleted product storage cylinders, a 14-ton partially depleted product cylinder was discovered breached. The cylinder had been placed in long-term storage in 1977 on the top row of Portsmouth`s (two rows high) storage area. The breach was observed when an inspector noticed a pile of green material along side of the cylinder. The breach was estimated to be approximately 8- inches wide and 16-inches long, and ran under the first stiffening ring of the cylinder. During the continuing inspection of the storage area, a second 14-ton product cylinder was discovered breached. This cylinder was stacked on the bottom row in the storage area in 1986. This breach was also located adjacent to a stiffening ring. This paper will discuss the contributing factors of the breaching of the cylinders, the immediate response, subsequent actions in support of the investigation, and corrective actions.

Boelens, R.A. [Martin Marietta Energy Systems, Inc., Piketon, OH (United States)

1991-12-31T23:59:59.000Z

50

Depleted Uranium  

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

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

51

Accidents  

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

Health Risks » Accidents Health Risks » Accidents DUF6 Health Risks line line Accidents Storage Conversion Manufacturing Disposal Transportation Accidents A discussion of accidents involving depleted UF6 storage cylinders, including possible health effects, accident risk, and accident history. Potential Health Effects from Cylinder Accidents Accidents involving depleted UF6 storage cylinders are a concern because they could result in an uncontrolled release of UF6 to the environment, which could potentially affect the health of workers and members of the public living downwind of the accident site. Accidental release of UF6 from storage cylinders or during processing activities could result in injuries or fatalities. The most immediate hazard after a release would be from inhalation of hydrogen fluoride (HF), a highly corrosive gas formed when

52

gas cylinder storage guidelines  

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

Compressed Gas Cylinder Storage Guidelines Compressed Gas Cylinder Storage Guidelines All cylinders must be stored vertical, top up across the upper half the cylinder but below the shoulder. Small cylinder stands or other methods may be appropriate to ensure that the cylinders are secured from movement. Boxes, cartons, and other items used to support small cylinders must not allow water to accumulate and possible cause corrosion. Avoid corrosive chemicals including salt and fumes - keep away from direct sunlight and keep objects away that could fall on them. Use Gas pressure regulators that have been inspected in the last 5 years. Cylinders that contain fuel gases whether full or empty must be stored away from oxidizer cylinders at a minimum of 20 feet. In the event they are stored together, they must be separated by a wall 5 feet high with

53

Quick release engine cylinder  

DOE Patents (OSTI)

A quick release engine cylinder allows optical access to an essentially unaltered combustion chamber, is suitable for use with actual combustion processes, and is amenable to rapid and repeated disassembly and cleaning. A cylinder member, adapted to constrain a piston to a defined path through the cylinder member, sealingly engages a cylinder head to provide a production-like combustion chamber. A support member mounts with the cylinder member. The support-to-cylinder mounting allows two relationships therebetween. In the first mounting relationship, the support engages the cylinder member and restrains the cylinder against the head. In the second mounting relationship, the cylinder member can pass through the support member, moving away from the head and providing access to the piston-top and head.

Sunnarborg, Duane A. (1123 Lucille St., Livermore, Alameda County, CA 94550)

2000-01-01T23:59:59.000Z

54

Compressed Gas Cylinder Policy  

E-Print Network (OSTI)

storage rack, a wall mounted cylinder rack, anchored to a fixed bench top, vented gas cabinet, or other

55

Depleted uranium  

Science Journals Connector (OSTI)

The potential health effects arising from exposure to depleted uranium have been much in the news of late. Naturally occurring uranium contains the radioisotopes 238U (which dominates, at a current molar proportion of 99.3%), 235U and a small amount of 234U. Depleted uranium has an isotopic concentration of 235U that is below the 0.7% found naturally. This is either because the uranium has passed through a nuclear reactor which uses up some of the fissile 235U that fuels the fission chain-reaction, or because it is the uranium that remains when enriched uranium with an elevated concentration of 235U is produced in an enrichment plant, or because of a combination of these two processes. Depleted uranium has a lower specific activity than naturally occurring uranium because of the lower concentrations of the more radioactive isotopes 235U and 234U, but account must be taken of any contaminating radionuclides or exotic radioisotopes of uranium if the uranium has been irradiated. Uranium is a particularly dense element (about twice as dense as lead), and this property makes it useful in certain military applications, such as armour-piercing munitions. Depleted uranium, rather than natural uranium, is used because of its availability and, since the demise of the fast breeder reactor programme, the lack of alternative use. Depleted uranium weapons were used in the Gulf War of 1990 and also, to a lesser extent, more recently in the Balkans. This has led to speculation that depleted uranium may be associated with `Gulf War Syndrome', or other health effects that have been reported by military and civilian personnel involved in these conflicts and their aftermath. Although, on the basis of present scientific knowledge, it seems most unlikely that exposure to depleted uranium at the levels concerned could produce a detectable excess of adverse health effects, and in such a short timescale, the issue has become one of general concern and contention. As a consequence, any investigation needs to be thorough to produce sufficiently comprehensive evidence to stand up to close scrutiny and gain the support of the public, whatever the conclusions. Unfortunately, it is the nature of such inquiries that they take time, which is frustrating for some. In the UK, the Royal Society has instigated an independent investigation into the health effects of depleted uranium by a working group chaired by Professor Brian Spratt. This inquiry has been underway since the beginning of 2000. The working group's findings will be reviewed by a panel appointed by the Council of the Royal Society, and it is anticipated that the final report will be published in the summer of 2001. Further details can be found at www.royalsoc.ac.uk/templates/press/showpresspage.cfm?file=2001010801.txt. Nick Priest has summarised current knowledge on the toxicity (both radiological and chemical) of depleted uranium in a commentary in The Lancet (27 January 2001, 357 244-6). For those wanting to read a comprehensive review of the literature, in 1999 RAND published `A Review of the Scientific Literature as it Pertains to Gulf War Illnesses, Volume 7: Depleted Uranium' by Naomi Harley and her colleagues, which can be found at www.rand.org/publications/MR/MR1018.7/MR1018.7.html. An interesting article by Jan Olof Snihs and Gustav Akerblom entitled `Use of depleted uranium in military conflicts and possible impact on health and environment' was published in the December 2000 issue of SSI News (pp 1-8), and can be found at the website of the Swedish Radiation Protection Institute: www.ssi.se/tidningar/PDF/lockSSIn/SSI-news2000.pdf. Last year, a paper was published in the June issue of this Journal that is of some relevance to depleted uranium. McGeoghegan and Binks (2000 J. Radiol. Prot. 20 111-37) reported the results of their epidemiological study of the health of workers at the Springfields uranium production facility near Preston during 1946-95. This study included almost 14 000 radiation workers. Although organ-specific doses due to uranium are not yet available for these worker

Richard Wakeford

2001-01-01T23:59:59.000Z

56

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

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

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

57

Transportation  

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

Health Risks » Transportation Health Risks » Transportation DUF6 Health Risks line line Accidents Storage Conversion Manufacturing Disposal Transportation Transportation A discussion of health risks associated with transport of depleted UF6. Transport Regulations and Requirements In the future, it is likely that depleted uranium hexafluoride cylinders will be transported to a conversion facility. For example, it is currently anticipated that the cylinders at the ETTP Site in Oak Ridge, TN, will be transported to the Portsmouth Site, OH, for conversion. Uranium hexafluoride has been shipped safely in the United States for over 40 years by both truck and rail. Shipments of depleted UF6 would be made in accordance with all applicable transportation regulations. Shipment of depleted UF6 is regulated by the

58

An update on corrosion monitoring in cylinder storage yards  

SciTech Connect

Depleted uranium, from US uranium isotope enrichment activities, is stored in the form of solid uranium hexafluoride (UF{sub 6}) in A285 and A516 steel cylinders designed and manufactured to ASME Boiler and Pressure Vessel Code criteria. In general, storage facilities are open areas adjacent to the enrichment plants where the cylinders are exposed to weather. This paper describes the Oak Ridge program to determine the general corrosion behavior of UF{sub 6} cylinders, to determine cylinder yard conditions which are likely to affect long term storage of this material, and to assess cylinder storage yards against these criteria. This program is targeted at conditions specific to the Oak Ridge cylinder yards. Based on (a) determination of the current cylinder yard conditions, (b) determination of rusting behavior in regions of the cylinders showing accelerated attack, (c) monitoring of corrosion rates through periodic measurement of test coupons placed within the cylinder yards, and (d) establishment of a computer base to incorporate and retain these data, the technical division is working with the enrichment sites to implement an upgraded system for storage of this material until such time as it is used or converted.

Henson, H.M.; Newman, V.S.; Frazier, J.L. [Oak Ridge K-25 Site, TN (United States)

1991-12-31T23:59:59.000Z

59

Charge Depleting:  

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

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

60

Gas Cylinders: Proper Management  

E-Print Network (OSTI)

Compressed Gas Cylinders: Proper Management And Use Published by the Office of Environment, Health;1 Introduction University of California, Berkeley (UC Berkeley) departments that use compressed gas cylinders (MSDS) and your department's Job Safety Analyses (JSAs). Talk to your gas supplier about hands

Boyer, Elizabeth W.

Note: This page contains sample records for the topic "depleted uf6 cylinder" 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

Prediction of External Corrosion for Steel Cylinders--2004 Report  

SciTech Connect

Depleted uranium hexafluoride (UF{sub 6}) is stored in over 60,000 steel cylinders at the East Tennessee Technology Park (ETTP) in Oak Ridge, Tennessee, at the Paducah Gaseous Diffusion Plant (PGDP) in Paducah, Kentucky, and at the Portsmouth Gaseous Diffusion Plant (PORTS) in Portsmouth, Ohio. The cylinders range in age from 4 to 53 years. Although when new the cylinders had wall thicknesses specified to within manufacturing tolerances, over the years corrosion has reduced their actual wall thicknesses. The UF{sub 6} Cylinder Project is managed by the United States Department of Energy (DOE) to safely maintain the UF{sub 6} and the cylinders containing it. This report documents activities that address UF{sub 6} Cylinder Project requirements and actions involving forecasting cylinder wall thicknesses. These requirements are delineated in the System Requirements Document (LMES 1997a), and the actions needed to fulfill them are specified in the System Engineering Management Plan (LMES 1997b). The report documents cylinder wall thickness projections based on models fit to ultrasonic thickness (UT) measurement data. UT data is collected at various locations on randomly sampled cylinders. For each cylinder sampled, the minimum UT measurement approximates the actual minimum thickness of the cylinder. Projections of numbers of cylinders expected to fail various thickness criteria are computed from corrosion models relating minimum wall thickness to cylinder age, initial thickness estimates, and cylinder subpopulations defined in terms of plant site, yard, top or bottom storage positions, nominal thickness, etc. In this report, UT data collected during FY03 is combined with UT data collected in earlier years (FY94-FY02), and all of the data is inventoried chronologically and by various subpopulations. The UT data is used to fit models of maximum pit depth and minimum thickness, and the fitted models are used to extrapolate minimum thickness estimates into the future and in turn to compute estimates of numbers of cylinders expected to fail various thickness criteria. A model evaluation is performed comparing UT measurements made in FY03 with model-fitted projections based only on data collected before FY03.

Schmoyer, RLS

2004-07-07T23:59:59.000Z

62

The uranium cylinder assay system for enrichment plant safeguards  

SciTech Connect

Safeguarding sensitive fuel cycle technology such as uranium enrichment is a critical component in preventing the spread of nuclear weapons. A useful tool for the nuclear materials accountancy of such a plant would be an instrument that measured the uranium content of UF{sub 6} cylinders. The Uranium Cylinder Assay System (UCAS) was designed for Japan Nuclear Fuel Limited (JNFL) for use in the Rokkasho Enrichment Plant in Japan for this purpose. It uses total neutron counting to determine uranium mass in UF{sub 6} cylinders given a known enrichment. This paper describes the design of UCAS, which includes features to allow for unattended operation. It can be used on 30B and 48Y cylinders to measure depleted, natural, and enriched uranium. It can also be used to assess the amount of uranium in decommissioned equipment and waste containers. Experimental measurements have been carried out in the laboratory and these are in good agreement with the Monte Carlo modeling results.

Miller, Karen A [Los Alamos National Laboratory; Swinhoe, Martyn T [Los Alamos National Laboratory; Marlow, Johnna B [Los Alamos National Laboratory; Menlove, Howard O [Los Alamos National Laboratory; Rael, Carlos D [Los Alamos National Laboratory; Iwamoto, Tomonori [JNFL; Tamura, Takayuki [JNFL; Aiuchi, Syun [JNFL

2010-01-01T23:59:59.000Z

63

Depleted Uranium Health Effects  

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

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

64

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

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

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

65

Depleted uranium: A DOE management guide  

SciTech Connect

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

NONE

1995-10-01T23:59:59.000Z

66

Depleted Uranium Technical Brief  

E-Print Network (OSTI)

and radiological health concerns involved with depleted uranium in the environment. This technical brief was developed to address the common misconception that depleted uranium represents only a radiological healthDepleted Uranium Technical Brief United States Environmental Protection Agency Office of Air

67

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

68

Transportation Impact Assessment for Shipment of Uranium Hexafluoride (UF<sub>6</sub>) Cylinders from the East Tennessee Technology Park to the Portsmouth and Paducah Gaseous Diffusion  

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

2 2 Transportation Impact Assessment for Shipment of Uranium Hexafluoride (UF 6 ) Cylinders from the East Tennessee Technology Park to the Portsmouth and Paducah Gaseous Diffusion Plants Environmental Assessment Division Argonne National Laboratory Operated by The University of Chicago, under Contract W-31-109-Eng-38, for the United States Department of Energy Argonne National Laboratory Argonne National Laboratory, with facilities in the states of Illinois and Idaho, is owned by the United States Government and operated by The University of Chicago under the provisions of a contract with the Department of Energy. This technical memorandum is a product of Argonne's Environmental Assessment Division (EAD). For information on the division's scientific and engineering

69

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

70

Prediction of external corrosion for steel storage cylinders  

SciTech Connect

The US Department of Energy (DOE) currently manages the UF{sub 6} Cylinder Program (the program). The program was formed to address the depleted-uranium hexafluoride (UF{sub 6}) stored in approximately 50,000 carbon steel cylinders. The cylinders are located at three DOE sites: the K-25 site (K-25) at Oak Ridge, Tennessee; the Paducah Gaseous Diffusion Plant (PGDP) in Paducah, Kentucky, and the Portsmouth Gaseous Diffusion Plant (PORTS) in Portsmouth, Ohio. The System Requirements Document (SRD) (LMES 1996a) delineates the requirements of the program. The appropriate actions needed to fulfill these requirements are then specified within the System Engineering Management Plan (SEMP) (LMES 1996b). The report presented herein documents activities that in whole or in part satisfy specific requirements and actions stated in the UF{sub 6} Cylinder Program SRD and SEMP with respect to forecasting cylinder conditions. The wall thickness projections made in this report are based on the assumption that the corrosion trends noted will continue. Some activities planned may substantially reduce the rate of corrosion, in which case the results presented here are conservative. The results presented here are intended to supersede those presented previously, as the quality of several of the datasets has improved.

Lyon, B.F.

1997-02-01T23:59:59.000Z

71

Acoustically invisible cylinder  

Science Journals Connector (OSTI)

Coatings of new type recently proposed by the author (Acoustical Physics 2007 vol. 53 N5 pp. 535?545) are applied to bodies of cylindrical geometry to reduce reflection or scattering of sound and thus to make them undetectable by imaging systems. Such a coating called as a coating with extended reaction represents a periodic set of small elements with coupling between the neighboring elements. Appropriate choice of the coupling parameters makes its efficiency much higher than that of commonly used coatings. In the present paper it is shown by computer simulation that a rather simple coating of this type can reduce the back?scattered pressure amplitude more than 40 dB (with respect to the rigid cylinder) practically at all frequencies. Considerable reduction of the scattered power can also be achieved in a low frequency range. The width of this range and the reduction index depend on the number of couplings introduced into the coating.

Yuri Bobrovnitskii

2008-01-01T23:59:59.000Z

72

Results of the remote sensing feasibility study for the uranium hexafluoride storage cylinder yard program  

SciTech Connect

The US DOE manages the safe storage of approximately 650,000 tons of depleted uranium hexafluoride remaining from the Cold War. This slightly radioactive, but chemically active, material is contained in more than 46,000 steel storage cylinders that are located at Oak Ridge, Tennessee; Paducah, Kentucky; and Portsmouth, Ohio. Some of the cylinders are more than 40 years old, and approximately 17,500 are considered problem cylinders because their physical integrity is questionable. These cylinders require an annual visual inspection. The remainder of the 46,000-plus cylinders must be visually inspected every four years. Currently, the cylinder inspection program is extremely labor intensive. Because these inspections are accomplished visually, they may not be effective in the early detection of leaking cylinders. The inspection program requires approximately 12--14 full-time-equivalent (FTE) employees. At the cost of approximately $125K per FTE, this translates to $1,500K per annum just for cylinder inspection. As part of the technology-development portion of the DOE Cylinder Management Program, the DOE Office of Facility Management requested the Remote Sensing Laboratory (RSL) to evaluate remote sensing techniques that have potential to increase the effectiveness of the inspection program and, at the same time, reduce inspection costs and personnel radiation exposure. During two site visits (March and May 1996) to the K-25 Site at Oak Ridge, TN, RSL personnel tested and characterized seven different operating systems believed to detect leakage, surface contamination, thickness and corrosion of cylinder walls, and general area contamination resulting from breached cylinders. The following techniques were used and their performances are discussed: Laser-induced fluorescent imaging; Long-range alpha detection; Neutron activation analysis; Differential gamma-ray attenuation; Compton scatterometry; Active infrared inspection; and Passive thermal infrared imaging.

Balick, L.K.; Bowman, D.R. [Bechtel Nevada, Las Vegas, NV (United States). Remote Sensing Lab.; Bounds, J.H. [Los Alamos National Lab., NM (United States)] [and others

1997-02-01T23:59:59.000Z

73

Neurotoxicity of depleted uranium  

Science Journals Connector (OSTI)

Depleted uranium (DU) is a byproduct of the enrichment process of uranium for its more radioactive isotopes to be ... neurotoxicity of DU. This review reports on uranium uses and its published health effects, wit...

George C. -T. Jiang; Michael Aschiner

2006-04-01T23:59:59.000Z

74

A concept of a nonfissile uranium hexafluoride overpack for storage, transport, and processing of corroded cylinders  

SciTech Connect

There is a need to develop a means of safely transporting breached 48-in. cylinders containing depleted uranium hexafluoride (UF{sub 6}) from current storage locations to locations where the contents can be safely removed. There is also a need to provide a method of safely and easily transporting degraded cylinders that no longer meet the US Department of Transportation (DOT) and American National Standards Institute, Inc., (ANSI) requirements for shipments of depleted UF{sub 6}. A study has shown that an overpack can be designed and fabricated to satisfy these needs. The envisioned overpack will handle cylinder models 48G, 48X, and 48Y and will also comply with the ANSI N14.1 and the American Society of Mechanical Engineers (ASME) Sect. 8 requirements.

Pope, R.B.; Cash, J.M. [Oak Ridge National Lab., TN (United States); Singletary, B.H. [Lockheed Martin Energy Systems, Oak Ridge, TN (United States)

1996-06-01T23:59:59.000Z

75

Axial cylinder internal combustion engine  

SciTech Connect

This patent describes improvement in a barrel type internal combustion engine including an engine block having axial-positioned cylinders with reciprocating pistons arranged in a circular pattern: a drive shaft concentrically positioned within the cylinder block having an offset portion extending outside the cylinder block; a wobble spider rotatably journaled to the offset portion; connecting rods for each cylinder connecting each piston to the wobble spider. The improvement comprising: a first sleeve bearing means supporting the drive shaft in the engine block in a cantilevered manner for radial loads; a second sleeve bearing means rotatably supporting the wobble spider on the offset portion of the drive shaft for radial loads; a first roller bearing means positioned between the offset portion of the drive shaft and the wobble spider carrying thrust loadings only; a second roller bearing means carrying thrust loads only reacting to the first roller bearing located on the opposite end of the driveshaft between the shaft and the engine block.

Gonzalez, C.

1992-03-10T23:59:59.000Z

76

Rubber Economy in Typewriter Cylinders  

Science Journals Connector (OSTI)

... rubber is vulcanized on the arbor, and then ground to the proper size and to roughen its surface so as to grip the paper firmly. With extensive use, the cylinders ...

1942-11-28T23:59:59.000Z

77

Safety and core design of large liquid-metal cooled fast breeder reactors  

E-Print Network (OSTI)

quantities of depleted uranium hexafluoride (DUF 6 ), known85 kg of enriched uranium hexafluoride (UF 6 ) and ?915 kg

Qvist, Staffan Alexander

2013-01-01T23:59:59.000Z

78

Characterization of options and their analysis requirements for the long-term management of depleted uranium hexafluoride  

SciTech Connect

The Department of Energy (DOE) is examining alternative strategies for the long-term management of depleted uranium hexafluoride (UF{sub 6}) currently stored at the gaseous diffusion plants at Portsmouth, Ohio, and Paducah, Kentucky, and on the Oak Ridge Reservation in Oak Ridge, Tennessee. This paper describes the methodology for the comprehensive and ongoing technical analysis of the options being considered. An overview of these options, along with several of the suboptions being considered, is presented. The long-term management strategy alternatives fall into three broad categories: use, storage, or disposal. Conversion of the depleted UF6 to another form such as oxide or metal is needed to implement most of these alternatives. Likewise, transportation of materials is an integral part of constructing the complete pathway between the current storage condition and ultimate disposition. The analysis of options includes development of pre-conceptual designs; estimates of effluents, wastes, and emissions; specification of resource requirements; and preliminary hazards assessments. The results of this analysis will assist DOE in selecting a strategy by providing the engineering information necessary to evaluate the environmental impacts and costs of implementing the management strategy alternatives.

Dubrin, J.W.; Rosen, R.S.; Zoller, J.N.; Harri, J.W.; Schwertz, N.L.

1995-12-01T23:59:59.000Z

79

Chemical aspects of cylinder corrosion and a scenario for hole development  

SciTech Connect

In June 1990, two cylinders in the depleted UF{sub 6} cylinder storage yards at Portsmouth were discovered to have holes in their walls at the valve-end stiffening ring at a point below the level of the gas-solid interface of the UF{sub 6}. The cylinder with the larger hole, which extended under the stiffening ring, was stacked in a top row 13 years ago. The cylinder with the smaller hole had been stacked in a bottom row 4 years ago. The lifting lugs of the adjacent cylinders pointed directly at the holes. A Cylinder Investigating Committee was appointed to determine the cause or causes of the holes and to assess the implications of these findings. This report contains a listing of the chemically related facts established by the Investigating Committee with the cooperation of the Operations and Technical Support Divisions at the Portsmouth Gaseous Diffusion Plant, the scenario developed to explain these findings and some implications of this scenario. In summary, the interrelated reactions of water, solid UF{sub 6} and iron presented by R. L. Ritter are used to develop a scenario which explains the observations and deductions made during the investigation. The chemical processes are intimately related to the course of the last three of the four stages of hole development. A simple model is proposed which permits semiquantitative prediction of such information as the HF loss rates as a function of time, the rate of hole enlargement, the time to hydrolyze a cylinder of UF{sub 6} and the approximate size of the hole. The scenario suggests that the environmental consequences associated with a developing hole in a depleted UF{sub 6} cylinder are minimal for the first several years but will become significant if too many years pass before detection. The overall environmental picture is presented in more detail elsewhere.

Barber, E.J. [Martin Marietta Energy Systems, Oak Ridge, TN (United States)

1991-12-31T23:59:59.000Z

80

A novel multiport cylinder dryer.  

SciTech Connect

A multiport dryer design concept that could create breakthroughs in the drying of pulp and paper is under development. The feasibility of this novel concept was demonstrated in a proof-of-concept test. Experiments were performed in a specially designed test apparatus to investigate the condensing heat-transfer characteristics of a single channel (representative of a multiport cylinder dryer) under typical operating conditions. The experimental results showed that multiport cylinder-dryer technology provides very high heat-transfer coefficients of 15,000 W/m{sup 2}{center_dot}K (2600 Btu/h{center_dot}ft{sup 2} {sup o}F) and a highly uniform distribution of cylinder-wall temperature. These experimental results suggest that a multiport cylinder dryer can increase the rate of paper drying compared with a conventional cylinder dryer. The increased dryer efficiency translates into either a reduction in the number of dryers at the same level of production or an increase in the rate of production with the same number of dryers.

Choi, S. U.; Yu, W.; France, D. M.; Wambsganss, M. W.; Energy Technology; Univ. of Illinois at Chicago

2001-02-01T23:59:59.000Z

Note: This page contains sample records for the topic "depleted uf6 cylinder" 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

Compressed Gas Cylinder Safe Handling, Use and  

E-Print Network (OSTI)

Compressed Gas Cylinder Safe Handling, Use and Storage 2012 Workplace Safety and Environmental Protection #12;i College/Unit: Workplace Safety and Environmental Protection Procedure Title: Compressed Gas................................................ 4 7 General Gas Cylinder Information

Saskatchewan, University of

82

Plunging cylinder liquid piston Stirling engine  

SciTech Connect

A Stirling engine is described comprising, in combination, cylinders having tops and open lower ends, tanks containing hot and cold fluid, with a means plunging the cylinders out of phase into the hot and cold fluid. There is at least one connecting tube providing a passage between the upper portions of the cylinders. A working gas provided in the upper portion of the cylinders and the connecting tube.

Tailer, P.L.; West, J.H.

1987-06-30T23:59:59.000Z

83

Depleted uranium management alternatives  

SciTech Connect

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

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

1994-08-01T23:59:59.000Z

84

Contact Us  

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

Contact Us Contact Us Contact Us Your comments, questions, and feedback about this web site and the Depleted UF6 Conversion EISs are welcomed. Please contact us with any questions or comments you may have about the Depleted UF6 Conversion EIS or the Depleted UF6 Management Program web site. Your questions or comments will be forwarded to the appropriate persons to answer or provide assistance. The purpose of this web site is to inform and involve the public in the Depleted UF6 Management Program, including the Depleted UF6 Conversion EIS process. We want it to meet your needs. Please feel free to make suggestions about additional features or services you would like to see on this web site, or ways you think we could improve the site. For general questions or comments about the Depleted UF6 Management Program web site or the Depleted UF6 Conversion EIS, contact us at: duf6webmaster@anl.gov.

85

Polyethylene Encapsulated Depleted Uranium  

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

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

86

Storage  

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

Storage Storage DUF6 Health Risks line line Accidents Storage Conversion Manufacturing Disposal Transportation Storage A discussion of depleted UF6 cylinder storage activities and associated risks. Management Activities for Cylinders in Storage The long-term management of the existing DUF6 storage cylinders and the continual effort to remediate and maintain the safe condition of the DUF6 storage cylinders will remain a Departmental responsibility for many years into the future. The day to day management of the DUF6 cylinders includes actions designed to cost effectively maintain and improve their storage conditions, such as: General storage cylinder and storage yard maintenance; Performing regular inspections of cylinders; Restacking and respacing the cylinders to improve drainage and to

87

Fire testing of bare uranium hexafluoride cylinders  

SciTech Connect

In 1965, the Oak Ridge Gaseous Diffusion Plant (ORGDP), now the K-25 Site, conducted a series of tests in which bare cylinders of uranium hexafluoride (UF{sub 6}) were exposed to engulfing oil fires for the US Atomic Energy Commission (AEC), now the US Department of Energy (DOE). The tests are described and the results, conclusions, and observations are presented. Two each of the following types of cylinders were tested: 3.5-in.-diam {times} 7.5-in.-long cylinders of Monel (Harshaw), 5.0-in.-diam {times} 30-in.-long cylinders of Monel, and 8-in.-diam {times} 48-in.-long cylinders of nickel. The cylinders were filled approximately to the standard UF{sub 6} fill limits of 5, 55, and 250 lb, respectively, with a U-235 content of 0.22%. The 5-in.- and 8-in.-diam cylinders were tested individually with and without their metal valve covers. For the 3.5-in.-diam Harshaw cylinders and the 5.0-in.-diam cylinder without a valve cover the valves failed and UF{sub 6} was released. The remaining cylinders ruptured explosively in time intervals ranging from about 8.5 to 11 min.

Pryor, W.A. [PAI Corp., Oak Rige, TN (United States)

1991-12-31T23:59:59.000Z

88

Fire testing of bare uranium hexafluoride cylinders  

SciTech Connect

In 1965, the Oak Ridge Gaseous Diffusion Plant (ORGDP), now the K-25 Site, conducted a series of tests in which bare cylinders of uranium hexafluoride (UF{sub 6}) were exposed to engulfing oil fires for the US Atomic Energy Commission (AEC), now the US Department of Energy (DOE). The tests are described and the results, conclusions, and observations are presented. Two each of the following types of cylinders were tested: 3.5-in.-diam {times} 7.5-in.-long cylinders of Monel (Harshaw), 5.0-in.-diam {times} x 30-in.-long cylinders of Monel, and 8-in.-diam {times} 48-in.-long cylinders of nickel. The cylinders were filled approximately to the standard UF{sub 6} fill limits of 5, 55, and 250 lb, respectively, with a U-235 content of 0.22%. The 5-in.- and 8-in.-diam cylinders were tested individually with and without their metal valve covers. For the 3.5-in.-diam Harshaw cylinders and the 5.0-in.-diam cylinder without a valve cover, the valves failed and UF{sub 6} was released. The remaining 6 cylinders ruptured explosively in time intervals ranging from about 8.5 to 11 min.

Pryor, W.A. [PAI Corp., Oak Ridge, TN (United States)

1991-12-31T23:59:59.000Z

89

Depleted Uranium Hexafluoride Management  

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

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

90

Ozone Depletion and Global Warming.  

E-Print Network (OSTI)

??Abstract This thesis examines global warming and the possible contribution that ozone depletion provides to this warming. An examination is performed to determine the extent… (more)

Fow, Alista John

2006-01-01T23:59:59.000Z

91

Corrosion monitoring in the UF{sub 6} cylinder yards at the Oak Ridge K-25 Site: FY 1994 report  

SciTech Connect

Depleted uranium hexafluoride (UF{sub 6}) at the U.S. Department of Energy`s K-25 Site at Oak Ridge, Tennessee, has been stored in large steel cylinders that have undergone significant atmospheric corrosion damage over the last 35 years. A detailed experimental program to characterize the corrosion damage was initiated in 1992. Large amounts of corrosion scale and deep pits are found to cover UF{sub 6} cylinder surfaces. Ultrasonic wall thickness measurements have shown uniform corrosion losses up to 20 mils (0.5 mm) and pits up to 100 mils (2.5 mm) deep. Electrical resistance corrosion probes, TOW sensors, and thermocouples have been attached to cylinder bodies. Atmospheric conditions are monitored using rain gauges, relative humidity sensors, and thermocouples. Long-term (16-year) data are being obtained from mild steel corrosion coupons on test racks as well as attached directly to cylinder surfaces. Corrosion rates have been found to be intimately related to the times-of-wetness, both tending to be higher on cylinder tops due to apparent sheltering effects. Data from the various tests are compared, discrepancies are discussed, and a pattern of cylinder corrosion as a function of cylinder position and location is described.

Rao, M. [Midwest Technical Inc., Oak Ridge, TN (United States); Adamski, R.; Broders, J.; Ellis, A.; Freels, D.; Kelley, D.; Phillips, B. [Oak Ridge K-25 Site, TN (United States)

1994-10-01T23:59:59.000Z

92

A new cylinder cooling system using oil  

SciTech Connect

The design of engine cylinders must satisfy two conflicting requirements, good cooling performance and ease of manufacture. A cooling system was designed to permit the circulation of engine lubricating oil as a coolant at high speed through grooves provided on the external periphery of the cylinder liner. Testing in an actual operating engine confirmed that this cooling system design not only provides better heat transfer and higher cooling performance but also simplifies the manufacturing of the cylinder since external cooling fins are not required. In this paper, the authors will discuss the cylinder cooling effect of the new cylinder cooling system, referring mainly to the test results of a single-cylinder motorcycle engine with lubricating oil from the crankcase used as the coolant.

Harashina, Kenichi; Murata, Katsuhiro; Satoh, Hiroshi; Shimizu, Yasuo; Hamamura, Masahiro

1995-12-31T23:59:59.000Z

93

Cylinder valve packing nut studies  

SciTech Connect

The design, manufacture, and use of cylinder valve packing nuts have been studied to improve their resistance to failure from stress corrosion cracking. Stress frozen photoelastic models have been analyzed to measure the stress concentrations at observed points of failure. The load effects induced by assembly torque and thermal expansion of stem packing were observed by strain gaging nuts. The effects of finishing operations and heat treatment were studied by the strain gage hole boring and X-ray methods. Modifications of manufacturing and operation practices are reducing the frequency of stress corrosion failures.

Blue, S.C. [Martin Marietta Energy Systems, Inc., Paducah, KY (United States)

1991-12-31T23:59:59.000Z

94

Interactions of solitary waves with cylinder arrays  

SciTech Connect

This paper addresses a numerical investigation of solitary waves interactions with an array of multiple surface-piercing vertical cylinders and the corresponding nonlinear hydrodynamic loads on each individual cylinder. The theoretical model adopted for simulation is the generalized Boussinesq two-equation model. The boundary-fitted coordinate transformation and multiple-grid technique are utilized here to simplify the computational domain and to facilitate the applications of the boundary conditions on the cylinder surfaces. The scattered wave field and the hydrodynamic forces on each cylinder during wave impact are numerically evaluated. Study of sheltering effect by the neighboring structures on wave loads is conducted. It is found that the presence of the neighboring cylinders has shown significantly influence on the wave loads and the scattering of the primary incident waves. For a tandem two cylinders, the shielding effect plays an important role to reduce the force acting on the rear cylinder. For transversely arranged two cylinders, the in-line force distribution is mostly independent of the gap distance between cylinders. However, the transverse force coefficient increases as the separation distance decreases.

Wang, K.H.; Jiang, L. [Univ. of Houston, TX (United States). Dept. of Civil and Environmental Engineering

1994-12-31T23:59:59.000Z

95

Overseas shipments of 48Y cylinders  

SciTech Connect

This paper describes experiences with two incidents of overseas shipments of uranium hexafluoride (UF{sub 6}) cylinders. The first incident involved nine empty UF{sub 6} cylinders in enclosed sea containers. Three UF{sub 6} cylinders broke free from their tie-downs and damaged and contaminated several sea containers. This paper describes briefly how decontamination was carried out. The second incident involved a shipment of 14 full UF{sub 6} cylinders. Although the incident did not cause an accident, the potential hazard was significant. The investigation of the cause of the near accident is recounted. Recommendations to alleviate future similar incidents for both cases are presented.

Tanaka, R.T.; Furlan, A.S. [Cameco Corp., Port Hope, Ontario (Canada)

1991-12-31T23:59:59.000Z

96

Fire exposure of empty 30B cylinders  

SciTech Connect

Cylinders for UF{sub 6} handling, transport, and storage are designed and built as unfired pressure vessels under ASME Boiler and Pressure Vessel Code criteria and standards. They are normally filled and emptied while UF{sub 6} is in its liquid phase. Transport cylinders such as the Model 30B are designed for service at 200 psi and 250{degrees}F, to sustain the process conditions which prevail during filling or emptying operations. While in transport, however, at ambient temperature the UF{sub 6} is solid, and the cylinder interior is well below atmospheric pressure. When the cylinders contain isotopically enriched product (above 1.0 percent U-235), they are transported in protective overpacks which function to guard the cylinders and their contents against thermal or mechanical damage in the event of possible transport accidents. Two bare Model 30B cylinders were accidentally exposed to a storage warehouse fire in which a considerable amount of damage was sustained by stored materials and the building structure, as well as by the cylinder valves and valve protectors. The cylinders were about six years old, and had been cleaned, inspected, hydrotested, and re-certified for service, but were still empty at the time of the fire. The privately-owned cylinders were transferred to DOE for testing and evaluation of the fire damage.

Ziehlke, K.T. [MJB Technical Associates, Inc., Knoxville, TN (United States)

1991-12-31T23:59:59.000Z

97

Compressed Gas Cylinder Safety I. Background. Due to the nature  

E-Print Network (OSTI)

Compressed Gas Cylinder Safety I. Background. Due to the nature of gas cylinders hazards of a ruptured cylinder. There are almost 200 different types of materials in gas cylinders, there are several general procedures to follow for safe storage and handling of a compressed gas cylinder: II

Suzuki, Masatsugu

98

Miller wins Early Career Award  

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

the area of advanced detection systems for nondestructive assay of uranium enrichment in uranium hexafluoride (UF6) cylinders. A 2010 Science magazine article featured the first...

99

U.S. Department of Energy Portsmouth/Paducah Project Office  

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

steam generation boilers with several smaller, more efficient steam boilers; transfer of uranium hexafluoride (UF 6 ) to compliant cylinders; treatment of cells to remove...

100

Natural Gas Vehicle Cylinder Safety, Training and Inspection...  

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

Natural Gas Vehicle Cylinder Safety, Training and Inspection Project Natural Gas Vehicle Cylinder Safety, Training and Inspection Project Presentation from the U.S. DOE Office of...

Note: This page contains sample records for the topic "depleted uf6 cylinder" 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

Assessment of exposure to depleted uranium  

Science Journals Connector (OSTI)

......Article Assessment of exposure to depleted uranium P. Roth V. Hollriegl E. Werner...for determining the amount of depleted uranium (DU) incorporated. The problems...Assessment of exposure to depleted uranium. | In most circumstances......

P. Roth; V. Höllriegl; E. Werner; P. Schramel

2003-07-01T23:59:59.000Z

102

Parabolic cylinder functions implemented in Matlab  

E-Print Network (OSTI)

Routines for computation of Weber's parabolic cylinder functions and their derivatives are implemented in Matlab for both moderate and great values of the argument. Standard, real solutions are considered. Tables of values are included.

E. Cojocaru

2009-01-15T23:59:59.000Z

103

Fully depleted back illuminated CCD  

DOE Patents (OSTI)

A backside illuminated charge coupled device (CCD) is formed of a relatively thick high resistivity photon sensitive silicon substrate, with frontside electronic circuitry, and an optically transparent backside ohmic contact for applying a backside voltage which is at least sufficient to substantially fully deplete the substrate. A greater bias voltage which overdepletes the substrate may also be applied. One way of applying the bias voltage to the substrate is by physically connecting the voltage source to the ohmic contact. An alternate way of applying the bias voltage to the substrate is to physically connect the voltage source to the frontside of the substrate, at a point outside the depletion region. Thus both frontside and backside contacts can be used for backside biasing to fully deplete the substrate. Also, high resistivity gaps around the CCD channels and electrically floating channel stop regions can be provided in the CCD array around the CCD channels. The CCD array forms an imaging sensor useful in astronomy.

Holland, Stephen Edward (Hercules, CA)

2001-01-01T23:59:59.000Z

104

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

SciTech Connect

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

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

1997-09-01T23:59:59.000Z

105

Shape from Contour: Straight Homogeneous Generalized Cylinders and Constant Cross Section Generalized Cylinders  

Science Journals Connector (OSTI)

Abstract¿ We analyze the properties of Straight Homogeneous Generalized Cylinders (SHGCs) and Constant Cross Section Generalized Cylinders (CGCs), and derive the types of symmetries that the limb boundaries and cross sections of these objects produce ... Keywords: Shape from contour, staright homogeneous generalized cones, constant cross section generalized cones, symmetry analysis, shape constraints.

Faith Ulupinar; Ramakant Nevatia

1995-02-01T23:59:59.000Z

106

UF{sub 6} cylinder fire test  

SciTech Connect

With the increasing number of nuclear reactors for power generation, there is a comparable increase in the amount of UF{sub 6} being transported. Likewise, the probability of having an accident involving UF{sub 6}-filled cylinders also increases. Accident scenarios which have been difficult to assess are those involving a filled UF{sub 6} cylinder subjected to fire. A study is underway at the Oak Ridge K-25 Site, as part of the US DOE Enrichment Program, to provide empirical data and a computer model that can be used to evaluate various cylinder-in-fire scenarios. It is expected that the results will provide information leading to better handling of possible fire accidents as well as show whether changes should be made to provide different physical protection during shipment. The computer model being developed will be capable of predicting the rupture of various cylinder sizes and designs as well as the amount of UF{sub 6}, its distribution in the cylinder, and the conditions of the fire.

Park, S.H. [Oak Ridge K-25 Site, Oak Ridge, TN (United States)

1991-12-31T23:59:59.000Z

107

UF{sub 6} cylinder inspections at PGDP  

SciTech Connect

Routine inspections of all UF{sub 6} cylinders at the Paducah Gaseous Diffusion Plant have been mandated by the Department of Energy. A specific UF{sub 6} cylinder inspection procedure for what items to inspect and training for the operators prior to inspection duty are described. The layout of the cylinder yards and the forms used in the inspections are shown. The large number of cylinders (>30,000) to inspect and the schedule for completion on the mandated time table are discussed. Results of the inspections and the actions to correct the deficiencies are explained. Future inspections and movement of cylinders for relocation of certain cylinder yards are defined.

Lamb, G.W.; Whinnery, W.N. [Martin Marietta Energy Systems, Inc., Paducah, KY (United States)

1991-12-31T23:59:59.000Z

108

Potential Uses of Depleted Uranium  

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

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

109

Natural convection heat transfer from two horizontal cylinders  

SciTech Connect

Natural convection heat transfer from a single horizontal cylinder and a pair of vertically aligned horizontal cylinders is investigated. Surface heat transfer distributions around the circumference of the cylinders are presented for Rayleigh numbers of 2 x 10{sup 6}, 4 x 10{sup 6} and 6 x 10{sup 6} and a range of cylinder spacings of 1.5, 2 and 3 diameters. With a cylinder pairing the lower cylinder is unaffected by the presence of the second cylinder; the same is true of the upper cylinder if the lower one is not heated. However, when both cylinders are heated it has been found that a plume rising from the heated lower cylinder interacts with the upper cylinder and significantly affects the surface heat transfer distribution. Spectral analysis of surface heat transfer signals has established the influence of the plume oscillations on the heat transfer. Thus, when the plume from the lower cylinder oscillates out of phase with the flow around the upper cylinder it increases the mixing and results in enhanced heat transfer. (author)

Reymond, Olivier; Murray, Darina B. [Department of Mechanical and Manufacturing Engineering, Trinity College Dublin (Ireland); O'Donovan, Tadhg S. [School of Engineering and Physical Sciences, Heriot-Watt University, Nasmyth Building, Edinburgh EH14 4AS (United Kingdom)

2008-09-15T23:59:59.000Z

110

Defect Analysis of Vehicle Compressed Natural Gas Composite Cylinder  

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

Defect Analysis of Vehicle Defect Analysis of Vehicle Compressed Natural Gas Composite Cylinder A China Paper on Type 4 Cylinder, translated and presented by J. P. Hsu, PhD, Smart Chemistry Reason for Defect Analysis of CNG Composite Cylinder * Safety Issue - Four explosion accidents of auto used CNG composite material cylinders resulting huge personnel and vehicles loss. * Low Compliance Rate - Inspect 12119 Auto used CNG composite cylinders and only 3868 are qualified with compliance rate of 32%. Plastic CNG Composite Cylinder Process Fitting Internal Plastic Liner External Composite Layer Metal Fitting HDPE Cylinder Liner * HDPE has a high density, great stiffness, good anti-permeability and high melting point, but poor environmental stress cracking Resistance (ESCR). * The defects of cylinder liner quality can be

111

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

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

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

112

Degen generalized cylinders and their properties  

Science Journals Connector (OSTI)

Generalized cylinder (GC) has played an important role in computer vision since it was introduced in the 1970s. While studying GC models in human visual perception of shapes from contours, Marr assumed that GC's limbs are planar curves. Later, Koenderink ...

Liangliang Cao; Jianzhuang Liu; Xiaoou Tang

2006-05-01T23:59:59.000Z

113

Physics of Fully Depleted CCDs  

E-Print Network (OSTI)

In this work we present simple, physics-based models for two effects that have been noted in the fully depleted CCDs that are presently used in the Dark Energy Survey Camera. The first effect is the observation that the point-spread function increases slightly with the signal level. This is explained by considering the effect on charge-carrier diffusion due to the reduction in the magnitude of the channel potential as collected signal charge acts to partially neutralize the fixed charge in the depleted channel. The resulting reduced voltage drop across the carrier drift region decreases the vertical electric field and increases the carrier transit time. The second effect is the observation of low-level, concentric ring patterns seen in uniformly illuminated images. This effect is shown to be most likely due to lateral deflection of charge during the transit of the photogenerated carriers to the potential wells as a result of lateral electric fields. The lateral fields are a result of space charge in the fully...

Holland, S E; Kolbe, W F; Lee, J S

2014-01-01T23:59:59.000Z

114

Solitary wave scattering by a vertical cylinder: Experimental study  

SciTech Connect

The nonlinear interaction of a solitary wave and a vertical circular cylinder is examined. The wave field was measured at various locations near the cylinder and the detailed process of wave reflection, diffraction and scattering is discussed. The formation of the first and second scattered wave is observed as the incident wave first encounters the cylinder and as it leaves the cylinder respectively. Comparisons are made to the generalized Boussinesq (gB) model which is found to give quite good results for the wave heights except very close to the cylinder surface and in the immediate wake region behind the cylinder. The net force on the cylinder in the direction of incident wave propagation was measured as a function of time, and good agreement with the gB model is obtained.

Yates, G.T. [Univ. of Hong Kong (Hong Kong); Wang, K.H. [Univ. of Houston, TX (United States)

1994-12-31T23:59:59.000Z

115

Radiation levels on empty cylinders containing heel material  

SciTech Connect

Empty UF{sub 6} cylinders containing heel material were found to emit radiation levels in excess of 200 mr/hr, the maximum amount stated in ORO-651. The radiation levels were as high as 335 mr/hr for thick wall (48X and 48Y) cylinders and 1050 mr/hr for thin wall (48G and 48H) cylinders. The high readings were found only on the bottom of the cylinders. These radiation levels exceeded the maximum levels established in DOT 49 CFR, Part 173.441 for shipment of cylinders. Holding periods of four weeks for thick-wall cylinders and ten weeks for thin-wall cylinders were established to allow the radiation levels to decay prior to shipment.

Shockley, C.W. [Martin Marietta Energy Systems, Inc., Paducah, KY (United States)

1991-12-31T23:59:59.000Z

116

Alternative Fuels Data Center: CNG Fuel System and Cylinder Maintenance  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

CNG Fuel System and CNG Fuel System and Cylinder Maintenance to someone by E-mail Share Alternative Fuels Data Center: CNG Fuel System and Cylinder Maintenance on Facebook Tweet about Alternative Fuels Data Center: CNG Fuel System and Cylinder Maintenance on Twitter Bookmark Alternative Fuels Data Center: CNG Fuel System and Cylinder Maintenance on Google Bookmark Alternative Fuels Data Center: CNG Fuel System and Cylinder Maintenance on Delicious Rank Alternative Fuels Data Center: CNG Fuel System and Cylinder Maintenance on Digg Find More places to share Alternative Fuels Data Center: CNG Fuel System and Cylinder Maintenance on AddThis.com... More in this section... Natural Gas Basics Benefits & Considerations Stations Vehicles Availability Conversions Emissions Maintenance & Safety

117

Paramagnetic Reentrance Effect in NS Proximity Cylinders  

E-Print Network (OSTI)

A scenario for the unusual paramagnetic reentrance behavior at ultra-low temperatures in Nb-Ag, Nb-Au, and Nb-Cu cylinders is presented. For the diamagnetic response down to temperatures of the order 15 mK, the standard theory (quasi-classical approximation) for superconductors appears to work very well, assuming that Ag, Au, and Cu remain in the normal state except for the proximity-induced superconductivity. Here it is proposed that these noble metals may become p-wave superconductors with a transition temperature of order 10 mK. Below this temperature, p-wave triplet superconductivity emerges around the periphery of the cylinder. The diamagnetic current flowing in the periphery is compensated by a quantized paramagnetic current in the opposite direction, thus providing a simple explanation for the observed increase in the susceptibility at ultra-low temperatures. In 1990 Visani et al. [1] reported a surprising paramagnetic reentrance phenomenon at ultra-low temperatures. When a Nb cylinder of diameter ? 20-100 µm, covered with a

Kazumi Maki; Stephan Haas

2008-01-01T23:59:59.000Z

118

Depleted Argon from Underground Sources  

SciTech Connect

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

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

2011-04-27T23:59:59.000Z

119

Vehicle Technologies Office: Fact #643: October 4, 2010 Four Cylinder  

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

3: October 4, 3: October 4, 2010 Four Cylinder Engine Installations Continue to Rise to someone by E-mail Share Vehicle Technologies Office: Fact #643: October 4, 2010 Four Cylinder Engine Installations Continue to Rise on Facebook Tweet about Vehicle Technologies Office: Fact #643: October 4, 2010 Four Cylinder Engine Installations Continue to Rise on Twitter Bookmark Vehicle Technologies Office: Fact #643: October 4, 2010 Four Cylinder Engine Installations Continue to Rise on Google Bookmark Vehicle Technologies Office: Fact #643: October 4, 2010 Four Cylinder Engine Installations Continue to Rise on Delicious Rank Vehicle Technologies Office: Fact #643: October 4, 2010 Four Cylinder Engine Installations Continue to Rise on Digg Find More places to share Vehicle Technologies Office: Fact #643:

120

New Findings Allay Concerns Over Depleted Uranium  

Science Journals Connector (OSTI)

...poses virtually no cancer risk. Moreover, Danesi's...VISAR KRYEZIU/AP Depleted uranium is what's left...the munitions to cancer cases, particularly...VISAR KRYEZIU/AP Depleted uranium is what's left...the munitions to cancer cases, particularly...

Richard Stone

2002-09-13T23:59:59.000Z

Note: This page contains sample records for the topic "depleted uf6 cylinder" 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

New Findings Allay Concerns Over Depleted Uranium  

Science Journals Connector (OSTI)

...least some of the uranium had been irradiated...not represent a health threat,” says Danesi...VISAR KRYEZIU/AP Depleted uranium is what's left...not represent a health threat, says...VISAR KRYEZIU/AP Depleted uranium is what's left...

Richard Stone

2002-09-13T23:59:59.000Z

122

Depleted argon from underground sources  

SciTech Connect

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

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

2011-09-01T23:59:59.000Z

123

Safety analysis of in-use vehicle wrapping cylinder  

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

The focus of this presentation is on the security analysis for wrapped cylinders used in vehicles and analyzing safety conditions and environmental effects through testing.

124

Tunable capillary-induced attraction between vertical cylinders  

E-Print Network (OSTI)

Deformation of a fluid interface caused by the presence of objects at the interface can lead to large lateral forces between the objects. We explore these fluid-mediated attractive force between partially submerged vertical cylinders. Forces are experimentally measured by slowly separating cylinder pairs and cylinder triplets after capillary rise is initially established for cylinders in contact. For cylinder pairs, numerical computations and a theoretical model are found to be in good agreement with measurements. The model provides insight into the relative importance of the contributions to the total force. For small separations, the pressure term dominates, while at large separations, surface tension becomes more important. A cross-over between the two regimes occurs at a separation of around half of a capillary length. The experimentally measured forces between cylinder triplets are also in good agreement with numerical computations, and we show that pair-wise contributions account for nearly all of the attractive force between triplets. For cylinders with equilibrium capillary rise height greater than the height of the cylinder, we find that the attractive force depends on the height of the cylinders above the submersion level, which provides a means to create precisely-controlled tunable cohesive forces between objects deforming a fluid interface.

Jennifer M. Rieser; P. E. Arratia; A. G. Yodh; J. P. Gollub; D. J. Durian

2014-12-02T23:59:59.000Z

125

UF{sub 6} pressure excursions during cylinder heating  

SciTech Connect

As liquid UF{sub 6} inside a cylinder changes from a liquid to a solid, it forms a porous solid which occupies approximately the same volume as that of the liquid before cooling. Simultaneously as the liquid cools, UF{sub 6} vapor in the cylinder ullage above the liquid desublimes on the upper region of the inner cylinder wall. This solid is a dense, glass-like material which can accumulate to a significant thickness. The thickness of the solid coating on the upper cylinder wall and directly behind the cylinder valve area will vary depending on the conditions during the cooling stage. The amount of time lapsed between UF{sub 6} solidification and UF{sub 6} liquefaction can also affect the UF{sub 6} coating. This is due to the daily ambient heat cycle causing the coating to sublime from the cylinder wall to cooler areas, thus decreasing the thickness. Structural weakening of the dense UF{sub 6} layer also occurs due to cylinder transport vibration and thermal expansion. During cylinder heating, the UF{sub 6} nearest the cylinder wall will liquefy first. As the solid coating behind the cylinder valve begins to liquefy, it results in increased pressure depending upon the available volume for expansion. At the Paducah Gaseous Diffusion Plant (PGDP) during the liquefaction of the UF{sub 6} in cylinders in the UF{sub 6} feed and sampling autoclaves, this pressure increase has resulted in the activation of the systems rupture discs which are rated at 100 pounds per square inch differential.

Brown, P.G. [Martin Marietta Energy Systems, Inc., Paducah, KY (United States)

1991-12-31T23:59:59.000Z

126

Modeling Cylinder Valve in Hydrogen Fuel Cell Car  

Science Journals Connector (OSTI)

We develop a fast alternative to a complex finite element analysis (FEA) model of cylinder valve in hydrogen fuel cell car based on support vector machine (SVM). The inputs of model are shape parameters of core and plunger of the valve, and the output ... Keywords: modeling, cylinder valve, SVM, uniform design

Liang Yu; Shengnian Cai; Wang Na

2011-03-01T23:59:59.000Z

127

Artificial Neural Nets and Cylinder Pressures in Diesel  

E-Print Network (OSTI)

Artificial Neural Nets and Cylinder Pressures in Diesel Engine Fault Diagnosis * Gopi O diagnosis system for a diesel engine, which uses artificial neural nets to identify faults on the basis­temporal representation of cylinder pressures. Draw cards and power cards are regularly assessed for the condition

Sharkey, Amanda

128

Statistics on cylinder wear in marine diesel engines  

Science Journals Connector (OSTI)

A description of the United Steamship Company's efforts to elucidate statistically the problems in connection with cylinder wear in marine diesel engines, by the use of punched cards and electronic digital computers. Further, some hypotheses concerning the causes of cylinder wear and the way to overcome it are given.

H.D. Lees

1959-01-01T23:59:59.000Z

129

Technical section: A potential-based generalized cylinder representation  

Science Journals Connector (OSTI)

Generalized cylinder (GC) is a class of parametric shapes that is very flexible and capable of modeling many different types of real-world objects, and have subsequently been the focus of considerable research in the vision community. Most of the related ... Keywords: 3D Shape representation, Generalized cylinder, Potential field

Jen-Hui Chuang; Narendra Ahuja; Chien-Chou Lin; Chi-Hao Tsai; Cheng-Hui Chen

2004-12-01T23:59:59.000Z

130

Technical basis for flawed cylinder test specification to assure adequate fracture resistance of ISO high strength steel cylinder  

SciTech Connect

High pressure industrial gases (such as oxygen, nitrogen, argon, hydrogen, etc.) are stored and transported in portable cylinders. ISO TC58 SC3 has developed a draft specification 9809 for design and fabrication of high pressure cylinders with maximum tensile strength limitation of 1,100 N/mm{sup 2}. In order to extend the ISO 9809 rules for higher than 1,100 N/mm{sup 2} strength level cylinders, a working group WG14 was formed in 1989 to develop new rules to assure adequate fracture resistance. In 1994, WG14 recommended a simple, but unique flawed cylinder test method for design qualification of the cylinder and acceptance criteria to assure adequate fracture resistance. WG14 also recommended Charpy-V-Notch impact tests to control the required fracture resistance on production cylinders. This paper presents the technical basis that was employed in developing the flawed cylinder test method and acceptance criteria. The specification was developed for seamless steel cylinders having actual strength in the range of 1,100 to 1,400 N/mm{sup 2} and cylindrical section wall thickness in the range of 3mm to 10mm. Flawed cylinder tests were conducted on several hundred cylinders of varying sizes and strength levels. The specification requires to demonstrate LEAK-BEFORE-BREAK performance of the cylinder having flaw length equal to 1.6(O.D. {times} t{sub design}){sup 0.5} at failure pressure = (t{sub design}/t{sub actual}) {times} Design Pressure.

Rana, M.D. [Praxair, Inc., Tonawanda, NY (United States). Process and Systems R and D; Smith, J.H. [National Inst. of Standards and Technology, Gaithersburg, MD (United States). Metallurgy Div.; Tribolet, R.O.

1996-12-01T23:59:59.000Z

131

Technical basis for flawed cylinder test specification to assure adequate fracture resistance of ISO high-strength steel cylinder  

SciTech Connect

High-pressure industrial gases (such as oxygen, nitrogen, argon, hydrogen, etc.) are stored and transported in portable cylinders. ISO TC58 SC3 has developed a draft specification 9809 for design and fabrication of high-pressure cylinders with maximum tensile strength limitation of 1,100 N/mm{sup 2}. In order to extend the ISO 9809 rules for higher than 1,100 N/mm{sup 2} strength level cylinders, a working group WG14 was formed in 1989 to develop new rules to assure adequate fracture resistance. In 1994, WG14 recommended a simple, but unique flawed cylinder test method for design qualification of the cylinder and acceptance criteria to assure adequate fracture resistance. WG14 also recommended Charpy-V-notch impact tests to control the required fracture resistance on production cylinders. This paper presents the technical basis that was employed in developing the flawed cylinder test method and acceptance criteria. The specification was developed for seamless steel cylinders having actual strength in the range of 1,100 to 1,400 N/mm{sup 2} and cylindrical section wall thickness in the range of 3 to 10 mm. Flawed cylinder tests were conducted on several hundred cylinders of varying sizes and strength levels. The specification requires to demonstrate LEAK-BEFORE-BREAK performance of the cylinder having flaw length equal to 1.6 (o.d. {times} t{sub design}){sup 0.5} at failure pressure = (t{sub design}/t{sub actual}) x Design Pressure.

Rana, M.D. [Praxair, Inc., Tonawanda, NY (United States); Smith, J.H. [National Inst. of Standards and Technology, Gaithersburg, MD (United States). Metallurgy Div.; Tribolet, R.O. [Tribolet (R.O.), Van Wert, OH (United States)

1997-11-01T23:59:59.000Z

132

Depleted uranium exposure and health effects in Gulf War veterans  

Science Journals Connector (OSTI)

...2006 research-article Depleted uranium exposure and health effects in Gulf War...Medicine) Gulf War and health. In Depleted uranium, pyridostigmine bromide...McDiarmid, M.A , Health effects of depleted uranium on exposed Gulf War...

2006-01-01T23:59:59.000Z

133

Excretion of depleted uranium by Gulf war veterans  

Science Journals Connector (OSTI)

......Dosimetry Article Excretion of depleted uranium by Gulf war veterans R. E...personnel had potential intakes of depleted uranium (DU), including shrapnel...excretion rate. Excretion of depleted uranium by Gulf War veterans. | During......

R. E. Toohey

2003-07-01T23:59:59.000Z

134

Depleted uranium - induced malignant transformation in human lung epithelial cells.  

Science Journals Connector (OSTI)

...Washington, DC Abstract 3590: Depleted uranium-induced leukemia: Epigenetic...with leukemia development. Depleted uranium is used in military missions...Karvelisse Miller, Max Costa. Depleted uranium-induced leukemia: Epigenetic...

Aldona A. Karaczyn; Hong Xie; and John P. Wise

2006-04-15T23:59:59.000Z

135

Flow visualization around cylinders in a channel flow using Particle Image Velocimetry  

E-Print Network (OSTI)

The objective of the undertaken study was to apply state-of the-art Particle Image Velocimetry to measure full field turbulent flow around cylinders, starting with one cylinder and eventually to a quad cylinder arrangement. Particle Image...

Martinez, Ramiro Serna

2012-06-07T23:59:59.000Z

136

Fact #643: October 4, 2010 Four Cylinder Engine Installations Continue to Rise  

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

The share of 4 cylinder engines installed in light vehicles has been increasing since 2004. Beginning in 2006, cars have shown an increase in 4 cylinder engine installations while 8 cylinder engine...

137

SRP Scientific Meeting: Depleted Uranium  

Science Journals Connector (OSTI)

London, January 2002 The meeting was organised by the SRP to review current research and discuss the use, dispersion into the environment and radiological impact of depleted uranium (DU) by the UK and US in recent military conflicts. Brian Spratt chaired the morning session of the meeting and stressed the need to gauge the actual risks involved in using DU and to balance professional opinions with public mistrust of scientists and government bodies. He asked whether more could be done by the radiation protection profession to improve communication with the media, pressure groups and the public in general. Ron Brown, of the MOD Dstl Radiological Protection Services, gave a thorough overview of the origins and properties of DU, focusing on munitions, in the UK and abroad and public concerns arising from its use in the 1991 Gulf War. He gave a brief overview of past DU munitions studies by the UK and US governments and contrasted this with the lack of hard data used to back up claims made by pressure groups. He compared the known risks of DU with other battlefield risks, e.g. biological agents, chemical attacks and vaccines, and questioned whether peacetime dose limits should apply to soldiers on the battlefield. Barry Smith, of the British Geological Survey, spoke on DU transport, pathways and exposure routes focusing on groundwater as an important example in the Former Yugoslav Republic of Kosovo. He discussed the large amount of work that has already been done on natural uranium in groundwater, with particular emphasis on its mobility within the soil and rock profile being strongly dependent on precipitation and the local geochemical conditions. Therefore, generic risk assessments will not be sufficient in gauging risks to local populations after the introduction of DU into their environment; local geochemical conditions must be taken into account. However, experiments are required to fully appreciate the extent to which DU, particularly DU:Ti alloys used in munitions, disperses into the environment in a variety of soil types. Barry outlined recent computer modelling work investigating the time taken for DU to migrate from a buried munition to a borehole in three different scenarios. The modelling revealed times from 30 years to 5 ? 109 years depending on the local geochemical environment and the depth of the DU penetrator in the soil profile. This suggests the real possibility of borehole contamination within a human lifetime in wet conditions similar to those found in Kosovo. Nick Priest, of Middlesex University, discussed methods of biological monitoring for natural and depleted uranium. The preferred method of detection is by 24 h urine sampling, with measurement of the total mass or isotopic ratios of uranium using mass spectroscopy (ICPMS). This is because uranium is only deposited in new areas of bone growth, a slow process in healthy adults, the remainder is filtered by the kidneys and excreted in urine, giving a non-invasive and rapid sample collection method. Nick also described a rapid assessment technique to look for total uranium and DU in a sample, using a multi-collector ICPMS, specifically looking at the 235U:238U ratio with 236U as a tracer to determine the total mass of uranium present and its source. The MC-ICPMS method was applied in a BBC Scotland funded study of uptakes of uranium in three populations in the Balkans during March 2001. Variable levels of DU were found in each population. The age of the subject was found to influence the excretion of natural uranium and DU to the same degree, increasing age leading to increased excretion. Overall, the levels of DU were extremely small (tens of µg), but DU was found to be present in each population investigated. The MC-ICPMS method is capable of detecting  1% DU in natural uranium and Nick intends to extend the study to include ground and drinking water samples and food in the same populations. Neil Stradling gave a talk on the contribution of the NRPB to the WHO report on DU published in April 2001. It addressed the biokinetics of inhaled uranium

David Kestell

2002-01-01T23:59:59.000Z

138

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

139

Assessment of exposure to depleted uranium  

Science Journals Connector (OSTI)

......ingestion of natural uranium in food and drink, and...for the measurement of uranium in urine samples, DU...respect to potential health hazards can be detected...Assessment of exposure to depleted uranium. | In most circumstances......

P. Roth; V. Höllriegl; E. Werner; P. Schramel

2003-07-01T23:59:59.000Z

140

Polyethylene Encapsulation of Depleted Uranium Trioxide  

Science Journals Connector (OSTI)

Depleted uranium, in the form of uranium trioxide (UO3) powder, was encapsulated in molten polyethylene forming a stable, dense composite henceforth known as DUPoly (patent pending). Materials were fed by calibra...

J. W. Adams; P. R. Lageraaen; P. D. Kalb…

2002-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "depleted uf6 cylinder" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


141

Editorial - Depleted Uranium: A Problem of Perception rather than Reality  

Science Journals Connector (OSTI)

......Radiation Protection Dosimetry Editorial Editorial - Depleted Uranium: A Problem of Perception rather than Reality R. L. Kathren Depleted uranium: a problem of perception rather than reality......

R. L. Kathren

2001-05-01T23:59:59.000Z

142

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

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

60: Depleted Uranium Oxide Conversion Product at the Portsmouth, Ohio Site EIS-0360: Depleted Uranium Oxide Conversion Product at the Portsmouth, Ohio Site Summary This...

143

Buckling behaviour of ring-stiffned cylinders; experimental study  

Science Journals Connector (OSTI)

The effect of the number and size of rings on the buckling strength of ring-stiffened cylinders is studied experimentally. The results of ten machined ring-stiffened cylinders subjected to lateral pressure are presented. Five of the cylinders failed by the general instability mode and the rest failed by the shell instability mode. A sample of the experimental results which shows longitudinal and circumferential strains as well as the development of the circularity contours till collapse is presented. Buckling pressures obtained from the experiments are shown to be within ±30% of the corresponding value obtained from the theoretical analysis available in the literature.

S.S. Seleim; J. Roorda

1986-01-01T23:59:59.000Z

144

The corrosion of depleted uranium in terrestrial and marine environments  

Science Journals Connector (OSTI)

Depleted Uranium alloyed with titanium is used in armour penetrating munitions that have been fired in a number of conflict zones and testing ranges including the UK ranges at Kirkcudbright and Eskmeals. The study presented here evaluates the corrosion of DU alloy cylinders in soil on these two UK ranges and in the adjacent marine environment of the Solway Firth. The estimated mean initial corrosion rates and times for complete corrosion range from 0.13 to 1.9 g cm?2 y?1 and 2.5–48 years respectively depending on the particular physical and geochemical environment. The marine environment at the experimental site was very turbulent. This may have caused the scouring of corrosion products and given rise to a different geochemical environment from that which could be easily duplicated in laboratory experiments. The rate of mass loss was found to vary through time in one soil environment and this is hypothesised to be due to pitting increasing the surface area, followed by a build up of corrosion products inhibiting further corrosion. This indicates that early time measurements of mass loss or corrosion rate may be poor indicators of late time corrosion behaviour, potentially giving rise to incorrect estimates of time to complete corrosion. The DU alloy placed in apparently the same geochemical environment, for the same period of time, can experience very different amounts of corrosion and mass loss, indicating that even small variations in the corrosion environment can have a significant effect. These effects are more significant than other experimental errors and variations in initial surface area.

C. Toque; A.E. Milodowski; A.C. Baker

2014-01-01T23:59:59.000Z

145

Depleted Uranium (DU) Cermet Waste Package  

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

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

146

Neutral depletion and the helicon density limit  

SciTech Connect

It is straightforward to create fully ionized plasmas with modest rf power in a helicon. It is difficult, however, to create plasmas with density >10{sup 20} m{sup ?3}, because neutral depletion leads to a lack of fuel. In order to address this density limit, we present fast (1 MHz), time-resolved measurements of the neutral density at and downstream from the rf antenna in krypton helicon plasmas. At the start of the discharge, the neutral density underneath the antenna is reduced to 1% of its initial value in 15 ?s. The ionization rate inferred from these data implies that the electron temperature near the antenna is much higher than the electron temperature measured downstream. Neutral density measurements made downstream from the antenna show much slower depletion, requiring 14 ms to decrease by a factor of 1/e. Furthermore, the downstream depletion appears to be due to neutral pumping rather than ionization.

Magee, R. M.; Galante, M. E.; Carr, J. Jr.; Lusk, G.; McCarren, D. W.; Scime, E. E. [West Virginia University, Morgantown, West Virginia 26506 (United States)] [West Virginia University, Morgantown, West Virginia 26506 (United States)

2013-12-15T23:59:59.000Z

147

Casimir energies of cylinders: Universal function  

SciTech Connect

New exact results are given for the interior Casimir energies of infinitely long waveguides of triangular cross section (equilateral, hemiequilateral, and isosceles right triangles). Results for cylinders of rectangular cross section are rederived. In particular, results are obtained for interior modes belonging to Dirichlet and Neumann boundary conditions (TM and TE modes). These results are expressed in rapidly convergent series using the Chowla-Selberg formula, and in fact may be given in closed form, except for general rectangles. The energies are finite because only the first three heat-kernel coefficients can be nonzero for the case of polygonal boundaries. What appears to be a universal behavior of the Casimir energy as a function of the shape of the regular or quasiregular cross-sectional figure is presented. Furthermore, numerical calculations for arbitrary right triangular cross sections suggest that the universal behavior may be extended to waveguides of general polygonal cross sections. The new exact and numerical results are compared with the proximity force approximation (PFA).

Abalo, E. K.; Milton, K. A.; Kaplan, L. [Homer L. Dodge Department of Physics and Astronomy, University of Oklahoma, Norman, Oklahoma 73019 (United States); Department of Physics, Tulane University, New Orleans, Louisiana 70118 (United States)

2010-12-15T23:59:59.000Z

148

Simulation of wear characteristics of engine cylinders  

Science Journals Connector (OSTI)

This present work shows that a pin-on-disc (POD) tester is able to simulate the wear conditions occurring in real, marine diesel engines. This is promising, because a simple POD apparatus thus can be used to select new candidate materials for marine diesel engines, before more expensive and realistic tests are conducted. This early selection of materials will be based on relative measurements of new materials and existing materials with known properties. In its present form, the method is not based on quantitative measurements. In addition, the present work intends to clarify the mechanisms leading to the wear phenomena known as smearing and scuffing in two-stroke marine diesel engines. The tribo-system of the pin and disc is examined extensively, using scanning electron microscopy (SEM), transmission electron microscopy (TEM) and Vickers hardness indentation. Based on these findings an empirical model of smearing and scuffing has been established. This four-stage model is well supported by previous experimental [Wear 100 (1984) 315; Proc. Inst. Mech. Eng. 185 (1971/1972) 21; Wear 236 (1999) 199; Wear 236 (1999) 210] and theoretical [Wear 236 (1999) 199; Wear 236 (1999) 210; Wear 212 (1997) 213] work based on the wedge model of friction. By applying the empirical simulation data in the materials selection process, better materials for cylinders may be expected in the future.

Martin F Jensen; Jørgen Bøttiger; Henrik H Reitz; Michael E Benzon

2002-01-01T23:59:59.000Z

149

A REPORT ON CRITICAL DIMENSIONS OF CYLINDERS | OSTI, US Dept...  

Office of Scientific and Technical Information (OSTI)

DIMENSIONS OF CYLINDERS Re-direct Destination: Temp Data Fields Keen, R. C. Temp Data Storage 3: Oak Ridge National Lab., TN (US) Short URL for this Page http:t.osti.gov3rH...

150

Wave runup on cylinders subject to deep water random waves  

E-Print Network (OSTI)

was measured close to the test cylinders are analyzed. These data on wave runup in deepwater random waves were generated at similar water depths with significant wave heights and spectral peak periods. Statistical parameters, zero crossing analysis...

Indrebo, Ann Kristin

2012-06-07T23:59:59.000Z

151

Radiation dose rates from UF{sub 6} cylinders  

SciTech Connect

This paper describes the results of many studies, both theoretical and experimental, which have been carried out by Urenco over the last 15 years into radiation dose rates from uranium hexafluoride (UF{sub 6}) cylinders. The contents of the cylinder, its history, and the geometry all affect the radiation dose rate. These factors are all examined in detail. Actual and predicted dose rates are compared with levels permitted by IAEA transport regulations.

Friend, P.J. [Urenco, Capenhurst (United Kingdom)

1991-12-31T23:59:59.000Z

152

Study on Influence of Cylinder Liner Surface Texture on Lubrication Performance for Cylinder Liner–Piston Ring Components  

Science Journals Connector (OSTI)

A marine diesel engine, where the cylinder liner–piston ... rubbing pairs, is the heart of a marine system. Studying the lubrication characteristics of the ... for rational design of the CLPR to reduce wear and p...

Zhiwei Guo; Chengqing Yuan; Peng Liu; Zhongxiao Peng; Xinping Yan

2013-07-01T23:59:59.000Z

153

Nuclear conflict and ozone depletion Quick summary  

E-Print Network (OSTI)

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

Toohey, Darin W.

154

Results of ultrasonic testing evaluations on UF{sub 6} storage cylinders  

SciTech Connect

The three site cylinder management program is responsible for the safe storage of the DOE owned UF{sub 6} storage cylinders at PORTS, PGDP and at the K-25 site. To ensure the safe storage of the UF{sub 6} in the cylinders, the structural integrity of the cylinders must be evaluated. This report represents the latest cylinder integrity investigation that utilized wall thickness evaluations to identify thinning due to atmospheric exposure.

Lykins, M.L.

1997-02-01T23:59:59.000Z

155

DUF6 Guide  

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

DUF6 Guide DUF6 Guide Depleted UF6 Guide An introduction to uranium and its compounds, depleted uranium, and depleted uranium hexafluoride (depleted UF6). Uranium has unique properties that make it valuable as an energy source, yet potentially hazardous to human health and the environment. The Guide provides basic information about the properties of uranium compounds and the uranium enrichment process that produces depleted UF6. This information will help you understand the unique challenges involved in managing DOE's inventory of depleted UF6 in a safe and efficient manner. Overview Presentation DUF6 Health Risks Uranium and Its Compounds DUF6 Environmental Risks Depleted Uranium DUF6 Videos Uranium Hexafluoride Uranium Quick Facts DUF6 Production and Handling

156

FIREPLUME model for plume dispersion from fires: Application to uranium hexafluoride cylinder fires  

SciTech Connect

This report provides basic documentation of the FIREPLUME model and discusses its application to the prediction of health impacts resulting from releases of uranium hexafluoride (UF{sub 6}) in fires. The model application outlined in this report was conducted for the Draft Programmatic Environmental Impact Statement for Alternative Strategies for the Long-Term Management and Use of Depleted UF{sub 6}. The FIREPLUME model is an advanced stochastic model for atmospheric plume dispersion that predicts the downwind consequences of a release of toxic materials from an explosion or a fire. The model is based on the nonbuoyant atmospheric dispersion model MCLDM (Monte Carlo Lagrangian Dispersion Model), which has been shown to be consistent with available laboratory and field data. The inclusion of buoyancy and the addition of a postprocessor to evaluate time-varying concentrations lead to the current model. The FIREPLUME model, as applied to fire-related UF{sub 6} cylinder releases, accounts for three phases of release and dispersion. The first phase of release involves the hydraulic rupture of the cylinder due to heating of the UF{sub 6} in the fire. The second phase involves the emission of material into the burning fire, and the third phase involves the emission of material after the fire has died during the cool-down period. The model predicts the downwind concentration of the material as a function of time at any point downwind at or above the ground. All together, five fire-related release scenarios are examined in this report. For each scenario, downwind concentrations of the UF{sub 6} reaction products, uranyl fluoride and hydrogen fluoride, are provided for two meteorological conditions: (1) D stability with a 4-m/s wind speed, and (2) F stability with a 1-m/s wind speed.

Brown, D.F.; Dunn, W.E. [Univ. of Illinois, Champaign-Urbana, IL (United States). Dept. of Mechanical Engineering; Policastro, A.J.; Maloney, D. [Argonne National Lab., IL (United States)

1997-06-01T23:59:59.000Z

157

Field Trial of LANL On-Line Advanced Enrichment Monitor for UF6 GCEP  

SciTech Connect

The outline of this presentation is: (1) Technology basis of on-line enrichment monitoring; (2) Timescale of trial; (3) Description of installed equipment; (4) Photographs; (5) Results; (6) Possible further development; and (7) Conclusions. Summary of the good things about the Advanced Enrichment Monitor (AEM) performance is: (1) High accuracy - normally better than 1% relative, (2) Active system as accurate as passive system, (3) Fast and accurate detection of enrichment changes, (4) Physics is well understood, (5) Elegant method for capturing pressure signal, and (6) Data capture is automatic, low cost and fast. A couple of negative things are: (1) Some jumps in measured passive enrichment - of around +2% relative (due to clock errors?); and (2) Data handling and evaluation is off-line, expensive and very slow. Conclusions are: (1) LANL AEM is being tested on E23 plant at Capenhurst; (2) The trial is going very well; (3) AEM could detect production of HEU at potentially much lower cost than existing CEMO; (4) AEM can measure {sup 235}U assay accurately; (5) Active system using X-Ray source would avoid need for pressure measurement; (6) Substantial work lies ahead to go from current prototype to a production instrument.

Ianakiev, Kiril D. [Los Alamos National Laboratory; Lombardi, Marcie [Los Alamos National Laboratory; MacArthur, Duncan W. [Los Alamos National Laboratory; Parker, Robert F. [Los Alamos National Laboratory; Smith, Morag K. [Los Alamos National Laboratory; Keller, Clifford [Los Alamos National Laboratory; Friend, Peter [URENCO; Dunford, Andrew [URENCO

2012-07-13T23:59:59.000Z

158

Depleted Uranium Uses: Regulatory Requirements and Issues  

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

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

159

Depleted uranium hexafluoride: Waste or resource?  

SciTech Connect

the US Department of Energy is evaluating technologies for the storage, disposal, or re-use of depleted uranium hexafluoride (UF{sub 6}). This paper discusses the following options, and provides a technology assessment for each one: (1) conversion to UO{sub 2} for use as mixed oxide duel, (2) conversion to UO{sub 2} to make DUCRETE for a multi-purpose storage container, (3) conversion to depleted uranium metal for use as shielding, (4) conversion to uranium carbide for use as high-temperature gas-cooled reactor (HTGR) fuel. In addition, conversion to U{sub 3}O{sub 8} as an option for long-term storage is discussed.

Schwertz, N.; Zoller, J.; Rosen, R.; Patton, S. [Lawrence Livermore National Lab., CA (United States); Bradley, C. [USDOE Office of Nuclear Energy, Science, Technology, Washington, DC (United States); Murray, A. [SAIC (United States)

1995-07-01T23:59:59.000Z

160

Improvements in EBR-2 core depletion calculations  

SciTech Connect

The need for accurate core depletion calculations in Experimental Breeder Reactor No. 2 (EBR-2) is discussed. Because of the unique physics characteristics of EBR-2, it is difficult to obtain accurate and computationally efficient multigroup flux predictions. This paper describes the effect of various conventional and higher order schemes for group constant generation and for flux computations; results indicate that higher-order methods are required, particularly in the outer regions (i.e. the radial blanket). A methodology based on Nodal Equivalence Theory (N.E.T.) is developed which allows retention of the accuracy of a higher order solution with the computational efficiency of a few group nodal diffusion solution. The application of this methodology to three-dimensional EBR-2 flux predictions is demonstrated; this improved methodology allows accurate core depletion calculations at reasonable cost. 13 refs., 4 figs., 3 tabs.

Finck, P.J.; Hill, R.N.; Sakamoto, S.

1991-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "depleted uf6 cylinder" 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

Assessment of Preferred Depleted Uranium Disposal Forms  

SciTech Connect

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

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

2000-06-01T23:59:59.000Z

162

Carbon sequestration in depleted oil shale deposits  

SciTech Connect

A method and apparatus are described for sequestering carbon dioxide underground by mineralizing the carbon dioxide with coinjected fluids and minerals remaining from the extraction shale oil. In one embodiment, the oil shale of an illite-rich oil shale is heated to pyrolyze the shale underground, and carbon dioxide is provided to the remaining depleted oil shale while at an elevated temperature. Conditions are sufficient to mineralize the carbon dioxide.

Burnham, Alan K; Carroll, Susan A

2014-12-02T23:59:59.000Z

163

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

164

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

E-Print Network (OSTI)

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

Germano D'Abramo

2003-05-28T23:59:59.000Z

165

Chemical and radiochemical characterization of depleted uranium in contaminated soils  

Science Journals Connector (OSTI)

The main results of chemical and radiochemical characterization and fractionation of depleted uranium in soils contaminated during the Balkan conflict ... the paper. Alpha-spectrometric analysis of used depleted

M. B. Radenkovi?; A. B. Kandi?; I. S. Vukana?…

2007-09-01T23:59:59.000Z

166

Depleted uranium - induced malignant transformation in human lung epithelial cells.  

Science Journals Connector (OSTI)

...transmission of genetic damage by depleted uranium and tungsten alloy Alexandra Miller...The radioactive heavy metal, depleted uranium (DU), an alpha-particle emitter...fragments will affect the long-term health of offspring conceived by these...

Aldona A. Karaczyn; Hong Xie; and John P. Wise

2006-04-15T23:59:59.000Z

167

Depleted uranium internal contamination: Carcinogenesis and leukemogenesis in vivo  

Science Journals Connector (OSTI)

...Association for Cancer Research 1 May 2005...Proc Amer Assoc Cancer Res, Volume 46, 2005 Depleted uranium internal contamination...Proc Amer Assoc Cancer Res, Volume 46, 2005] 2080 Depleted uranium is a heavy metal...

Alexandra C. Miller; Mike Stewart; Rafael Rivas; Robert Merlot; and Paul Lison

2005-05-01T23:59:59.000Z

168

Depleted uranium - induced malignant transformation in human lung epithelial cells.  

Science Journals Connector (OSTI)

...Association for Cancer Research 15 April...Proc Amer Assoc Cancer Res, Volume 47, 2006 Depleted uranium - induced malignant...Proc Amer Assoc Cancer Res, Volume 47, 2006] 5215 Depleted uranium (DU) has been...

Aldona A. Karaczyn; Hong Xie; and John P. Wise

2006-04-15T23:59:59.000Z

169

Depleted uranium internal contamination: Carcinogenesis and leukemogenesis in vivo  

Science Journals Connector (OSTI)

...Abstract 3464: Epigenetic mechanism is involved in depleted uranium-induced transformation in human lung epithelial...Wise 1 1Univ. of Southern Maine, Portland, ME. Depleted uranium (DU) is commonly used in military applications...

Alexandra C. Miller; Mike Stewart; Rafael Rivas; Robert Merlot; and Paul Lison

2005-05-01T23:59:59.000Z

170

Numerical simulation for formed projectile of depleted uranium alloy  

Science Journals Connector (OSTI)

The numerical simulation for forming projectile of depleted uranium alloy with the SPH (Smooth Particle Hydrodynamic ... . To describe the deformed behaviors of the depleted uranium alloy under high pressure and ...

Song Shun-cheng; Gao Ping; Cai Hong-nian

2003-09-01T23:59:59.000Z

171

Casimir effect at nonzero temperature for wedges and cylinders  

SciTech Connect

We consider the Casimir-Helmholtz free energy at nonzero temperature T for a circular cylinder and perfectly conducting wedge closed by a cylindrical arc, either perfectly conducting or isorefractive. The energy expression at nonzero temperature may be regularized to obtain a finite value, except for a singular corner term in the case of the wedge which is present also at zero temperature. Assuming the medium in the interior of the cylinder or wedge be nondispersive with refractive index n, the temperature dependence enters only through the nondimensional parameter 2{pi}naT, a being the radius of the cylinder or cylindrical arc. We show explicitly that the known zero-temperature result is regained in the limit aT{yields}0 and that previously derived high-temperature asymptotics for the cylindrical shell are reproduced exactly.

Ellingsen, Simen A.; Brevik, Iver; Milton, Kimball A. [Department of Energy and Process Engineering, Norwegian University of Science and Technology, N-7491 Trondheim (Norway); Oklahoma Center for High Energy Physics and Homer L. Dodge Department of Physics and Astronomy, University of Oklahoma, Norman, Oklahoma 73019 (United States)

2010-03-15T23:59:59.000Z

172

RESEARCH ARTICLE Open Access Susceptibility to ATP depletion of primary  

E-Print Network (OSTI)

RESEARCH ARTICLE Open Access Susceptibility to ATP depletion of primary proximal tubular cell subjected to ATP depletion using antimycin A. Results: Surprisingly, there was no difference in the amount, Viability, Survival, Apoptosis knockout mice, shRNA, ATP depletion, Metabolic stress, Antimycin Background

Paris-Sud XI, Université de

173

An experimental study of jet impingement on a circular cylinder  

E-Print Network (OSTI)

diameter of 6 5/8 inches. The jet was impinged upon the cylinder at nozzle distances of 7, 15, and 30 nozzle diameters, and at velocities of' 400 and 500 ft/s. The free jet was studied and found to be "typical" by comparing it to earlier studies done... Instrumentation schematic 17 5 Cylindrical suriace coordinate system 22 6 Photograph of the cylinder with "grid" 23 7 Photograph of the wall jet traversing apparatus 24 8 Orientation of the hot film sensor 25 9 Free jet geometry and parameters 30 10 Velocity...

Potts, Dennis Wayne

2012-06-07T23:59:59.000Z

174

Plasmonic modes and extinction properties of a random nanocomposite cylinder  

SciTech Connect

We study the properties of surface plasmon-polariton waves of a random metal-dielectric nanocomposite cylinder, consisting of bulk metal embedded with dielectric nanoparticles. We use the Maxwell-Garnett formulation to model the effective dielectric function of the composite medium and show that there exist two surface mode bands. We investigate the extinction properties of the system, and obtain the dependence of the extinction spectrum on the nanoparticles’ shape and concentration as well as the cylinder radius and the incidence angle for both TE and TM polarization.

Moradi, Afshin, E-mail: a.moradi@kut.ac.ir [Department of Basic Sciences, Kermanshah University of Technology, Kermanshah, Iran and Department of Nano Science, Institute for Studies in Theoretical Physics and Mathematics (IPM), Tehran (Iran, Islamic Republic of)] [Department of Basic Sciences, Kermanshah University of Technology, Kermanshah, Iran and Department of Nano Science, Institute for Studies in Theoretical Physics and Mathematics (IPM), Tehran (Iran, Islamic Republic of)

2014-04-15T23:59:59.000Z

175

High-Efficiency Clean Combustion in Light-Duty Multi-Cylinder...  

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

High-Efficiency Clean Combustion in Light-Duty Multi-Cylinder Diesel Engines High-Efficiency Clean Combustion in Light-Duty Multi-Cylinder Diesel Engines 2010 DOE Vehicle...

176

High Efficiency Clean Combustion in Multi-Cylinder Light-Duty...  

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

Efficiency Clean Combustion in Multi-Cylinder Light-Duty Engines High Efficiency Clean Combustion in Multi-Cylinder Light-Duty Engines 2012 DOE Hydrogen and Fuel Cells Program and...

177

Fact #725: April 30, 2012 Cylinder Deactivation is More Prevalent in Light Trucks than Cars  

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

Cylinder deactivation is a fuel-saving technology that allows a vehicle to shut down some of its cylinders when extra power is not needed like when cruising down the highway at a constant speed....

178

A dynamic model of a self-vibration cycle in a stirling engine with opposed cylinders  

Science Journals Connector (OSTI)

A dynamic model of the self-vibration cycle in an engine with opposed cylinders and two pistons located on a common guide bar is studied. To each cylinder containing a working liquid, a pair of hydraulic accum...

M. Ya. Izrailovich; A. V. Sinev…

2007-06-01T23:59:59.000Z

179

The application of eccentric rotating cylinder apparatus for the improved study of particle coagulation  

E-Print Network (OSTI)

Concentric rotating cylinder and turbulent mixing devices have been frequently used in studying mixing and particle coagulation. However, these apparatus develop simple laminar flow (concentric rotating cylinders) or do not have well-defined flow...

Lee, Chun Woo

2004-11-15T23:59:59.000Z

180

High-Efficiency Clean Combustion in Light-Duty Multi-Cylinder...  

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

* Cylinder-to-cylinder balancing important for high efficiency. * Swirl level has optimum level depending on gasoline-to-diesel ratio and has strong impact on BTE. * Pressure rise...

Note: This page contains sample records for the topic "depleted uf6 cylinder" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


181

High Efficiency Clean Combustion in Multi-Cylinder Light-Duty...  

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

High Efficiency Clean Combustion in Multi-Cylinder Light-Duty Engines High Efficiency Clean Combustion in Multi-Cylinder Light-Duty Engines 2013 DOE Hydrogen and Fuel Cells Program...

182

Capstone Depleted Uranium Aerosols: Generation and Characterization  

SciTech Connect

In a study designed to provide an improved scientific basis for assessing possible health effects from inhaling depleted uranium (DU) aerosols, a series of DU penetrators was fired at an Abrams tank and a Bradley fighting vehicle. A robust sampling system was designed to collect aerosols in this difficult environment and continuously monitor the sampler flow rates. Aerosols collected were analyzed for uranium concentration and particle size distribution as a function of time. They were also analyzed for uranium oxide phases, particle morphology, and dissolution in vitro. The resulting data provide input useful in human health risk assessments.

Parkhurst, MaryAnn; Szrom, Fran; Guilmette, Ray; Holmes, Tom; Cheng, Yung-Sung; Kenoyer, Judson L.; Collins, John W.; Sanderson, T. Ellory; Fliszar, Richard W.; Gold, Kenneth; Beckman, John C.; Long, Julie

2004-10-19T23:59:59.000Z

183

Coupled heat conduction and deformation in a viscoelastic composite cylinder  

E-Print Network (OSTI)

conditions, Finite Element(FE) analysis of the composite cylinder is performed and the results of analytical and FE method are found to be in good agreement. Parametric studies are carried out to understand the effect of change in material parameters namely...

Shah, Sneha

2010-01-16T23:59:59.000Z

184

UF{sub 6} cylinder lifting equipment enhancements  

SciTech Connect

This paper presents numerous enhancements that have been made to the Portsmouth lifting equipment to ensure the safe handling of cylinders containing liquid uranium hexafluoride (UF{sub 6}). The basic approach has been to provide redundancy to all components of the lift path so that any one component failure would not cause the load to drop or cause any undesirable movement.

Hortel, J.M. [Martin Marietta Energy Systems, Inc., Piketon, OH (United States)

1991-12-31T23:59:59.000Z

185

Alternative method of retesting UF{sub 6} cylinders  

SciTech Connect

The paper describes an alternative method to perform the periodic inspection of UF{sub 6} cylinders. The hydraulic test is replaced by ultrasonic checking of wall thickness and by magnetic particle testing of all the weld seams. Information about the legal background, the air leak test and the qualification of inspectors is also given.

Christ, R. [Nuclear Crago + Service GmbH, Hanau (Germany)

1991-12-31T23:59:59.000Z

186

Turbulent flow between counter-rotating concentric cylinders: a ...  

E-Print Network (OSTI)

We report three-dimensional direct numerical simulations of the turbulent flow ... Comparisons between the standard Taylor–Couette system (rotating inner cylinder, .... 2004) and implemented using the message passing interface (MPI). ..... (negative peak), ZC0, provides a measure for the characteristic size of the near-wall.

S. DONG

2008-10-13T23:59:59.000Z

187

Temporary patching of damaged UF{sub 6} cylinders  

SciTech Connect

Patching techniques based on application of epoxy resins have been developed for temporarily repairing UF{sub 6} cylinders which have sustained relatively minor damage and must be safely emptied. The method is considerably faster and simpler than metallurgical weld repairs. Laboratory tests, detailed operational procedures, and case histories of experience at the Portsmouth Gaseous Diffusion Plant are described.

Cardenas, A.L. [Martin Marietta Energy Systems, Inc., OH (United States)

1991-12-31T23:59:59.000Z

188

Management Responsibilities  

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

Management Responsibilities Management Responsibilities Depleted UF6 Management Responsibilities DOE has responsibility for safe and efficient management of approximately 700,000 metric tons of depleted UF6. Organizational Responsibilities In the United States, the U.S. Department of Energy is responsible for managing all the depleted uranium that has been generated by the government and has been declared surplus to national defense needs. In addition, as a result of two memoranda of agreement that have been signed between the DOE and USEC, the DOE has assumed management responsibility for approximately 145,000 metric tons of depleted UF6 that has been or will be generated by USEC. Any additional depleted UF6 that USEC generates will be USEC's responsibility to manage. DOE Management Responsibility

189

Experimental studies of unrestrained cylinders on an impermeable bottom under currents  

E-Print Network (OSTI)

gravities (2.77-3.17) range from 0.64-0.66, slightly below 0.70. However, the threshold and superthreshold velocities are smaller for a cylinder with smaller specific gravity. Analysis of angular and linear motion of the cylinders shows that the cylinders do...

Fenical, Scott William

2012-06-07T23:59:59.000Z

190

A critical comparison of ionospheric depletion chemicals  

SciTech Connect

Six chemicals, H{sub 2}, H{sub 2}O, CO{sub 2}, SF{sub 6}, CF{sub 3}BR, and Ni(CO){sub 4}, are considered as ionospheric modification agents. Each of these species reacts in the F region to produce localized plasma depletions. The first three interact with O{sup +} and yield polyatomic ions which dissociatively recombine with electrons to give neutrals. The last three dissociatively attach electrons to produce heavy negative ions which become mutually neutralized by reactions with O{sup +}. The effectiveness of these chemicals depends on the amount which goes into the vapor state upon release. Thermodynamic calculations show that H{sub 2}O has the lowest vapor yield of about 20% from a heated, pressurized tank. Over 60% of the other substances should be vented in gaseous form. Based on estimates of plasma density reduction and airglow stimulation, nickel carbonyl is the most efficient of the six species for modifying the nighttime ionosphere. During the daytime, CF{sub 3}BR and SF{sub 6} provide the largest depletions.

Bernhardt, P.A. (Los Alamos National Lab., NM (United States))

1987-05-01T23:59:59.000Z

191

Video: Metamorphosis (Physical Characteristics of Uranium Hexafluoride)  

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

Metamorphosis Metamorphosis Metamorphosis (Physical Characteristics of Uranium Hexafluoride) The Uranium Hexafluoride phase diagram is investigated. An experimental setup is shown to look at the gas, liquid, and solid phases at various temperatures and pressures. This information is used to understand what happens inside a DUF6 storage cylinder. View this Video in Real Player format Download free RealPlayer SP Highlights of the Video: Video 00:12 Metamorphosis from the U.S. Department of Energy Video 00:45 Laboratory setup to examine the phases of UF6 Video 01:45 UF6 Phase Diagram Video 03:25 Liquid UF6 appearing in a glass tube Video 03:38 Cloud of HF from moisture reaction dissolving in UF6 gas Video 04:27 Beginning of UF6 phase change from liquid to solid Video 04:40 Formation of porous solid structure

192

Notice of Intent (NOI) to Prepare DUF6 PEIS  

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

1, No. 17 / Thursday, January 25, 1996 / Notice 1, No. 17 / Thursday, January 25, 1996 / Notice [Pages 2239-2242] From the Federal Register Online via GPO Access [wais.access.gpo.gov] Alternative Strategies for the Long-Term Management and Use o f Depleted Uranium Hexafluoride AGENCY: Department of Energy ACTION: Notice of Intent (NOI). SUMMARY: The Department of Energy (DOE) announces its intent to prepare a programmatic environmental impact statement (PEIS) pursuant to the National Environmental Policy Act (NEPA) of 1969 (42 USC 4321 et seq.). The PEIS will assess the potential environmental impacts of alternative strategies for the long-term management and use of 560,000 metric tons of depleted uranium hexafluoride (UF 6 ) currently stored in cylinders at DOE's three gaseous diffusion plant sites located near Paducah, Kentucky; Portsmouth, Ohio; and Oak

193

Motion of a Viscoelastic Micellar Fluid Around a Cylinder: Flow and Fracture  

E-Print Network (OSTI)

We present an experimental study of the motion of a viscoelastic micellar material around a moving cylinder, which ranges in response from fluid-like flow to solid-like tearing and fracture, depending on the cylinder radius and velocity. The observation of viscoelastic crack propagation driven by the cylinder indicates an extremely low tear strength, approximately equal to the steady state surface tension of the fluid. At the highest speeds a driven crack is observed in front of the cylinder, propagating with a fluctuating speed equal on average to the cylinder speed, here as low as 5% of the elastic wave speed in the medium.

Joseph R. Gladden; Andrew Belmonte

2006-05-25T23:59:59.000Z

194

Regulation of New Depleted Uranium Uses  

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

2-5 2-5 Regulation of New Depleted Uranium Uses Environmental Assessment Division Argonne National Laboratory Operated by The University of Chicago, under Contract W-31-109-Eng-38, for the United States Department of Energy DISCLAIMER This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency thereof, nor The University of Chicago, nor any of their employees or officers, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights. Reference herein to any specific commercial product, process, or service by trade name, trademark,

195

Depleted uranium waste assay at AWE  

SciTech Connect

The Atomic Weapons Establishment (AWE) at Aldermaston has recently conducted a Best Practical Means (BPM) study, for solid Depleted Uranium (DU) waste assay, in order to satisfy key stakeholders that AWE is applying best practice. This study has identified portable passive High Resolution Gamma Spectrometry (HRGS), combined with an analytical software package called Spectral Nondestructive Assay Platform (SNAP), as the preferred option with the best balance between performance and costs. HRGS/SNAP performance has been assessed by monitoring 200 l DU waste drum standards and also heterogeneous, high density drums from DU firing trials. Accuracy was usually within 30 % with Detection Limits (DL) in the region of 10 g DU for short count times. Monte Carlo N-Particle (MCNP) calculations have been used to confirm the shape of the calibration curve generated by the SNAP software procured from Eberline Services Inc. (authors)

Miller, T.J. [AWE, Aldermaston, Reading, Berkshire, England, RG7 4PR (United Kingdom)

2007-07-01T23:59:59.000Z

196

Processing depleted uranium quad alloy penetrator rods  

SciTech Connect

Two depleted uranium (DU) quad alloys were cast, extruded and rolled to produce penetrator rods. The two alloy combinations were (1) 1 wt % molybdenum (Mo), 1 wt % niobium (Nb), and 0.75 wt % titanium (Ti); and (2) 1 wt % tantalum (Ta), 1 wt % Nb, and 0.75 wt % Ti. This report covers the processing and results with limited metallographic information available. The two alloys were each vacuum induction melted (VIM) into an 8-in. log, extruded into a 3-in. log, then cut into 4 logs and extruded at 4 different temperatures into 0.8-in. bars. From the 8 conditions (2 alloys, 4 extrusion temperatures each), 10 to 13 16-in. rods were cut for rolling and swaging. Due to cracking problems, the final processing changed from rolling and swaging to limited rolling and heat treating. The contracted work was completed with the delivery of 88 rods to Dr. Zabielski. 28 figs.

Bokan, S.L.

1987-02-19T23:59:59.000Z

197

The health effects of depleted uranium  

Science Journals Connector (OSTI)

There has been a substantial amount of public discussion on the health effects of the use of depleted uranium (DU) munitions. In response to this concern the Royal Society set up an independent, expert working group to investigate the health effects of DU munitions. The Royal Society has now produced two reports, and this summary covering the key conclusions and recommendations from both reports. The part I report considered the increased risks of radiation-induced cancer from exposures to DU on the battlefield. Part II dealt with the risks from the chemical toxicity of uranium, non-malignant radiation effects from DU intakes, the long-term environmental consequences of the deployment of DU munitions and responses to part I including issues arising at a public meeting to discuss the part I report.

The Royal Society Working Group on the Health Hazards of

2002-01-01T23:59:59.000Z

198

Deuterium depletion and magnesium enhancement in the local disc  

E-Print Network (OSTI)

The local disc deuter is known to be depleted in comparison to the local bubble. We show, that the same lines of sight that are depleted in deuter, are enhanced in magnesium. Heavier elements - Si and Fe do not show any difference in the abundance between the local disc and the local bubble. This observation implicates that astration is responsible for both deuter depletion and magnesium enhancement.

Piotr Gnacinski

2005-07-19T23:59:59.000Z

199

ISO test method to determine sustained-load-cracking resistance of aluminium cylinders  

SciTech Connect

Leak as well as rupture types of failures related to sustained-load-cracking (SLC) have been observed in high-pressure gas cylinders fabricated from certain aluminium alloy. The stable crack growth mechanism observed primarily in the cylinder neck and shoulder area have been identified as the SLC mechanism occurring at room temperature without any environmental effect. The International Organization for standardization (ISO) Sub-Committee 3, Working Group 16 has developed a test method to measure the SLC resistance using fracture mechanics specimens along with an acceptance criterion for aluminium cylinders. The technical rationale for the proposed test method and the physical significance of the acceptance criterion to the cylinder performance in terms of critical stress-crack size relationship is presented. Application of the developed test method for characterizing new aluminium alloy for manufacturing cylinders is demonstrated. SLC characteristics of several aluminium cylinders as well as on-board cylinders for natural gas vehicles assessed by the authors are discussed.

Bhuyan, G.S. [Powertech Labs. Inc., Surrey, British Columbia (Canada); Rana, M.D. [Praxair, Inc., Tonawanda, NY (United States)

1999-08-01T23:59:59.000Z

200

Cracked lifting lug welds on ten-ton UF{sub 6} cylinders  

SciTech Connect

Ten-ton, Type 48X, UF{sub 6} cylinders are used at the Portsmouth Gaseous Diffusion Plant to withdraw enriched uranium hexafluoride from the cascade, transfer enriched uranium hexafluoride to customer cylinders, and feed enriched product to the cascade. To accomplish these activities, the cylinders are lifted by cranes and straddle carriers which engage the cylinder lifting lugs. In August of 1988, weld cracks on two lifting lugs were discovered during preparation to lift a cylinder. The cylinder was rejected and tagged out, and an investigating committee formed to determine the cause of cracking and recommend remedial actions. Further investigation revealed the problem may be general to this class of cylinder in this use cycle. This paper discusses the actions taken at the Portsmouth site to deal with the cracked lifting lug weld problem. The actions include inspection activities, interim corrective actions, metallurgical evaluation of cracked welds, weld repairs, and current monitoring/inspection program.

Dorning, R.E. [Martin Marietta Energy Systems, Inc., Piketon, OH (United States)

1991-12-31T23:59:59.000Z

Note: This page contains sample records for the topic "depleted uf6 cylinder" 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

Subsurface transformations of depleted uranium at Aberdeen Proving Ground, Maryland.  

E-Print Network (OSTI)

?? Approximately 130,000 kg of depleted uranium (DU) from ammunition testing have been deposited in soils since 1974 and remain in the environment at Aberdeen… (more)

Oxenberg, Tanya Palmateer

2007-01-01T23:59:59.000Z

202

Analysis of Serum Total and Free PSA Using Immunoaffinity Depletion...  

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

Serum Total and Free PSA Using Immunoaffinity Depletion Coupled to SRM: Correlation with Clinical Immunoassay Tests. Analysis of Serum Total and Free PSA Using Immunoaffinity...

203

Application of thermal depletion model to geothermal reservoirs...  

Open Energy Info (EERE)

of thermal depletion model to geothermal reservoirs with fracture and pore permeability Jump to: navigation, search OpenEI Reference LibraryAdd to library Conference Proceedings:...

204

Modeling of Depleted Uranium Transport in Subsurface Systems  

Science Journals Connector (OSTI)

Groundwater and soil contamination with depleted uranium (DU) isan important public concern because ... four extremecases of climate and existing conditions of uranium penetrator fragments. The simulations demons...

J. Paul Chen; Sotira Yiacoumi

2002-10-01T23:59:59.000Z

205

Microscale Depletion of High Abundance Proteins in Human Biofluids...  

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

by nonspecific binding to the column matrix. Additionally, the cost of the depletion media can be prohibitive for larger scale studies. Modern LC-MS instrumentation provides...

206

Rolling friction for hard cylinder and sphere on viscoelastic solid  

E-Print Network (OSTI)

We calculate the friction force acting on a hard cylinder or spherical ball rolling on a flat surface of a viscoelastic solid. The rolling friction coefficient depends non-linearly on the normal load and the rolling velocity. For a cylinder rolling on a viscoelastic solid characterized by a single relaxation time Hunter has obtained an exact result for the rolling friction, and our result is in very good agreement with his result for this limiting case. The theoretical results are also in good agreement with experiments of Greenwood and Tabor. We suggest that measurements of rolling friction over a wide range of rolling velocities and temperatures may constitute an useful way to determine the viscoelastic modulus of rubber-like materials.

B. N. J. Persson

2010-08-26T23:59:59.000Z

207

Another Cold War-era building at the Department of Energys...  

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

as the Metals Plant. It operated from 1953 to 1962, and from 1968 to 1973, to convert depleted uranium hexafluoride, or UF 6 , into uranium metal. Two of the five structures...

208

April 2011 Recovery News  

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

Plant spanned roughly 65,000 square feet and operated from 1953-62 and 1968-73 to convert depleted uranium hexafluoride (UF 6 ) into uranium metal and uranium tetrafluoride. It is...

209

Federal Register  

National Nuclear Security Administration (NNSA)

of Decision (ROD) are available on the DOE National Environmental Policy Act (NEPA) Web site at http: www.eh.doe.govnepa and on the Depleted UF 6 Management Information...

210

Invariant Properties of Straight Homogeneous Generalized Cylinders and Their Contours  

Science Journals Connector (OSTI)

A fundamental group in computer vision is the recovery of three-dimensional shape from image data. While this problem is in general underconstrained, the authors show that it can be simplified in the case where the objects being viewed are generalized ... Keywords: 3D shape recovery, Gaussian curvature, computer vision, computerised pattern recognition, computerised picture processing, image contours, invariant property, segmentation, straight homogeneous generalized cylinders

J. Ponce; D. Chelberg; W. B. Mann

1989-09-01T23:59:59.000Z

211

Precise instrumentation of a diesel single-cylinder research engine  

Science Journals Connector (OSTI)

The accuracy of any empirical result is a direct consequence of the quality of experimental setup and the strict control over testing conditions. For internal combustion engines, a large number of parameters that also exhibit complex interdependence may significantly affect the engine performance. Therefore, this work describes the essentials required to establish a high-quality diesel engine research laboratory. A single-cylinder diesel engine is taken as the fundamental building block and the requirements for all essential sub-systems including fuel, intake, exhaust, coolant and exhaust gas recirculation (EGR) are laid out. The measurement and analysis of cylinder pressure, and exhaust gas sampling/conditioning requirements for emission measurement are discussed in detail. The independent control of EGR and intake boost is also highlighted. The measurement and analysis techniques are supported with empirical data from a single-cylinder diesel engine setup. The emphasis is on providing the necessary guidelines for setting up a fully-instrumented diesel engine test laboratory.

Usman Asad; Raj Kumar; Xiaoye Han; Ming Zheng

2011-01-01T23:59:59.000Z

212

Preconceptual design studies and cost data of depleted uranium hexafluoride conversion plants  

SciTech Connect

One of the more important legacies left with the Department of Energy (DOE) after the privatization of the United States Enrichment Corporation is the large inventory of depleted uranium hexafluoride (DUF6). The DOE Office of Nuclear Energy, Science and Technology (NE) is responsible for the long-term management of some 700,000 metric tons of DUF6 stored at the sites of the two gaseous diffusion plants located at Paducah, Kentucky and Portsmouth, Ohio, and at the East Tennessee Technology Park in Oak Ridge, Tennessee. The DUF6 management program resides in NE's Office of Depleted Uranium Hexafluoride Management. The current DUF6 program has largely focused on the ongoing maintenance of the cylinders containing DUF6. However, the long-term management and eventual disposition of DUF6 is the subject of a Programmatic Environmental Impact Statement (PEIS) and Public Law 105-204. The first step for future use or disposition is to convert the material, which requires construction and long-term operation of one or more conversion plants. To help inform the DUF6 program's planning activities, it was necessary to perform design and cost studies of likely DUF6 conversion plants at the preconceptual level, beyond the PEIS considerations but not as detailed as required for conceptual designs of actual plants. This report contains the final results from such a preconceptual design study project. In this fast track, three month effort, Lawrence Livermore National Laboratory and Bechtel National Incorporated developed and evaluated seven different preconceptual design cases for a single plant. The preconceptual design, schedules, costs, and issues associated with specific DUF6 conversion approaches, operating periods, and ownership options were evaluated based on criteria established by DOE. The single-plant conversion options studied were similar to the dry-conversion process alternatives from the PEIS. For each of the seven cases considered, this report contains information on the conversion process, preconceptual plant description, rough capital and operating costs, and preliminary project schedule.

Jones, E

1999-07-26T23:59:59.000Z

213

Surface Depletion in the Vacuum Distillation of Metals from Bismuth  

SciTech Connect

Surface depletion was investigated in laboratory- and plant-scale distillation units with mixing by natural convection or by mechanical surface agitation. A model was developed for predicting the degree of surface depletion during the distillation of metals from bismuth as a function of temperature, still pot dimensions, and degree of agitation. This paper discusses those findings.

Bradley, R.F.

2001-08-29T23:59:59.000Z

214

Pumping induced depletion from two streams Dongmin Sun a  

E-Print Network (OSTI)

Author's personal copy Pumping induced depletion from two streams Dongmin Sun a , Hongbin Zhan b-domain and becomes identical to that of Hunt [Hunt B. Unsteady stream depletion from ground water pumping. Ground of the shortest distance from the pumping well to the other stream over the shortest distance between the two

Zhan, Hongbin

215

Depleted Uranium: Exposure and Possible Health Effects  

Science Journals Connector (OSTI)

Depleted uranium (DU) is a by-product of the enrichment process of 235U used for fission in nuclear reactors and nuclear weapons. It has both civilian and military applications. The military use of DU is of defensive as well as of offensive nature, being mainly employed as armor-piercing ammunition. So far, the usage of ammunitions containing DU has been officially confirmed in four military conflicts: Iraq (1991), Bosnia (1994), Kosovo (1999), and again Iraq (2003). During their deployment in the military actions, most penetrators are thought to have missed their intended targets. Therefore, a substantial amount of DU is still present in the environment and may act as a source of contamination for the environment and the population. The possible effects of this radioactive and chemically toxic material have attracted particular notice. To evaluate these consequences, it is important to have accurate methods to assess the exposure to DU in both environmental and biological samples. This article is therefore intended to point out the problematic nature of the experimental techniques and of the analytical methods so far used to quantify the exposure to DU in the light of possible health effects of DU.

U. Oeh

2011-01-01T23:59:59.000Z

216

FAQ 27-Are there any currently-operating disposal facilities that can  

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

currently-operating disposal facilities that can accept all of the depleted uranium oxide that would be generated from conversion of DOE's depleted UF6 inventory? currently-operating disposal facilities that can accept all of the depleted uranium oxide that would be generated from conversion of DOE's depleted UF6 inventory? Are there any currently-operating disposal facilities that can accept all of the depleted uranium oxide that would be generated from conversion of DOE's depleted UF6 inventory? With respect to available capacity, three sites could accept the entire inventory of depleted uranium oxide: the Department of Energy's (DOE's) Hanford site in Washington State, DOE's Nevada Test Site, or EnergySolution Clive, Utah Facility, a commercial site. Each of these sites would have sufficient capacity for either the grouted or ungrouted oxide forms of depleted uranium (for the two DOE sites, this also takes into account other projected disposal volumes through the year 2070).

217

Cost estimate report for the long-term management of depleted uranium hexafluoride : storage of depleted uranium metal.  

SciTech Connect

This report contains a cost analysis of the long-term storage of depleted uranium in the form of uranium metal. Three options are considered for storage of the depleted uranium. These options are aboveground buildings, partly underground vaults, and mined cavities. Three cases are presented. In the first case, all the depleted uranium metal that would be produced from the conversion of depleted uranium hexafluoride (UF{sub 6}) generated by the US Department of Energy (DOE) prior to July 1993 would be stored at the storage facility (100% Case). In the second case, half the depleted uranium metal would be stored at this storage facility (50% Case). In the third case, one-quarter of the depleted uranium metal would be stored at the storage facility (25% Case). The technical basis for the cost analysis presented in this report is principally found in the companion report, ANL/EAD/TM-100, ''Engineering Analysis Report for the Long-Term Management of Depleted Uranium Hexafluoride: Storage of Depleted Uranium Metal'', prepared by Argonne National Laboratory.

Folga, S.M.; Kier, P.H.; Thimmapuram, P.R.

2001-01-24T23:59:59.000Z

218

System and method of cylinder deactivation for optimal engine torque-speed map operation  

DOE Patents (OSTI)

This disclosure provides a system and method for determining cylinder deactivation in a vehicle engine to optimize fuel consumption while providing the desired or demanded power. In one aspect, data indicative of terrain variation is utilized in determining a vehicle target operating state. An optimal active cylinder distribution and corresponding fueling is determined from a recommendation from a supervisory agent monitoring the operating state of the vehicle of a subset of the total number of cylinders, and a determination as to which number of cylinders provides the optimal fuel consumption. Once the optimal cylinder number is determined, a transmission gear shift recommendation is provided in view of the determined active cylinder distribution and target operating state.

Sujan, Vivek A; Frazier, Timothy R; Follen, Kenneth; Moon, Suk-Min

2014-11-11T23:59:59.000Z

219

The legal status of UF{sub 6}-cylinder testing and licensing in Germany (and Europe)  

SciTech Connect

New German and European transport regulations for road and rail transport of UF{sub 6}-cylinders are presented, in particular those provisions which have direct impact on the majority of cylinders used in shipments touching ADR and RID member states. First experiences and difficulties in it`s application are highlighted taking into account experiences of a for running German regulation. A summary of research efforts on the behaviour of cylinders in fire environments concludes the paper.

Wieser, K.E. [Federal Institute for Material Research and Testing (BAM), Berlin (Germany); Tietze, A. [Bergische Universitaet - Gesamthochschule Wuppertal (Germany)

1991-12-31T23:59:59.000Z

220

Design of a cylinder chopper with a pneumatic airjet cleaner for sugarcane  

E-Print Network (OSTI)

EQUIPMENT Feed Conveyor Cylinder Chopper . Airjet Cleaner . Hydraulic Power Unit Sugarcane Instrumentation PROCEDURE Cylinder Chopper . Cylinder Chopper-Airjet Cleaner, Statistical Analysis Experimental Test Procedure RESULTS AND DISCUSSION Test... This plot shows the effect of airjet force on sugarcane trajectories. 17 I11ustration of complete test system Complete test system The feed in conveyor 20 20 10 12 13 14 This plot illustrates the relationship between the feed conveyor variables...

Reidenbach, Vincent George

2012-06-07T23:59:59.000Z

Note: This page contains sample records for the topic "depleted uf6 cylinder" 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

In-Cylinder Processes of EGR-Diluted Low-Load, Low-Temperature...  

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

Model for Partially PremixedLow-Temperature Diesel Combustion Based onIn-Cylinder Laser Diagnostics and Chemical Kinetics Modeling Heavy-Duty Low-Temperature and Diesel...

222

Strategies for In-Cylinder Reductions to Reach Bin 2 and LEV...  

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

conditions lowers in-cylinder NOx for diesels and reduces pumping losses and improves knock resistance for gasoline engines. p-03czarnowski.pdf More Documents & Publications...

223

An experimental study on heat transfer from a horizontal heated circular cylinder enhanced by water spray.  

E-Print Network (OSTI)

??A series of experiments were conducted to investigate the heat transfer which occurs with a heated, constant heat flux, horizontal, single circular cylinder is exposed… (more)

Chau, Man Hei

2009-01-01T23:59:59.000Z

224

Flow fields and heat transfer of liquid falling film on horizontal cylinders.  

E-Print Network (OSTI)

??A liquid film flowing over horizontal cylinders is of great importance as a high rate of heat transfer exists between the falling liquid film and… (more)

Jafar, Farial A

2011-01-01T23:59:59.000Z

225

Addressing the Challenges of RCCI Operation on a Light-Duty Multi-Cylinder Engine  

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

ORNL and UW collaboration in evaluating and developing RCCI operation in fully built multi-cylinder engine to address hardware, aftertreatment, and control challenges

226

An In-Cylinder Imaging Survey of Low-Temperature, High-Efficiency Combustion Strategies  

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

High speed imaging of in-cylinder spray and combustion luminosity of low temperature combustion strategies are contrasted to conventional gasoline and diesel engine combustion

227

EGR Spatial Uniformity & Cylinder-Resolved Transients-Measurements using an Absorption Spectroscopy Probe  

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

This poster describes development and application of an EGR probe for assessing steady-state spatial uniformity and cylinder-resolved EGR dynamics.

228

High Efficiency Clean Combustion in Multi-Cylinder Light-Duty...  

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

temperature effects to better understand implementation of low temperature combustion processes on multi-cylinder engines (September 30, 2008). FY 2008 Milestone complete...

229

In-Cylinder Mechanisms of PCI Heat-Release Rate Control by Fuel...  

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

Mechanisms of PCI Heat-Release Rate Control by Fuel Reactivity Stratification In-Cylinder Mechanisms of PCI Heat-Release Rate Control by Fuel Reactivity Stratification Explores...

230

Challenges dealing with depleted uranium in Germany - Reuse or disposal  

SciTech Connect

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

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

2007-07-01T23:59:59.000Z

231

The Reproductive Effects in Rats after Chronic Oral Exposure to Low-dose Depleted Uranium  

Science Journals Connector (OSTI)

......I (2009) Depleted uranium: properties, military...Teratogenicity of depleted uranium aerosols: a review...expression in female breast cancer among an Iraqi population exposed to depleted uranium. J Carcinog 7: 8......

Yuhui Hao; Rong Li; Yanbing Leng; Jiong Ren; Jing Liu; Guoping Ai; Hui Xu; Yongping Su; Tianmin Cheng

2012-05-01T23:59:59.000Z

232

Identification of Health Risks in Workers Staying and Working on the Terrains Contaminated with Depleted Uranium  

Science Journals Connector (OSTI)

......ionizing radiation. Health risks|Depleted uranium|Chromosome aberrations...and Jadranko SIMIC2 Health risks/Depleted uranium/Chromosome aberrations...Institute symposia "The Health Effects of Depleted Uranium." Remarks and slides......

Snezana Milacic; Jadranko Simic

2009-05-01T23:59:59.000Z

233

Estimating the lung burden from exposure to aerosols of depleted uranium  

Science Journals Connector (OSTI)

......Society. The Health Hazards of Depleted Uranium Munitions-Part...Carpenter D. O. Depleted uranium contamination...implications for health assessment...Sunder S. Depleted uranium dust from fired...properties. Health Phys (2004......

Marcelo Valdés

2009-02-01T23:59:59.000Z

234

Measuring aerosols generated inside armoured vehicles perforated by depleted uranium ammunition  

Science Journals Connector (OSTI)

......War about the health significance of exposure to depleted uranium (DU), the...perforated by depleted uranium ammunition...War about the health significance of exposure to depleted uranium (DU), the......

M. A. Parkhurst

2003-07-01T23:59:59.000Z

235

Radon levels and doses in dwellings in two villages in Kosovo, affected by depleted uranium  

Science Journals Connector (OSTI)

......Kosovo, affected by depleted uranium G. Nafezi 1 A. Gregoric...the study was hit by depleted uranium projectiles during...M. , Haldimann M. Depleted uranium in Kosovo: an assessment...exposure for aid workers. Health Phys. (2002) 82......

G. Nafezi; A. Gregoric; J. Vaupotic; M. Bahtijari; M. Kuqali

2014-02-01T23:59:59.000Z

236

The Reproductive Effects in Rats after Chronic Oral Exposure to Low-dose Depleted Uranium  

Science Journals Connector (OSTI)

......Fairlie I (2009) Depleted uranium: properties, military use and health risks. Med Confl...et al (2002) Health effects of embedded depleted uranium. Mil Med 167...et al (2000) Health effects of depleted uranium on exposed Gulf......

Yuhui Hao; Rong Li; Yanbing Leng; Jiong Ren; Jing Liu; Guoping Ai; Hui Xu; Yongping Su; Tianmin Cheng

2012-05-01T23:59:59.000Z

237

Clinical diagnostic indicators of renal and bone damage in rats intramuscularly injected with depleted uranium  

Science Journals Connector (OSTI)

......Abou-Donia, M. Depleted and natural uranium: chemistry...Environ. Health B Crit...et al. Health effects of embedded depleted uranium. Mil. Med...determinations in depleted uranium exposed Gulf...veterans. Health Phys. 77......

S. Fukuda; M. Ikeda; M. Chiba; K. Kaneko

2006-06-01T23:59:59.000Z

238

Accumulation and Distribution of Uranium in Rats after Implantation with Depleted Uranium Fragments  

Science Journals Connector (OSTI)

......Environmental and health consequences of depleted uranium use in the 1991 Gulf...Properties, use and health effects of depleted uranium (DU): a general...J. (2002). Health effects of embedded depleted uranium. Mil Med. 167......

Guoying Zhu; Mingguang Tan; Yulan Li; Xiqiao Xiang; Heping Hu; Shuquan Zhao

2009-05-01T23:59:59.000Z

239

Abstract 3590: Depleted uranium-induced leukemia: Epigenetic and genetic changes.  

Science Journals Connector (OSTI)

...Association for Cancer Research April...Abstract 3590: Depleted uranium-induced leukemia...development. Depleted uranium is used in military...Max Costa. Depleted uranium-induced leukemia...Association for Cancer Research; 2013...

Alexandra C. Miller; Hailey Clancy; Thomas Kluz; Stuart Cohen; Rafael Rivas; Karvelisse Miller; and Max Costa

2013-04-15T23:59:59.000Z

240

Abstract 3590: Depleted uranium-induced leukemia: Epigenetic and genetic changes.  

Science Journals Connector (OSTI)

...Washington, DC Abstract 3590: Depleted uranium-induced leukemia: Epigenetic...with leukemia development. Depleted uranium is used in military missions...Karvelisse Miller, Max Costa. Depleted uranium-induced leukemia: Epigenetic...

Alexandra C. Miller; Hailey Clancy; Thomas Kluz; Stuart Cohen; Rafael Rivas; Karvelisse Miller; and Max Costa

2013-04-15T23:59:59.000Z

Note: This page contains sample records for the topic "depleted uf6 cylinder" 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

Abstract B41: Depleted uranium-induced oxidative stress in human bronchial epithelial cells  

Science Journals Connector (OSTI)

...Carefree, AZ Abstract B41: Depleted uranium-induced oxidative stress in...as occupational exposures to depleted uranium via military action. Cellular...to evaluate the toxicity of depleted uranium (DU) in its soluble and insoluble...

Monica Yellowhair; Leigh A. Henricksen; Aneesha Hossain; Kathleen Dixon; and R. Clark Lantz

2009-02-01T23:59:59.000Z

242

Estimating the lung burden from exposure to aerosols of depleted uranium  

Science Journals Connector (OSTI)

......from exposure to aerosols of depleted uranium Marcelo Valdes * * Corresponding...Following exposure to aerosols of depleted uranium (DU), biological samples...uranyl phosphates. INTRODUCTION Depleted uranium (DU) is a waste product of......

Marcelo Valdés

2009-02-01T23:59:59.000Z

243

Accumulation and Distribution of Uranium in Rats after Implantation with Depleted Uranium Fragments  

Science Journals Connector (OSTI)

......Rats after Implantation with Depleted Uranium Fragments Guoying Zhu 1 * Mingguang...and distribution of uranium in depleted uranium (DU) implanted rats. Materials...of chronic exposure to DU. Depleted uranium|Bone|Kidney|Distribution......

Guoying Zhu; Mingguang Tan; Yulan Li; Xiqiao Xiang; Heping Hu; Shuquan Zhao

2009-05-01T23:59:59.000Z

244

Measuring aerosols generated inside armoured vehicles perforated by depleted uranium ammunition  

Science Journals Connector (OSTI)

......armoured vehicles perforated by depleted uranium ammunition M. A. Parkhurst...significance of exposure to depleted uranium (DU), the US Department of...armoured vehicles perforated by depleted uranium ammunition. | In response to......

M. A. Parkhurst

2003-07-01T23:59:59.000Z

245

Identification of Health Risks in Workers Staying and Working on the Terrains Contaminated with Depleted Uranium  

Science Journals Connector (OSTI)

......the Terrains Contaminated with Depleted Uranium Snezana Milacic 1 * Jadranko...originated from ammunition containing depleted uranium (DU). The studied population...ionizing radiation. Health risks|Depleted uranium|Chromosome aberrations| J......

Snezana Milacic; Jadranko Simic

2009-05-01T23:59:59.000Z

246

The Reproductive Effects in Rats after Chronic Oral Exposure to Low-dose Depleted Uranium  

Science Journals Connector (OSTI)

......Oral Exposure to Low-dose Depleted Uranium Yuhui Hao Rong Li * Yanbing...study evaluated the effects of depleted uranium (DU) on reproduction in rats...effects were obvious in F1 rats. Depleted uranium|Ingestion|Reproductive effects......

Yuhui Hao; Rong Li; Yanbing Leng; Jiong Ren; Jing Liu; Guoping Ai; Hui Xu; Yongping Su; Tianmin Cheng

2012-05-01T23:59:59.000Z

247

Radon levels and doses in dwellings in two villages in Kosovo, affected by depleted uranium  

Science Journals Connector (OSTI)

......villages in Kosovo, affected by depleted uranium G. Nafezi 1 A. Gregoric 2...included in the study was hit by depleted uranium projectiles during the North...1999. Although no impact of depleted uranium on radon levels has been observed......

G. Nafezi; A. Gregoric; J. Vaupotic; M. Bahtijari; M. Kuqali

2014-02-01T23:59:59.000Z

248

Clinical diagnostic indicators of renal and bone damage in rats intramuscularly injected with depleted uranium  

Science Journals Connector (OSTI)

......intramuscularly injected with depleted uranium S. Fukuda 1 M. Ikeda 1 M...related to kidney and bone in depleted uranium (DU)-injected rats were...injected is low. INTRODUCTION Depleted uranium (DU) accumulates like natural......

S. Fukuda; M. Ikeda; M. Chiba; K. Kaneko

2006-06-01T23:59:59.000Z

249

Electrorefining cell with parallel electrode/concentric cylinder cathode  

DOE Patents (OSTI)

A cathode-anode arrangement for use in an electrolytic cell is adapted for electrochemically refining spent nuclear fuel from a nuclear reactor and recovering purified uranium for further treatment and possible recycling as a fresh blanket or core fuel in a nuclear reactor. The arrangement includes a plurality of inner anodic dissolution baskets that are each attached to a respective support rod, are submerged in a molten lithium halide salt, and are rotationally displaced. An inner hollow cylindrical-shaped cathode is concentrically disposed about the inner anodic dissolution baskets. Concentrically disposed about the inner cathode in a spaced manner are a plurality of outer anodic dissolution baskets, while an outer hollow cylindrical-shaped is disposed about the outer anodic dissolution baskets. Uranium is transported from the anode baskets and deposited in a uniform cylindrical shape on the inner and outer cathode cylinders by rotating the anode baskets within the molten lithium halide salt. Scrapers located on each anode basket abrade and remove the spent fuel deposits on the surfaces of the inner and outer cathode cylinders, with the spent fuel falling to the bottom of the cell for removal. Cell resistance is reduced and uranium deposition rate enhanced by increasing the electrode area and reducing the anode-cathode spacing. Collection efficiency is enhanced by trapping and recovery of uranium dendrites scrapped off of the cylindrical cathodes which may be greater in number than two.

Gay, Eddie C. (Park Forest, IL); Miller, William E. (Naperville, IL); Laidler, James J. (Burr Ridge, IL)

1997-01-01T23:59:59.000Z

250

Electrorefining cell with parallel electrode/concentric cylinder cathode  

DOE Patents (OSTI)

A cathode-anode arrangement for use in an electrolytic cell is adapted for electrochemically refining spent nuclear fuel from a nuclear reactor and recovering purified uranium for further treatment and possible recycling as a fresh blanket or core fuel in a nuclear reactor. The arrangement includes a plurality of inner anodic dissolution baskets that are each attached to a respective support rod, are submerged in a molten lithium halide salt, and are rotationally displaced. An inner hollow cylindrical-shaped cathode is concentrically disposed about the inner anodic dissolution baskets. Concentrically disposed about the inner cathode in a spaced manner are a plurality of outer anodic dissolution baskets, while an outer hollow cylindrical-shaped is disposed about the outer anodic dissolution baskets. Uranium is transported from the anode baskets and deposited in a uniform cylindrical shape on the inner and outer cathode cylinders by rotating the anode baskets within the molten lithium halide salt. Scrapers located on each anode basket abrade and remove the spent fuel deposits on the surfaces of the inner and outer cathode cylinders, with the spent fuel falling to the bottom of the cell for removal. Cell resistance is reduced and uranium deposition rate enhanced by increasing the electrode area and reducing the anode-cathode spacing. Collection efficiency is enhanced by trapping and recovery of uranium dendrites scrapped off of the cylindrical cathodes which may be greater in number than two. 12 figs.

Gay, E.C.; Miller, W.E.; Laidler, J.J.

1997-07-22T23:59:59.000Z

251

DOE Selects Contractor for Depleted Hexafluoride Conversion Project Support  

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

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

252

DOE Issues Request for Quotations for Depleted Uranium Hexafluoride  

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

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

253

DOE Issues Request for Quotations for Depleted Uranium Hexafluoride  

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

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

254

DOE Selects Contractor for Depleted Hexafluoride Conversion Project Support  

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

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

255

Machining of depleted uranium using coated cutting tools  

Science Journals Connector (OSTI)

The machining of depleted uranium and its alloys are discussed in this...1-x-y-z Al x Cr y Y2N alloys, with y=0.03 and z=0.02, h...

M. J. Jackson; G. M. Robinson

2006-04-01T23:59:59.000Z

256

Depleted uranium mobility and fractionation in contaminated soil (Southern Serbia)  

Science Journals Connector (OSTI)

During the Balkan conflict in 1999, soil in contaminated areas was enriched in depleted uranium (DU) isotopic signature, relative to the in-situ natural uranium present. After the military activities, most...

Mirjana B. Radenkovi?; Svjetlana A. Cupa?…

2008-01-01T23:59:59.000Z

257

Lichens as Biomonitors of Depleted Uranium in Kosovo  

Science Journals Connector (OSTI)

This paper reports the results of a study using lichens as biomonitors to investigate the environmental distribution of depleted uranium (DU) at selected Kosovo sites as...235U/238U measurements did not indicate ...

S. Loppi; L. A. Di Lella; L. Frati; G. Protano…

2004-11-01T23:59:59.000Z

258

Hyperspectral stimulated emission depletion microscopy and methods of use thereof  

DOE Patents (OSTI)

A hyperspectral stimulated emission depletion ("STED") microscope system for high-resolution imaging of samples labeled with multiple fluorophores (e.g., two to ten fluorophores). The hyperspectral STED microscope includes a light source, optical systems configured for generating an excitation light beam and a depletion light beam, optical systems configured for focusing the excitation and depletion light beams on a sample, and systems for collecting and processing data generated by interaction of the excitation and depletion light beams with the sample. Hyperspectral STED data may be analyzed using multivariate curve resolution analysis techniques to deconvolute emission from the multiple fluorophores. The hyperspectral STED microscope described herein can be used for multi-color, subdiffraction imaging of samples (e.g., materials and biological materials) and for analyzing a tissue by Forster Resonance Energy Transfer ("FRET").

Timlin, Jerilyn A; Aaron, Jesse S

2014-04-01T23:59:59.000Z

259

Depleted uranium: a contemporary controversy for the teaching of radioactivity  

Science Journals Connector (OSTI)

Depleted uranium has been used in recent military conflicts and the media have reported the danger from radioactivity. This context provides a good way to keep students' attention when introducing the subject of radioactivity at GCSE or advanced level.

Mark Whalley

2006-01-01T23:59:59.000Z

260

Retrieval of buried depleted uranium from the T-1 trench  

SciTech Connect

The Trench 1 remediation project will be conducted this year to retrieve depleted uranium and other associated materials from a trench at Rocky Flats Environmental Technology Site. The excavated materials will be segregated and stabilized for shipment. The depleted uranium will be treated at an offsite facility which utilizes a novel approach for waste minimization and disposal through utilization of a combination of uranium recycling and volume efficient uranium stabilization.

Burmeister, M. [Rocky Mountain Remediation Services, Golden, CO (United States); Castaneda, N. [Dept. of Energy, Golden, CO (United States). Rocky Flats Field Office; Greengard, T. [Kaiser-Hill Co., Golden, CO (United States)]|[Science Applications International Corp. (United States); Hull, C. [S.M. Stoller Corp., Boulder, CO (United States); Barbour, D.; Quapp, W.J. [Starmet Corp. (United States)

1998-07-01T23:59:59.000Z

Note: This page contains sample records for the topic "depleted uf6 cylinder" 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

E-Print Network 3.0 - aerosol depletion test Sample Search Results  

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

depletion test Search Powered by Explorit Topic List Advanced Search Sample search results for: aerosol depletion test Page: << < 1 2 3 4 5 > >> 1 Supervolcanoes General feedback...

262

Impact of carbon dioxide sequestration in depleted gas-condensate reservoirs.  

E-Print Network (OSTI)

??Depleted gas-condensate reservoirs are becoming important targets for carbon dioxide sequestration. Since depleted below the dew point, retrograde condensate has been deposited in the pore… (more)

Ramharack, Richard M.

2010-01-01T23:59:59.000Z

263

Brain accumulation of depleted uranium in rats following 3- or 6-month treatment with implanted depleted uranium pellets  

Science Journals Connector (OSTI)

Depleted uranium (DU) is used to reinforce armor ... were weighed weekly as a measure of general health, with no statistically significant differences observed among ... midbrain, hippocampus, striatum, and corte...

Vanessa A. Fitsanakis; Keith M. Erikson…

2006-01-01T23:59:59.000Z

264

Assigning mass values to in-house standard UF/sub 6/ cylinders  

SciTech Connect

A statistical experimental design called the Fast 4-1 Series is used to assign mass values to in-house standard UF/sub 6/ cylinders. This design is intended to minimize the number of weighings of large cylinders yet provide acceptable estimates of mass values and their precision. 5 refs.

Goldman, A.; McGuire, D.; Croarkin, C.

1987-01-01T23:59:59.000Z

265

Vortices and Rossby waves in cylinder wakes on a parabolic -plane observed by altimetric imaging velocimetry  

E-Print Network (OSTI)

, geostrophic and gradient wind velocity, and potential vorticity fields with very high spatial resolutionVortices and Rossby waves in cylinder wakes on a parabolic -plane observed by altimetric imaging in the wake of a circular cylinder are investigated in a rotating parabolic polar -plane fluid. This system

Afanassiev, Iakov

266

Electric Field Induced Sphere-to-Cylinder Transition in Diblock Copolymer Thin Films  

E-Print Network (OSTI)

Electric Field Induced Sphere-to-Cylinder Transition in Diblock Copolymer Thin Films Ting Xu, A. V Manuscript Received June 21, 2004 ABSTRACT: An electric field induced sphere-to-cylinder transition in thin. In the absence of an applied electric field, thin films of the asymmetric diblock copolymer consisted of layers

Ocko, Ben

267

Tonal Noise Excited by Plasma in Cylinder Wakes Using Closed-loop Control  

E-Print Network (OSTI)

atmosphere uniform glow discharge surface plasma," IEEE International Conference on Plasma Science, IEEETonal Noise Excited by Plasma in Cylinder Wakes Using Closed-loop Control Wenjun Yu , and Xun Huang controlled by a closed-loop plasma control system was demonstrated in this work. The flow around a cylinder

Huang, Xun

268

An experimental investigation of the mean flow field of a wavy cylinder at critical Reynolds numbers  

E-Print Network (OSTI)

Fluid flow around a wavy cylinder geometry was investigated in the Texas A&M University 2'x3' wind tunnel. Tests consisted of mean surface static pressure and mean wake dynamic pressure measurements around two wavy cylinders of differing wavelength...

Damiana, Thomas Anthony

2012-06-07T23:59:59.000Z

269

Biaxial testing of high strength carbon fiber composite cylinders for pulsed magnet reinforcement  

E-Print Network (OSTI)

Biaxial testing of high strength carbon fiber composite cylinders for pulsed magnet reinforcement N A methodology is introduced to test carbon-fiber-reinforced, hoop-wound composite cylinders for their biaxial. Testing of actual pulsed magnets to ascertain design change effects of composite reinforcement schemes

Garmestani, Hamid

270

Hollow cylinder dynamic pressurization and radial flow through permeability tests for cementitous materials  

E-Print Network (OSTI)

........................................................................ 9 3.2 Radial Flow Through Apparatus ....................................................................... 10 3.3 Hollow Dynamic Pressurization Apparatus ...................................................... 13 3.4 Solid Dynamic Pressurization... Figure 4. Comparison of relaxation functions for solid and hollow cylinders. Note that the early behavior (? 10.16 cm (4 inch) diameter cylinder...

Jones, Christopher Andrew

2009-05-15T23:59:59.000Z

271

Department of Mechanical Engineering Spring 2013 Designing an educational dissection activity for a four cylinder engine  

E-Print Network (OSTI)

PENNSTATE Department of Mechanical Engineering Spring 2013 Designing an educational dissection activity for a four cylinder engine Overview General Motors had donated several four cylinder Chevy Cruze engines to the university. The team was challenged with creating an activity that uses these engines

Demirel, Melik C.

272

Energy Loss Distribution in the Taylor-Couette Flow between Concentric Rotating Cylinders  

E-Print Network (OSTI)

The distribution of energy loss due to viscosity friction in plane Couette flow and Taylor-Couette Flow between concentric rotating cylinders are studied in detail for various flow conditions. The energy loss is related to the industrial processes in some fluid delivery devices and has significant influence on the flow efficiency, flow stability, turbulent transition, mixing, and heat transfer behaviours, etc. Therefore, it is very helpful to know about the energy loss distribution in the flow domain and to know its influence on the flow for understanding the flow physics. The calculation method of the energy loss distribution in the Taylor-Couette Flow between concentric rotating cylinders has not been found in open literature. In this note, the principle and the calculation are given for single cylinder rotating of inner or outer cylinder, and counter and same direction rotating of two cylinders. For comparison, the distribution of energy loss in a plane Couette flow is also derived for various flow conditi...

Dou, H S; Phan-Thien, N; Yeo, K S; Dou, Hua-Shu; Khoo, Boo Cheong; Phan-Thien, Nhan; Yeo, Khoon Seng

2005-01-01T23:59:59.000Z

273

Prediction of External Corrosion for Steel Cylinders-2001 Report  

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

64 64 Prediction of External Corrosion for Steel Cylinders-2001 Report Rick Schmoyer and B. F. Lyon 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; prices available from 615-576-8401, FTS 626-8401. Available to the public from the National Technical Information Service, U.S. Department of Commerce, 5285 Port Royal Rd., Springfield, VA 22161. This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency thereof, nor any of their employees, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy,

274

Prediction of External Corrosion for Steel Cylinders-2002 Report  

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

43 43 Prediction of External Corrosion for Steel Cylinders-2002 Report Rick Schmoyer and B. F. Lyon 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; prices available from 615-576-8401, FTS 626-8401. Available to the public from the National Technical Information Service, U.S. Department of Commerce, 5285 Port Royal Rd., Springfield, VA 22161. This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency thereof, nor any of their employees, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy,

275

Steady Deflagration of PBX-9501 Within a Copper Cylinder  

SciTech Connect

A copper cylinder cook-off experiment has been designed to cause steady deflagration in PBX-9501 explosive material. The design is documented and preliminary copper expansion results are presented for steady deflagration with a reaction speed of 1092 +/- 24 m/s. The expansion of reaction products from the detonation of an explosive is something that is well understood, and reasonably simulated using documented equations of state (EOS) for many explosives of interest. These EOS were historically measured using a 'standard' copper cylinder test design; this design comprised an annealed, oxygen-free high conductivity (OFHC) copper tube filled with explosive material and detonated from one end. Expansion of the copper wall was measured as a function of time using either a streak camera (for classic testing), or more recently using laser velocimetry techniques. Expansion data were then used to derive the EOS in various preferred forms - which are not discussed here for the sake of brevity. [Catanach, et. al., 1999] When an explosive deflagrates rather than detonating, simulation becomes more difficult. Reaction products are released on a slower time scale, and the reactions are much more affected by the geometry and local temperature within the reaction environment. It is assumed that the standard, documented EOS will no longer apply. In an effort to establish a first order approximation of deflagration product behavior, a cook-off test has been designed to cause steady deflagration in PBX-9501 explosive material, and to record the copper expansion profile as a function of time during this test. The purpose of the current paper is to document the initial test design and report some preliminary results. A proposal for modification of the design is also presented.

Pemberton, Steven J. [Los Alamos National Laboratory; Herrera, Dennis H. [Los Alamos National Laboratory; Herrera, Tommy J. [Los Alamos National Laboratory; Arellano, Jesus C. [Los Alamos National Laboratory; Sandoval, Thomas D. [Los Alamos National Laboratory

2012-06-26T23:59:59.000Z

276

Gas Cylinder Storage and Handling Serious accidents can result from the misuse, abuse, or mishandling of compressed gas  

E-Print Network (OSTI)

Gas Cylinder Storage and Handling Serious accidents can result from the misuse, abuse, or mishandling of compressed gas cylinders. Safe procedures for their use are as follows: · All compressed gas combustible material. · Keep cylinders out of the direct sun and do not allow them to be overheated. · Gas

de Lijser, Peter

277

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

E-Print Network (OSTI)

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

1980-01-01T23:59:59.000Z

278

International aspects of restrictions of ozone-depleting substances  

SciTech Connect

This report summarizes international efforts to protect stratospheric ozone. Also included in this report is a discussion of activities in other countries to meet restrictions in the production and use of ozone-depleting substances. Finally, there is a brief presentation of trade and international competitiveness issues relating to the transition to alternatives for the regulated chlorofluorocarbons (CFCs) and halons. The stratosphere knows no international borders. Just as the impact of reduced stratospheric ozone will be felt internationally, so protection of the ozone layer is properly an international effort. Unilateral action, even by a country that produces and used large quantities of ozone-depleting substances, will not remedy the problem of ozone depletion if other countries do not follow suit. 32 refs., 7 tabs.

McDonald, S.C.

1989-10-01T23:59:59.000Z

279

Effect of Shim Arm Depletion in the NBSR  

SciTech Connect

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

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

2013-02-22T23:59:59.000Z

280

Depleted uranium as a backfill for nuclear fuel waste package  

DOE Patents (OSTI)

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

Forsberg, Charles W. (Oak Ridge, TN)

1998-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "depleted uf6 cylinder" 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

Depleted uranium as a backfill for nuclear fuel waste package  

DOE Patents (OSTI)

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

Forsberg, C.W.

1998-11-03T23:59:59.000Z

282

Application of thermal depletion model to geothermal reservoirs with  

Open Energy Info (EERE)

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

283

Draft Environmental Impact Statement for Construction and Operation of a Depleted Uranium Hexafluoride Conversion Facility at the Paducah, Kentucky, Site  

SciTech Connect

This document is a site-specific environmental impact statement (EIS) for construction and operation of a proposed depleted uranium hexafluoride (DUF{sub 6}) conversion facility at the U.S. Department of Energy (DOE) Paducah site in northwestern Kentucky (Figure S-1). The proposed facility would convert the DUF{sub 6} stored at Paducah to a more stable chemical form suitable for use or disposal. In a Notice of Intent (NOI) published in the ''Federal Register'' (FR) on September 18, 2001 (''Federal Register'', Volume 66, page 48123 [66 FR 48123]), DOE announced its intention to prepare a single EIS for a proposal to construct, operate, maintain, and decontaminate and decommission two DUF{sub 6} conversion facilities at Portsmouth, Ohio, and Paducah, Kentucky, in accordance with the National Environmental Policy Act of 1969 (NEPA) (''United States Code'', Title 42, Section 4321 et seq. [42 USC 4321 et seq.]) and DOE's NEPA implementing procedures (''Code of Federal Regulations'', Title 10, Part 1021 [10 CFR Part 1021]). Subsequent to award of a contract to Uranium Disposition Services, LLC (hereafter referred to as UDS), Oak Ridge, Tennessee, on August 29, 2002, for design, construction, and operation of DUF{sub 6} conversion facilities at Portsmouth and Paducah, DOE reevaluated its approach to the NEPA process and decided to prepare separate site-specific EISs. This change was announced in a ''Federal Register'' Notice of Change in NEPA Compliance Approach published on April 28, 2003 (68 FR 22368); the Notice is included as Attachment B to Appendix C of this EIS. This EIS addresses the potential environmental impacts from the construction, operation, maintenance, and decontamination and decommissioning (D&D) of the proposed conversion facility at three alternative locations within the Paducah site; from the transportation of depleted uranium conversion products to a disposal facility; and from the transportation, sale, use, or disposal of the fluoride-containing conversion products (hydrogen fluoride [HF] or calcium fluoride [CaF{sub 2}]). Although not part of the proposed action, an option of shipping all cylinders (DUF{sub 6}, low-enriched UF{sub 6} [LEU-UF{sub 6}], and empty) stored at the East Tennessee Technology Park (ETTP) near Oak Ridge, Tennessee, to Paducah rather than to Portsmouth is also considered. In addition, this EIS evaluates a no action alternative, which assumes continued storage of DUF{sub 6} in cylinders at the Paducah site. A separate EIS (DOE/EIS-0360) evaluates the potential environmental impacts for the proposed Portsmouth conversion facility.

N /A

2003-11-28T23:59:59.000Z

284

Biological assessment of the effects of construction and operation of a depleted uranium hexafluoride conversion facility at the Paducah, Kentucky, site.  

SciTech Connect

The U.S. Department of Energy (DOE) Depleted Uranium Hexafluoride (DUF{sub 6}) Management Program evaluated alternatives for managing its inventory of DUF{sub 6} and issued the ''Programmatic Environmental Impact Statement for Alternative Strategies for the Long-Term Management and Use of Depleted Uranium Hexafluoride'' (DUF{sub 6} PEIS) in April 1999 (DOE 1999). The DUF{sub 6} inventory is stored in cylinders at three DOE sites: Paducah, Kentucky; Portsmouth, Ohio; and East Tennessee Technology Park (ETTP), near Oak Ridge, Tennessee. In the Record of Decision for the DUF{sub 6} PEIS, DOE stated its decision to promptly convert the DUF6 inventory to a more stable chemical form. Subsequently, the U.S. Congress passed, and the President signed, the ''2002 Supplemental Appropriations Act for Further Recovery from and Response to Terrorist Attacks on the United States'' (Public Law No. 107-206). This law stipulated in part that, within 30 days of enactment, DOE must award a contract for the design, construction, and operation of a DUF{sub 6} conversion plant at the Department's Paducah, Kentucky, and Portsmouth, Ohio, sites, and for the shipment of DUF{sub 6} cylinders stored at ETTP to the Portsmouth site for conversion. This biological assessment (BA) has been prepared by DOE, pursuant to the National Environmental Policy Act of 1969 (NEPA) and the Endangered Species Act of 1974, to evaluate potential impacts to federally listed species from the construction and operation of a conversion facility at the DOE Paducah site.

Van Lonkhuyzen, R.

2005-09-09T23:59:59.000Z

285

Fundamental differences between Arctic and Antarctic ozone depletion  

Science Journals Connector (OSTI)

...binary sulfuric acid?water aerosols can deplete...National Oceanic and Atmospheric Administration. Satellite observations...Relative influences of atmospheric chemistry and transport...RP Pinto J ( 1986 ) Condensation of HNO 3 and HCl in...Implications for recovery of springtime Antarctic...

Susan Solomon; Jessica Haskins; Diane J. Ivy; Flora Min

2014-01-01T23:59:59.000Z

286

Learning about ozone depletion Paul J. Crutzen & Michael Oppenheimer  

E-Print Network (OSTI)

Learning about ozone depletion Paul J. Crutzen & Michael Oppenheimer Received: 12 January 2007 Mainz, Germany M. Oppenheimer (*) Department of Geosciences, Princeton University, Princeton, NJ 08544, USA e-mail: omichael@princeton.edu M. Oppenheimer Woodrow Wilson School of Public and International

Oppenheimer, Michael

287

Characterization of Thermal Properties of Depleted Uranium Metal Microspheres  

E-Print Network (OSTI)

that combines these previous two methods to characterize the diffusivity of a packed bed of microspheres of depleted uranium (DU) metal, which have a nominal diameter of 250 micrometers. The new apparatus is designated as the Crucible Heater Test Assembly (CHTA...

Humrickhouse, Carissa Joy

2012-07-16T23:59:59.000Z

288

Defending Resource Depletion Attacks on Implantable Medical Devices  

E-Print Network (OSTI)

that could deplete IMD resources (e.g., battery power) quickly. The RD attacks could reduce the lifetime are powered by a non-rechargeable battery and replacing the battery requires surgery. Re-charging an IMD from an external RF electromagnetic source causes thermal effects in the organs and thus is not recommended. Unlike

Wu, Jie

289

Disposal Options for Depleted Uranium Trioxide (DU03) Study  

SciTech Connect

There exists at SRS 50 million pounds of depleted UO3 (DUO) stored in 55-gallon drums stacked three high in several buildings. This storage configuration does not allow access to the individual drums for monitoring drum integrity and material accountability.

Jones, T.M.

2002-08-02T23:59:59.000Z

290

The Variation of Magnesium Depletion with Line of Sight Conditions  

E-Print Network (OSTI)

In this paper we report on the gas-phase abundance of singly-ionized magnesium (Mg II) in 44 lines of sight, using data from the Hubble Space Telescope (HST). We measure Mg II column densities by analyzing medium- and high-resolution archival STIS spectra of the 1240 A doublet of Mg II. We find that Mg II depletion is correlated with many line of sight parameters (e.g. F(H_2), E_(B-V), E_(B-V)/r, A_V, and A_V/r) in addition to the well-known correlation with . These parameters should be more directly related to dust content and thus have more physical significance with regard to the depletion of elements such as magnesium. We examine the significance of these additional correlations as compared to the known correlation between Mg II depletion and . While none of the correlations are better predictors of Mg II depletion than , some are statistically significant even assuming fixed . We discuss the ranges over which these correlations are valid, their strength at fixed , and physical interpretations.

Adam G. Jensen; Theodore P. Snow

2007-10-04T23:59:59.000Z

291

Depleted-Heterojunction Colloidal Quantum Dot Solar Cells  

E-Print Network (OSTI)

Depleted-Heterojunction Colloidal Quantum Dot Solar Cells Andras G. Pattantyus-Abraham,, Illan J and Computer Engineering, University of Toronto, 10 King's College Road, Toronto, Ontario M5S 3G4, Canada-circuit voltage (Voc) and fill factor (FF). The power conversion efficiency ( ) for an in- put solar intensity

292

Coal slurry combustion optimization on single cylinder engine  

SciTech Connect

Under the sponsorship of the US Department of Energy, Morgantown Energy Technology Center, GE Transportation System has been conducting a proof of concept program to use coal water slurry (CWS) fuel to power a diesel engine locomotive since 1988. As reported earlier [1], a high pressure electronically controlled accumulator injector using a diamond compact insert nozzle was developed for this project. The improved reliability and durability of this new FIE allowed for an improved and more thorough study of combustion of CWS fuel in a diesel engine. It was decided to include a diesel pilot fuel injector in the combustion system mainly due to engine start and low load operation needs. BKM, Inc. of San Diego, CA was contracted to develop the electronic diesel fuel pilot/starting FIE for the research engine. As a result, the experimental combustion study was very much facilitated due to the ability of changing pilot/CWS injection timings and quantities without having to stop the engine. Other parameters studied included combustion chamber configuration (by changing CWS fuel injector nozzle hole number/shape/angle), as well as injection pressure. The initial phase of this combustion study is now complete. The results have been adopted into the design of a 12 cylinder engine FIE, to be tested in 1992. This paper summarizes the main findings of this study.

Not Available

1992-09-01T23:59:59.000Z

293

Experimental critical parameters of plutonium metal cylinders flooded with water  

SciTech Connect

Forty-nine critical configurations are reported for experiments involving arrays of 3 kg plutonium metal cylinders moderated and reflected by water. Thirty-four of these describe systems assembled in the laboratory, while 15 others are derived critical parameters inferred from 46 subcritical cases. The arrays included 2x2xN, N = 2, 3, 4, and 5, in one program and 3x3x3 configurations in a later study. All were three-dimensional, nearly square arrays with equal horizontal lattice spacings but a different vertical lattice spacing. Horizontal spacings ranged from units in contact to 180 mm center-to-center; and vertical spacings ranged from about 80 mm to almost 400 mm center-to-center. Several nearly-equilateral 3x3x3 arrays exhibit an extremely sensitive dependence upon horizontal separation for identical vertical spacings. A line array of unreflected and essentially unmoderated canned plutonium metal units appeared to be well subcritical based on measurements made to assure safety during the manual assembly operations. All experiments were performed at two widely separated times in the mid-1970s and early 1980s under two programs at the Rocky Flats Plant`s Critical Mass Laboratory.

NONE

1996-07-01T23:59:59.000Z

294

Laboratory investigation of lateral dispersion within dense arrays of randomly distributed cylinders at transitional Reynolds number  

E-Print Network (OSTI)

Relative (effective) lateral dispersion of a passive solute was examined at transitional Reynolds numbers within a two-dimensional array of randomly distributed circular cylinders of uniform diameter d. The present work ...

Nepf, Heidi

295

E-Print Network 3.0 - adiabatic circular cylinder Sample Search...  

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

1983;105:161-7. 2 Balabani S, Yianneskis M... on the flow past a circular cylinder at a subcritical ... Source: Luo, Xiaoyu - Department of Mathematics, University of Glasgow...

296

Aluminium cylinder crankcase for V6-diesel engines from Daimler-Chrysler  

Science Journals Connector (OSTI)

Based on many years experience in the production of cylinder crankcases, which have been supplied to customers in the European and North American markets since 1994, Hydro Aluminium Alucast GmbH, ... manufacture ...

Dirk Barschkett; Klaus Lellig; Jens Püschel; Marcus Speicher

2006-02-01T23:59:59.000Z

297

Rocking and rolling down an incline : the dynamics of nested cylinders on a ramp  

E-Print Network (OSTI)

In this thesis, I report the results of a combined experimental and theoretical investigation of a journal bearing, specifically, a cylinder suspended in a viscous fluid housed within a cylindrical shell, rolling down an ...

Vener, David Paul

2006-01-01T23:59:59.000Z

298

In-Cylinder Mechanisms of PCI Heat-Release Rate Control by Fuel Reactivity Stratification  

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

Explores in-cylinder mechanisms by which fuel reactivity stratification via a two fuel system affects premixed charge compression ignition heat release rate to achieve diesel-like efficiency

299

In situ control of lubricant properties for reduction of power cylinder friction through thermal barrier coating  

E-Print Network (OSTI)

Lowering lubricant viscosity to reduce friction generally carries a side effect of increased metal-metal contact in mixed or boundary lubrication, for example near top ring reversal along the engine cylinder liner. A ...

Molewyk, Mark Allen

2014-01-01T23:59:59.000Z

300

Stochastic Processes for Modeling the Wear of Marine Engine Cylinder Liners  

Science Journals Connector (OSTI)

In this chapter, a stochastic process-based approach is adopted to formulate the reliability function for cylinder liners of diesel engines used for marine propulsion, which fail when their wear exceeds a specifi...

Massimiliano Giorgio; Maurizio Guida; Gianpaolo Pulcini

2009-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "depleted uf6 cylinder" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


301

Tribological behavior of plasma spray coatings for marine diesel engine piston ring and cylinder liner  

Science Journals Connector (OSTI)

High-temperature wear characteristics between plasma spray coated piston rings and cylinder liners were investigated to find the optimum combination of coating materials using the disc-on-plate reciprocating w...

Jong-Hyun Hwang; Myoung-Seoup Han…

2006-06-01T23:59:59.000Z

302

Spark-plug-mounted fiber optic sensor for measuring in-cylinder pressure in engines  

E-Print Network (OSTI)

A new design for an in-cylinder fiber Fabry-Perot interferometer (FFPI) pressure sensor suitable for automotive engines has been investigated experimentally. The FFPI sensor consists of a single mode fiber containing two internal mirrors which form...

Bae, Taehan

2012-06-07T23:59:59.000Z

303

Wave Interactions with Arrays of Bottom-Mounted Circular Cylinders: Investigation of Optical and Acoustical Analogies  

E-Print Network (OSTI)

Wave scattering by arrays of cylinders has received special attention by many authors and analytical solutions have been derived. The investigation of optical and acoustical analogies to the problem of interaction of water waves with rigid...

Baquet, Aldric

2010-10-12T23:59:59.000Z

304

Wave Energy Extraction from an Oscillating Water Column in a Truncated Circular Cylinder  

E-Print Network (OSTI)

Oscillating Water Column (OWC) device is a relatively practical and convenient way that converts wave energy to a utilizable form, which is usually electricity. The OWC is kept inside a fixed truncated vertical cylinder, which is a hollow structure...

Wang, Hao

2013-07-19T23:59:59.000Z

305

Spectral modeling of two incline cylinders with validation in the time domain  

E-Print Network (OSTI)

Clusters of long slender members such as risers or tendons are commonly found on deep water offshore platforms. Current practice is to space these slender structural members far enough apart to assume that they behave as a single cylinder without...

Oswalt, Aaron Jacob

2012-06-07T23:59:59.000Z

306

Testing of one-inch UF{sub 6} cylinder valves under simulated fire conditions  

SciTech Connect

Accurate computational models which predict the behavior of UF{sub 6} cylinders exposed to fires are required to validate existing firefighting and emergency response procedures. Since the cylinder valve is a factor in the containment provided by the UF{sub 6} cylinder, its behavior under fire conditions has been a necessary assumption in the development of such models. Consequently, test data is needed to substantiate these assumptions. Several studies cited in this document provide data related to the behavior of a 1-inch UF{sub 6} cylinder valve in fire situations. To acquire additional data, a series of tests were conducted at the Paducah Gaseous Diffusion Plant (PGDP) under a unique set of test conditions. This document describes this testing and the resulting data.

Elliott, P.G. [Martin Marietta Energy Systems, Inc., Paducah, KY (United States)

1991-12-31T23:59:59.000Z

307

The torsional vibrations of marine Diesel engines under fault operation of its cylinders  

Science Journals Connector (OSTI)

The torsional vibrations calculation of Diesel engines is usually performed for different speeds of revolutions but for uniform operation and behaviour of each cylinder. This condition is true only for new of ...

Dr.-Ing. Ioannis E. Margaronis

1992-01-01T23:59:59.000Z

308

Formation of Colloidal Shells on Acidic Droplets Undergoing Neutralization in Marine Diesel Engine Cylinder Oils  

Science Journals Connector (OSTI)

In this study, a novel colloidal shell formation phenomenon was observed when sulfuric acid droplets underwent neutralization in marine cylinder lubricant at 115 ± 5 °C ... the formation of well-known deposits fo...

Miguel Garcia-Bermudes; Riccardo Rausa; Kyriakos Papadopoulos

2013-07-01T23:59:59.000Z

309

Strain localization and cyclic damage of polyurethane foam cylinders: experimental tests and theoretical model  

E-Print Network (OSTI)

Strain localization and cyclic damage of polyurethane foam cylinders: experimental tests subject to progressive damage. The chain of springs models the strain localization, and the second series qualitative agreement with the experiments. Keywords: polyurethane foams; strain localization; cyclic damage

Boyer, Edmond

310

The control of air flow separation on a cylinder by rearward mass ejection  

E-Print Network (OSTI)

THE CONTROL OF AIR FLOW SEPARATION ON A CYLINDER BY REARWARD MASS EJECTION A Thesis By LEOPOLDO FERNANDO PEREZ Submitted to the Graduate College oi the Texas A 4 M University in partial fulfillment of the requirements for the degree... of MASTER OF SCIENCE May 1965 Major Subject; Aerospace Engineering THE CONTROL OF AIR FLOW SEPARATION ON A CYLINDER BY REARWARD MASS EJECTION A Thesis By LEOPOLDO FERNANDO PEREZ Approved as to style and content by: (C airman of Committee) (Head...

Perez, Leopoldo Fernando

1965-01-01T23:59:59.000Z

311

A three dimensional finite element code for the analysis of damage in helically wound composite cylinders  

E-Print Network (OSTI)

A THREE DIMENSIONAL FINITE ELEMENT CODE FOR THE ANALYSIS OF DAMAGE IN HELICALLY WOUND COMPOSITE CYLINDERS A Thesis MARVIiN AiNTHONY ZOCHER Submitted to the Office of Graduate Studies of Texas Ag:M University in partial fulfillment... of the requirements for the degree of MASTER OF SCIENCE December 1990 Major Subject; Aerospace Engineering A THREE DIMENSIONAL FINITE ELEMENT CODE FOR THE ANALYSIS OF DAMAGE IN HELICALLY WOUND COMPOSITE CYLINDERS A Thesis by i%1ARVIN ANTHONY ZOCHER Approved...

Zocher, Marvin Anthony

2012-06-07T23:59:59.000Z

312

Fourier analysis for generalized cylinders with polar models of cross-sections  

E-Print Network (OSTI)

FOURIER ANALYSIS FOR GENERALIZED CYLINDERS WITH POLAR MODELS OF CROSS-SECTIONS A Thesis by WILLIAM CLARENCE FORSYTHE Submitted to the Office of Graduate Studies of Texas A&M University in partial fulfillment of the requirements for the degree... of MASTER OF SCIENCE May 1990 Major Subject: Computer Science FOURIER ANALYSIS FOR GENERALIZED CYLINDERS WITH POLAR MODELS OF CROSS-SECTIONS A Thesis by WILLIAM CLARENCE FORSYTHE Approved as to style and content by: Amitabha Mukerjee (Chair...

Forsythe, William Clarence

2012-06-07T23:59:59.000Z

313

Cermet Waste Packages Using Depleted Uranium Dioxide and Steel  

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

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

314

Shock induced multi-mode damage in depleted uranium  

SciTech Connect

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

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

2009-01-01T23:59:59.000Z

315

depleted underground oil shale for the permanent storage of carbon  

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

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

316

Copper-triazole interaction and coolant inhibitor depletion  

SciTech Connect

To a large extent, the depletion of tolyltriazole (TTZ) observed in several field tests may be attributed to the formation of a protective copper-triazole layer. Laboratory aging studies, shown to correlate with field experience, reveal that copper-TTZ layer formation depletes coolant TTZ levels in a fashion analogous to changes observed in the field. XPS and TPD-MS characterization of the complex formed indicates a strong chemical bond between copper and the adsorbed TTZ which can be desorbed thermally only at elevated temperatures. Electrochemical polarization experiments indicate that the layer provides good copper protection even when TTZ is absent from the coolant phase. Examination of copper cooling system components obtained after extensive field use reveals the presence of a similar protective layer.

Bartley, L.S.; Fritz, P.O.; Pellet, R.J.; Taylor, S.A.; Van de Ven, P. [Texaco Fuels and Lubricants Technology Dept., Beacon, NY (United States)

1999-08-01T23:59:59.000Z

317

Safety evaluation for packaging (onsite) depleted uranium waste boxes  

SciTech Connect

This safety evaluation for packaging (SEP) allows the one-time shipment of ten metal boxes and one wooden box containing depleted uranium material from the Fast Flux Test Facility to the burial grounds in the 200 West Area for disposal. This SEP provides the analyses and operational controls necessary to demonstrate that the shipment will be safe for the onsite worker and the public.

McCormick, W.A.

1997-08-27T23:59:59.000Z

318

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

E-Print Network (OSTI)

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

D'Abramo, G

2003-01-01T23:59:59.000Z

319

E-Print Network 3.0 - allogeneic t-cell depleted Sample Search...  

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

t-cell depleted Search Powered by Explorit Topic List Advanced Search Sample search results for: allogeneic t-cell depleted Page: << < 1 2 3 4 5 > >> 1 haematologicathe hematology...

320

Diversity of Glycosyl Hydrolases from Cellulose-Depleting Communities Enriched from Casts of Two Earthworm Species  

Science Journals Connector (OSTI)

...metagenomic fosmid libraries from cellulose-depleting...annotated in public databases as...introducing myRDP space and quality controlled public data. Nucleic...metagenomic fosmid libraries from cellulose-depleting...annotated in public databases as...

Ana Beloqui; Taras Y. Nechitaylo; Nieves López-Cortés; Azam Ghazi; María-Eugenia Guazzaroni; Julio Polaina; Axel W. Strittmatter; Oleg Reva; Agnes Waliczek; Michail M. Yakimov; Olga V. Golyshina; Manuel Ferrer; Peter N. Golyshin

2010-07-09T23:59:59.000Z

Note: This page contains sample records for the topic "depleted uf6 cylinder" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


321

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

E-Print Network (OSTI)

??Texture evolution of depleted uranium is investigated using a viscoplastic self-consistent model. Depleted uranium, which has the same structure as alpha-uranium, is difficult to model… (more)

Ho, John

2012-01-01T23:59:59.000Z

322

Transgenerational transmission of genetic damage by depleted uranium and tungsten alloy  

Science Journals Connector (OSTI)

...Abstract 3464: Epigenetic mechanism is involved in depleted uranium-induced transformation in human lung epithelial...Wise 1 1Univ. of Southern Maine, Portland, ME. Depleted uranium (DU) is commonly used in military applications...

Alexandra Miller

2007-05-01T23:59:59.000Z

323

Clinical diagnostic indicators of renal and bone damage in rats intramuscularly injected with depleted uranium  

Science Journals Connector (OSTI)

......M. Depleted and natural uranium: chemistry and toxicological...internal contamination with uranium. Croat. Med. J. 40...1999). 5. Mould, R. F. Depleted uranium and radiation-induced lung cancer and leukaemia. Br. J......

S. Fukuda; M. Ikeda; M. Chiba; K. Kaneko

2006-06-01T23:59:59.000Z

324

Identification of Health Risks in Workers Staying and Working on the Terrains Contaminated with Depleted Uranium  

Science Journals Connector (OSTI)

......p 105185. 5. UNEP. (2001) Depleted Uranium in Kosovo. Post Conflict Environmental...pp 98115. 6. UNEP. (2002) Depleted Uranium in Serbia and Montenegro Post...Lundin, A. (2004) Incidence of cancer among Swedish military and civil......

Snezana Milacic; Jadranko Simic

2009-05-01T23:59:59.000Z

325

E-Print Network 3.0 - antarctic ozone depletion Sample Search...  

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

-B and Biosphere." Oecologia 128(1-2): 1-296. (1997). Ozone depletion FAQ Part IV: UV radiation and its effects... -B radiation due to stratospheric ozone depletion on global...

326

Transgenerational transmission of genetic damage by depleted uranium and tungsten alloy  

Science Journals Connector (OSTI)

...Epigenetic mechanism is involved in depleted uranium-induced transformation in human...Southern Maine, Portland, ME. Depleted uranium (DU) is commonly used in military...research information on the potential health hazards of DU exposure. In our...

Alexandra Miller

2007-05-01T23:59:59.000Z

327

Abstract B41: Depleted uranium-induced oxidative stress in human bronchial epithelial cells  

Science Journals Connector (OSTI)

...Science of Cancer Health Disparities- Feb...AZ Abstract B41: Depleted uranium-induced oxidative...Science of Cancer Health Disparities- Feb...high deposits of uranium or tailings. There...occupational exposures to depleted uranium via military...

Monica Yellowhair; Leigh A. Henricksen; Aneesha Hossain; Kathleen Dixon; and R. Clark Lantz

2009-02-01T23:59:59.000Z

328

Abstract B41: Depleted uranium-induced oxidative stress in human bronchial epithelial cells  

Science Journals Connector (OSTI)

...Association for Cancer Research 1 February...The Science of Cancer Health Disparities...Abstract B41: Depleted uranium-induced oxidative...Carefree, AZ Cancer and mortality...deposits of uranium or tailings...exposures to depleted uranium via...

Monica Yellowhair; Leigh A. Henricksen; Aneesha Hossain; Kathleen Dixon; and R. Clark Lantz

2009-02-01T23:59:59.000Z

329

Transgenerational transmission of genetic damage by depleted uranium and tungsten alloy  

Science Journals Connector (OSTI)

...American Association for Cancer Research April 15, 2010...mechanism is involved in depleted uranium-induced transformation...Maine, Portland, ME. Depleted uranium (DU) is commonly...American Association for Cancer Research; 2010 Apr 17-21...

Alexandra Miller

2007-05-01T23:59:59.000Z

330

Depleted uranium hexafluoride – technogenic raw material for obtaining high-purity inorganic fluorides  

Science Journals Connector (OSTI)

The problem of handling depleted uranium hexafluoride is discussed. An effective and ecologically safe variant of complex recycling of depleted uranium hexafluoride with uranium oxides, organic compounds, and hig...

E. P. Magomedbekov; S. V. Chizhevskaya; O. M. Klimenko; A. V. Davydov…

2012-02-01T23:59:59.000Z

331

Are plasma depletions in Saturn's ionosphere a signature of time-dependent water input?  

E-Print Network (OSTI)

Are plasma depletions in Saturn's ionosphere a signature of time- dependent water input? Luke Moore the presence of numerous ``ionospheric holes'', or plasma depletions, in Saturn's upper atmosphere that cannot the observed plasma depletions. The required influxes present a target to assess for the possible sources

Mendillo, Michael

332

Spacelab-2 Plasma Depletion Experiments for Ionospheric and Radio Astronomical Studies  

Science Journals Connector (OSTI)

...Spacelab-2 Plasma Depletion...Spacelab-2 Plasma Depletion...releasing large amounts of...Earth's upper atmosphere to chemically...spanned an area of several...16.5-MHZ AND THE GALACTIC...Spacelab-2 plasma depletion...releasing large amounts of...Earth's upper atmosphere to chemically...spanned an area of several...

M. MENDILLO; J. BAUMGARDNER; D. P. ALLEN; J. FOSTER; J. HOLT; G. R.A. ELLIS; A. KLEKOCIUK; G. REBER

1987-11-27T23:59:59.000Z

333

Flow patterns and heat transfer around six in-line circular cylinders at low Reynolds number  

E-Print Network (OSTI)

The flow field and the heat transfer around six in-line iso-thermal circular cylinders has been studied by mean of numerical simulations. Two values of the center to center spacing ($s=3.6d$ and $4d$, where $d$ is the cylinder diameter) at Reynolds number of $100$ and Prandtl number of $0.7$ has been investigated. Similarly to the in-line two cylinder configuration, in this range a transition in the flow and in the heat transfer occurs. Two different flow patterns have been identified: the stable shear layer (SSL) mode and the shear layer secondary vortices (SLSV) mode, at $3.6$ and $4$ spacing ratio ($s/d$), respectively. At $s/d=3.6$ the flow pattern causes the entrainment of cold fluid on the downstream cylinders enhancing the heat transfer. On the other hand at $s/d=4$ two stable opposite shear layer prevent the cold fluid entrainment over the downstream cylinders reducing their heat exchange. The overall time average heat transfer of the array is enhanced up to 25% decreasing the spacing ratio from $4$ t...

Fornarelli, Francesco; Lippolis, Antonio

2014-01-01T23:59:59.000Z

334

A study Assessing the Genotoxicity in Rats after Chronic Oral Exposure to a Low Dose of Depleted Uranium  

Science Journals Connector (OSTI)

......A. (2001) Depleted uranium and public health. BMJ. 322...phenotype by depleted uranium-uranyl chloride. Environ. Health Perspect 106...radiological risk from depleted uranium in war scenarious. Health Phys. 82: 1420......

Yuhui Hao; Rong Li; Yanbing Leng; Jiong Ren; Jing Liu; Guoping Ai; Hui Xu; Yongping Su; Tianmin Cheng

2009-11-01T23:59:59.000Z

335

Abstract 3464: Epigenetic mechanism is involved in depleted uranium-induced transformation in human lung epithelial cells  

Science Journals Connector (OSTI)

...Association for Cancer Research 15 April...Abstract 3590: Depleted uranium-induced leukemia...development. Depleted uranium is used in military...Max Costa. Depleted uranium-induced leukemia...Association for Cancer Research; 2013...

Hong Xie; Carolyne LaCerte; and John P. Wise

2010-04-15T23:59:59.000Z

336

Variations of the Isotopic Ratios of Uranium in Environmental Samples Containing Traces of Depleted Uranium: Theoretical and Experimental Aspects  

Science Journals Connector (OSTI)

......Samples Containing Traces of Depleted Uranium: Theoretical and Experimental...for the detection of traces of depleted uranium (DU) in environmental samples...percentage composition is about 20% depleted uranium and 80% natural uranium, for......

M. Magnoni; S. Bertino; B. Bellotto; M. Campi

2001-12-01T23:59:59.000Z

337

Characterisation and dissolution of depleted uranium aerosols produced during impacts of kinetic energy penetrators against a tank  

Science Journals Connector (OSTI)

......Characterisation and dissolution of depleted uranium aerosols produced during impacts...Aerosols produced during impacts of depleted uranium (DU) penetrators against the...Characterisation and dissolution of depleted uranium aerosols produced during impacts......

V. Chazel; P. Gerasimo; V. Debouis; P. Laroche; F. Paquet

2003-07-01T23:59:59.000Z

338

A study Assessing the Genotoxicity in Rats after Chronic Oral Exposure to a Low Dose of Depleted Uranium  

Science Journals Connector (OSTI)

......Oral Exposure to a Low Dose of Depleted Uranium Yuhui Hao Rong Li * Yanbing...by chronic oral exposure to depleted uranium (DU). Materials and methods...exposure to a low dose of DU. Depleted uranium|Ingestion|Genotoxicity......

Yuhui Hao; Rong Li; Yanbing Leng; Jiong Ren; Jing Liu; Guoping Ai; Hui Xu; Yongping Su; Tianmin Cheng

2009-11-01T23:59:59.000Z

339

Efficacy of oral and intraperitoneal administration of CBMIDA for removing uranium in rats after parenteral injections of depleted uranium  

Science Journals Connector (OSTI)

......after parenteral injections of depleted uranium S. Fukuda 1 * M. Ikeda 1 M...intramuscular (i.m.) injections of depleted uranium (DU) was examined and the...with uranium. INTRODUCTION Depleted uranium (DU) can affect human health......

S. Fukuda; M. Ikeda; M. Nakamura; X. Yan; Y. Xie

2009-01-01T23:59:59.000Z

340

Detonation product equation-of-state directly from the cylinder test  

SciTech Connect

A quasi-analytic method is presented for obtaining the detonation-product expansion isentrope directly from cylinder test data. The idea actually dates to G.I. Taylor`s invention of the cylinder test--though he did not implement it for lack of data--but has received little attention since. The method uses the fact that the pressure may be determined from the measured wall trajectory, whereupon the associated specific volume follows from the equations of continuity and momentum. Using the HMX-based explosive PBX9501 as an example, the method makes a good prediction of the detonation pressure and the basic form of {gamma}, the isentropic exponent. However, the model isentrope is slightly low in the mid-range, perhaps because the standard cylinder test is not optimal for this analysis. A better-suited design is proposed, and a simple ad-hoc correction is offered that reconciles the standard test.

Hill, L.G.

1997-10-01T23:59:59.000Z

Note: This page contains sample records for the topic "depleted uf6 cylinder" 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

Aspects of uranium chemistry pertaining to UF{sub 6} cylinder handling  

SciTech Connect

Under normal conditions, the bulk of UF{sub 6} in storage cylinders will be in the solid state with an overpressure of gaseous UF{sub 6} well below one atmosphere. Corrosion of the interior of the cylinder will be very slow, with formation of a small amount of reduced fluoride, probably U{sub 2}F{sub 9}. The UO{sub 3}-HF-H{sub 2}O phase diagram indicates that reaction of any inleaking water vapor with the solid UF{sub 6} will generate the solid material [H{sub 3}O]{sub 2}(U(OH){sub 4}F{sub 4}) in equilibrium with an aqueous HF solution containing only small amounts of uranium. The corrosion of the steel cylinder by these materials may be enhanced over that observed with gaseous anhydrous UF{sub 6}.

Ritter, R.L.; Barber, E.J. [Martin Marietta Energy Systems, Inc., Oak Ridge, TN (United States)

1991-12-31T23:59:59.000Z

342

Heat transfer to a horizontal cylinder in a shallow bubble column  

Science Journals Connector (OSTI)

Abstract Heat transfer coefficient correlations for tall bubble columns are unable to predict heat transfer in shallow bubble columns, which have unique geometry and fluid dynamics. In this work, the heat transfer coefficient is measured on the surface of a horizontal cylinder immersed in a shallow air–water bubble column. Superficial velocity, liquid depth, and cylinder height and horizontal position with respect to the sparger orifices are varied. The heat transfer coefficient is found to increase with height until reaching a critical height, and a dimensionless, semi-theoretical correlation is developed that incorporates superficial velocity, liquid properties, and height. Additionally, the more minor effects of flow regime, column region, and bubble impact are discussed. Notably, the heat transfer coefficient can be as high in the region of bubble coalescence as in the bulk of the column, but only if bubbles impact the cylinder. The correlation and discussion provide a framework for modeling and designing shallow, coil-cooled bubble columns.

Emily W. Tow; John H. Lienhard V

2014-01-01T23:59:59.000Z

343

Selection of a management strategy for depleted uranium hexafluoride  

SciTech Connect

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

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

1995-09-06T23:59:59.000Z

344

Inhibition of lytic infection of pseudorabies virus by arginine depletion  

SciTech Connect

Pseudorabies virus (PRV) is a member of Alphahepesviruses; it is an enveloped virus with a double-stranded DNA genome. Polyamines (such as spermine and spermidine) are ubiquitous in animal cells and participate in cellular proliferation and differentiation. Previous results of our laboratory showed that the PRV can accomplish lytic infection either in the presence of exogenous spermine (or spermidine) or depletion of cellular polyamines. The amino acid arginine is a precursor of polyamine biosynthesis. In this work, we investigated the role of arginine in PRV infection. It was found that the plaque formation of PRV was inhibited by arginase (enzyme catalyzing the conversion of arginine into ornithine and urea) treatment whereas this inhibition can be reversed by exogenous arginine, suggesting that arginine is essential for PRV proliferation. Western blotting was conducted to study the effect of arginine depletion on the levels of structural proteins of PRV in virus-infected cells. Four PRV structural proteins (gB, gE, UL47, and UL48) were chosen for examination, and results revealed that the levels of viral proteins were obviously reduced in long time arginase treatment. However, the overall protein synthesis machinery was apparently not influenced by arginase treatment either in mock or PRV-infected cells. Analyzing with native gel, we found that arginase treatment affected the mobility of PRV structural proteins, suggesting the conformational change of viral proteins by arginine depletion. Heat shock proteins, acting as molecular chaperons, participate in protein folding and translocation. Our results demonstrated that long time arginase treatment could reduce the expression of cellular heat shock proteins 70 (hsc70 and hsp70), and transcriptional suppression of heat shock protein 70 gene promoter was one of the mechanisms involved in this reduced expression.

Wang, H.-C. [Department of Veterinary Medicine, College of Veterinary Medicine, National Chung-Hsing University, Taichung 402, Taiwan (China); Kao, Y.-C. [Department of Veterinary Medicine, College of Veterinary Medicine, National Chung-Hsing University, Taichung 402, Taiwan (China); Chang, T-J. [Department of Veterinary Medicine, College of Veterinary Medicine, National Chung-Hsing University, Taichung 402, Taiwan (China); Wong, M.-L. [Department of Veterinary Medicine, College of Veterinary Medicine, National Chung-Hsing University, Taichung 402, Taiwan (China)]. E-mail: mlwong@dragon.nchu.edu.tw

2005-08-26T23:59:59.000Z

345

Engineering Analysis for Disposal of Depleted Uranium Tetrafluoride (UF4)  

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

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

346

Depleted uranium storage and disposal trade study: Summary report  

SciTech Connect

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

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

2000-02-01T23:59:59.000Z

347

Microstructure of depleted uranium under uniaxial strain conditions  

Science Journals Connector (OSTI)

Uranium samples of two different purities were used for spall strength measurements. Samples of depleted uranium were taken from very high purity material (38 ppm of carbon) and from material containing 280 ppm carbon. Experimental conditions were chosen to effectively arrest the microstructural damage at two places in the development to full spall separation. Samples were soft recovered and characterized with respect to the microstructure and the form of damage. This allowed determination of the dependence of spall mechanisms on stress level stress state and sample purity. This information is used in developing a model to predict the mode of fracture.

A. K. Zurek; J. D. Embury; A. Kelly; W. R. Thissell; R. L. Gustavsen; J. E. Vorthman; R. S. Hixson

1998-01-01T23:59:59.000Z

348

Background Fact Sheet Transfer of Depleted Uranium and Subsequent Transactions  

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

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

349

Random wave forces on a free-to-surge vertical cylinder  

E-Print Network (OSTI)

of offshore structures and may explain some of the variability between measured and calculated forces. 45 REFERENCES [2] [31 [4] [51 [6] [71 [8] [10] [12] Aagsard, P. lvl. and Dean, R. G. , "Wave Forces: Data Analysis and Engineering Calculation...' the fluid, and D is the diameter of thc pile or cylinder. The total wave induced force acting on the cylinder is considered as the sum of a viscous drag force component and an inertia component. VVhen the structure moves in response to hydrodynamic loads...

Sajonia, Charles Blake

2012-06-07T23:59:59.000Z

350

A study of gravity wave induced pressure variations in the presence of a submerged cylinder  

E-Print Network (OSTI)

11 5 Recorder Calibration For A Water Depth of 28 Inches 13 6 Sample Oscillograph Record 16 7 Comparison of Wave Pressure for Three Wave Lengths 23 8 Comparison of Wave Pressure at Different Cylinder Depths 24-25 9 Comparison of Wave Pressure... of sufficiently small height A p = P ft ? 2.9 With no cylinder present, it follows from 2*6 that ( A p ) ^ = p Ao* cosh k(y + d) sin (kx - crt) ? 2*10 In view of relation 2*14 below, relation 2*11 as applied at the bottom (y = - d) reduces to ( A p...

Ellis, Roy

2013-10-04T23:59:59.000Z

351

A simultaneous parametric analysis of the in-cylinder processes for diesel engines  

Science Journals Connector (OSTI)

This paper describes the basic methodological principles and the results of development and practical application of simultaneous complex parametric analysis of the in-cylinder processes and thermal load on Cylinder Piston Units (CPU) in diesel engines. The application of this method to research and conceptualise engine design allows us to choose an optimal combination of the CPU parameters and diesel engine control. As a result, an admissible level of thermal stress in the CPU and low fuel consumption are achieved. The method was practically used for upgrading high-speed diesel engines of the trademarks CHN 16.5/18.5, BMD and D20.

S. Lebedevas; G. Lebedeva; A. Pikunas; B. Spruogis

2011-01-01T23:59:59.000Z

352

Internal combuston engine having separated cylinder head oil drains and crankcase ventilation passages  

DOE Patents (OSTI)

An internal combustion engine includes separated oil drain-back and crankcase ventilation passages. The oil drain-back passages extend from the cylinder head to a position below the top level of oil in the engine's crankcase. The crankcase ventilation passages extend from passages formed in the main bearing bulkheads from positions above the oil level in the crankcase and ultimately through the cylinder head. Oil dams surrounding the uppermost portions of the crankcase ventilation passages prevent oil from running downwardly through the crankcase ventilation passages.

Boggs, David Lee (Bloomfield Hills, MI); Baraszu, Daniel James (Plymouth, MI); Foulkes, David Mark (Erfstadt, DE); Gomes, Enio Goyannes (Ann Arbor, MI)

1998-01-01T23:59:59.000Z

353

Modeling the Effect of Fuel Ethanol Concentration on Cylinder Pressure Evolution in Direct-Injection Flex-Fuel Engines  

E-Print Network (OSTI)

Modeling the Effect of Fuel Ethanol Concentration on Cylinder Pressure Evolution in Direct the fuel vaporization pro- cess for ethanol-gasoline fuel blends and the associated charge cooling effect experimental cylinder pressure for different gasoline-ethanol blends and various speeds and loads on a 2.0 L

Stefanopoulou, Anna

354

Energy-Saving Control of Single-Rod Hydraulic Cylinders with Programmable Valves and Improved Working Mode Selection  

E-Print Network (OSTI)

Energy-Saving Control of Single-Rod Hydraulic Cylinders with Programmable Valves and Improved. ABSTRACT This paper studies the energy-saving adaptive robust precision motion control of a single and individual cylinder chamber pressure control for better energy saving. With a typical four-way directional

Yao, Bin

355

Cylinder Pressures and Vibration in Internal Combustion Engine Condition G O Chandroth, A J C Sharkey and N E Sharkey  

E-Print Network (OSTI)

of sensory information. Inducing several faults in a 4 stroke diesel engine, cylinder pressure (P­stroke high speed diesel engine. The explosion of the hydrocarbon­air mixture within the complex geometryCylinder Pressures and Vibration in Internal Combustion Engine Condition Monitoring G O Chandroth

Sharkey, Amanda

356

Deterministic and stochastic state model of right generalized cylinder (RGC-sm): application in computer phantoms synthesis  

Science Journals Connector (OSTI)

RGC-sm is a state model proposed to describe complex-shaped objects within the family of right generalized cylinders (RGCs). A continuous deformation of a planar curve (contour) along the object's axis describes its surface. The contour, locally orthogonal ... Keywords: 3D image analysis, blood vessel, generalized cylinder, phantom synthesis, segmentation, state model

Jacques Azencot; Maciej Orkisz

2003-11-01T23:59:59.000Z

357

Sampling Plan for Assaying Plates Containing Depleted or Normal Uranium  

SciTech Connect

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

Ivan R. Thomas

2011-11-01T23:59:59.000Z

358

Calculating Capstone Depleted Uranium Aerosol Concentrations from Beta Activity Measurements  

SciTech Connect

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

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

2009-03-01T23:59:59.000Z

359

Radiological air quality in a depleted uranium storage vault  

SciTech Connect

The radiological air quality of two storage vaults, one with depleted uranium (DU) and one without, was evaluated and compared. The intent of the study was to determine if the presence of stored DU would significantly contribute to the gaseous/airborne radiation level compared to natural background. Both vaults are constructed out of concrete and are dimensionally similar. The vaults are located on the first floor of the same building. Neither vault has air supply or air exhaust. The doors to both vaults remained closed during the evaluation period, except for brief and infrequent access by the operational group. One vault contained 700 KG of depleted uranium, and the other vault contained documents inside of file cabinets. Radon detectors and giraffe air samplers were used to gather data on the quantity of gaseous/airborne radionuclides in both vaults. The results of this study indicated that there was no significant difference in the quantity of gaseous/airborne radionuclides in the two vaults. This paper gives a discussion of the effects of the stored DU on the air quality, and poses several theories supporting the results.

Robinson, T.; Cucchiara, A.L.

1999-03-01T23:59:59.000Z

360

Depleted uranium residual radiological risk assessment for Kosovo sites  

Science Journals Connector (OSTI)

During the recent conflict in Yugoslavia, depleted uranium rounds were employed and were left in the battlefield. Health concern is related to the risk arising from contamination of areas in Kosovo with depleted uranium penetrators and dust. Although chemical toxicity is the most significant health risk related to uranium, radiation exposure has been allegedly related to cancers among veterans of the Balkan conflict. Uranium munitions are considered to be a source of radiological contamination of the environment. Based on measurements and estimates from the recent Balkan Task Force UNEP mission in Kosovo, we have estimated effective doses to resident populations using a well-established food-web mathematical model (RESRAD code). The UNEP mission did not find any evidence of widespread contamination in Kosovo. Rather than the actual measurements, we elected to use a desk assessment scenario (Reference Case) proposed by the UNEP group as the source term for computer simulations. Specific applications to two Kosovo sites (Planeja village and Vranovac hill) are described. Results of the simulations suggest that radiation doses from water-independent pathways are negligible (annual doses below 30 ?Sv). A small radiological risk is expected from contamination of the groundwater in conditions of effective leaching and low distribution coefficient of uranium metal. Under the assumptions of the Reference Case, significant radiological doses (>1 mSv/year) might be achieved after many years from the conflict through water-dependent pathways. Even in this worst-case scenario, DU radiological risk would be far overshadowed by its chemical toxicity.

Marco Durante; Mariagabriella Pugliese

2003-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "depleted uf6 cylinder" 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

SHOCKWAVE PROFILE AND BAUSCHINGER EFFECT IN DEPLETED URANIUM  

Science Journals Connector (OSTI)

Dynamic damage evolution in materials is of growing interest in particular the role of defect structure on material strength during a dynamic experiment. Many studies in the past have seen strong correlations between the shockwave profile and the defect structure during dynamic experiments such as quasi?elastic release behavior. Bauschinger effect is a microstructurally controlled process in which a material displays a change in stress?strain characterisitics due to a change in the defect structure. Studies on depleted uranium have revealed indications of Bauschinger effect being a mechanism present during quasi?static experiments which could be a result of the large amount of twinning observed in these materials. As work continues to improve strength models it becomes imperitive to understand the role of defect structure on the properties of materials under dynamic conditions. The study reported here is an observation of the release wave behavior in depleted uranium that first undergoes compressive shock loading followed by a reversal of the loading direction upon release.

D. D. Koller; G. T. Gray III; R. S. Hixson

2007-01-01T23:59:59.000Z

362

Depleted uranium instead of lead in munitions: the lesser evil  

Science Journals Connector (OSTI)

Uranium has many similarities to lead in its exposure mechanisms, metabolism and target organs. However, lead is more toxic, which is reflected in the threshold limit values. The main potential hazard associated with depleted uranium is inhalation of the aerosols created when a projectile hits an armoured target. A person can be exposed to lead in similar ways. Accidental dangerous exposures can result from contact with both substances. Encountering uranium fragments is of minor significance because of the low penetration depth of alpha particles emitted by uranium: they are unable to penetrate even the superficial keratin layer of human skin. An additional cancer risk attributable to the uranium exposure might be significant only in case of prolonged contact of the contaminant with susceptible tissues. Lead intoxication can be observed in the wounded, in workers manufacturing munitions etc; moreover, lead has been documented to have a negative impact on the intellectual function of children at very low blood concentrations. It is concluded on the basis of the literature overview that replacement of lead by depleted uranium in munitions would be environmentally beneficial or largely insignificant because both lead and uranium are present in the environment.

Sergei V Jargin

2014-01-01T23:59:59.000Z

363

Subcriticality measurements for coupled uranium metal cylinders using the /sup 252/Cf-source-driven neutron noise analysis method  

SciTech Connect

Experiments performed with two coupled uranium metal cylinders are the first application to coupled systems of the /sup 252/Cf-source-driven neutron noise analysis method for obtaining the subcritical neutron multiplication factor. These coaxial cylinders were separated axially by various thicknesses of either air or borated plaster between the flat surfaces. In all measurements, the /sup 252/Cf neutron source was located at the center of the outer flat surface of one cylinder, and the two detectors were located in three configurations. By comparing the subcriticality from the measurements performed with borated plaster separating the uranium cylinders to those separated by air, it was found that the neutron multiplication factor was always increased by the insertion of borated plaster between the cylinders, regardless of their separation.

Mihalezo, J.T.; King, W.T.; Blakeman, E.D.

1987-01-01T23:59:59.000Z

364

Documents  

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

Discovery of Uranium Discovery of Uranium Uranium was discovered in 1789 by Martin Klaproth, a German chemist, who isolated an oxide of uranium while analyzing pitchblende samples from the Joachimsal silver mines in the former Kingdom of Bohemia located in the present day Czech Republic. more facts >> Mailing List Signup Receive e-mail updates about this project and web site. your e-mail address Sign Me Up Search: OK Button DUF6 Guide DU Uses DUF6 Management and Uses DUF6 Conversion EIS Documents News FAQs Internet Resources Glossary Home » Documents Search Documents: Search PDF Documents View a list of all documents Depleted UF6 Management Program Documents Downloadable documents about depleted UF6 management and related topics, including Depleted UF6 Conversion and Programmatic EIS documents

365

High–rate material modelling and validation using the Taylor cylinder impact test  

Science Journals Connector (OSTI)

...validation using the Taylor cylinder impact test P. J. Maudlin G. T. Gray III C. M...topography) with measured shapes from post-test Taylor specimens and quasi-static compression...extracted from the experimental post-test geometries using classical r-value definitions...

1999-01-01T23:59:59.000Z

366

Lattice Boltzmann simulations of 2D laminar flows past two tandem cylinders  

E-Print Network (OSTI)

Lattice Boltzmann simulations of 2D laminar flows past two tandem cylinders Alberto Mussa the lattice Boltzmann equation (LBE) with multiple-relaxation-time (MRT) colli- sion model to simulate laminar. Introduction In recent years the lattice Boltzmann equation (LBE) has become a viable means for computational

Luo, Li-Shi

367

On the Critical Solutions in Coating and Rimming Flow on a Uniformly Rotating Horizontal Cylinder  

Science Journals Connector (OSTI)

......Mathematics, University of Strathclyde, Livingstone Tower, 26 Richmond Street, Glasgow G1 1XH) [Received...results (fi lled squares denote results for SAE 30 oil, open squares ' Gold X ' oil, and stars SAE 50 oil) FLOW ON A ROTATING CYLINDER 381 Fig......

S. K. Wilson; R. Hunt; B. R. Duffy

2002-08-01T23:59:59.000Z

368

Fiber optic sensing technology for measuring in-cylinder pressure in automotive engines  

E-Print Network (OSTI)

A new fiber optic sensing technology for measuring in-cylinder pressure in automotive engines was investigated. The optic sensing element consists of two mirrors in an in-line single mode fiber that are separated by some distance. To withstand...

Bae, Taehan

2006-10-30T23:59:59.000Z

369

AIAA 2002-3297 INTERFERENCE BETWEEN TWO SIDE-BY-SIDE CYLINDERS IN HYPERSONIC  

E-Print Network (OSTI)

AIAA 2002-3297 INTERFERENCE BETWEEN TWO SIDE-BY-SIDE CYLINDERS IN HYPERSONIC RAREFIED-GAS FLOWS Vladimir V. Riabov* Rivier College, Nashua, New Hampshire 03060 Abstract Hypersonic rarefied-gas flows near of simple shape bodies have provided valuable information related to physics of hypersonic flows about

Riabov, Vladimir V.

370

Experimental and vector analysis on gamma type Stirling engine with hot power cylinder  

SciTech Connect

In 1993, the superiority of hot end connected power cylinder gamma type Stirling engine (HEC) compared to the conventional cold end connected power cylinder engine (CEC) was reported by Prof. J.Kentfield of the University of Calgary. It is a great thing that he introduced the HEC engine, and it reminded the authors that in 1980, they built and experimented with a three cylinder 3kW Stirling engine SRI-1, in which two cylinders are positively heated by gas, that is called HCH (Hot, Cold and Hot) engine as shown in a figure, and having similarity to the above HEC. The authors have developed a quite simple and understandable approximate harmonic vector analysis method for Stirling machines. By this, Kentfield`s HEC engine and their HCH engine are expressed by the same figure as shown in the paper. The similarity and superiority of HEC and HCH compared to CEC and CHC are easily shown by the vector analysis method with physical reason.

Isshiki, Naotsugu [Nihon Univ., Tokyo (Japan); Tsukahara, Shigeji [Ship Research Inst., Mitaka, Tokyo (Japan); Ohtomo, Michihiro [Tohoku Electric Power Co., Sendai (Japan)

1995-12-31T23:59:59.000Z

371

An automotive engine model for air-fuel ratio control using cylinder pressure information  

E-Print Network (OSTI)

and proven to have enough information for a feedback controller to be designed to close the loop so that the response of the system meets the specified objectives. A proposed control scheme based on the in-cylinder pressure information is presented. Analysis...

Nana, Emmanuel Tomdio

2012-06-07T23:59:59.000Z

372

PANS method of turbulence: simulation of high and low Reynolds number flows past a circular cylinder  

E-Print Network (OSTI)

cylinder are performed at ReD 140,000 and ReD 3900 using the PANS model. The high Reynolds number PANS results are compared with experimental results from Cantwell and Coles, Large Eddy Simulation results from Breuer, and Detached Eddy Simulation results...

Lakshmipathy, Sunil

2006-04-12T23:59:59.000Z

373

Extending the range of applicability of HTS cylinders in inductive superconducting fault current limiters  

Science Journals Connector (OSTI)

In the numerical routine used to estimate the temperature of the weak zones (channels) an error was introduced. Once the error is eliminated, the improvement in the thermal refrigeration of the inductive fault current limiters with artificial weak zones still remains but its importance is reduced; a channelled cylinder can refrigerate faster than a non-channelled one, as heat is removed also by conduction to the cold parts, but under a current fault the temperature of the weak zones is very much above those displayed in figure 3(b) and figure 4 (140 K is our best result, Tc being 105 K). As a consequence, the channelled cylinder needs about 9 s to get the critical temperature for the nominal current, whereas the non-channelled cylinder requires more than 15 s (both refrigerated by liquid nitrogen). Although appreciable, this improvement is still far from the usually required recovery time, which is about 1 s. This design could be more appropriate for a fault current limiter working in a slightly lower power grid or in a gaseous atmosphere, where the channelled sample is definitely much better than the non-channelled cylinder. To be competitive when operating in liquid nitrogen some additional mechanism should be implemented to avoid the excessive heating of the weak zones.

M R Osorio; J A Lorenzo; J A Veira; F Vidal

2008-01-01T23:59:59.000Z

374

Steady states and oscillatory instability of swirling flow in a cylinder with rotating top and bottom  

E-Print Network (OSTI)

/radius of the cylinder 1.5. The stability analysis showed that there are several most unstable linear modes instability may lead to an appearance and coexistence of more than one oscillating separation vortex bubble by the sudden appearance of a weak meridional recirculation also called ``separation vortex bubble'' near

Gelfgat, Alexander

376

ZPR-3 Assembly 11 : A cylindrical sssembly of highly enriched uranium and depleted uranium with an average {sup 235}U enrichment of 12 atom % and a depleted uranium reflector.  

SciTech Connect

Over a period of 30 years, more than a hundred Zero Power Reactor (ZPR) critical assemblies were constructed at Argonne National Laboratory. The ZPR facilities, ZPR-3, ZPR-6, ZPR-9 and ZPPR, were all fast critical assembly facilities. The ZPR critical assemblies were constructed to support fast reactor development, but data from some of these assemblies are also well suited for nuclear data validation and to form the basis for criticality safety benchmarks. A number of the Argonne ZPR/ZPPR critical assemblies have been evaluated as ICSBEP and IRPhEP benchmarks. Of the three classes of ZPR assemblies, engineering mockups, engineering benchmarks and physics benchmarks, the last group tends to be most useful for criticality safety. Because physics benchmarks were designed to test fast reactor physics data and methods, they were as simple as possible in geometry and composition. The principal fissile species was {sup 235}U or {sup 239}Pu. Fuel enrichments ranged from 9% to 95%. Often there were only one or two main core diluent materials, such as aluminum, graphite, iron, sodium or stainless steel. The cores were reflected (and insulated from room return effects) by one or two layers of materials such as depleted uranium, lead or stainless steel. Despite their more complex nature, a small number of assemblies from the other two classes would make useful criticality safety benchmarks because they have features related to criticality safety issues, such as reflection by soil-like material. ZPR-3 Assembly 11 (ZPR-3/11) was designed as a fast reactor physics benchmark experiment with an average core {sup 235}U enrichment of approximately 12 at.% and a depleted uranium reflector. Approximately 79.7% of the total fissions in this assembly occur above 100 keV, approximately 20.3% occur below 100 keV, and essentially none below 0.625 eV - thus the classification as a 'fast' assembly. This assembly is Fast Reactor Benchmark No. 8 in the Cross Section Evaluation Working Group (CSEWG) Benchmark Specificationsa and has historically been used as a data validation benchmark assembly. Loading of ZPR-3 Assembly 11 began in early January 1958, and the Assembly 11 program ended in late January 1958. The core consisted of highly enriched uranium (HEU) plates and depleted uranium plates loaded into stainless steel drawers, which were inserted into the central square stainless steel tubes of a 31 x 31 matrix on a split table machine. The core unit cell consisted of two columns of 0.125 in.-wide (3.175 mm) HEU plates, six columns of 0.125 in.-wide (3.175 mm) depleted uranium plates and one column of 1.0 in.-wide (25.4 mm) depleted uranium plates. The length of each column was 10 in. (254.0 mm) in each half of the core. The axial blanket consisted of 12 in. (304.8 mm) of depleted uranium behind the core. The thickness of the depleted uranium radial blanket was approximately 14 in. (355.6 mm), and the length of the radial blanket in each half of the matrix was 22 in. (558.8 mm). The assembly geometry approximated a right circular cylinder as closely as the square matrix tubes allowed. According to the logbook and loading records for ZPR-3/11, the reference critical configuration was loading 10 which was critical on January 21, 1958. Subsequent loadings were very similar but less clean for criticality because there were modifications made to accommodate reactor physics measurements other than criticality. Accordingly, ZPR-3/11 loading 10 was selected as the only configuration for this benchmark. As documented below, it was determined to be acceptable as a criticality safety benchmark experiment. A very accurate transformation to a simplified model is needed to make any ZPR assembly a practical criticality-safety benchmark. There is simply too much geometric detail in an exact (as-built) model of a ZPR assembly, even a clean core such as ZPR-3/11 loading 10. The transformation must reduce the detail to a practical level without masking any of the important features of the critical experiment. And it must do this without increasing the total uncertain

Lell, R. M.; McKnight, R. D.; Tsiboulia, A.; Rozhikhin, Y.; National Security; Inst. of Physics and Power Engineering

2010-09-30T23:59:59.000Z

377

Counts-in-Cylinders in the Sloan Digital Sky Survey with Comparisons to N-Body  

SciTech Connect

Environmental statistics provide a necessary means of comparing the properties of galaxies in different environments and a vital test of models of galaxy formation within the prevailing, hierarchical cosmological model. We explore counts-in-cylinders, a common statistic defined as the number of companions of a particular galaxy found within a given projected radius and redshift interval. Galaxy distributions with the same two-point correlation functions do not necessarily have the same companion count distributions. We use this statistic to examine the environments of galaxies in the Sloan Digital Sky Survey, Data Release 4. We also make preliminary comparisons to four models for the spatial distributions of galaxies, based on N-body simulations, and data from SDSS DR4 to study the utility of the counts-in-cylinders statistic. There is a very large scatter between the number of companions a galaxy has and the mass of its parent dark matter halo and the halo occupation, limiting the utility of this statistic for certain kinds of environmental studies. We also show that prevalent, empirical models of galaxy clustering that match observed two- and three-point clustering statistics well fail to reproduce some aspects of the observed distribution of counts-in-cylinders on 1, 3 and 6-h{sup -1}Mpc scales. All models that we explore underpredict the fraction of galaxies with few or no companions in 3 and 6-h{sup -1} Mpc cylinders. Roughly 7% of galaxies in the real universe are significantly more isolated within a 6 h{sup -1} Mpc cylinder than the galaxies in any of the models we use. Simple, phenomenological models that map galaxies to dark matter halos fail to reproduce high-order clustering statistics in low-density environments.

Berrier, Heather D.; Barton, Elizabeth J.; /UC, Irvine; Berrier, Joel C.; /Arkansas U.; Bullock, James S.; /UC, Irvine; Zentner, Andrew R.; /Pittsburgh U.; Wechsler, Risa H. /KIPAC, Menlo Park /SLAC

2010-12-16T23:59:59.000Z

378

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

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

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

379

Measurement of Holmium Rydberg series through MOT depletion spectroscopy  

E-Print Network (OSTI)

We report measurements of the absolute excitation frequencies of $^{165}$Ho $4f^{11}6sns$ and $4f^{11}6snd$ odd-parity Rydberg series. The states are detected through depletion of a magneto-optical trap via a two-photon excitation scheme. Measurements of 162 Rydberg levels in the range $n=40-101$ yield quantum defects well described by the Rydberg-Ritz formula. We observe a strong perturbation in the $ns$ series around $n=51$ due to an unidentified interloper at 48515.47(4) cm$^{-1}$. From the series convergence, we determine the first ionization potential $E_\\mathrm{IP}=48565.939(4)$ cm$^{-1}$, which is three orders of magnitude more accurate than previous work. This work represents the first time such spectroscopy has been done in Holmium and is an important step towards using Ho atoms for collective encoding of a quantum register.

Hostetter, J; Lawler, J E; Saffman, M

2014-01-01T23:59:59.000Z

380

Military use of depleted uranium assessment of prolonged population exposure  

E-Print Network (OSTI)

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

Giannardi, C

2001-01-01T23:59:59.000Z

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381

Depleted Uranium Report from the Health Council of the Netherlands  

Science Journals Connector (OSTI)

The Health Council of the Netherlands, which is an independent scientific advisory body established in 1902 `to advise the government and Parliament on the current level of knowledge with respect to public health issues', has recently published an overview report on depleted uranium. The title of the report is `Health risks of exposure to depleted uranium' and it is freely available in both English and the original Dutch language. A brief summary of the report that was published on 16 May 2001 is presented here. The use of ammunition containing depleted uranium (DU) in Kosovo and elsewhere in the Balkans has provoked disquiet in Europe. In the Netherlands, concern over the release of this material had already been aroused previously following the crash of the El-Al airliner in the Bijlmermeer district of Amsterdam in 1992. It was against this background that the President of the Health Council decided to set up a Committee charged with the task of reviewing the health risks of exposure to DU and the preventive measures required for individuals present in areas where DU has been released into the environment. After reviewing the properties of uranium in general and depleted uranium in particular, and presenting data on the occurrence of the element in the environment and biological tissues, the committee assessed the chemical and radiological health effect of uranium and uranium compounds. The Health Council Committee concludes that radioactive contamination of the lungs is the principal health risk to be considered in connection with exposure to slightly soluble uranium compounds in the atmosphere. For soluble compounds, the chemical toxic effect in the kidneys is the primary consideration. The toxicological effects are to some extent concordant with those of other heavy metals. For relevant exposure scenarios the Committee does not anticipate that exposure to DU will result in a demonstrable increased risk of diseases and symptoms among exposed individuals as a result of a radiological or chemical toxic effect exerted by this substance. Cancer In view of the fact that DU emits ionising radiation in the form of alpha particles, the induction of cancer, in principle, needs to be taken into account in relation to individuals exhibiting internal contamination with DU. In case of inhalation of slightly soluble DU compounds, attention will in particular need to be focused on the lungs. The radiation dose caused by incidental exposure to DU in the exposure scenarios considered is limited compared with the radiation dose received during a lifetime of exposure to natural uranium. As at the common levels of exposure to natural uranium a contribution to the induction of cancer in the population cannot be demonstrated, the Committee concludes that the same is true for exposure to DU. This general conclusion is also valid for the appearance of lung cancer and for the appearance of leukaemia after the inhalation of dust containing slightly soluble uranium compounds. Renal damage For soluble compounds, the risk posed by exposure to DU is principally of a chemical toxic nature. In the case of increasing exposure, abnormalities will first of all appear in the kidneys. Exposure to small amounts (milligrams) of uranium over short periods will therefore result in changes in the kidneys, which lead to acute, usually reversible, renal impairment. No such dose-dependency has been observed, however, in the frequency of chronic renal disorders among population groups who are chronically exposed to enhanced quantities of natural uranium. Nor have studies involving workers in the uranium industry and ex-military personnel (including the group with shrapnel in the body) to date produced any evidence that uranium can cause renal impairment. Thus the present body of scientific data tends to suggest an absence of irreparable renal damage as a result of the intake of DU in the exposure scenarios considered. Prevention Although the risks associated with exposure to DU for the exposure scenarios considered appear to be very limited, the fundamental prin

W F Passchier; J W N Tuyn

2002-01-01T23:59:59.000Z

382

Data Sheet No. 140 - World Energy Reserves and Depletion Policy  

Science Journals Connector (OSTI)

Publisher Summary This chapter focuses on world energy reserves and depletion policy. Viewed in the long term, it is extremely difficult to obtain an accurate view of the total energy reserves of the world. Even small, very well-explored countries such as the United Kingdom and Holland have discovered new reserves in the past 20 years. Solar power and wave power are available in vast quantities, but the percentage that can be recovered is debatable. The percentage recovery of oil and gas is open to improvement, and it may be that much smaller percentage recoveries of coal will be contemplated in the future when undersea mining or extraction without miners is contemplated. Nuclear power, using thermal reactors, does not extract all the power within the uranium or any of the power available from reserves of thorium. The coal industry will have to double its output and even greater demands may be made on it to provide liquid fuels for the transport industry.

Wilfrid Francis; Martin C. Peters

1980-01-01T23:59:59.000Z

383

The Lithium Depletion Boundary as a Clock and Thermometer  

E-Print Network (OSTI)

We take a critical look at the lithium depletion boundary (LDB) technique that has recently been used to derive the ages of open clusters. We identify the sources of experimental and systematic error and show that the probable errors are larger by approximately a factor two than presently claimed in the literature. We then use the Pleiades LDB age and photometry in combination with evolutionary models to define empirical colour-T_eff relations that can be applied to younger clusters. We find that these relationships DO NOT produce model isochrones that match the younger cluster data. We propose that this is due either to systematic problems in the evolutionary models or an age (gravity) sensitivity in the colour-T_eff relation which is not present in published atmospheric models.

R. D. Jeffries; T. Naylor

2000-09-12T23:59:59.000Z

384

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

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

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

385

E-Print Network 3.0 - arctic ozone depletion Sample Search Results  

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

1 Introduction Stratospheric ozone depletion has been one... (Chubachi, 1984; Farman et al., 1985), winter ozone ... Source: Ecole Polytechnique, Centre de mathmatiques...

386

EIS-0329: Proposed Construction, Operation, Decontamination/Decommissioning of Depleted Uranium Hexafluoride Conversion Facilities  

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

This EIS analyzes DOE's proposal to construct, operate, maintain, and decontaminate and decommission two depleted uranium hexafluoride (DUF 6) conversion facilities, at Portsmouth, Ohio, and Paducah, Kentucky.

387

Alloy of depleted uranium: Material for ?-protection of shipment packing sets  

Science Journals Connector (OSTI)

The effect of thermal action on the structure and physical and mechanical properties of an alloy based on depleted uranium and used for biological protection from ionizing...

V. K. Orlov; V. M. Sergeev; A. G. Semenov; V. V. Noskov…

388

E-Print Network 3.0 - antioxidant defence depletion Sample Search...  

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

for: antioxidant defence depletion Page: << < 1 2 3 4 5 > >> 1 Journal of Applied Ecology 2007 Summary: of antioxidants during their annual migrations to neutralize free...

389

High Pressure Fuel Storage Cylinders Periodic Inspection and End of Life Issues  

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

6/2010 6/2010 www.cleanvehicle.org 1 High Pressure Fuel Storage Cylinders Periodic Inspection and End of Life Issues DOE Vehicular Tank Workshop April 29, 2010 Douglas Horne, PE The Facts  High pressure Type 4 gaseous fuel tanks are now designed under standards that specify finite lifetimes of 15, 20 and 25 years based on specific design and testing (the HGV2 standard under development had a life as short as 10 years as an option)  It is unique within the transportation industry to have a critical device (the fuel tank) with a designated life that may be shorter than the vehicle itself  Although vehicle owners are told up front of the limited life fuel storage cylinders some tend to forget after 15 years  A parallel concern is the requirement for these fuel tanks

390

Non-Abelian vortices on a cylinder: Duality between vortices and walls  

SciTech Connect

We investigate vortices on a cylinder in supersymmetric non-Abelian gauge theory with hypermultiplets in the fundamental representation. We identify moduli space of periodic vortices and find that a pair of wall-like objects appears as the vortex moduli is varied. Usual domain walls also can be obtained from the single vortex on the cylinder by introducing a twisted boundary condition. We can understand these phenomena as a T duality among D-brane configurations in type II superstring theories. Using this T-duality picture, we find a one-to-one correspondence between the moduli space of non-Abelian vortices and that of kinky D-brane configurations for domain walls.

Eto, Minoru; Fujimori, Toshiaki; Isozumi, Youichi; Nitta, Muneto; Ohashi, Keisuke; Sakai, Norisuke [Department of Physics, Tokyo Institute of Technology, Tokyo 152-8551 (Japan); Ohta, Kazutoshi [Theoretical Physics Laboratory, The Institute of Physical and Chemical Research (RIKEN), Wako 351-0198 (Japan)

2006-04-15T23:59:59.000Z

391

Hydrodynamic particle migration in a concentrated suspension undergoing flow between rotating eccentric cylinders  

SciTech Connect

We report on experimental measurements and numerical predictions of shear-induced migration of particles in concentrated suspensions subjected to flow in the wide gap between a rotating inner cylinder placed eccentrically within a fixed outer cylinder (a cylindrical bearing). The suspensions consists of large, noncolloidal spherical particles suspended in a viscous Newtonian liquid. Nuclear magnetic resonance (NMR) imaging is used to measure the time evolution of concentration and velocity profiles as the flow induced particle migration from the initial, well-mixed state. A model originally proposed by Phillips et al. (1992) is generalized to two dimensions. The coupled equations of motion and particle migration are solved numerically using an explicit pseudo-transient finite volume formulation. While not all of the qualitative features observed in the experiments are reproduced by this general numerical implementation, the velocity predictions show moderately good agreement with the experimental data.

Phan-Thien, Nhan [Univ. of Sydney, Sydney, New South Wales (Australia). Dept. of Mechanical Engineering; Graham, A.L.; Abbott, J.R. [Los Alamos National Lab., NM (United States); Altobelli, S.A. [Lovelace Medical Foundation, Albuquerque, New Mexico (United States); Mondy, L.A. [Sandia National Labs., Albuquerque, NM (United States)

1995-07-01T23:59:59.000Z

392

Role of photonic angular momentum states in nonreciprocal diffraction from magneto-optical cylinder arrays  

SciTech Connect

Optical eigenstates in a concentrically symmetric resonator are photonic angular momentum states (PAMSs) with quantized optical orbital angular momentums (OAMs). Nonreciprocal optical phenomena can be obtained if we lift the degeneracy of PAMSs. In this article, we provide a comprehensive study of nonreciprocal optical diffraction of various orders from a magneto-optical cylinder array. We show that nonreciprocal diffraction can be obtained only for these nonzero orders. Role of PAMSs, the excitation of which is sensitive to the directions of incidence, applied magnetic field, and arrangement of the cylinders, are studied. Some interesting phenomena such as a dispersionless quasi-omnidirectional nonreciprocal diffraction and spikes associated with high-OAM PAMSs are present and discussed.

Guo, Tian-Jing; Wu, Li-Ting; Yang, Mu; Guo, Rui-Peng; Cui, Hai-Xu; Chen, Jing, E-mail: jchen4@nankai.edu.cn [MOE Key Laboratory of Weak-Light Nonlinear Photonics, School of Physics, Nankai University, Tianjin 300071 (China)

2014-07-15T23:59:59.000Z

393

DOUBLE SHELL TANK (DST) HYDROXIDE DEPLETION MODEL FOR CARBON DIOXIDE ABSORPTION  

SciTech Connect

This document generates a supernatant hydroxide ion depletion model based on mechanistic principles. The carbon dioxide absorption mechanistic model is developed in this report. The report also benchmarks the model against historical tank supernatant hydroxide data and vapor space carbon dioxide data. A comparison of the newly generated mechanistic model with previously applied empirical hydroxide depletion equations is also performed.

OGDEN DM; KIRCH NW

2007-10-31T23:59:59.000Z

394

Roles of ATP in Depletion and Replenishment of the Releasable Pool of Synaptic Vesicles  

E-Print Network (OSTI)

Roles of ATP in Depletion and Replenishment of the Releasable Pool of Synaptic Vesicles RUTH Matthews. Roles of ATP in depletion and replenishment of the releasable pool of synaptic vesicles. J a pool of readily releasable synaptic vesicles that undergo rapid calcium-dependent release. ATP

Pennsylvania, University of

395

Radon levels and doses in dwellings in two villages in Kosovo, affected by depleted uranium  

Science Journals Connector (OSTI)

......Kosovo, affected by depleted uranium G. Nafezi 1 A. Gregoric...major cause of lung cancer, second only to cigarette...Kosovo was initiated by uranium prospecting in the period...the study was hit by depleted uranium projectiles during the......

G. Nafezi; A. Gregoric; J. Vaupotic; M. Bahtijari; M. Kuqali

2014-02-01T23:59:59.000Z

396

Can ozone depletion and global warming interact to produce rapid climate change?  

E-Print Network (OSTI)

Can ozone depletion and global warming interact to produce rapid climate change? Dennis L. Hartmann of Climate Change (IPCC) assess- ment of the status of global warming, which reported that winter stratospheric ozone depletion and greenhouse warming are possible. These interactions may be responsible

Limpasuvan, Varavut

397

Stratospheric ozone depletion: a key driver of recent precipitation trends in South Eastern South America  

E-Print Network (OSTI)

. In this paper we focus on South Eastern South America (SESA), a region that has exhibited one of the largest South America 1 Introduction The depletion of ozone in the polar Antarctic strato- sphere (i.e. `theStratospheric ozone depletion: a key driver of recent precipitation trends in South Eastern South

398

Abortive HIV Infection Mediates CD4 T-Cell Depletion and Inflammation in Human Lymphoid Tissue  

E-Print Network (OSTI)

factors like HIV-1 Tat, Vpr, and Nef released from infected cells (Schindler et al., 2006; Westendorp etAbortive HIV Infection Mediates CD4 T-Cell Depletion and Inflammation in Human Lymphoid Tissue 94143 Summary The mechanism by which CD4 T-cells are depleted in HIV-infected hosts remains poorly

Levin, Judith G.

399

PBX 9404 detonation copper cylinder tests: a comparison of new and aged material  

SciTech Connect

We present detonation copper cylinder test results on aged PBX 9404 (94 wt% HMX, 3 wt% CEF, 2.9 wt% NC, 0.1 wt% DPA) explosive. The charges were newly pressed from 37.5 year-old molding powder. We compare these results to equivalent data performed on the same lot when it was 3.5 years old. Comparison of the detonation energy inferred from detonation speed to that inferred from wall motion suggests that the HMX energy is unchanged but the NC energy has decreased to {approx}25% of its original value. The degradation of explosives and their binders is a subject of continual interest. Secondary explosives such as HMX are sufficiently stable near room temperature that they do not measurably degrade over a period of at least several decades. For formulated systems the bigger concern is binder degradation, for which the three main issues are strength, initiation safety, and (if the binder is energetic) energy content. In this paper we examine the detonation energy of new and aged PBX 9404 (94 wt% HMX, 3 wt% tris-{beta} chloroethylphosphate (CEF), 2.9 wt% nitrocellulose (NC), 0.1 wt% diphenylamine (DPA) [1, 2]), measured via the detonation copper cylinder test. In 1959, two independent PBX 9404 accidents [3] raised serious concerns about the safety of the formulation. Over about a decade's time, Los Alamos pursued a safer, energetically equivalent replacement, which ultimately became PBX 9501. In order to accurately compare the performance of the PBX 9404 and PBX 9501 formulations, W. Campbell and R. Engelke (C & E) developed a stringent cylinder test protocol that they called the Los Alamos Precision Cylinder Test [4]. The present aging study is possible because excellent PBX 9404 data from those qualification tests endures.

Hill, Larry G [Los Alamos National Laboratory; Mier, Robert [Los Alamos National Laboratory; Briggs, Matthew E [Los Alamos National Laboratory

2009-01-01T23:59:59.000Z

400

Dynamics of a horizontal cylinder oscillating as a wave energy converter about an off-centred axis.   

E-Print Network (OSTI)

The hydrodynamic properties of a horizontal cylinder which is free to pitch about an off-centred axis are studied and used to derive the equations of motion of a wave energy converter which extracts energy from incoming ...

Lucas, Jorge

2011-11-22T23:59:59.000Z

Note: This page contains sample records for the topic "depleted uf6 cylinder" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


401

Real-time diagnostic system using acoustic emission for a cylinder liner in a large two-stroke diesel engine  

Science Journals Connector (OSTI)

Damage that originates from abnormal wear in the cylinder liner of marine diesel engines causes a considerable loss of ... anticipate the damage that is caused by abnormal wear, such as scuffing, by investigating...

Jang Kyu Kim; Min Cheol Lee

2009-07-01T23:59:59.000Z

402

2-dimensional numerical simulations for the wave-wake-body interactions around circular cylinders in motion near seabed  

E-Print Network (OSTI)

grid system. In this thesis, several flow configurations, such as stationary and oscillating cylinder, were studied in order to predict and to understand the hydrodynamic forces. The results from the different simulations were compared with available...

Tavassoli, Armin

1999-01-01T23:59:59.000Z

403

Design, Construction, and Validation of an In-Cylinder Pressure Recording System for Internal Combustion Engine Analysis  

E-Print Network (OSTI)

agreement with published works and resulted in correlations for fuel properties that were not discussed in literature. In chapter three, the design, construction, and validation of an engine cylinder pressure recording system are covered. In particular...

Mangus, Michael D.

2012-05-31T23:59:59.000Z

404

Simultaneous two-axis vibration measurement of a nonmetallic cylinder by electromagnetic induction and metallic foil loops  

Science Journals Connector (OSTI)

This work presents a method based on electromagnetic induction for the simultaneous non-contact measurement of two-axis lateral vibrations of a nonmetallic cylinder. The suggested method ... pair of loop is induc...

Soon Woo Han; Jin Ki Kim; Yoon Young Kim

2011-08-01T23:59:59.000Z

405

Study On Magnetic Shielding Type Superconducting Fault Current Limiter Using Bi-Sr-Ca-Cu-O Cylinder  

Science Journals Connector (OSTI)

The power application of a superconductor to restrain a fault current has been researched. A superconducting fault current limiter using a Bi-Sr-Ca-Cu-O cylinder has been developed. This limiter consists of the p...

Michiharu Ichikawa; Hiroyuki Kado; Kunikazu Izumi

1994-01-01T23:59:59.000Z

406

Compressive Sensing Based Machine Learning Strategy For Characterizing The Flow Around A Cylinder With Limited Pressure Measurements  

SciTech Connect

Compressive sensing is used to determine the flow characteristics around a cylinder (Reynolds number and pressure/flow field) from a sparse number of pressure measurements on the cylinder. Using a supervised machine learning strategy, library elements encoding the dimensionally reduced dynamics are computed for various Reynolds numbers. Convex L1 optimization is then used with a limited number of pressure measurements on the cylinder to reconstruct, or decode, the full pressure field and the resulting flow field around the cylinder. Aside from the highly turbulent regime (large Reynolds number) where only the Reynolds number can be identified, accurate reconstruction of the pressure field and Reynolds number is achieved. The proposed data-driven strategy thus achieves encoding of the fluid dynamics using the L2 norm, and robust decoding (flow field reconstruction) using the sparsity promoting L1 norm.

Bright, Ido; Lin, Guang; Kutz, Nathan

2013-12-05T23:59:59.000Z

407

INTERPLANETARY MAGNETIC FLUX DEPLETION DURING PROTRACTED SOLAR MINIMA  

SciTech Connect

We examine near-Earth solar wind observations as assembled within the Omni data set over the past 15 years that constitute the latest solar cycle. We show that the interplanetary magnetic field continues to be depleted at low latitudes throughout the protracted solar minimum reaching levels below previously predicted minima. We obtain a rate of flux removal resulting in magnetic field reduction by 0.5 nT yr{sup -1} at 1 AU when averaged over the years 2005-2009 that reduces to 0.3 nT yr{sup -1} for 2007-2009. We show that the flux removal operates on field lines that follow the nominal Parker spiral orientation predicted for open field lines and are largely unassociated with recent ejecta. We argue that the field line reduction can only be accomplished by ongoing reconnection of nominally open field lines or very old closed field lines and we contend that these two interpretations are observationally equivalent and indistinguishable.

Connick, David E.; Smith, Charles W.; Schwadron, Nathan A., E-mail: davideconnick@gmail.com, E-mail: Charles.Smith@unh.edu, E-mail: N.Schwadron@unh.edu [Physics Department, Space Science Center, University of New Hampshire, Durham, NH (United States)

2011-01-20T23:59:59.000Z

408

Properties, use and health effects of depleted uranium  

Science Journals Connector (OSTI)

Depleted uranium (DU) has been claimed to contribute to health problems both in military personnel directly involved in war actions as well in military and civilian individuals who resided in areas where DU ammunition was expended. Due to the low specific radioactivity and the dominance of alpha-radiation, no acute health risk can be attributed to external exposure to DU. Internalised DU is both chemo- and radio-toxic. The major risk is from inhalation of DU dust or particles with less than 10 ?m aerodynamic-equivalent diameter, formed when DU ammunitions hit hard targets (aerosol formation) or during weathering of DU penetrators. One major conclusion is that for all post-conflict situations, the inhaled DU quantities (central estimates) produced radiation doses that would be only a fraction of those normally received by the lung from natural radiation. Hence no long term lung effects due to these DU amounts can be expected. These conclusions also hold for whole-body exposure from ingestion of DU in local food and water.

W. Burkart; P.R. Danesi; J.H. Hendry

2005-01-01T23:59:59.000Z

409

Depleted-Uranium Weapons the Whys and Wherefores  

E-Print Network (OSTI)

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

Gsponer, A

2003-01-01T23:59:59.000Z

410

Assessment of depleted uranium in South-Western Iran  

Science Journals Connector (OSTI)

Abstract Depleted uranium (DU) has been used in a number of conflicts most notably during the Gulf War in Iraq and existence of it has been reported in Kuwait by IAEA experts. Due to heavy sand storms prevailing into the direction to South West of Iran transporting sand originating from Iraq, the probability that DU could be moved is considered high. Therefore it was decided to take some air and soil samples near border line and some nearest cities. The study was focused on finding DU in air and soil of these south-west provinces. 22 air samples and 20 soil samples were collected and analyzed on their contents of uranium isotopes by alpha, beta and gamma spectrometry. The air and soil samples have been measured by use of an alpha-beta counter and by a gamma spectrometer, respectively. Results showed that there is no radiation impact from DU and so no DU has been transported via sand storms since all results were obtained below the detection limit.

Hossein Yousefi; Abdullah Najafi

2013-01-01T23:59:59.000Z

411

Kr ion irradiation study of the depleted-uranium alloys.  

SciTech Connect

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

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

2010-12-01T23:59:59.000Z

412

Kr Ion Irradiation Study of the Depleted-Uranium Alloys  

SciTech Connect

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

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

2010-12-01T23:59:59.000Z

413

Development of commercial NGV cylinders. Final report, September 1990-August 1991  

SciTech Connect

The state-of-the-art feasibility has been demonstrated for manufacturing and testing large, light-weight CNG cylinders for transit buses. The objective of the program is to establish the viability of this concept over a broad range of sizes and economic issues. To establish the viability of these cylinders, the latest requirements and standards were used in the program. The project included the design of various size tanks with regard to length as well as diameter. Tanks in two sizes were fabricated and submitted to test. The test program was established using the most severe tests from the U.S. and Canadian regulatory agencies. Upon successful completion of these tests, a qualification test report was prepared and submitted to the U.S. Department of Transportation for approval. The results of the program will provide the compressed natural gas vehicle industry with an economically viable, light-weight cylinder for both the original equipment manufacturers and the after market converters. The light-weight results in lower vehicle weight thus better fuel economy.

Berrisford, R.S.

1992-02-01T23:59:59.000Z

414

A competing risk model for the reliability of cylinder liners in marine Diesel engines  

Science Journals Connector (OSTI)

In this paper, a competing risk model is proposed to describe the reliability of the cylinder liners of a marine Diesel engine. Cylinder liners presents two dominant failure modes: wear degradation and thermal cracking. The wear process is described through a stochastic process, whereas the failure time due to the thermal cracking is described by the Weibull distribution. The use of the proposed model allows performing goodness-of-fit test and parameters estimation on the basis of both wear and failure data. Moreover, it enables reliability estimates of the state of the liners to be obtained and the hierarchy of the failure mechanisms to be determined for any given age and wear level of the liner. The model has been applied to a real data set: 33 cylinder liners of Sulzer RTA 58 engines, which equip twin ships of the Grimaldi Group. Estimates of the liner reliability and of other quantities of interest under the competing risk model are obtained, as well as the conditional failure probability and mean residual lifetime, given the survival age and the accumulated wear. Furthermore, the model has been used to estimate the probability that a liner fails due to one of the failure modes when both of these modes act.

D. Bocchetti; M. Giorgio; M. Guida; G. Pulcini

2009-01-01T23:59:59.000Z

415

Operation of a Four-Cylinder 1.9L Propane Fueled HCCI Engine  

SciTech Connect

A four-cylinder 1.9 Volkswagen TDI Engine has been converted to run in Homogeneous Charge Compression Ignition (HCCI) mode. The stock configuration is a turbocharged direct injection Diesel engine. The combustion chamber has been modified by discarding the in-cylinder Diesel fuel injectors and replacing them with blank inserts (which contain pressure transducers). The stock pistons contain a reentrant bowl and have been retained for the tests reported here. The intake and exhaust manifolds have also been retained, but the turbocharger has been removed. A heater has been installed upstream of the intake manifold and fuel is added just downstream of this heater. The performance of this engine in naturally aspirated HCCI operation, subject to variable intake temperature and fuel flow rate, has been studied. The engine has been run with propane fuel at a constant speed of 1800 rpm. This work is intended to characterize the HCCI operation of the engine in this configuration that has been minimally modified from the base Diesel engine. The performance (BMEP, IMEP, efficiency, etc) and emissions (THC, CO, NOx) of the engine are presented, as are combustion process results based on heat release analysis of the pressure traces from each cylinder.

Flowers, D; Aceves, S M; Martinez-Frias, J; Smith, J R; Au, M; Girard, J; Dibble, R

2001-03-15T23:59:59.000Z

416

CFD Calculation of Internal Natural Convection in the Annulus between Horizontal Concentric Cylinders  

SciTech Connect

The objective of this heat transfer and fluid flow study is to assess the ability of a computational fluid dynamics (CFD) code to reproduce the experimental results, numerical simulation results, and heat transfer correlation equations developed in the literature for natural convection heat transfer within the annulus of horizontal concentric cylinders. In the literature, a variety of heat transfer expressions have been developed to compute average equivalent thermal conductivities. However, the expressions have been primarily developed for very small inner and outer cylinder radii and gap-widths. In this comparative study, interest is primarily focused on large gap widths (on the order of half meter or greater) and large radius ratios. From the steady-state CFD analysis it is found that the concentric cylinder models for the larger geometries compare favorably to the results of the Kuehn and Goldstein correlations in the Rayleigh number range of about 10{sup 5} to 10{sup 8} (a range that encompasses the laminar to turbulent transition). For Rayleigh numbers greater than 10{sup 8}, both numerical simulations and experimental data (from the literature) are consistent and result in slightly lower equivalent thermal conductivities than those obtained from the Kuehn and Goldstein correlations.

N.D. Francis, Jr; M.T. Itamura; S.W. Webb; D.L. James

2002-10-01T23:59:59.000Z

417

Tribological evaluation of piston skirt/cylinder liner contact interfaces under boundary lubrication conditions.  

SciTech Connect

The friction and wear between the piston and cylinder liner significantly affects the performance of internal combustion engines. In this paper, segments from a commercial piston/cylinder system were tribologically tested using reciprocating motion. The tribological contact consisted of aluminium alloy piston segments, either uncoated, coated with a graphite/resin coating, or an amorphous hydrogenated carbon (a-C : H) coating, in contact with gray cast iron liner segments. Tests were conducted in commercial synthetic motor oils and base stocks at temperatures up to 120 C with a 2 cm stroke length at reciprocating speeds up to 0.15 m s{sup -1}. The friction dependence of these piston skirt and cylinder liner materials was studied as a function of load, sliding speed and temperature. Specifically, an increase in the sliding speed led to a decrease in the friction coefficient below approximately 70 C, while above this temperature, an increase in sliding speed led to an increase in the friction coefficient. The presence of a coating played an important role. It was found that the graphite/resin coating wore quickly, preventing the formation of a beneficial tribochemical film, while the a-C : H coating exhibited a low friction coefficient and provided significant improvement over the uncoated samples. The effect of additives in the oils was also studied. The tribological behaviour of the interface was explained based on viscosity effects and subsequent changes in the lubrication regime, formation of chemical and tribochemical films.

Demas, N. G.; Erck, R. A.; Fenske, G. R.; Energy Systems

2010-03-01T23:59:59.000Z

418

Quantification of initial-data uncertainty on a shock-accelerated gas cylinder  

SciTech Connect

We quantify initial-data uncertainties on a shock accelerated heavy-gas cylinder by two-dimensional well-resolved direct numerical simulations. A high-resolution compressible multicomponent flow simulation model is coupled with a polynomial chaos expansion to propagate the initial-data uncertainties to the output quantities of interest. The initial flow configuration follows previous experimental and numerical works of the shock accelerated heavy-gas cylinder. We investigate three main initial-data uncertainties, (i) shock Mach number, (ii) contamination of SF{sub 6} with acetone, and (iii) initial deviations of the heavy-gas region from a perfect cylindrical shape. The impact of initial-data uncertainties on the mixing process is examined. The results suggest that the mixing process is highly sensitive to input variations of shock Mach number and acetone contamination. Additionally, our results indicate that the measured shock Mach number in the experiment of Tomkins et al. [“An experimental investigation of mixing mechanisms in shock-accelerated flow,” J. Fluid. Mech. 611, 131 (2008)] and the estimated contamination of the SF{sub 6} region with acetone [S. K. Shankar, S. Kawai, and S. K. Lele, “Two-dimensional viscous flow simulation of a shock accelerated heavy gas cylinder,” Phys. Fluids 23, 024102 (2011)] exhibit deviations from those that lead to best agreement between our simulations and the experiment in terms of overall flow evolution.

Tritschler, V. K., E-mail: volker.tritschler@aer.mw.tum.de; Avdonin, A.; Hickel, S.; Hu, X. Y.; Adams, N. A. [Institute of Aerodynamics and Fluid Mechanics, Technische Universität München, 85747 Garching (Germany)] [Institute of Aerodynamics and Fluid Mechanics, Technische Universität München, 85747 Garching (Germany)

2014-02-15T23:59:59.000Z

419

Separation of sheet flow on the surface of a circular cylinder  

Science Journals Connector (OSTI)

The shape of a spout of a pot is very important for the liquid to flow smoothly from the pot. This is known as the “teapot effect.” Separation of flow must take place at the tip of the spout. Separation of sheet flow on the surface of a circular cylinder may provide an explanation as to why pot spouts have such a unique shape. As can be easily observed by a simple experiment separation of sheet flow from the surface of a circular cylinder is a very interesting phenomenon beyond intuition. In the nonviscous case the flow released at the top of the surface may proceed completely around the surface and come back to the flow start point without separation. In the present paper effects of gravity and viscosity on sheet flow are theoretically explained and the theory is verified by experiments. The results of the theoretical model proposed in the present study were very similar to the experimental measurements. In the present study the effects of viscosity on sheet flow on a circular cylinder the location of flow separation and other associated responses were investigated.

Hiroshi Isshiki; Bum-Sang Yoon; Deuk-Joon Yum

2009-01-01T23:59:59.000Z

420

Determination of the theoretical feasibility for the transmutation of europium isotopes from high flux isotope reactor control cylinders  

SciTech Connect

The High Flux Isotope Reactor (HFIR) at the Oak Ridge National Laboratory (ORNL) is a 100 MWth light-water research reactor designed and built in the 1960s primarily for the production of transuranic isotopes. The HFIR is equipped with two concentric cylindrical blade assemblies, known as control cylinders, that are used to control reactor power. These control cylinders, which become highly radioactive from neutron exposure, are periodically replaced as part of the normal operation of the reactor. The highly radioactive region of the control cylinders is composed of europium oxide in an aluminum matrix. The spent HFIR control cylinders have historically been emplaced in the ORNL Waste Area Grouping (WAG) 6. The control cylinders pose a potential radiological hazard due to the long lived radiotoxic europium isotopes {sup 152}Eu, {sup 154}Eu, and {sup 155}Eu. In a 1991 health evaluation of WAG 6 (ERD 1991) it was shown that these cylinders were a major component of the total radioactivity in WAG 6 and posed a potential exposure hazard to the public in some of the postulated assessment scenarios. These health evaluations, though preliminary and conservative in nature, illustrate the incentive to investigate methods for permanent destruction of the europium radionuclides. When the cost of removing the control cylinders from WAG 6, performing chemical separations and irradiating the material in HFIR are factored in, the option of leaving the control cylinders in place for decay must be considered. Other options, such as construction of an engineered barrier around the disposal silos to reduce the chance of migration, should also be analyzed.

Elam, K.R.; Reich, W.J.

1995-09-01T23:59:59.000Z

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421

Radiological and Depleted Uranium Weapons: Environmental and Health Consequences  

Science Journals Connector (OSTI)

The effects of nuclear weapons are due to the release of blast and thermal energy and the immediate and residual ionizing radiation energy. Most of the short-term damages to the environment and the human health are caused by the blast and thermal energies. Ionizing radiation energy received in large doses at high dose rates (victims of nuclear explosions) can produce acute radiation sickness and can even be lethal. Individuals having received lower radiation doses, or even high doses at low dose rates, may suffer from stochastic effects, primarily, the induction of cancer. Studies of exposed populations suggest the probability of developing a lethal cancer following low dose rate exposure is increased by approximately 5% for each Sv the whole-body receives. This risk is added, of course, to the risk of dying from cancer without exposure to radiation, which is more than 20% worldwide. For radiological weapons (radiological dispersion devices or dirty bombs), the health effects due to radiation are expected to be minor in most cases. Casualties will mainly occur due to the conventional explosive. Fear, panic, and decontamination costs will be the major effects. Significant radiation damage to individuals would likely be limited to very few persons. Depleted uranium (DU) weapons leave in the battlefield fragmented or intact DU penetrators as well as DU dust. The latter, if inhaled, could represent a radiological risk, especially to individuals spending some time in vehicles hit by DU munitions. All studies conducted so far have shown the outdoors doses to be so low not to represent a significant risk. For those spending 10 h per year in vehicles hit by DU munitions, the risk of developing a lethal cancer is slightly higher (?0.2%).

P.R. Danesi

2011-01-01T23:59:59.000Z

422

Capstone Depleted Uranium Aerosol Biokinetics, Concentrations, and Doses  

SciTech Connect

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

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

2009-02-26T23:59:59.000Z

423

Radiological Risk Assessment of Capstone Depleted Uranium Aerosols  

SciTech Connect

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

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

2009-02-26T23:59:59.000Z

424

SFR with once-through depleted uranium breed & burn blanket  

Science Journals Connector (OSTI)

Abstract This paper assesses the feasibility of Sodium-cooled Fast Reactor (SFR) cores that have TRU recycled seeds and once-through depleted uranium blankets. The design objective of these Seed-and-Blanket (S&B) cores is to maximize the power generated by the blanket. As the blanket fuel cost is significantly lower than the cost of the seed fuel and does not need reprocessing, increasing the fraction of reactor power generated by the blanket will reduce the total fuel cycle cost and the fuel reprocessing capacity required per unit of electricity generated. The S&B core is designed to have a prolate (“cigar”) shape seed (“driver”) to maximize the fraction of neutrons that radially leak into the subcritical blanket and reduce neutron loss via axial leakage. Both seed and blanket contain multiple batches; the blanket batches are gradually shuffled inward, while one third of the fuel batches in the seed are recycled. The preliminary study found that it is possible to design the seed to accommodate a wide range of TRU conversion ratios (CR) without significantly penalizing the burnup reactivity swing. The relatively small burnup reactivity swing enables to design the S&B core to operate at longer cycles and discharge its fuel at a higher burnup relative to conventional TRU transmutation cores with identical CR. The S&B cores can generate 1000 \\{MWth\\} and fit within the S-PRISM reactor vessel. The fraction of core power generated by the blanket is between 40% and 50% without exceeding the radiation damage constraint of 200 Displacements per Atom (DPA); this fraction increases when the seed is designed to have a smaller CR. These features are expected to improve the economics of SFR.

Guanheng Zhang; Ehud Greenspan; Alejandra Jolodosky; Jasmina Vujic

2014-01-01T23:59:59.000Z

425

Toxicity of depleted uranium on isolated rat kidney mitochondria  

Science Journals Connector (OSTI)

Background Kidney is known as the most sensitive target organ for depleted uranium (DU) toxicity in comparison to other organs. Although the oxidative stress and mitochondrial damage induced by DU has been well investigated, the precise mechanism of DU-induced nephrotoxicity has not been thoroughly recognized yet. Methods Kidney mitochondria were obtained using differential centrifugation from Wistar rats and mitochondrial toxicity endpoints were then determined in both in vivo and in vitro uranyl acetate (UA) exposure cases. Results Single injection of UA (0, 0.5, 1 and 2 mg/kg, i.p.) caused a significant increase in blood urea nitrogen and creatinine levels. Isolated mitochondria from the UA-treated rat kidney showed a marked elevation in oxidative stress accompanied by mitochondrial membrane potential (MMP) collapse as compared to control group. Incubation of isolated kidney mitochondria with UA (50, 100 and 200 ?M) manifested that UA can disrupt the electron transfer chain at complex II and III that leads to induction of reactive oxygen species (ROS) formation, lipid peroxidation, and glutathione oxidation. Disturbances in oxidative phosphorylation were also demonstrated through decreased ATP concentration and ATP/ADP ratio in UA-treated mitochondria. In addition, UA induced a significant damage in mitochondrial outer membrane. Moreover, MMP collapse, mitochondrial swelling and cytochrome c release were observed following the UA treatment in isolated mitochondria. General significance Both our in vivo and in vitro results showed that UA-induced nephrotoxicity is linked to the impairment of electron transfer chain especially at complex II and III which leads to subsequent oxidative stress.

Fatemeh Shaki; Mir-Jamal Hosseini; Mahmoud Ghazi-Khansari; Jalal Pourahmad

2012-01-01T23:59:59.000Z

426

FEASIBILITY STUDY OF DUPOLY TO RECYCLE DEPLETED URANIUM.  

SciTech Connect

DUPoly, depleted uranium (DU) powder microencapsulated in a low-density polyethylene binder, has been demonstrated as an innovative and efficient recycle product, a very durable high density material with significant commercial appeal. DUPoly was successfully prepared using uranium tetrafluoride (UF{sub 4}) ''green salt'' obtained from Fluor Daniel-Fernald, a U.S. Department of Energy reprocessing facility near Cincinnati, Ohio. Samples containing up to 90 wt% UF{sub 4} were produced using a single screw plastics extruder, with sample densities of up to 3.97 {+-} 0.08 g/cm{sup 3} measured. Compressive strength of as-prepared samples (50-90 wt% UF4 ) ranged from 1682 {+-} 116 psi (11.6 {+-} 0.8 MPa) to 3145 {+-} 57 psi (21.7 {+-} 0.4 MPa). Water immersion testing for a period of 90 days produced no visible degradation of the samples. Leach rates were low, ranging from 0.02 % (2.74 x 10{sup {minus}6} gm/gm/d) for 50 wt% UF{sub 4} samples to 0.72 % (7.98 x 10{sup {minus}5} gm/gm/d) for 90 wt% samples. Sample strength was not compromised by water immersion. DUPoly samples containing uranium trioxide (UO{sub 3}), a DU reprocessing byproduct material stockpiled at the Savannah River Site, were gamma irradiated to 1 x 10{sup 9} rad with no visible deterioration. Compressive strength increased significantly, however: up to 200% for samples with 90 wt% UO{sub 3}. Correspondingly, percent deformation (strain) at failure was decreased for all samples. Gamma attenuation data on UO{sub 3} DUPoly samples yielded mass attenuation coefficients greater than those for lead. Neutron removal coefficients were calculated and shown to correlate well with wt% of DU. Unlike gamma attenuation, both hydrogenous and nonhydrogenous materials interact to attenuate neutrons.

ADAMS,J.W.; LAGERAAEN,P.R.; KALB,P.D.; RUTENKROGER,S.P.

1998-02-01T23:59:59.000Z

427

Efficacy of oral and intraperitoneal administration of CBMIDA for removing uranium in rats after parenteral injections of depleted uranium  

Science Journals Connector (OSTI)

......chemical forms of the uranium in the body after intake...REFERENCES 1 Mould R. F. Depleted uranium and radiation-induced lung cancer and leukaemia. Br. J...Abou-Donia M. B. Depleted and natural uranium: chemistry and toxicological......

S. Fukuda; M. Ikeda; M. Nakamura; X. Yan; Y. Xie

2009-01-01T23:59:59.000Z

428

Abstract 3464: Epigenetic mechanism is involved in depleted uranium-induced transformation in human lung epithelial cells  

Science Journals Connector (OSTI)

...Epigenetic mechanism is involved in depleted uranium-induced transformation in human...Southern Maine, Portland, ME. Depleted uranium (DU) is commonly used in military...research information on the potential health hazards of DU exposure. In our...

Hong Xie; Carolyne LaCerte; and John P. Wise

2010-04-15T23:59:59.000Z

429

Efficacy of oral and intraperitoneal administration of CBMIDA for removing uranium in rats after parenteral injections of depleted uranium  

Science Journals Connector (OSTI)

......contaminated accidentally with uranium. INTRODUCTION Depleted uranium (DU) can affect human health via chemical and radiation...B. Teratogenicity of depleted uranium aerosols: a review from...perspective. Environ. Health (2005) 4:17-35......

S. Fukuda; M. Ikeda; M. Nakamura; X. Yan; Y. Xie

2009-01-01T23:59:59.000Z

430

Management and Uses Conversion Activities  

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

Conversion Conversion Depleted UF6 Conversion DOE is planning to build two depleted UF6 conversion facilities, and site-specific environmental impact statements (EISs) to evaluate project alternatives. The Final Plan for Conversion and the Programmatic EIS The eventual disposition of depleted UF6 remains the subject of considerable interest within the U.S. Congress, and among concerned citizens and other stakeholders. Congress stated its intentions in Public Law (P. L.) 105-204, signed by the President in July 1998. P. L. 105-204 required DOE to develop a plan to build two depleted UF6 conversion facilities, one each at Portsmouth, Ohio, and Paducah, Kentucky. DOE submitted the required plan, Final Plan for the Conversion of Depleted Uranium Hexafluoride, to Congress in July 1999. This document provided a discussion of DOE's technical approach and schedule to implement this project. Although much of the information provided in this report is still valid, a few aspects of this plan have changed since its publication.

431

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

E-Print Network (OSTI)

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

1985-01-01T23:59:59.000Z

432

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

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

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

433

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

DOE Patents (OSTI)

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

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

2000-02-29T23:59:59.000Z

434

Depleted uranium human health risk assessment, Jefferson Proving Ground, Indiana  

SciTech Connect

The risk to human health from fragments of depleted uranium (DU) at Jefferson Proving Ground (JPG) was estimated using two types of ecosystem pathway models. A steady-state, model of the JPG area was developed to examine the effects of DU in soils, water, and vegetation on deer that were hunted and consumed by humans. The RESRAD code was also used to estimate the effects of farming the impact area and consuming the products derived from the farm. The steady-state model showed that minimal doses to humans are expected from consumption of deer that inhabit the impact area. Median values for doses to humans range from about 1 mrem ({plus_minus}2.4) to 0.04 mrem ({plus_minus}0.13) and translate to less than 1 {times} 10{sup {minus}6} detriments (excess cancers) in the population. Monte Carlo simulation of the steady-state model was used to derive the probability distributions from which the median values were drawn. Sensitivity analyses of the steady-state model showed that the amount of DU in airborne dust and, therefore, the amount of DU on the vegetation surface, controlled the amount of DU ingested by deer and by humans. Human doses from the RESRAD estimates ranged from less than 1 mrem/y to about 6.5 mrem/y in a hunting scenario and subsistence fanning scenario, respectively. The human doses exceeded the 100 mrem/y dose limit when drinking water for the farming scenario was obtained from the on-site aquifer that was presumably contaminated with DU. The two farming scenarios were unrealistic land uses because the additional risk to humans due to unexploded ordnance in the impact area was not figured into the risk estimate. The doses estimated with RESRAD translated to less than 1 {times} 10{sup {minus}6} detriments to about 1 {times} 10{sup {minus}3} detriments. The higher risks were associated only with the farming scenario in which drinking water was obtained on-site.

Ebinger, M.H.; Hansen, W.R.

1994-04-29T23:59:59.000Z

435

The distribution of depleted uranium contamination in Colonie, NY, USA  

Science Journals Connector (OSTI)

Uranium oxide particles were dispersed into the environment from a factory in Colonie (NY, USA) by prevailing winds during the 1960s and '70s. Uranium concentrations and isotope ratios from bulk soil samples have been accurately measured using inductively coupled plasma quadrupole mass spectrometry (ICP-QMS) without the need for analyte separation chemistry. The natural range of uranium concentrations in the Colonie soils has been estimated as 0.7–2.1 ?g g? 1, with a weighted geometric mean of 1.05 ?g g? 1; the contaminated soil samples comprise uranium up to 500 ± 40 ?g g? 1. A plot of 236U/238U against 235U/238U isotope ratios describes a mixing line between natural uranium and depleted uranium (DU) in bulk soil samples; scatter from this line can be accounted for by heterogeneity in the DU particulate. The end-member of DU compositions aggregated in these bulk samples comprises (2.05 ± 0.06) × 10? 3 235U/238U, (3.2 ± 0.1) × 10? 5 236U/238U, and (7.1 ± 0.3) × 10? 6 234U/238U. The analytical method is sensitive to as little as 50 ng g? 1 DU mixed with the natural uranium occurring in these soils. The contamination footprint has been mapped northward from site, and at least one third of the uranium in a soil sample from the surface 5 cm, collected 5.1 km NNW of the site, is DU. The distribution of contamination within the surface soil horizon follows a trend of exponential decrease with depth, which can be approximated by a simple diffusion model. Bioturbation by earthworms can account for dispersal of contaminant from the soil surface, in the form of primary uranium oxide particulates, and uranyl species that are adsorbed to organic matter. Considering this distribution, the total mass of uranium contamination emitted from the factory is estimated to be c. 4.8 tonnes.

N.S. Lloyd; S.R.N. Chenery; R.R. Parrish

2009-01-01T23:59:59.000Z

436

Piston Bowl Optimization for RCCI Combustion in a Light-Duty Multi-Cylinder Engine  

SciTech Connect

Reactivity Controlled Compression Ignition (RCCI) is an engine combustion strategy that that produces low NO{sub x} and PM emissions with high thermal efficiency. Previous RCCI research has been investigated in single-cylinder heavy-duty engines. The current study investigates RCCI operation in a light-duty multi-cylinder engine at 3 operating points. These operating points were chosen to cover a range of conditions seen in the US EPA light-duty FTP test. The operating points were chosen by the Ad Hoc working group to simulate operation in the FTP test. The fueling strategy for the engine experiments consisted of in-cylinder fuel blending using port fuel-injection (PFI) of gasoline and early-cycle, direct-injection (DI) of diesel fuel. At these 3 points, the stock engine configuration is compared to operation with both the original equipment manufacturer (OEM) and custom machined pistons designed for RCCI operation. The pistons were designed with assistance from the KIVA 3V computational fluid dynamics (CFD) code. By using a genetic algorithm optimization, in conjunction with KIVA, the piston bowl profile was optimized for dedicated RCCI operation to reduce unburned fuel emissions and piston bowl surface area. By reducing these parameters, the thermal efficiency of the engine was improved while maintaining low NOx and PM emissions. Results show that with the new piston bowl profile and an optimized injection schedule, RCCI brake thermal efficiency was increased from 37%, with the stock EURO IV configuration, to 40% at the 2,600 rev/min, 6.9 bar BMEP condition, and NOx and PM emissions targets were met without the need for exhaust after-treatment.

Hanson, Reed M [ORNL; Curran, Scott [ORNL; Wagner, Robert M [ORNL; Reitz, Rolf [University of Wisconsin; Kokjohn, Sage [University of Wisconsin, Madison

2012-01-01T23:59:59.000Z

437

E-Print Network 3.0 - alarming oxygen depletion Sample Search...  

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

protecting life on Earth (1). In 1985, scientists and the public became alarmed when Farman et al. (2... studies (5-8). These studies showed that ozone depletion has a large...

438

Effect of catechins and tannins on depleted uranium-induced DNA strand breaks  

Science Journals Connector (OSTI)

The effects of polyphenols on plasmid DNA strand breaks by depleted uranium were studied using four catechins: (+)...2 2+) with hydrogen peroxide (H2O2) were strongly enhanced by EGC, EGCG, MMT, a...

Emiko Matsuda; Akira Nakajima

2012-08-01T23:59:59.000Z

439

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

E-Print Network (OSTI)

??The neutron emission rates from five very pure actinide samples (Th-232, Np-237, Pu-239, Pu-241 and depleted uranium) were measured following equilibrium irradiation in fast and… (more)

Stone, Joseph C.

2012-01-01T23:59:59.000Z

440

Effects of hydroxyl radicals generated from the depleted uranium-hydrogen peroxide systems  

Science Journals Connector (OSTI)

A complementary study of hydroxyl radical formation in the depleted uranium (DU)-hydrogen peroxide (H2O2) system and the effect of biosubstances on the system were examined using the spin-trapping method. Hydroxy...

A. Nakajima; Y. Ueda

2007-05-01T23:59:59.000Z

Note: This page contains sample records for the topic "depleted uf6 cylinder" 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

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

E-Print Network (OSTI)

The neutron emission rates from five very pure actinide samples (Th-232, Np-237, Pu-239, Pu-241 and depleted uranium) were measured following equilibrium irradiation in fast and thermal neutron fluxes. The relative abundances (alphas) for the first...

Stone, Joseph C.

2012-06-07T23:59:59.000Z

442

Leukemic transformation of hematopoietic cells in mice internally exposed to depleted uranium  

Science Journals Connector (OSTI)

Depleted uranium (DU) is a dense heavy metal ... have been wounded by DU shrapnel. The health effects of embedded DU are unknown. Published...in vitro can transform immortalized human osteoblast cells (HOS) to th...

Alexandra C. Miller; Catherine Bonait-Pellie…

2005-11-01T23:59:59.000Z

443

Teratogenicity of depleted uranium aerosols: A review from an epidemiological perspective  

Science Journals Connector (OSTI)

Depleted uranium is being used increasingly often as a component of munitions in military conflicts. Military personnel, civilians and the DU munitions producers are being exposed to the DU aerosols that are g...

Rita Hindin; Doug Brugge; Bindu Panikkar

2005-08-01T23:59:59.000Z

444

Evaluation of Environmental and Health Consequences of Depleted Uranium Armor use in Yugoslavia  

Science Journals Connector (OSTI)

In the paper there is discussed a possible radiation effect a combat application of armor - piercing ammunitions with a “depleted uranium” (DU) in Iraqian and Yugoslavian conflicts ... a noticeable additional inf...

V. A. Vetrov; O. A. Pavlovsky

2003-01-01T23:59:59.000Z

445

Depleted Uranium Disturbs Immune Parameters in Zebrafish, Danio rerio: An Ex Vivo/In Vivo Experiment  

Science Journals Connector (OSTI)

In this study, we investigated the effects of depleted uranium (DU), the byproduct of nuclear enrichment of uranium, on several parameters related to defence system...Danio rerio, using flow cytometry. Several im...

Béatrice Gagnaire; Anne Bado-Nilles…

2014-10-01T23:59:59.000Z

446

Long-term corrosion and leaching of depleted uranium (DU) in soil  

Science Journals Connector (OSTI)

Corrosion and leaching of depleted uranium (DU) was investigated for 3 years...238U was determined in the effluents by inductively coupled plasma mass spectrometry. In addition, 235U was measured occasionally to ...

W. Schimmack; U. Gerstmann; W. Schultz; G. Geipel

2007-08-01T23:59:59.000Z

447

Leaching of depleted uranium in soil as determined by column experiments  

Science Journals Connector (OSTI)

The basic features of the leachability of depleted uranium (DU) projectiles in soil was investigated...235U and 238U were determined by inductively coupled plasma mass spectrometry. The leaching rates of 238U fro...

W. Schimmack; U. Gerstmann; U. Oeh; W. Schultz…

2005-12-01T23:59:59.000Z

448

Biological monitoring and surveillance results of Gulf War I veterans exposed to depleted uranium  

Science Journals Connector (OSTI)

Objective: To relate medical surveillance outcomes to uranium biomonitoring results in a group of depleted uranium (DU)-exposed, Gulf War I veterans...Methods...: Thirty-two veterans of Gulf War ...

Melissa A. McDiarmid; Susan M. Engelhardt…

2006-01-01T23:59:59.000Z

449

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

Science Journals Connector (OSTI)

We present spectra of depleted uranium metal from laser plasmas generated by nanosecond Nd:YAG (1064?nm) and femtosecond Ti:sapphire (800?nm) laser pulses. The latter pulses produce...

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

2011-01-01T23:59:59.000Z

450

Depleted uranium is not toxic to rat brain endothelial (RBE4) cells  

Science Journals Connector (OSTI)

Studies on Gulf War veterans with depleted uranium (DU) fragments embedded in their soft...3O8 uranyl chloride form of DU into RBE4 cells is efficient, but there are little or no resulting cytotoxic effects on th...

Allison W. Dobson; Anna K. Lack; Keith M. Erikson…

2006-04-01T23:59:59.000Z

451

Characterization of uranium isotopic abundances in depleted uranium metal assay standard 115  

Science Journals Connector (OSTI)

Certified reference material (CRM) 115, Uranium (Depleted) Metal (Uranium Assay Standard), was analyzed using a ... TRITON Thermal Ionization Mass Spectrometer to characterize the uranium isotope-amount ratios. T...

K. J. Mathew; G. L. Singleton; R. M. Essex…

2013-04-01T23:59:59.000Z

452

Effects of depleted uranium after short-term exposure on vitamin D metabolism in rat  

Science Journals Connector (OSTI)

Uranium is a natural radioactive heavy metal. Its ... brain. Effects of an acute contamination by depleted uranium (DU) were investigated in vivo on...3 biosynthetic pathway. Rats received an intragastric adminis...

E. Tissandie; Y. Guéguen; J. M. A. Lobaccaro; F. Paquet…

2006-08-01T23:59:59.000Z

453

Geological conditions of safe long-term storage and disposal of depleted uranium hexafluoride  

Science Journals Connector (OSTI)

The production of enriched uranium used in nuclear weapons and fuel for ... power plants is accompanied by the formation of depleted uranium (DU), the amount of which annually ... DU mass is stored as environ-men...

N. P. Laverov; V. I. Velichkin; B. I. Omel’yanenko…

2010-08-01T23:59:59.000Z

454

Effects of Depleted Uranium on Oxidative Stress, Detoxification, and Defence Parameters of Zebrafish Danio rerio  

Science Journals Connector (OSTI)

In this study, we investigated the effects of depleted uranium (DU), the by-product of nuclear enrichment of uranium, on several parameters related to oxidative stress...Danio rerio. Several parameters were recor...

Beatrice Gagnaire; Isabelle Cavalie…

2013-01-01T23:59:59.000Z

455

Renal dysfunction induced by long-term exposure to depleted uranium in rats  

Science Journals Connector (OSTI)

Depleted uranium (DU) is a kind of radioactive ... euthanized and tissue samples were collected, and uranium levels were measured in a variety of ... to analyze the dynamic changes and distribution of uranium in ...

Guoying Zhu; Xiqiao Xiang; Xiao Chen; Lihua Wang; Heping Hu…

2009-01-01T23:59:59.000Z

456

Experimental and simulation studies of sequestration of supercritical carbon dioxide in depleted gas reservoirs  

E-Print Network (OSTI)

he feasibility of sequestering supercritical CO2 in depleted gas reservoirs. The experimental runs involved the following steps. First, the 1 ft long by 1 in. diameter carbonate core is inserted into a viton Hassler sleeve and placed inside...

Seo, Jeong Gyu

2004-09-30T23:59:59.000Z

457

Milestones Keep DUF6 Plants Moving Ahead | Department of Energy  

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

Milestones Keep DUF6 Plants Moving Ahead Milestones Keep DUF6 Plants Moving Ahead Milestones Keep DUF6 Plants Moving Ahead May 30, 2013 - 12:00pm Addthis Cylinders containing depleted uranium hexafluoride. Cylinders containing depleted uranium hexafluoride. The depleted uranium hexafluoride conversion plant in Paducah. The depleted uranium hexafluoride conversion plant in Paducah. Workers inspect cylinders containing depleted uranium hexafluoride. Workers inspect cylinders containing depleted uranium hexafluoride. The operating room at a depleted uranium hexafluoride conversion plant. The operating room at a depleted uranium hexafluoride conversion plant. Cylinders containing depleted uranium hexafluoride. The depleted uranium hexafluoride conversion plant in Paducah. Workers inspect cylinders containing depleted uranium hexafluoride.

458

Simultaneous wave and current forces on a cylinder near the bottom boundary  

E-Print Network (OSTI)

) December 1979 1Z43363 ABSTRACT Simultaneous Wave and Current Forces on a Cylinder Near the Bottom Boundary. (December 1979) David Alex Knoll, B. S. , University of Missouri at Rolls Chai. rman of Advisory Committee: Dr. J. B. Herbich This paper is a.... ACKNOWLEDGEMENT S The author wishes to extend his appreciation to Dr. John B. Herbich of the Ocean Engineering Program for assistance and guidance in the work and preparation of this thesis. The author is also grateful to Dr. T. C. Su of the Ocean Engineer...

Knoll, David Alex

2012-06-07T23:59:59.000Z

459

Development of a UF{sub 6} cylinder transient heat transfer/stress analysis model  

SciTech Connect

A heat transfer/stress analysis model is being developed to simulate the heating to a point of rupture of a cylinder containing UF{sub 6} when it is exposed to a fire. The assumptions underlying the heat transfer portion of the model, which has been the focus of work to date, will be discussed. A key aspect of this model is a lumped parameter approach to modeling heat transfer. Preliminary results and future efforts to develop an integrated thermal/stress model will be outlined.

Williams, W.R. [Martin Marietta Energy Systems, Inc., Oak Ridge, TN (United States)

1991-12-31T23:59:59.000Z

460

Fully pseudospectral solution of the conformally invariant wave equation near the cylinder at spacelike infinity  

E-Print Network (OSTI)

We study the scalar, conformally invariant wave equation on a four-dimensional Minkowski background in spherical symmetry, using a fully pseudospectral numerical scheme. Thereby, our main interest is in a suitable treatment of spatial infinity, which is represented as a cylinder. We consider both Cauchy problems, where we evolve data from a Cauchy surface to future null infinity, as well as characteristic initial value problems with data at past null infinity, and demonstrate that highly accurate numerical solutions can be obtained for a small number of grid points.

Jörg Frauendiener; Jörg Hennig

2014-04-02T23:59:59.000Z

Note: This page contains sample records for the topic "depleted uf6 cylinder" 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.


461

Experimental Investigations of Mixing?Processes in The Wake of A Circular Cylinder in Stratified Flows  

Science Journals Connector (OSTI)

The existence of oxygen?rich saltwater in the deeper basins of the Baltic Sea is mainly caused by sporadic inflow?events of salty and oxygen?rich saltwater from the North Sea into the Baltic Sea. These inflows take place over the narrow and shallow Drogden Sill into the first basin the Arkona Sea. Actually different offshore wind farms are planned in this region which opens a whole string of questions about the ecological influence of offshore wind farms on the mixing of both layers. To answer these questions numerical simulations of the mixing processes in the wake of wind turbine bases have been carried out. For the evaluation and quantification of these mixing processes a laboratory?experiment with a simplified model of the natural configuration has been realized. For this purpose a new water?channel has been build. This channel allows to simulate the inflow of saltwater in a size?scale of 1:100 to reality by keeping the densimetric Froude?Number. The experimental configuration consists of a long circular cylinder with a diameter of 8 cm in a 10 cm thick saltwater?layer flowing under a stationary fresh?water layer of 30 cm thickness. Focus point of this investigation is the wake of the cylinder in the stratified flow and the mixing?processes in the shear?layer due to the influence of the cylinder. The stratified flow around the cylinder induces the typical Karman?vortex wake horseshoe?vortices at the bottom and in the shear layer and Kelvin?Helmholtz?instabilities in the shear?layer. Nonintrusive optical measurements were taken with planar laser?induced fluorescence (PLIF) combined with two dimensional particle imaging velocimetry (PIV). The combination of both techniques allows the determination of instantaneous velocity components u and w from PIV?measurements the salinity s from PLIF?experiments their variations u? w? s? and the correlations of those like Reynolds?stress terms (u?u? u?w? w?w?) and turbulent? or Reynolds?flux terms (w?s? u?s?). Especially the vertical Reynolds?flux w?s? is the characteristic parameter to evaluate entrainment?velocity and entrainment?coefficient.

Peter Menzel; Frank Hüttmann; Martin Brede; Alfred Leder

2007-01-01T23:59:59.000Z

462

Forensics of Soot: Nanostructure as a Diagnostic of In-Cylinder Chemistry  

SciTech Connect

We report observations of changes in the microstructure of soot from an experimental light-duty diesel engine, produced with varying levels of biodiesel fuel blending. Based on these changes, we propose a hypothesis for how these changes relate to in-cylinder combustion chemistry. Our hypothesis centers on the assumption that fullerenic lamellar structures in soot trace their origin to 5-membered rings (C5s) formed early in the combustion process from gas-phase reaction intermediates. We also speculate that fullerenic microstructures may be a general feature of soot produced with oxygenated fuels and might be useful for diagnosing important changes in combustion trajectories.

Vander Wal, Dr. Randy [Pennsylvania State University, State College, PA] [Pennsylvania State University, State College, PA; Strzelec, Dr. Andrea [Texas A& M University] [Texas A& M University; Toops, Todd J [ORNL] [ORNL; Daw, C Stuart [ORNL] [ORNL

2012-01-01T23:59:59.000Z

463

Fact #852 December 22, 2014 Turbocharged Engines Account for 64.7% of all Four-Cylinder Gasoline Car Engines in 2014- Dataset  

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

Excel file with dataset for Fact #852 December 22, 2014 Turbocharged Engines Account for 64.7% of all Four-Cylinder Gasoline Car Engines in 2014

464

PIV study of the effect of piston position on the in-cylinder swirling flow during the scavenging process in large two-stroke marine diesel engines  

Science Journals Connector (OSTI)

A simplified model of a low speed large two-stroke marine diesel engine cylinder is developed. The effect of piston...

S. Haider; T. Schnipper; A. Obeidat…

2013-03-01T23:59:59.000Z

465

Evaluation of coverage of enriched UF{sub 6} cylinder storage lots by existing criticality accident alarms  

SciTech Connect

The Portsmouth Gaseous Diffusion Plant (PORTS) is leased from the US Department of Energy (DOE) by the United States Enrichment Corporation (USEC), a government corporation formed in 1993. PORTS is in transition from regulation by DOE to regulation by the Nuclear Regulatory Commission (NRC). One regulation is 10 CFR Part 76.89, which requires that criticality alarm systems be provided for the site. PORTS originally installed criticality accident alarm systems in all building for which nuclear criticality accidents were credible. Currently, however, alarm systems are not installed in the enriched uranium hexafluoride (UF{sub 6}) cylinder storage lots. This report analyzes and documents the extent to which enriched UF{sub 6} cylinder storage lots at PORTS are covered by criticality detectors and alarms currently installed in adjacent buildings. Monte Carlo calculations are performed on simplified models of the cylinder storage lots and adjacent buildings. The storage lots modelled are X-745B, X-745C, X745D, X-745E, and X-745F. The criticality detectors modelled are located in building X-343, the building X-344A/X-342A complex, and portions of building X-330. These criticality detectors are those located closest to the cylinder storage lots. Results of this analysis indicate that the existing criticality detectors currently installed at PORTS are largely ineffective in detecting neutron radiation from criticality accidents in most of the cylinder storage lots at PORTS, except sometimes along portions of their peripheries.

Lee, B.L. Jr.; Dobelbower, M.C.; Woollard, J.E.; Sutherland, P.J.; Tayloe, R.W. Jr.

1995-03-01T23:59:59.000Z

466

A UNIFIED REPRESENTATION OF GAS-PHASE ELEMENT DEPLETIONS IN THE INTERSTELLAR MEDIUM  

SciTech Connect

A study of gas-phase element abundances reported in the literature for 17 different elements sampled over 243 sight lines in the local part of our Galaxy reveals that the depletions into solid form (dust grains) are extremely well characterized by trends that employ only three kinds of parameters. One is an index that describes the overall level of depletion applicable to the gas in any particular sight line, and the other two represent linear coefficients that describe how to derive each element's depletion from this sight-line parameter. The information from this study reveals the relative proportions of different elements that are incorporated into dust at different stages of grain growth. An extremely simple scheme is proposed for deriving the dust contents and metallicities of absorption-line systems that are seen in the spectra of distant quasars or the optical afterglows of gamma-ray bursts. Contrary to presently accepted thinking, the elements sulfur and krypton appear to show measurable changes in their depletions as the general levels of depletions of other elements increase, although more data are needed to ascertain whether or not these findings are truly compelling. Nitrogen appears to show no such increase. The incorporation of oxygen into solid form in the densest gas regions far exceeds the amounts that can take the form of silicates or metallic oxides; this conclusion is based on differential measurements of depletion and thus is unaffected by uncertainties in the solar abundance reference scale.

Jenkins, Edward B. [Princeton University Observatory, Princeton, NJ 08544-1001 (United States)], E-mail: ebj@astro.princeton.edu

2009-08-01T23:59:59.000Z

467

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

SciTech Connect

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

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

2012-07-01T23:59:59.000Z

468

Forecasts on the Dark Energy and Primordial Non-Gaussianity Observations with the Tianlai Cylinder Array  

E-Print Network (OSTI)

The Tianlai experiment is dedicated to the observation of large scale structures (LSS) by the 21 cm intensity mapping technique. In this paper we make forecasts on its capability at observing or constraining the dark energy parameters and the primordial non-Gaussianity. From the LSS data one can use the baryon acoustic oscillation (BAO) and the growth rate derived from the redshift space distortion (RSD) to measure the dark energy density and equation of state. The primordial non-Gaussianity can be constrained either by looking for scale-dependent bias in the power spectrum, or by using the bispectrum. Here we consider three cases: the Tianlai cylinder array pathfinder which is currently being built, an upgrade of the pathfinder array with more receiver units, and the full-scale Tianlai cylinder array. Using the full-scale Tianlai experiment, we expect $\\sigma_{w_0} \\sim 0.082$ and $\\sigma_{w_a} \\sim 0.21$ from the BAO and RSD measurements, $\\sigma_{\\rm f_{NL}}^{\\rm local} \\sim 14$ from the power spectrum mea...

Xu, Yidong; Chen, Xuelei

2014-01-01T23:59:59.000Z

469

Effects of Magnetic Field on the Turbulent Wake of a Cylinder in MHD Channel Flow  

SciTech Connect

Results from a free-surface MHD flow experiment are presented detailing the modi cation of vortices in the wake of a circular cylinder with its axis parallel to the applied magnetic fi eld. Experiments were performed with a Reynolds number near Re ~ 104 as the interaction parameter, N = |j x#2; B| / |? (? ? ?), was increased through unity. By concurrently sampling the downstream fluid velocity at sixteen cross-stream locations in the wake, it was possible to extract an ensemble of azimuthal velocity profi les as a function of radius for vortices shed by the cylinder at varying strengths of magnetic field. Results indicate a signi cant change in vortex radius and rotation as N is increased. The lack of deviations from the vortex velocity pro file at high magnetic fi elds suggests the absence of small-scale turbulent features. By sampling the wake at three locations downstream in subsequent experiments, the decay of the vortices was examined and the effective viscosity was found to decrease as N-049±0.4. This reduction in effective viscosity is due to the modi cation of the small-scale eddies by the magnetic fi eld. The slope of the energy spectrum was observed to change from a k-1.8 power-law at low N to a k-3.5 power-law for N > 1. Together, these results suggest the flow smoothly transitioned to a quasi-two-dimensional state in the range 0 < N < 1.

John Rhoads, Eric Edlund and Hantao Ji

2013-04-17T23:59:59.000Z

470

Reactivity Controlled Compression Ignition (RCCI) Combustion on a Multi-Cylinder Light-Duty Diesel Engine  

SciTech Connect

Reactivity controlled compression ignition is a low-temperature combustion technique that has been shown, both in computational fluid dynamics modeling and single-cylinder experiments, to obtain diesel-like efficiency or better with ultra-low nitrogen oxide and soot emissions, while operating primarily on gasoline-like fuels. This paper investigates reactivity controlled compression ignition operation on a four-cylinder light-duty diesel engine with production-viable hardware using conventional gasoline and diesel fuel. Experimental results are presented over a wide speed and load range using a systematic approach for achieving successful steady-state reactivity controlled compression ignition combustion. The results demonstrated diesel-like efficiency or better over the operating range explored with low engine-out nitrogen oxide and soot emissions. A peak brake thermal efficiency of 39.0% was demonstrated for 2600 r/min and 6.9 bar brake mean effective pressure with nitrogen oxide emissions reduced by an order of magnitude compared to conventional diesel combustion operation. Reactivity controlled compression ignition emissions and efficiency results are compared to conventional diesel combustion operation on the same engine.

Curran, Scott [ORNL; Hanson, Reed M [ORNL; Wagner, Robert M [ORNL

2012-01-01T23:59:59.000Z

471

MotorWeek Video Transcript: BlueTec Clean Diesel and GM's Cylinder Cut-off  

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

BlueTec Clean Diesel and GM's Cylinder Cut-off BlueTec Clean Diesel and GM's Cylinder Cut-off Jessica Shea Choksey:Mercedes-Benz has over 80 years of diesel experience. So it's no surprise they are on the cutting edge of making them environmentally friendly. The full-size seven-passenger 2007 Mercedes-Benz GL320 BlueTec is the cleanest diesel sport-utility vehicle in the world. Named after the color of the emission reducing urea fluid injected into the catalyst system, BlueTec is the technology that can ultimately make clean diesels the obvious choice for Americans. Using Mercedes latest 3.2 liter Turbo diesel V-6, the GL320 will also be the most efficient big SUV with an anticipated highway fuel economy of over 25 miles per gallon. The GL BlueTec goes on sale in January. Also making fuel-saving automotive news is General Motors. As part of

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Replication of engine block cylinder bridge microstructure and mechanical properties with lab scale 319 Al alloy billet castings  

SciTech Connect

In recent years, aluminum alloy gasoline engine blocks have in large part successfully replaced nodular cast iron engine blocks, resulting in improved vehicle fuel efficiency. However, because of the inadequate wear resistance properties of hypoeutectic Al–Si alloys, gray iron cylinder liners are required. These liners cause the development of large tensile residual stress along the cylinder bores and necessitate the maximization of mechanical properties in this region to prevent premature engine failure. The aim of this study was to replicate the engine cylinder bridge microstructure and mechanical properties following TSR treatment (which removes the sand binder to enable easy casting retrieval) using lab scale billet castings of the same alloy composition with varying cooling rates. Comparisons in microstructure between the engine block and the billet castings were carried out using optical and scanning electron microscopy, while mechanical properties were assessed using tensile testing. The results suggest that the microstructure at the top and middle of the engine block cylinder bridge was successfully replicated by the billet castings. However, the microstructure at the bottom of the cylinder was not completely replicated due to variations in secondary phase morphology and distribution. The successful replication of engine block microstructure will enable the future optimization of heat treatment parameters. - Highlights: • A method to replicate engine block microstructure was developed. • Billet castings will allow cost effective optimization of heat treatment process. • The replication of microstructure in the cylinder region was mostly successful. • Porosity was more clustered in the billet castings compared to the engine block. • Mechanical properties were lower in billet castings due to porosity and inclusions.

Lombardi, A., E-mail: a2lombar@ryerson.ca [Centre for Near-net-shape Processing of Materials, Ryerson University, 101 Gerrard Street East, Toronto, Ontario M5B2K3 (Canada); D'Elia, F.; Ravindran, C. [Centre for Near-net-shape Processing of Materials, Ryerson University, 101 Gerrard Street East, Toronto, Ontario M5B2K3 (Canada); MacKay, R. [Nemak of Canada Corporation, 4600 G.N. Booth Drive, Windsor, Ontario N9C4G8 (Canada)

2014-01-15T23:59:59.000Z

473

Three-dimensional balancing of the Stiller-Smith mechanism for application to an eight cylinder I. C. engine  

SciTech Connect

The Stiller-Smith Mechanism employs a double cross-slider to convert linear reciprocating motion into rotational motion. It has previously been shown that a four-cylinder configuration utilizing this motion conversion device can be balanced in two dimensions. The inherent planar nature of this mechanism makes it possible to produce a compact, eight cylinder configuration for use as an internal combustion engine which is balanced in three dimensions. This paper develops and presents the necessary requirements for such a balanced engine. Relative merits of various configurations are discussed and analytical results of different balancing schemes are presented.

McKisic, A.D.; Smith, J.E.; Craven, R.; Prucz, J.

1987-01-01T23:59:59.000Z

474

Depleted uranium munitions—where are we now?  

Science Journals Connector (OSTI)

Kinetic energy weapons that contain a penetrator of depleted uranium (DU) were first used in the Gulf War of 1991 and were subsequently used in the Balkans. DU penetrators are considered to have significant operational advantages over those made of tungsten as they are capable of penetrating the heavy armour of the modern battle tank. The use of DU rounds in military conflicts has, however, provoked a wide debate about the health consequences for soldiers and the local population since DU is a toxic metal and is radioactive. The Royal Society became involved in the debate about the health hazards of DU munitions as a result of public concern, to produce an independent view on the science and the uncertainties, uninfluenced by the conflicting interests of governments and the military, who consider that the risks are very slight, and of other individuals and organisations, some of whom have suggested that hundreds of thousands of deaths from cancer may result from the use of DU in the Gulf War. Large quantities of DU rounds were deployed in the Gulf War (about 340 tonnes) and much smaller amounts in the Balkans (about 11 tonnes). In both conflicts the majority of the DU rounds were fired from aircraft in strafing attacks where most of the penetrators miss their target and penetrate several metres into the soil. Consequently, large numbers of DU penetrators are believed to remain buried in the ground. Corrosion of these penetrators will occur with the possibility of a gradual rise in the uranium levels in local water supplies. About 10,000 larger calibre DU rounds were fired from tanks during the Gulf War, although these were not used in the Balkans. DU rounds that penetrate a target vehicle may pass straight through or, particularly if they hit heavy armour, may release a variable proportion of the penetrator as DU particles which ignite to produce an aerosol of DU oxides. The DU particles released during such impacts will be inhaled by those surviving within a struck tank or by those in the path of the DU aerosol. Unless adequate respiratory protection is used, DU particles will also be inhaled by those charged with cleaning up DU-contaminated vehicles. The fraction of a DU penetrator that is aerosolised and the fraction of the particles of DU oxides that are within the respirable range, as well as the solubility properties of the DU oxides, are not well documented and depend on the type of impact, but a range of values is available from test firings of DU rounds. A number of exposure scenarios were considered in the two Royal Society reports on the Health Hazards of DU Munitions [1, 2] and central and worst-case intakes of DU were estimated from the range of values obtained from test firings. These estimated intakes, and the range of reported values of the properties of the DU oxides released during an impact or fire, were used to produce central estimates and worst-case estimates of risks for soldiers on the battlefield. Although there are uncertainties about the intakes of DU, and of the properties of the DU oxides, there is a clear view among radiation biologists that, given the equivalent doses to tissues, the excess lifetime risks of various fatal cancers can be estimated, perhaps with an order of magnitude of uncertainty. Therefore if the intakes of DU, or the properties of DU oxides, are in future better defined, the estimates of risk given in the Royal Society reports can be adjusted appropriately. There are very different views on the health hazards of DU munitions. Most of the concerns of veterans and their advisors focus on the radiological effects of DU and consequently these are the focus of this editorial. Effects on the kidney and environmental consequences are, however, considered in the second of the Royal Society reports [2] and the main conclusions of both of the reports are outlined in the summary document published in this issue of the journal (page 131). The main radiological concerns focus on the irradiation of lung tissues from inhaled DU particles and irradiation resulting from the translocation

Brian G Spratt

2002-01-01T23:59:59.000Z

475

Defining the needs for non-destructive assay of UF6 feed, product, and tails at gas centrifuge enrichment plants and possible next steps  

SciTech Connect

Current safeguards approaches used by the IAEA at gas centrifuge enrichment plants (GCEPs) need enhancement in order to detect undeclared LEU production with adequate detection probability using non destructive assay (NDA) techniques. At present inspectors use attended systems, systems needing the presence of an inspector for operation, during inspections to verify the mass and {sup 235}U enrichment of UF{sub 6} bulk material used in the process of enrichment at GCEPS. The inspectors also take destructive assay (DA) samples for analysis off-site which provide accurate, on the order of 0.1 % to 0.5% uncertainty, data on the enrichment of the UF{sub 6} feed, tails, and product. However, DA sample taking is a much more labor intensive and resource intensive exercise for the operator and inspector. Furthermore, the operator must ship the samples off-site to the IAEA laboratory which delays the timeliness of the results and contains the possibility of the loss of the continuity of knowledge of the samples during the storage and transit of the material. Use of the IAEA's inspection sampling algorithm shows that while total sample size is fixed by the total population of potential samples and its intrinsic qualities, the split of the samples into NDA or DA samples is determined by the uncertainties in the NDA measurements. Therefore, the larger the uncertainties in the NDA methods, more of the sample taken must be DA samples. Since the DA sampling is arduous and costly, improvements in NDA methods would reduce the number of DA samples needed. Furthermore, if methods of on-site analysis of the samples could be developed that have uncertainties in the 1-2% range, a lot of the problems inherent in DA sampling could be removed. The use of an unattended system that could give an overview of the entire process giving complementary data on the enrichment process as well as accurate measures of enrichment and weights of the UF{sub 6} feed, tails, and product would be a major step in enhancing the ability of NDA beyond present attended systems. The possibility of monitoring the feed, tails, and product header pipes in such a way as to gain safeguards relevant flow and enrichment information without compromising the intellectual property of the operator including proprietary equipment and operational parameters would be a huge step forward. This paper contains an analysis of possible improvements in unattended and attended NDA systems including such process monitoring and possible on-site analysis of DA samples that could reduce the uncertainty of the inspector measurements reducing the difference between the operator's and inspector's measurements providing more effective and efficient IAEA GeEPs safeguards.

Boyer, Brian D [Los Alamos National Laboratory; Swinhoe, Martyn T [Los Alamos National Laboratory; Moran, Bruce W [IAEA; Lebrun, Alain [IAEA

2009-01-01T23:59:59.000Z

476

Vibro-acoustical comfort in cars at idle : human perception of simulated sounds and vibrations from three and four cylinder diesel engines  

E-Print Network (OSTI)

three and four cylinder diesel engines Etienne Parizet, Maël Amari Laboratoire Vibrations Acoustique This paper deals with comfort in diesel cars running at idle. A bench was used to reproduce the vertical cylinder engines. In the first one, subjects were exposed to seat vertical vibrations only, and had

Paris-Sud XI, Université de

477

Power, Efficiency, and Emissions Optimization of a Single Cylinder Direct-Injected Diesel Engine for Testing of Alternative Fuels through Heat Release Modeling  

E-Print Network (OSTI)

Power, Efficiency, and Emissions Optimization of a Single Cylinder Direct-Injected Diesel Engine for Testing of Alternative Fuels through Heat Release Modeling BY Jonathan Michael Stearns Mattson Submitted to