Powered by Deep Web Technologies
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.


1

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

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

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

2

Depleted UF6 Management Program Overview Presentation  

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

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

3

Depleted UF6 Overview Presentation  

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

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

4

Depleted UF6 Health Risks  

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

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

5

Depleted UF6 Internet Resources  

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

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

6

Environmental Risks of Depleted UF6 Disposal  

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

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

7

Production and Handling Slide 31: Certification of UF6 Cylinder...  

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

UF6 Cylinder Volume Skip Presentation Navigation First Slide Previous Slide Next Slide Last Presentation Table of Contents Certification of UF6 Cylinder Volume The cylinder...

8

Depleted UF6 Production and Handling Slide Presentation  

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

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

9

NGSI: IAEA Verification of UF6 Cylinders  

Science Conference Proceedings (OSTI)

The International Atomic Energy Agency (IAEA) is often ignorant of the location of declared, uranium hexafluoride (UF6) cylinders following verification, because cylinders are not typically tracked onsite or off. This paper will assess various methods the IAEA uses to verify cylinder gross defects, and how the task could be ameliorated through the use of improved identification and monitoring. The assessment will be restricted to current verification methods together with one that has been applied on a trial basis—short-notice random inspections coupled with mailbox declarations. This paper is part of the NNSA Office of Nonproliferation and International Security’s Next Generation Safeguards Initiative (NGSI) program to investigate the concept of a global monitoring scheme that uniquely identifies and tracks UF6 cylinders.

Curtis, Michael M.

2012-06-05T23:59:59.000Z

10

Health Risks Associated with Conversion of Depleted UF6  

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

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

11

Depleted UF6 Conversion facility EIS Topics  

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

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

12

Unsubscribe from the Depleted UF6 E-mail List  

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

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

13

Production and Handling Slide 29: UF6 Cylinder Fill Limit Criteria  

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

Criteria Skip Presentation Navigation First Slide Previous Slide Next Slide Last Presentation Table of Contents UF6 Cylinder Fill Limit Criteria No UF6 cylinder shall be filled...

14

News Media Exits for Depleted Uranium and Depleted UF6 Articles  

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

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

15

Production and Handling Slide 35: UF6 Cylinder Data Summary  

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

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

16

Environmental Risks Associated with Conversion of Depleted UF6  

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

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

17

Enrichment Assay Methods for a UF6 Cylinder Verification Station  

Science Conference Proceedings (OSTI)

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 cylinder inventory. These enrichment assay methods interrogate only a small fraction of the total cylinder volume, and are time-consuming and expensive to execute for inspectors. Pacific Northwest National Laboratory (PNNL) is developing an unattended measurement system capable of automated enrichment measurements over the full volume of Type 30B and Type 48 cylinders. This 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 focus of this paper is the development of nondestructive assay (NDA) methods that combine “traditional” enrichment signatures (e.g. 185-keV emission from U-235) and more-penetrating “non-traditional” signatures (e.g. high-energy neutron-induced gamma rays spawned primarily from U-234 alpha emission) collected by medium-resolution gamma-ray spectrometers (i.e. sodium iodide or lanthanum bromide). The potential of these NDA methods for the automated assay of feed, tail and product cylinders is explored through MCNP modeling and with field measurements on a cylinder population ranging from 0.2% to 5% in U-235 enrichment.

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

2010-11-30T23:59:59.000Z

18

Production and Handling Slide 30: UF6 Cylinder Fill Limit Weights  

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

Weights Skip Presentation Navigation First Slide Previous Slide Next Slide Last Presentation Table of Contents UF6 Cylinder Fill Limit Weights A minimum volume, stated in cubic...

19

Integrating UF6 Cylinder RF Tracking With Continuous Load Cell Monitoring for Verifying Declared UF6 Feed and Withdrawal Operations Verifying Declared UF6 Feed and Withdrawal Operations  

SciTech Connect

Oak Ridge National Laboratory is demonstrating the integration of UF6 cylinder tracking, using RF technology, with continuous load cell monitoring (CLCM) at mock UF6 feed and withdrawal (F&W) stations. CLCM and cylinder tracking are two of several continuous-monitoring technologies that show promise in providing integrated safeguards of F&W operations at enrichment plants. Integrating different monitoring technologies allows advanced, automated event processing to screen innocuous events thereby minimizing false alerts to independent inspectors. Traditionally, international inspectors rely on batch verification of material inputs and outputs derived from operator declarations and periodic on-site inspections at uranium enrichment plants or other nuclear processing facilities. Continuously monitoring F&W activities between inspections while providing filtered alerts of significant operational events will substantially increase the amount of valuable information available to inspectors thereby promising to enhance the effectiveness of safeguards and to improve efficiency in conducting on-site inspections especially at large plants for ensuring that all operations are declared.

Krichinsky, Alan M [ORNL; Miller, Paul [ORNL; Pickett, Chris A [ORNL; Richardson, Dave [ORNL; Rowe, Nathan C [ORNL; Whitaker, J Michael [ORNL; Younkin, James R [ORNL

2009-01-01T23:59:59.000Z

20

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

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

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

Science Conference Proceedings (OSTI)

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

22

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

23

Summary of Field Measurement on UF6 Cylinders Using Electro-Mechanically Cooled Systems  

SciTech Connect

Measurement of the enrichment of solid state UF6 stored within large metal cylinders is a task commonly performed by plant operators and inspectors. The measurement technologies typically used range from low-resolution, high-efficiency sodium iodide detectors to high-resolution, moderate-efficiency high-purity germanium (HPGe) detectors. The technology used and methods deployed are dependent upon the material being measured, environmental conditions, time constraints, and measurement-precision requirements. Operators and inspectors typically use specially designed, HPGe detectors that are cooled with liquid nitrogen in situations where high-resolution measurements are required. However, the requirement for periodically refilling the system with liquid nitrogen makes remote usage cumbersome and slow. The task of cooling the detector reduces the available time for the inspector to perform other safeguards activities while on site. If the inspector has to reduce the count time for each selected cylinder to ensure that all preselected cylinders are measured during the inspection, the resulting measurement uncertainties may be increased, making it more difficult to detect and verify potential discrepancies in the operator's declarations. However, recent advances in electromechanically cooled HPGe detectors may provide the inspector with an improved verification tool by eliminating the need for liquid nitrogen. This report provides a summary of test results for field measurements performed using electromechanically cooled HPGe detectors on depleted, natural, and low-enriched uranium cylinders. The results of the study provide valuable information to inspectors and operators regarding the capabilities and limitations of electromechanically cooled systems based on true field-measurement conditions.

McGinnis, Brent R [ORNL; Smith, Steven E [ORNL; Solodov, Alexander A [ORNL; Whitaker, J Michael [ORNL; Morgan, James B [ORNL; MayerII, Richard L. [USEC; Montgomery, J. Brent [U.S. Enrichment Corporation Paducah Gaseous Diffusion Plant

2009-01-01T23:59:59.000Z

24

Environmental Risks of Depleted UF6-related Manufacturing Activities  

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

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

25

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

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

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

26

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

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

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

27

Prototype Radiation Detector Positioning System For The Automated Nondestructive Assay Of Uf6 Cylinders  

Science Conference Proceedings (OSTI)

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 cylinder inventory. These measurements are time-consuming, expensive, 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 efficiency and assay accuracy. This paper describes an approach denoted the Integrated Cylinder Verification Station (ICVS) that supports 100% cylinder verification, provides volume-averaged cylinder enrichment assay, and reduces inspector manpower needs. To allow field measurements to be collected to validate data collection algorithms, a prototype radiation detector positioning system was constructed. The system was designed to accurately position an array of radiation detectors along the length of a cylinder to measure UF6 enrichment. A number of alternative radiation shields for the detectors were included with the system. A collimated gamma-ray spectrometer module that allows translation of the detectors in the surrounding shielding to adjust the field of view, and a collimating plug in the end to further reduce the low-energy field of view, were also developed. Proof-of-principle measurements of neutron and high-energy gamma-ray signatures, using moderated neutron detectors and large-volume spectrometers in a fixed-geometry, portal-like configuration, supported an early assessment of the viability of the concept. The system has been used successfully on two testing campaigns at an AREVA fuel fabrication plant to scan over 30 product cylinders. This paper will describe the overall design of the detector positioning system and provide an overview of the Integrated Cylinder Verification Station (ICVS) approach.

Hatchell, Brian K.; Valdez, Patrick LJ; Orton, Christopher R.; Mace, Emily K.

2011-08-07T23:59:59.000Z

28

Determination of the 235U Mass and Enrichment within Small UF6 Cylinders via a Neutron Coincidence Well Counting System  

Science Conference Proceedings (OSTI)

The construction of three new uranium enrichment facilities in the United States has sparked renewed interest in the development and enhancement of methods to determine the enrichment and fissile mass content of UF6 cylinders. We describe the design and examine the expected performance of a UF6 bottle counter developed for the assay of Type 5A cylinders. The counter, as designed and subsequently constructed, is a tall passive neutron well counter with a clam-shell configuration and graphite end plugs operated in fast neutron mode. Factory performance against expectation is described. The relatively high detection efficiency and effectively 4 detection geometry provide a near-ideal measurement configuration, making the UF6 bottle counter a valuable tool for the evaluation of the neutron coincidence approach to UF6 cylinder assay. The impacts of non-uniform filling, voids, enrichment, and mixed enrichments are examined

McElroy, Robert Dennis [ORNL; Croft, Dr. Stephen [Los Alamos National Laboratory (LANL); Young, Brian M [Canberra Industries, Inc., Meriden, CT; Venkataraman, Ram [Canberra Industries, Inc., Meriden, CT

2011-01-01T23:59:59.000Z

29

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

Science Conference Proceedings (OSTI)

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

30

Signatures and Methods for the Automated Nondestructive Assay of UF6 Cylinders at Uranium Enrichment Plants  

Science Conference Proceedings (OSTI)

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 cylinder inventory. These measurements are time-consuming, expensive, 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. Such a station would use sensors that can be operated in an unattended mode at an industrial facility: medium-resolution scintillators for gamma-ray spectroscopy (e.g., NaI(Tl)) and moderated He-3 neutron detectors. This sensor combination allows the exploitation of additional, more-penetrating signatures beyond the traditional 185-keV emission from U-235: neutrons produced from F-19(?,n) reactions (spawned primarily from U 234 alpha emission) and high-energy gamma rays (extending up to 8 MeV) induced by neutrons interacting in the steel cylinder. This paper describes a study of these non-traditional signatures for the purposes of cylinder enrichment verification. The signatures and the radiation sensors designed to collect them are described, as are proof-of-principle cylinder measurements and analyses. Key sources of systematic uncertainty in the non-traditional signatures are discussed, and the potential benefits of utilizing these non-traditional signatures, in concert with an automated form of the traditional 185-keV-based assay, are discussed.

Smith, Leon E.; Mace, Emily K.; Misner, Alex C.; Shaver, Mark W.

2010-08-08T23:59:59.000Z

31

A "Proof-of-Concept" Demonstration of RF-Based Technologies for UF6 Cylinder Tracking at Centrifuge Enrichment Plant  

SciTech Connect

This effort describes how radio-frequency (RF) technology can be integrated into a uranium enrichment facility's nuclear materials accounting and control program to enhance uranium hexafluoride (UF6) cylinder tracking and thus provide benefits to both domestic and international safeguards. Approved industry-standard cylinders are used to handle and store UF6 feed, product, tails, and samples at uranium enrichment plants. In the international arena, the International Atomic Energy Agency (IAEA) relies on time-consuming manual cylinder inventory and tracking techniques to verify operator declarations and to detect potential diversion of UF6. Development of a reliable, automated, and tamper-resistant process for tracking and monitoring UF6 cylinders would greatly reduce the risk of false or misreported cylinder tare weights, diversion of nuclear material, concealment of excess production, utilization of undeclared cylinders, and misrepresentation of the cylinders contents. This paper will describe a "proof-of concept" system that was designed show the feasibility of using RF based technologies to track individual UF6 cylinders throughout their entire life cycle, and thus ensure both increased domestic accountability of materials and a more effective and efficient method for application of IAEA international safeguards at the site level. The proposed system incorporates RF-based identification devices, which provide a mechanism for a reliable, automated, and tamper-resistant tracking network. We explore how securely attached RF tags can be integrated with other safeguards technologies to better detect diversion of cylinders. The tracking system could also provide a foundation for integration of other types of safeguards that would further enhance detection of undeclared activities.

Pickett, Chris A [ORNL; Younkin, James R [ORNL; Kovacic, Donald N [ORNL; Dixon, E. T. [Los Alamos National Laboratory (LANL); Martinez, B. [Los Alamos National Laboratory (LANL)

2007-01-01T23:59:59.000Z

32

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

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

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

33

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

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

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

34

Cylinder Surveillance and Maintenance  

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

Surveillance and Maintenance Cylinder Surveillance and Maintenance DOE has a Cylinder Management program in place to inspect and maintain depleted UF6 cylinders, and to improve...

35

An Operator Perspective from a Facility Evaluation of an RFID-Based UF6 Cylinder Accounting and Tracking System  

SciTech Connect

An operational field test of a Radio-Frequency Identification (RFID) system for tracking and accounting UF6 cylinders was conducted at the Global Nuclear Fuel Americas (GNF) fuel fabrication plant in 2009. The Cylinder Accountability and Tracking System (CATS) was designed and deployed by Oak Ridge National Laboratory (ORNL) and evaluated in cooperation with GNF. The system required that passive RFID be attached to several UF6 30B cylinders as they were received at the site; then the cylinders were tracked as they proceeded to interim storage, to processing in an autoclave, and eventually to disposition from the site. This CATS deployment also provided a direct integration of scale data from the site accountability scales. The integration of this information into the tracking data provided an attribute for additional safeguards for evaluation. The field test provided insight into the advantages and challenges of using RFID at an operating nuclear facility. The RFID system allowed operators to interact with the technology and demonstrated the survivability of the tags and reader equipment in the process environment. This paper will provide the operator perspective on utilizing RFID technology for locating cylinders within the facility, thereby tracking the cylinders for process and for Material Control & Accounting functions. The paper also will present the operator viewpoint on RFID implemented as an independent safeguards system.

Martyn, Rose [Global Nuclear Fuels; Fitzgerald, Peter [Global Nuclear Fuels; Stehle, Nicholas D [ORNL; Rowe, Nathan C [ORNL; Younkin, James R [ORNL

2011-01-01T23:59:59.000Z

36

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

37

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

Science Conference Proceedings (OSTI)

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

38

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

39

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

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

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

40

Uranium Hexafluoride (UF6)  

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

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,

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.


41

Evaluation of a RF-Based Approach for Tracking UF6 Cylinders at a Uranium Enrichment Plant  

SciTech Connect

Approved industry-standard cylinders are used globally to handle and store uranium hexafluoride (UF{sub 6}) feed, product, tails, and samples at uranium enrichment plants. The International Atomic Energy Agency (IAEA) relies on time-consuming physical inspections to verify operator declarations and detect possible diversion of UF{sub 6}. Development of a reliable, automated, and tamper-resistant system for near real-time tracking and monitoring UF{sub 6} cylinders (as they move within an enrichment facility) would greatly improve the inspector function. This type of system can reduce the risk of false or misreported cylinder tare weights, diversion of nuclear material, concealment of excess production, utilization of undeclared cylinders, and misrepresentation of the cylinders contents. This paper will describe a proof-of-concept approach that was designed to evaluate the feasibility of using radio frequency (RF)-based technologies to track individual UF{sub 6} cylinders throughout a portion of their life cycle, and thus demonstrate the potential for improved domestic accountability of materials, and a more effective and efficient method for application of site-level IAEA safeguards. The evaluation system incorporates RF-based identification devices (RFID) which provide a foundation for establishing a reliable, automated, and near real-time tracking system that can be set up to utilize site-specific, rules-based detection algorithms. This paper will report results from a proof-of-concept demonstration at a real enrichment facility that is specifically designed to evaluate both the feasibility of using RF to track cylinders and the durability of the RF equipment to survive the rigors of operational processing and handling. The paper also discusses methods for securely attaching RF devices and describes how the technology can effectively be layered with other safeguard systems and approaches to build a robust system for detecting cylinder diversion. Additionally, concepts for off-site tracking of cylinders are described.

Pickett, Chris A [ORNL; Younkin, James R [ORNL; Kovacic, Donald N [ORNL; Laughter, Mark D [ORNL; Hines, Jairus B [ORNL; Boyer, Brian [Los Alamos National Laboratory (LANL); Martinez, B. [Los Alamos National Laboratory (LANL)

2008-01-01T23:59:59.000Z

42

Properties of UF6  

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

such as water vapor in the air, the UF6 and water react, forming corrosive hydrogen fluoride (HF) and a uranium-fluoride compound called uranyl fluoride (UO2F2). For more...

43

FAQ 18-What does a cylinder storage yard look like?  

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

cylinder storage yard look like? What does a cylinder storage yard look like? Pictures of depleted UF6 cylinder storage yards are shown below. Storage yards are large outdoor areas...

44

Health Effects Associated with Uranium Hexafluoride (UF6)  

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

Hexafluoride (UF6) UF6 Health Effects Uranium Hexafluoride (UF6) line line Properties of UF6 UF6 Health Effects Health Effects Associated with Uranium Hexafluoride (UF6) Uranium...

45

Production and Handling Slide 19: UF6  

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

Skip Presentation Navigation First Slide Previous Slide Next Slide Last Presentation Table of Contents UF6 Refer to caption below for image description Uranium hexafluoride UF6...

46

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

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

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

47

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

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

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

48

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

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

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

49

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

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

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

50

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

2008-01-01T23:59:59.000Z

51

Next Generations Safeguards Initiative: The Life of a Cylinder  

Science Conference Proceedings (OSTI)

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

52

Advancements of the Hybrid Method UF6 Container Inspection System  

Science Conference Proceedings (OSTI)

Safeguards inspectors currently visit uranium enrichment plants to verify UF6 cylinder enrichment declarations. Measurements are performed with handheld high-resolution detectors on a limited number of cylinders taken to be representative of the plant’s cylinder inventory. These enrichment assay methods interrogate only a small fraction of the total cylinder volume, and are time-consuming and expensive to execute. Pacific Northwest National Laboratory (PNNL) is developing an automated UF6 cylinder verification station concept based on the combined collection of traditional enrichment-meter data (186 keV photons from 235U) and non-traditional, neutron-induced, high-energy gamma-ray signatures (3-8 MeV) with an array of collimated, medium-resolution scintillators. Previous work at PNNL (2010) demonstrated proof-of-principle that this hybrid method yields accurate, full-volume assay of the cylinder enrichment, reduces systematic errors when compared to several other enrichment assay methods, and provides simplified instrumentation and algorithms suitable for long-term, unattended operations. This system aims to increase the number of inspected cylinders at higher accuracy and with lower cost than when compared to inspectors with hand-held instruments. Several measurement campaigns of 30B cylinder populations and a refined MCNP model will be reported. The MCNP model consists of per-gram basis vectors for the different uranium isotopes and several fill geometries, enabling fast generation of any UF6 enrichment level and multiple configurations. The refined model was used to optimize collimator design and detector configuration for the hybrid method. In addition, a new field prototype based on model results was utilized in a set of field measurements.

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

2011-07-17T23:59:59.000Z

53

Production and Handling Slide 22: UF6 Phase Diagram  

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

UF6 Phase Diagram Skip Presentation Navigation First Slide Previous Slide Next Slide Last Presentation Table of Contents UF6 Phase Diagram Refer to caption below for image...

54

Investigation of breached depleted UF sub 6 cylinders  

Science Conference Proceedings (OSTI)

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

DeVan, J.H.

1991-01-01T23:59:59.000Z

55

Method And Apparatus For Measuring Enrichment Of UF6  

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

For Measuring Enrichment Of UF6 A system and method are disclosed for determining the enrichment of .sup.235U in Uranium Hexafluoride (UF6) utilizing synthesized X-rays which...

56

Production and Handling Slide 33: Density of UF6  

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

of UF6 Skip Presentation Navigation First Slide Previous Slide Next Slide Last Presentation Table of Contents Density of UF6 Refer to caption below for image description The...

57

Production and Handling Slide 20: Advantages of UF6  

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

UF6 Skip Presentation Navigation First Slide Previous Slide Next Slide Last Presentation Table of Contents Advantages of UF6 Only one isotope of F2 Can be handled at reasonable...

58

FAQ 8-What is uranium hexafluoride (UF6)?  

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

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.

59

Investigation of breached depleted UF{sub 6} cylinders  

Science Conference Proceedings (OSTI)

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

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

1991-09-01T23:59:59.000Z

60

Investigation of breached depleted UF sub 6 cylinders  

Science Conference Proceedings (OSTI)

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

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

1991-09-01T23:59:59.000Z

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

Depleted Uranium Uses Research and Development  

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

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

62

METHOD AND APPARATUS FOR MEASURING ENRICHMENT OF UF6 - Energy ...  

A system and method are disclosed for determining the enrichment of .sup.235U in Uranium Hexafluoride (UF6) utilizing synthesized X-rays which are ...

63

Method and apparatus for measuring enrichment of UF6  

DOE Patents (OSTI)

A system and method are disclosed for determining the enrichment of .sup.235U in Uranium Hexafluoride (UF6) utilizing synthesized X-rays which are directed at a container test zone containing a sample of UF6. A detector placed behind the container test zone then detects and counts the X-rays which pass through the container and the UF6. In order to determine the portion of the attenuation due to the UF6 gas alone, this count rate may then be compared to a calibration count rate of X-rays passing through a calibration test zone which contains a vacuum, the test zone having experienced substantially similar environmental conditions as the actual test zone. Alternatively, X-rays of two differing energy levels may be alternately directed at the container, where either the container or the UF6 has a high sensitivity to the difference in the energy levels, and the other having a low sensitivity.

Hill, Thomas Roy (Santa Fe, NM); Ianakiev, Kiril Dimitrov (Los Alamos, NM)

2011-06-07T23:59:59.000Z

64

Video: The Depleted Uranium Hexafluoride Story  

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

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

65

Cylinder Leakage  

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

(breach) occurs and the depleted UF6 is exposed to water vapor in the air, uranyl fluoride (UO2F2) and hydrogen fluoride (HF) are formed. The uranyl fluoride is a solid that...

66

Overview of Depleted Uranium Hexafluoride Management Program  

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

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

67

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  

Science Conference Proceedings (OSTI)

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

68

Review of corrosion in 10- and 14-ton mild steel depleted UF{sub 6} storage cylinders  

Science Conference Proceedings (OSTI)

A literature review was conducted to determine the type, extent and severity of corrosion found in the 10- and 14-ton mild steel depleted UF{sub 6} storage cylinders. Also discussed in this review is corrosion found in the valves and plugs used in the cylinders. Corrosion of the cylinders is a gradual process which occurs slowly over time. Understanding corrosion of the cylinders is an important concern for long term storage of the UF{sub 6} in the cylinder yards, as well as the final disposition of the depleted UF{sub 6} tails inventory in the future. The following conclusions are made from the literature review: (1) The general external corrosion rate of the cylinders is about 1 to 2 mils per year (1 mil = 0.001{double_prime}). The highest general external corrosion rate was over 5 mpy on the 48G type cylinders. (2) General internal corrosion from the depleted UF{sub 6} is negligible under normal storage conditions. Crevice corrosion can occur at the cylinder/saddle interface from the retention of water in this area. Crevice corrosion can occur at the cylinder/skirt interface on the older skirted cylinders due to the lack of water drainage in this area. Crevice corrosion can occur on cylinders that have been in ground contact. Crevice corrosion and galvanic corrosion can occur where the stainless steel I.D. nameplates are attached to the cylinder. The packing nuts on the bronze one-inch valves used in the cylinders are susceptible to stress corrosion cracking (SCC). Mechanical damage from routine handling can lead to a breach in a cylinder with subsequent accelerated corrosion of the mild steel due to attack from HF and other UF{sub 6} hydrolysis by-products.

Lykins, M.L.

1995-08-01T23:59:59.000Z

69

MODEL AND ALGORITHM EVALUATION FOR THE HYBRID UF6 CONTAINER INSPECTION SYSTEM  

Science Conference Proceedings (OSTI)

ABSTRACT Pacific Northwest National Laboratory (PNNL) is developing an automated UF6 cylinder verification station concept based on the combined collection of traditional enrichment-meter (186 keV photons from U-235) data and non-traditional, neutron-induced, high-energy gamma-signatures (3-8.5 MeV) with an array of collimated, medium-resolution scintillators. Previous (2010) work at PNNL demonstrated proof-of-principle that this hybrid method yields accurate, full-volume assay of the cylinder enrichment, reduces systematic errors when compared to several other enrichment assay methods, and provides simplified instrumentation and algorithms suitable for long-term unattended operations. We used Monte Carlo modeling with MCNP5 to support system design (e.g., number and configuration of detector arrays, and design of iron/poly collimators for enhanced (n,?) conversion) and enrichment algorithm development. We developed a first-generation modeling framework in 2010. These tools have since been expanded, refined and benchmarked against field measurements with a prototype system of a 30B cylinder population (0.2 to 4.95 weight % U-235). The MCNP5 model decomposes the radiation transport problem into a linear superposition of “basis spectra” representing contributions from the different uranium isotopes and gamma-ray generation mechanisms (e.g. neutron capture). This scheme accommodates fast generation of “virtual assay signatures” for arbitrary enrichment, material age, and fill variations. Ongoing (FY-2011) refinements to the physics model include accounting for generation of bremsstrahlung photons, arising primarily from the beta decay of Pa-234m, a U-238 daughter. We are using the refined model to optimize collimator design for the hybrid method. The traditional assay method benefits from a high degree of collimation (to isolate each detector’s field-of-view) and relatively small detector area, while the non-traditional method benefits from a wide field-of-view, i.e. less collimation and larger detectors. We implement the enrichment-meter method by applying a square-wave digital filter to a raw spectrum and extracting the 186-keV peak area directly from the convolute spectrum. Ongoing enhancements to this approach include mitigating a systematic peak-area measurement deficit arising from curvature in the spectrum continuum shape. An optimized system prototype based on model results is utilized in a new set of 2011 field measurements, and model and measurement enrichment assay uncertainties are compared.

McDonald, Benjamin S.; Jordan, David V.; Orton, Christopher R.; Mace, Emily K.; Smith, Leon E.; Wittman, Richard S.

2011-06-14T23:59:59.000Z

70

DUF6 Storage  

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

of depleted UF6 is stored in steel cylinders at three sites in the U.S. Depleted UF6 Inventory and Storage Locations U.S. DOE's inventory of depleted UF6 consists of approximately...

71

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

Science Conference Proceedings (OSTI)

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

72

Results of Continuous Load Cell Monitoring Field Trial for UF6 Withdrawals at an Operating Industrial Plant  

Science Conference Proceedings (OSTI)

Continuous load cell monitoring (CLCM) has been implemented and tested for use as a safeguards tool during a 2009 field trial in an operating UF6 transfer facility. The transfer facility is part of the Portsmouth Gaseous Diffusion Plant in Piketon, Ohio, operated by the United States Enrichment Corporation. During the field trial, two process scales for UF{sub 6} cylinders were continuously monitored for a 6-month period as cylinders were being filled. The collected CLCM data were used in testing an event processor serving as a filter for highlighting measurements representing significant operational activities that are important in verifying declared operations. The collection of CLCM data, coupled with rules-based event processing, can provide inspectors with knowledge of a facility's feed and withdrawal activities occurring between site visits. Such process knowledge promises to enhance the effectiveness of safeguards by enabling inspectors to quantitatively compare declared activities directly with process measurements. Selected results of the field trial and event processing will be presented in the context of their value to an independent inspector and a facility operator.

Krichinsky, Alan M [ORNL; Bell, Lisa S [ORNL; Conchewski, Curtis A [ORNL; Peters, Benjamin R [ORNL; Pickett, Chris A [ORNL; Richardson, Dave [ORNL; Rowe, Nathan C [ORNL; Younkin, James R [ORNL

2010-01-01T23:59:59.000Z

73

FAQ 7-How is depleted uranium produced?  

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

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

74

Where DUF6 is Stored  

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

DUF6 is Stored Depleted UF6 Storage line line How DUF6 is Stored Where DUF6 is Stored DUF6 Storage Safety Cylinder Leakage Where Depleted UF6 is Stored in the United States The UF6...

75

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

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

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

76

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

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

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

77

DUF6 Storage Safety  

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

Storage Safety Depleted UF6 Storage line line How DUF6 is Stored Where DUF6 is Stored DUF6 Storage Safety Cylinder Leakage Depleted UF6 Storage Safety Continued cylinder storage is...

78

FAQ 21-What happens if a cylinder of uranium hexafluoride leaks...  

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

(breach) occurs and the depleted UF6 is exposed to water vapor in the air, uranyl fluoride (UO2F2) and hydrogen fluoride (HF) are formed. The uranyl fluoride is a solid that...

79

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

80

Ultra-low field NMR for detection and characterization of 235 UF6  

SciTech Connect

We have demonstrated the first ultra-low field (ULF) nuclear magnetic resonance measurements of uranium hexafluoride (UF{sub 6}), both depleted and 70% enriched, which is used in the uranium enrichment process. A sensitive non-invasive detection system would have an important role in non-proliferation surveillance. A two-frequency technique was employed to remove the transients induced by rapidly switching off the 50 mT pre-polarization field. A mean transverse relaxation time T{sub 2} of 24 ms was estimated for the un-enriched UF{sub 6} sample measured at a mean temperature of 80 C. Nuclear magnetic resonance at ULF has several advantages including the ability to measure through metal, such as pipes, and simple magnetic field generation hardware. We present here recent data and discuss the potential for non-proliferation monitoring of enrichment and flow velocity.

Espy, Michelle A [Los Alamos National Laboratory; Magnelind, Per E [Los Alamos National Laboratory; Matlashov, Andrei N [Los Alamos National Laboratory; Urbaitis, Algis V [Los Alamos National Laboratory; Volegov, Petr L [Los Alamos National Laboratory

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.


81

How DUF6 is Stored  

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

cylinder combines with the iron on the inner surfaces to form a surface layer of iron fluoride that inhibits internal corrosion. A new depleted UF6 cylinder Cylinders that exhibit...

82

Storage  

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

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

83

Transportation  

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

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.

84

A Mock UF6 Feed and Withdrawal System for Testing Safeguards Monitoring Systems and Strategies Intended for Nuclear Fuel Enrichment and Processing Plants  

SciTech Connect

This report describes an engineering-scale, mock UF6 feed and withdrawal (F&W) system, its operation, and its intended uses. This system has been assembled to provide a test bed for evaluating and demonstrating new methodologies that can be used in remote, unattended, continuous monitoring of nuclear material process operations. These measures are being investigated to provide independent inspectors improved assurance that operations are being conducted within declared parameters, and to increase the overall effectiveness of safeguarding nuclear material. Testing applicable technologies on a mock F&W system, which uses water as a surrogate for UF6, enables thorough and cost-effective investigation of hardware, software, and operational strategies before their direct installation in an industrial nuclear material processing environment. Electronic scales used for continuous load-cell monitoring also are described as part of the basic mock F&W system description. Continuous monitoring components on the mock F&W system are linked to a data aggregation computer by a local network, which also is depicted. Data collection and storage systems are described only briefly in this report. The mock UF{sub 6} F&W system is economical to operate. It uses a simple process involving only a surge tank between feed tanks and product and withdrawal (or waste) tanks. The system uses water as the transfer fluid, thereby avoiding the use of hazardous UF{sub 6}. The system is not tethered to an operating industrial process involving nuclear materials, thereby allowing scenarios (e.g., material diversion) that cannot be conducted otherwise. These features facilitate conducting experiments that yield meaningful results with a minimum of expenditure and quick turnaround time. Technologies demonstrated on the engineering-scale system lead to field trials (described briefly in this report) for determining implementation issues and performance of the monitoring technologies under plant operating conditions. The ultimate use of technologies tested on the engineering-scale test bed is to work with safeguards agencies to install them in operating plants (e.g., enrichment and fuel processing plants), thereby promoting new safeguards measures with minimal impact to operating plants. In addition, this system is useful in identifying features for new plants that can be incorporated as part of 'safeguards by design,' in which load cells and other monitoring technologies are specified to provide outputs for automated monitoring and inspector evaluation.

Krichinsky, Alan M [ORNL; Bates, Bruce E [ORNL; Chesser, Joel B [ORNL; Koo, Sinsze [ORNL; Whitaker, J Michael [ORNL

2009-12-01T23:59:59.000Z

85

Final DUF6 PEIS: Volume 2: Appendix J; Transportation  

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

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

86

Depleted uranium plasma reduction system study  

Science Conference Proceedings (OSTI)

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

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

1994-12-01T23:59:59.000Z

87

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

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

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

88

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

DOE Green Energy (OSTI)

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

89

Frequently Asked Questions (FAQs)  

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

Frequently Asked Questions (FAQs) Frequently asked questions (FAQs) about uranium, uranium hexafluoride (UF6), UF6 storage and depleted UF6 management. Below is a list of...

90

FAQ 19-Is storage of uranium hexafluoride safe?  

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

storage of uranium hexafluoride safe? Is storage of uranium hexafluoride safe? The advanced age of some of the steel cylinders in which the depleted UF6 is contained, and the way...

91

A more accurate and penetrating method to measure the enrichment and mass of UF6 storage containers using passive neutron self-interrogation  

Science Conference Proceedings (OSTI)

This paper describes an unattended mode neutron measurement that can provide the enrichment of the uranium in UF{sub 6} cylinders. The new passive neutron measurement provides better penetration into the uranium mass than prior gamma-ray enrichment measurement methods. The Passive Neutron Enrichment Monitor (PNEM) provides a new measurement technique that uses passive neutron totals and coincidence counting together with neutron self-interrogation to measure the enrichment in the cylinders. The measurement uses the neutron rates from two detector pods. One of the pods has a bare polyethylene surface next to the cylinder and the other polyethylene surface is covered with Cd to prevent thermal neutrons from returning to the cylinder. The primary neutron source from the enriched UF{sub 6} is the alpha-particle decay from the {sub 234}U that interacts with the fluorine to produce random neutrons. The singles neutron counting rate is dominated by the {sub 234}U neutrons with a minor contribution from the induced fissions in the {sub 235}U. However, the doubles counting rate comes primarily from the induced fissions (i.e., multiplication) in the {sub 235}U in enriched uranium. The PNEM concept makes use of the passive neutrons that are initially produced from the {sub 234}U reactions that track the {sub 235}U enrichment during the enrichment process. The induced fission reactions from the thermal-neutron albedo are all from the {sub 235}U and provide a measurement of the {sub 235}U. The Cd ratio has the desirable feature that all of the thermal-neutron-induced fissions in {sub 235}U are independent of the original neutron source. Thus, the ratio is independent of the uranium age, purity, and prior reactor history.

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

2010-01-01T23:59:59.000Z

92

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

93

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

94

Facilitate Intact Cylinder Reuse  

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

Facilitate Intact Cylinder Reuse Many DU hexafluoride storage cylinders are in relatively good condition and capable of further use as a container. However, even after being...

95

DUF6 Management  

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

Management Depleted UF6 Management An introduction to DOE's Depleted UF6 Management Program. The mission of the DOE's Depleted UF6 Management Program is to safely and efficiently...

96

Conversion of Yellow Cake to UF6  

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

Yellow cake is converted to uranium hexafluoride through a multi-step chemical process using nitric acid, ammonium hydroxide, hydrogen, hydrofluoric acid (HF) and fluorine (F2)....

97

Assessment of UF6 Equation of State  

SciTech Connect

A common assumption in the mathematical analysis of flows of compressible fluids is to treat the fluid as a perfect gas. This is an approximation, as no real fluid obeys the perfect gas relationships over all temperature and pressure conditions. An assessment of the validity of treating the UF{sub 6} gas flow field within a gas centrifuge with perfect gas relationships has been conducted. The definition of a perfect gas is commonly stated in two parts: (1) the gas obeys the thermal equation of state, p = {rho}RT (thermally perfect), and, (2) the gas specific heats are constant (calorically perfect). Analysis indicates the thermally perfect assumption is valid for all flow conditions within the gas centrifuge, including shock fields. The low operating gas pressure is the primary factor in the suitability of the thermally perfect equation of state for gas centrifuge computations. UF{sub 6} is not calorically perfect, as the specific heats vary as a function of temperature. This effect is insignificant within the bulk of the centrifuge gas field, as gas temperatures vary over a narrow range. The exception is in the vicinity of shock fields, where temperature, pressure, and density gradients are large, and the variation of specific heats with temperature should be included in the technically detailed analyses. Results from a normal shock analysis incorporating variable specific heats is included herein, presented in the conventional form of shock parameters as a function of inlet Mach Number. The error introduced by assuming constant specific heats is small for a nominal UF{sub 6} shock field, such that calorically perfect shock relationships can be used for scaling and initial analyses. The more rigorous imperfect gas analysis should be used for detailed analyses.

Brady, P; Chand, K; Warren, D; Vandersall, J

2009-02-11T23:59:59.000Z

98

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

99

Compressed Gas Cylinder Policy  

E-Print Network (OSTI)

, storage, and usage of compressed gas cylinders. 2.0 POLICY Colorado School of Mines ("Mines" or "the, storage, and usage requirements outlined below. This policy is applicable school-wide including all, or electrical circuits. Flammable gas cylinders must be stored in the building's gas cylinder storage cage until

100

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).

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

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

102

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

103

Fiber Tracking Cylinder Nesting  

SciTech Connect

The fiber tracker consists of 8 concentric carbon fiber cylinders of varying diameters, from 399mm to 1032.2mm and two different lengths. 1.66 and 2.52 meters. Each completed cylinder is covered over the entire o.d. with scintillating fiber ribbons with a connector on each ribbon. These ribbons are axial (parallel to the beam line) at one end and stereo (at 3 deg. to the beam line) at the other. The ribbon connectors have dowel pins which are used to match with the connectors on the wave guide ribbons. These dowel pins are also used during the nesting operation, locating and positioning measurements. The nesting operation is the insertion of one cylinder into another, aligning them with one another and fastening them together into a homogeneous assembly. For ease of assembly. the nesting operation is accomplished working from largest diameter to smallest. Although the completed assembly of all 8 cylinders glued and bolted together is very stiff. individual cylinders are relatively flexible. Therefore. during this operation, No.8 must be supported in a manner which maintains its integrity and yet allows the insertion of No.7. This is accomplished by essentially building a set of dummy end plates which replicate a No.9 cylinder. These end plates are mounted on a wheeled cart that becomes the nesting cart. Provisions for a protective cover fastened to these rings has been made and will be incorporated in finished product. These covers can be easily removed for access to No.8 and/or the connection of No.8 to No.9. Another wheeled cart, transfer cart, is used to push a completed cylinder into the cylinder(s) already mounted in the nesting cart.

Stredde, H.; /Fermilab

1999-03-30T23:59:59.000Z

104

Prediction of External Corrosion for Steel Cylinders--2004 Report  

Science Conference Proceedings (OSTI)

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

105

Prediction of External Corrosion for Steel Cylinders--2007 Report  

Science Conference Proceedings (OSTI)

Depleted uranium hexafluoride (DUF{sub 6}) is stored in over 62,000 containment cylinders at the Paducah Gaseous Diffusion Plant (PGDP) in Paducah, Kentucky, and at the Portsmouth Gaseous Diffusion Plant (PORTS) in Portsmouth, Ohio. Over 4,800 of the cylinders at Portsmouth were recently moved there from the East Tennessee Technology Park (ETTP) in Oak Ridge, Tennessee. The cylinders range in age up to 56 years and come in various models, but most are 48-inch diameter 'thin-wall'(312.5 mil) and 'thick-wall' (625 mil) cylinders and 30-inch diameter '30A' (including '30B') cylinders with 1/2-inch (500 mil) walls. Most of the cylinders are carbon steel, and they are subject to corrosion. The United States Department of Energy (DOE) manages the cylinders to maintain them and the DUF{sub 6} they contain. Cylinder management requirements are specified in the System Requirements Document (LMES 1997a), and the activities to fulfill them are specified in the System Engineering Management Plan (LMES 1997b). This report documents activities that address DUF{sub 6} cylinder management requirements involving measuring and forecasting cylinder wall thicknesses. As part of these activities, ultrasonic thickness (UT) measurements are made on samples of cylinders. For each sampled cylinder, multiple measurements are made in an attempt to find, approximately, the minimum wall thickness. Some cylinders have a skirt, which is an extension of the cylinder wall to protect the head (end) and valve. The head/skirt interface crevice is thought to be particularly vulnerable to corrosion, and for some skirted cylinders, in addition to the main body UT measurements, a separate suite of measurements is also made at the head/skirt interface. The main-body and head/skirt minimum thickness data are used to fit models relating minimum thickness to cylinder age, nominal thicknesses, and cylinder functional groups defined in terms of plant site, storage yard, top or bottom row storage positions, etc. These models are then used to compute projections of numbers of cylinders expected to fail various minimum wall thickness criteria. The minimum wall thickness criteria are as follows. For thin-wall cylinders: 0 (breach), 62.5, and 250 mils. For thick-wall cylinders: 0, 62.5, and 500 mils. For 30A cylinders: 0, 62.5, and 100 mils. Each of these criteria triplets are based respectively on (1) loss of DUF{sub 6} (breaching), (2) safe handling and stacking operations, and (3) ANSI N14.1 standards for off-site transport and contents transfer. This report complements and extends previous editions of the cylinder corrosion report by Lyon (1995, 1996, 1997, 1998, 2000), by Schmoyer and Lyon (2001, 2002, 2003), and by Schmoyer (2004). These reports are based on UT data collected in FY03 and before. In this report UT data collected after FY03 but before FY07 is combined with the earlier data, and all of the UT data is inventoried chronologically and by the various functional groups. The UT data is then used to fit models of maximum pit depth and minimum wall thickness, statistical outliers are investigated, and the fitted models are used to extrapolate minimum thickness estimates into the future and in turn to compute projections of numbers of cylinders expected to fail various thickness criteria. A model evaluation is performed comparing UT measurements made after FY05 with model-fitted projections based only on data collected in FY05 and before. As in previous reports, the projections depend on the treatment of outliers.

Schmoyer, Richard L [ORNL

2008-01-01T23:59:59.000Z

106

The uranium cylinder assay system for enrichment plant safeguards  

Science Conference Proceedings (OSTI)

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

107

Depleted Uranium Hexafluoride Management  

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

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

108

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

109

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

110

Depleted uranium: A DOE management guide  

Science Conference Proceedings (OSTI)

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

NONE

1995-10-01T23:59:59.000Z

111

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

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

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

112

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

113

Corrosion of breached UF[sub 6] storage cylinders  

Science Conference Proceedings (OSTI)

This paper describes the corrosion processes that occurred following the mechanical failure of two steel 14-ton storage cylinders containing depleted UF[sub 6]. The failures both were traced to small mechanical tears that occurred during stacking of the cylinders. Although subsequent corrosion processes greatly extended the openings in the wall. the reaction products formed were quite protective and prevented any significant environmental insult or loss of uranium. The relative sizes of the two holes correlated with the relative exposure times that had elapsed from the time of stacking. From the sizes and geometries of the two holes, together with analyses of the reaction products, it was possible to determine the chemical reactions that controlled the corrosion process and to develop a scenario for predicting the rate of hydrolysis of UF[sub 6], the loss rate of HF, and chemical attack of a breached UF[sub 6] storage cylinder.

Barber, E.J.; Taylor, M.S.; DeVan, J.H.

1993-01-01T23:59:59.000Z

114

Corrosion of breached UF{sub 6} storage cylinders  

Science Conference Proceedings (OSTI)

This paper describes the corrosion processes that occurred following the mechanical failure of two steel 14-ton storage cylinders containing depleted UF{sub 6}. The failures both were traced to small mechanical tears that occurred during stacking of the cylinders. Although subsequent corrosion processes greatly extended the openings in the wall. the reaction products formed were quite protective and prevented any significant environmental insult or loss of uranium. The relative sizes of the two holes correlated with the relative exposure times that had elapsed from the time of stacking. From the sizes and geometries of the two holes, together with analyses of the reaction products, it was possible to determine the chemical reactions that controlled the corrosion process and to develop a scenario for predicting the rate of hydrolysis of UF{sub 6}, the loss rate of HF, and chemical attack of a breached UF{sub 6} storage cylinder.

Barber, E.J.; Taylor, M.S.; DeVan, J.H.

1993-02-01T23:59:59.000Z

115

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

116

Prediction of external corrosion for steel storage cylinders  

Science Conference Proceedings (OSTI)

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

117

Prediction of External Corrosion for Steel Cylinders 2003 Report  

Science Conference Proceedings (OSTI)

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 six to 52 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. The requirements of the Project are delineated in the System Requirements Document (LMES 1997a), and the actions needed to fulfill those requirements are specified in the System Engineering Management Plan (LMES 1997b). This report documents activities that address requirements and actions involving forecasting cylinder wall thicknesses. Wall thickness forecasts are based on models fit to ultrasonic thickness (UT) measurement data. First, UT data collected during FY02 is combined with UT data collected in earlier years (FY92-FY01), and all of the data is inventoried chronologically and by various subpopulations. Next, the data is used to model either maximum pit depth or minimum thickness as a function of cylinder age, subpopulation (e.g., PGDP G-yard, bottom-row cylinders), and initial thickness estimates. The fitted models are then used to extrapolate minimum thickness estimates into the future and to compute estimates of numbers of cylinders expected to fail various thickness criteria. A model evaluation is performed comparing UT measurements made in FY02 with model-fitted projections based only on data collected before FY02. The FY02 UT data, entered into the corrosion model database and not available for the previous edition of this report (Schmoyer and Lyon 2002), consists of thickness measurements of 48'' thin-wall cylinders: 102 cylinders at Paducah, 104 at ETTP, and 117 at Portsmouth; and 72 thick-wall cylinders at Portsmouth. However, because of missing values, repeated measures on the same cylinders, outliers, and other data problems, not all of these measurements are necessarily used in the corrosion analysis, and some previous measurements may simply be replaced with the new ones. In this edition of the report, cylinder subpopulation definitions and counts are updated using the latest (as of June 2003) information from the Cylinder Inventory Database (CID). Cylinders identified in the CID as painted during the last ten years are excluded from subpopulations considered at-risk of failing minimum thickness criteria, because it is assumed that painting fully arrests corrosion for ten years. As in the previous edition of the report, two different approaches to corrosion modeling are pursued: (1) a direct approach in which minimum thickness is modeled directly as a function of age, subpopulation, and initial thickness estimates; and (2) an indirect approach, in which maximum pit depth is modeled, and the pit-depth model is then combined with a model of initial thickness to compute estimates of minimum thickness.

Schmoyer, RLS

2003-09-24T23:59:59.000Z

118

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

119

Gas Cylinder Lifting at the NCNR  

Science Conference Proceedings (OSTI)

... Gas Cylinder Lifting at the NCNR. ... We have recently made a gas cylinder lifting cage so that this transfer can be done in a safe manner. ...

120

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

Science Conference Proceedings (OSTI)

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

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

License Application Chapter 5 Nuclear Criticality Safety  

E-Print Network (OSTI)

uranium or other fissile material outside of check-sources and various standards for radiological measurement calibration. As such, no criticality safety programs or procedures are maintained or implemented at the facility; however, the IIFP Integrated Safety Analysis (ISA), as documented in the ISA Summary, did evaluate the potential for a criticality accident at the IIFP Site. The only potential method of having a criticality accident at the facility involves the inadvertent receipt and processing of fissile materials, which is addressed in the ISA. Controls are established to verify that no enriched uranium hexafluoride (UF6) is received and processed at the facility. The cylinders processed at the IIFP Facility are the large, 14-ton or 10-ton UF6 tails cylinders, not the 2 -ton enriched product cylinders. Processing equipment at the plant, namely the autoclaves, is not sized to handle these smaller cylinders, so there is no method to feed enriched material into the processing plants. Additionally, each cylinder will be scanned with a detector to verify that the incoming cylinders do not contain fissile materials. The scan does not determine the shipper’s assay exactness for the cylinder contents, but does provide a reasonable indication if the cylinder is depleted or enriched. Both the receipt inspection and the scan for the assay at the Facility Site are maintained as Items Relied on for Safety (IROFS) controls. Also, feed suppliers (UF6 enrichment plants) have redundant and

Uranium De-conversion; Revision B

2011-01-01T23:59:59.000Z

122

Photon compression in cylinders  

DOE Green Energy (OSTI)

It has been shown theoretically that intense microwave radiation is absorbed non-classically by a newly enunciated mechanism when interacting with hydrogen plasma. Fields > 1 Mg, lambda > 1 mm are within this regime. The predicted absorption, approximately P/sub rf/v/sub theta/sup e/, has not yet been experimentally confirmed. The applications of such a coupling are many. If microwave bursts approximately > 5 x 10/sup 14/ watts, 5 ns can be generated, the net generation of power from pellet fusion as well as various military applications becomes feasible. The purpose, then, for considering gas-gun photon compression is to obtain the above experimental capability by converting the gas kinetic energy directly into microwave form. Energies of >10/sup 5/ joules cm/sup -2/ and powers of >10/sup 13/ watts cm/sup -2/ are potentially available for photon interaction experiments using presently available technology. The following topics are discussed: microwave modes in a finite cylinder, injection, compression, switchout operation, and system performance parameter scaling.

Ensley, D.L.

1977-01-12T23:59:59.000Z

123

FAQ 29-What are the risks from accidents involving depleted uranium...  

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

The most immediate hazard after a release would be from inhalation of hydrogen fluoride (HF), a highly corrosive gas formed when UF6 reacts with moisture in air. Exposure to...

124

Battery depletion monitor  

SciTech Connect

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

Lee, Y.S.

1982-01-26T23:59:59.000Z

125

Depleted uranium valuation  

SciTech Connect

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

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

1979-04-01T23:59:59.000Z

126

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

127

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

Science Conference Proceedings (OSTI)

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

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

1995-12-01T23:59:59.000Z

128

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.

129

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

130

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

131

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.

132

Documents: Engineering Studies  

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

of Depleted UF6 99 KB details HTML Icon Preconceptual Design Studies and Cost Data of Depleted Uranium Hexafluoride Conversion Plants 4 KB details Engineering Analysis Report...

133

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

134

Production and Handling Slide 41: Cylinder Handler  

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

Handler Skip Presentation Navigation First Slide Previous Slide Next Slide Last Presentation Table of Contents Cylinder Handler Refer to caption below for image description...

135

Lubricated Reciprocating Frictional Properties of Marine Cylinder ...  

Science Conference Proceedings (OSTI)

... Process Design of the Ductile Cast Iron Cylinder Head for Marine Diesel Engine ... Heavy Section Ductile Iron Castings for Use in Wind Turbine Generators.

136

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

Science Conference Proceedings (OSTI)

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

137

Prediction of external corrosion for steel cylinders at the Paducah Gaseous Diffusion Plant: Application of an empirical method  

Science Conference Proceedings (OSTI)

During the summer of 1995, ultrasonic wall thickness data were collected for 100 steel cylinders containing depleted uranium (DU) hexafluoride located at Paducah Gaseous Diffusion Plant (PGDP) in Paducah, Kentucky. The cylinders were selected for measurement to assess the condition of the more vulnerable portion of the cylinder inventory at PGDP. The purpose of this report is to apply the method used in Lyon to estimate the effects of corrosion for larger unsampled populations as a function of time. The scope of this report is limited and is not intended to represent the final analyses of available data. Future efforts will include continuing analyses of available data to investigate defensible deviations from the conservative assumptions made to date. For each cylinder population considered, two basic types of analyses were conducted: (1) estimates were made of the number of cylinders as a function of time that will have a minimum wall thickness of either 0 mils (1 mil = 0.00 1 in.) or 250 mils and (2) the current minimum wall thickness distributions across cylinders were estimated for each cylinder population considered. Additional analyses were also performed investigating comparisons of the results for F and G yards with the results presented in Lyon (1995).

Lyon, B.F.

1996-02-01T23:59:59.000Z

138

Documents: Transportation  

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

Search Documents: Search PDF Documents View a list of all documents Transportation PDF Icon Transportation Impact Assessment for Shipment of Uranium Hexafluoride (UF6) Cylinders...

139

Production and Handling Slide 36: Full Cylinder in Autoclave...  

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

Cylinder in Autoclave Prior to Feeding Skip Presentation Navigation First Slide Previous Slide Next Slide Last Presentation Table of Contents Full Cylinder in Autoclave Prior to...

140

Production and Handling Slide 39: Weighing the Cylinder  

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

Weighing the Cylinder Skip Presentation Navigation First Slide Previous Slide Next Slide Last Presentation Table of Contents Weighing the Cylinder Refer to caption below for image...

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

Stability of Anisotropic Cylinder with Zero Expansion  

E-Print Network (OSTI)

We study the dynamical instability of anisotropic collapsing cylinder with the expansion-free condition, which generates vacuum cavity within fluid distribution. The perturbation scheme is applied to distinguish Newtonian, post-Newtonian and post-post Newtonian terms, which are used for constructing dynamical equation at Newtonian and post-Newtonian regimes. We analyze the role of pressure anisotropy and energy density inhomogeneity on the stability of collapsing cylinder. It turns out that stability of the cylinder depends upon these physical properties of the fluid, not on the stiffness of the fluid.

M. Sharif; M. Azam

2013-05-24T23:59:59.000Z

142

Stability of Anisotropic Cylinder with Zero Expansion  

E-Print Network (OSTI)

We study the dynamical instability of anisotropic collapsing cylinder with the expansion-free condition, which generates vacuum cavity within fluid distribution. The perturbation scheme is applied to distinguish Newtonian, post-Newtonian and post-post Newtonian terms, which are used for constructing dynamical equation at Newtonian and post-Newtonian regimes. We analyze the role of pressure anisotropy and energy density inhomogeneity on the stability of collapsing cylinder. It turns out that stability of the cylinder depends upon these physical properties of the fluid, not on the stiffness of the fluid.

Sharif, M

2013-01-01T23:59:59.000Z

143

Depleted Uranium (DU) Dioxide Fill  

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

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

144

FAQ 6-What is depleted uranium?  

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

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

145

Casimir forces between cylinders at different temperatures  

E-Print Network (OSTI)

We study Casimir interactions between cylinders in thermal nonequilibrium, where the objects as well as the environment are held at different temperatures. We provide the general formula for the force, in a one reflection ...

Golyk, Vladyslav A.

146

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

147

Pennsylvania Natural Gas Underground Storage Depleted Fields...  

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

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

148

Electromagnetic Casimir Forces in Elliptic Cylinder Geometries  

E-Print Network (OSTI)

The scattering theory approach makes it possible to carry out exact calculations of Casimir energies in any geometry for which the scattering T-matrix and a partial wave expansion of the free Green's function are available. We implement this program for the case of a perfectly conducting elliptic cylinder, thereby completing the set of geometries where electromagnetic scattering is separable. Particular emphasis is placed on the case of zero radius, where the elliptic cylinder reduces to a strip.

Noah Graham

2013-03-26T23:59:59.000Z

149

FAQ 26-Are there any uses for depleted uranium?  

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

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

150

Depleted Uranium Hexafluoride Management Program: Data Compilation...  

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

Impacts Associated with Continued Storage of the Entire Portsmouth Site Cylinder Inventory . . . . . . . . . . . . . . . . . . . . . . . . . . . 3-51 3.5.1 Approach Used to...

151

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

152

For More Information  

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

For More Information For More Information about the Conversion EIS Who to contact for more information about the Depleted UF6 Conversion EISs Please direct questions, comments, or...

153

DUF6 Draft EIS Public Hearing Transcripts  

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

Depleted UF6 Draft EIS Public Hearing Transcripts Transcripts from the DUF6 Conversion Draft EIS Public Hearings The following transcripts are from the DUF6 Conversion...

154

Historical Context  

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

Context Historical Context for the Conversion EISs Important events and decisions that led to development of the depleted UF6 Conversion EISs. 1992: Concerns Raised by Ohio...

155

About Us  

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

About Us About Us Argonne National Laboratory administers this web site for The U.S. DOE Office of Environmental Management. Responsibilities The Depleted UF6 Management Program...

156

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

Science Conference Proceedings (OSTI)

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

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

1995-12-31T23:59:59.000Z

157

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. _________________________

158

Including environmental concerns in management strategies for depleted uranium hexafluoride  

Science Conference Proceedings (OSTI)

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

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

1995-12-31T23:59:59.000Z

159

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

160

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

E-Print Network (OSTI)

of these gases can cause a cylinder to become a missile-like projectile, destroying everything in its path (empty or full) in storage should be separated from fuel-gas cylinders and combustible materials

Suzuki, Masatsugu

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

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

162

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

163

Intergalactic Filaments as Isothermal Gas Cylinders  

E-Print Network (OSTI)

Using a cosmological simulation at redshift 5, we find that the baryon-rich cores of intergalactic filaments radiating from galaxies commonly form isothermal gas cylinders. The central gas density is typically about 500 times the cosmic mean total density, and the temperature is typically 1-2 times 10^4 K, just above the Lyman alpha cooling floor. These findings argue that the hydrodynamic properties of the gas are more important than the dark matter in determining the structure. Filaments form a major pipeline for the transport of gas into the centers of galaxies. Since the temperature and ionization state of the gas completely determine the mass per unit length of an isothermal gas cylinder, our findings suggest a constraint upon gas transport into galaxies by this mechanism.

Harford, A Gayler

2010-01-01T23:59:59.000Z

164

DDES and IDDES of tandem cylinders.  

Science Conference Proceedings (OSTI)

The paper presents an overview of the authors contribution to the BANC-I Workshop on the flow past tandem cylinders (Category 2). It includes an outline of the simulation approaches, numerics, and grid used, the major results of the simulations, their comparison with available experimental data, and some preliminary conclusions. The effect of varying the spanwise period in the simulations is strong for some quantities, and not others.

Balakrishnan, R.; Garbaruk, A.; Shur, M.; Strelets, M.; Spalart, P.; New Technologies and Services - Russia; St.-Peterburg State Polytechnic Univ.; Boeing Commercial Airplanes

2010-09-09T23:59:59.000Z

165

Depleted uranium disposal options evaluation  

SciTech Connect

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

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

1994-05-01T23:59:59.000Z

166

Depleted Argon from Underground Sources  

Science Conference Proceedings (OSTI)

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

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

2011-04-27T23:59:59.000Z

167

High-voltage-compatible, fully depleted CCDs  

SciTech Connect

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

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

2006-05-15T23:59:59.000Z

168

From the lab to the real world : sources of error in UF6 gas enrichment monitoring.  

E-Print Network (OSTI)

??Safeguarding uranium enrichment facilities is a serious concern for the International Atomic Energy Agency (IAEA). Safeguards methods have changed over the years, most recently switching… (more)

Lombardi, Marcie

2012-01-01T23:59:59.000Z

169

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

Science Conference Proceedings (OSTI)

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

170

Evaluation of UF6 to UO2 Conversion Capability at Commercial...  

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

. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 17 2.2.7 Korea . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ....

171

,"Natural Gas Depleted Fields Storage Capacity "  

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

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

172

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:

173

WELDING THIN-WALLED URANIUM CYLINDERS  

SciTech Connect

One of Its Monograph Series, The Industrial Atom.'' The development of a satisfactory process for the fusion welding of thin-walled uranium cylinders is discussed. Optimum results were obtained using the inert-gas shielded-arc method without the use of filler metal. The ductility of the welded joints, however, was lower than that of cast metal. Surface conditions and and the purity of the inert gas used affected the weld soundness. Straight polarity direct current was used for welding to achieve maximum penetration and to provide are stability. Welding must be done in the flat position. (auth)

Brundige, E.L.; Taub, J.M.; Hanks, G.S.; Doll, D.T.

1957-01-01T23:59:59.000Z

174

Radial Segregation of Granular Materials in Rotating Cylinders  

Science Conference Proceedings (OSTI)

... tablet manufacturing to cement production to rock cutting transportation with drilling fluids. Rotating cylinders are used as kilns, mixers, dryers and granulators .

175

Depleted Uranium De-conversion  

E-Print Network (OSTI)

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

Fluorine Extraction Process

2009-01-01T23:59:59.000Z

176

Depleted argon from underground sources  

Science Conference Proceedings (OSTI)

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

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

2011-09-01T23:59:59.000Z

177

THE RIMINI PROTOCOL Oil Depletion Protocol  

E-Print Network (OSTI)

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

Keeling, Stephen L.

178

CYLINDER LENS ALIGNMENT IN THE LTP  

SciTech Connect

The Long Trace Profiler (LTP), is well-suited for the measurement of the axial figure of cylindrical mirrors that usually have a long radius of curvature in the axial direction but have a short radius of curvature in the sagittal direction. The sagittal curvature causes the probe beam to diverge in the transverse direction without coming to a focus on the detector, resulting in a very weak signal. It is useful to place a cylinder lens into the optical system above the mirror under test to refocus the sagittal divergence and increase the signal level. A positive cylinder lens can be placed at two positions above the surface: the Cat's Eye reflection position and the Wavefront-Matching position. The Cat's Eye position, is very tolerant to mirror misalignment, which is not good if absolute axial radius of curvature is to be measured. Lateral positioning and rotational misalignments of lens and the mirror combine to produce unusual profile results. This paper looks at various alignment issues with measurements and by raytrace simulations to determine the best strategy to minimize radius of curvature errors in the measurement of cylindrical aspheres.

TAKACS, P.Z.

2005-07-26T23:59:59.000Z

179

Reconstruction of mechanically recorded sound from an edison cylinder using three dimensional non-contact optical surface metrology  

E-Print Network (OSTI)

Recorded Sound from an Edison Cylinder using Threeet al. , “ Optomechanical method of Edison cylinders soundComments on Historical Edison Cylinder Styli ”, Association

Fadeyev, V.; Haber, C.; Maul, C.; McBride, J.W.; Golden, M.

2004-01-01T23:59:59.000Z

180

NGSI: FUNCTION REQUIREMENTS FOR A CYLINDER TRACKING SYSTEM  

SciTech Connect

While nuclear suppliers currently track uranium hexafluoride (UF{sub 6}) cylinders in various ways, for their own purposes, industry practices vary significantly. The NNSA Office of Nonproliferation and International Security's Next Generation Safeguards Initiative (NGSI) has begun a 5-year program to investigate the concept of a global monitoring scheme that uniquely identifies and tracks UF{sub 6} cylinders. As part of this effort, NGSI's multi-laboratory team has documented the 'life of a UF{sub 6} cylinder' and reviewed IAEA practices related to UF{sub 6} cylinders. Based on this foundation, this paper examines the functional requirements of a system that would uniquely identify and track UF{sub 6} cylinders. There are many considerations for establishing a potential tracking system. Some of these factors include the environmental conditions a cylinder may be expected to be exposed to, where cylinders may be particularly vulnerable to diversion, how such a system may be integrated into the existing flow of commerce, how proprietary data generated in the process may be protected, what a system may require in terms of the existing standard for UF{sub 6} cylinder manufacture or modifications to it and what the limiting technology factors may be. It is desirable that a tracking system should provide benefit to industry while imposing as few additional constraints as possible and still meeting IAEA safeguards objectives. This paper includes recommendations for this system and the analysis that generated them.

Branney, S.

2012-06-06T23:59:59.000Z

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.


181

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

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

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

182

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

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

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

183

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

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

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

184

California Working Natural Gas Underground Storage Depleted Fields...  

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

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

185

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

Annual Energy Outlook 2012 (EIA)

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

186

Maryland Natural Gas Underground Storage Depleted Fields Capacity...  

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

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

187

Tennessee Natural Gas Underground Storage Depleted Fields Capacity...  

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

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

188

Nebraska Natural Gas Underground Storage Depleted Fields Capacity...  

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

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

189

Arkansas Natural Gas Underground Storage Depleted Fields Capacity...  

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

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

190

Colorado Natural Gas Underground Storage Depleted Fields Capacity...  

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

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

191

Oklahoma Natural Gas Underground Storage Depleted Fields Capacity...  

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

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

192

Oregon Natural Gas Underground Storage Depleted Fields Capacity...  

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

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

193

Ohio Natural Gas Underground Storage Depleted Fields Capacity...  

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

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

194

Montana Natural Gas Underground Storage Depleted Fields Capacity...  

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

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

195

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

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

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

196

Static fluid cylinders and their fields: global solutions  

E-Print Network (OSTI)

The global properties of static perfect-fluid cylinders and their external Levi-Civita fields are studied both analytically and numerically. The existence and uniqueness of global solutions is demonstrated for a fairly general equation of state of the fluid. In the case of a fluid admitting a non-vanishing density for zero pressure, it is shown that the cylinder's radius has to be finite. For incompressible fluid, the field equations are solved analytically for nearly Newtonian cylinders and numerically in fully relativistic situations. Various physical quantities such as proper and circumferential radii, external conicity parameter and masses per unit proper/coordinate length are exhibited graphically.

J. Bicak; T. Ledvinka; B. G. Schmidt; M. Zofka

2004-03-02T23:59:59.000Z

197

Speed control with end cushion for high speed air cylinder  

DOE Patents (OSTI)

A high speed air cylinder in which the longitudinal movement of the piston within the air cylinder tube is controlled by pressurizing the air cylinder tube on the accelerating side of the piston and releasing pressure at a controlled rate on the decelerating side of the piston. The invention also includes a method for determining the pressure required on both the accelerating and decelerating sides of the piston to move the piston with a given load through a predetermined distance at the desired velocity, bringing the piston to rest safely without piston bounce at the end of its complete stroke. 4 figs.

Stevens, W.W.; Solbrig, C.W.

1989-06-20T23:59:59.000Z

198

EGR Distribution in Engine Cylinders Using Advanced Virtual Simulation  

DOE Green Energy (OSTI)

Exhaust Gas Recirculation (EGR) is a well-known technology for reduction of NOx in diesel engines. With the demand for extremely low engine out NOx emissions, it is important to have a consistently balanced EGR flow to individual engine cylinders. Otherwise, the variation in the cylinders' NOx contribution to the overall engine emissions will produce unacceptable variability. This presentation will demonstrate the effective use of advanced virtual simulation in the development of a balanced EGR distribution in engine cylinders. An initial design is analyzed reflecting the variance in the EGR distribution, quantitatively and visually. Iterative virtual lab tests result in an optimized system.

Fan, Xuetong

2000-08-20T23:59:59.000Z

199

Axial Compression of a Hollow Cylinder Filled with a Foam  

Science Conference Proceedings (OSTI)

Presentation Title, Axial Compression of a Hollow Cylinder Filled with a Foam: A Porcupine ... Characterization of (Ti,Mg)N Thin Film Coatings Produced Via Physical Vapor Deposition ... Non-Toxic SPD Processed Ti Alloys for Orthopaedics.

200

By-products from DU Storage (Fluorine and Empty Cylinders)  

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

By-products from DU Storage By-products from DU Storage (Fluorine and Empty Cylinders) Potential applications involving by-products from DUF6 storage include fluorine applications...

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

The Time-dependent Collapse of a Rotating Fluid Cylinder  

Science Conference Proceedings (OSTI)

The behavior of a reduced-gravity cylinder of fluid, released from rest in a rotating system, is considered. The eventual steady state, found by normal principles of conservation of angular momentum, mass, and potential vorticity, is shown to ...

Peter D. Killworth

1992-04-01T23:59:59.000Z

202

The New MCNP6 Depletion Capability  

SciTech Connect

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

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

2012-06-19T23:59:59.000Z

203

Criticality concerns in cleaning large uranium hexafluoride cylinders  

SciTech Connect

Cleaning large cylinders used to transport low-enriched uranium hexafluoride (UF{sub 6}) presents several challenges to nuclear criticality safety. This paper presents a brief overview of the cleaning process, the criticality controls typically employed and their bases. Potential shortfalls in implementing these controls are highlighted, and a simple example to illustrate the difficulties in complying with the Double Contingency Principle is discussed. Finally, a summary of recommended criticality controls for large cylinder cleaning operations is presented.

Sheaffer, M.K.; Keeton, S.C.; Lutz, H.F.

1995-06-01T23:59:59.000Z

204

Method of making superconducting cylinders for flux detectors  

DOE Patents (OSTI)

A method of making superconducting cylinders of the ''weak link'' type is provided. The method allows the weak link to be made much smaller than was heretofore possible, thereby greatly increasing sensitivity and operating temperature range when the cylinder is used in a flux detector. The resistance of the weak link is monitored continuously as metal is removed from the link by electrochemical action.

Goodkind, J.M.; Stolfa, D.L.

1971-07-06T23:59:59.000Z

205

Inspection of compressed natural gas cylinders on school buses  

DOE Green Energy (OSTI)

The US Department of Energy (DOE) is sponsoring compressed natural gas (CNF)-powered school bus demonstrations in various locations around the country. Early in 1994, two non-DOE-sponsored CNG pickup trucks equipped with composite-reinforced-aluminum fuel cylinders experienced cylinder ruptures during refueling. As reported by the Gas Research Institute (GRI): ...analysis of the cylinder ruptures on the pickup trucks revealed that they were due to acid-induced stress corrosion cracking (SCC) of the overwrap. The overwrap that GRI refers to is a resin-impregnated fiber that is wrapped around the outside of the gas cylinder for added strength. Because ensuring the safety of the CNG vehicles it sponsors is of paramount concern to DOE, the Department, through the National Renewable Energy Laboratory (NREL), conducted inspections of DOE-sponsored vehicles nationwide. The work had three objectives: inspection, documentation, and education. First, inspectors visited sites where CNG-powered school buses sponsored by DOE are based, and inspected the CNG cylinders for damage. Second, information learned during the inspections was collected for DOE. Third, the inspections found that the education and awareness of site personnel, in terms of cylinder damage detection, needed to be increased.

NONE

1995-07-01T23:59:59.000Z

206

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:

207

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

208

FAQ 13-How is uranium hexafluoride stored?  

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

atmospheric pressure in the top. The UF6 inside the cylinder combines with the iron on the inner surfaces to form a surface layer of iron fluoride that inhibits internal corrosion...

209

Sorption of Np and Tc in Underground Waters by Uranium Oxides  

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

worldwide. As a rule DUF 6 is stored in steel cylinders near power stations 1,2 in Russia, and at uranium en- richment plants in the U.S. It is desirable to convert the UF 6 to...

210

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

Science Conference Proceedings (OSTI)

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

211

In-Cylinder Fuel Blending of Gasoline/Diesel for Improved Efficiency and Lowest Possible Emissions on a Multi-Cylinder Light-Duty Diesel Engine  

DOE Green Energy (OSTI)

In-cylinder fuel blending of gasoline/diesel fuel is investigated on a multi-cylinder light-duty diesel engine as a potential strategy to control in-cylinder fuel reactivity for improved efficiency and lowest possible emissions. This approach was developed and demonstrated at the University of Wisconsin through modeling and single-cylinder engine experiments. The objective of this study is to better understand the potential and challenges of this method on a multi-cylinder engine. More specifically, the effect of cylinder-to-cylinder imbalances, heat rejection, and in-cylinder charge motion as well as the potential limitations imposed by real-world turbo-machinery were investigated on a 1.9-liter four-cylinder engine. This investigation focused on one engine condition, 2300 rpm, 4.2 bar brake mean effective pressure (BMEP). Gasoline was introduced with a port-fuel-injection system. Parameter sweeps included gasoline-to-diesel fuel ratio, intake air mixture temperature, in-cylinder swirl number, and diesel start-of-injection phasing. In addition, engine parameters were trimmed for each cylinder to balance the combustion process for maximum efficiency and lowest emissions. An important observation was the strong influence of intake charge temperature on cylinder pressure rise rate. Experiments were able to show increased thermal efficiency along with dramatic decreases in oxides of nitrogen (NOX) and particulate matter (PM). However, indicated thermal efficiency for the multi-cylinder experiments were less than expected based on modeling and single-cylinder results. The lower indicated thermal efficiency is believed to be due increased heat transfer as compared to the model predictions and suggest a need for improved cylinder-to-cylinder control and increased heat transfer control.

Curran, Scott [ORNL; Prikhodko, Vitaly Y [ORNL; Wagner, Robert M [ORNL; Parks, II, James E [ORNL; Cho, Kukwon [ORNL; Sluder, Scott [ORNL; Kokjohn, Sage [University of Wisconsin, Madison; Reitz, Rolf [University of Wisconsin

2010-01-01T23:59:59.000Z

212

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.

213

Electromagnetic Casimir Forces of Parabolic Cylinder and Knife-Edge Geometries  

E-Print Network (OSTI)

An exact calculation of electromagnetic scattering from a perfectly conducting parabolic cylinder is employed to compute Casimir forces in several configurations. These include interactions between a parabolic cylinder and a plane, two parabolic cylinders, and a parabolic cylinder and an ordinary cylinder. To elucidate the effect of boundaries, special attention is focused on the "knife-edge" limit in which the parabolic cylinder becomes a half-plane. Geometrical effects are illustrated by considering arbitrary rotations of a parabolic cylinder around its focal axis, and arbitrary translations perpendicular to this axis. A quite different geometrical arrangement is explored for the case of an ordinary cylinder placed in the interior of a parabolic cylinder. All of these results extend simply to nonzero temperatures.

Noah Graham; Alexander Shpunt; Thorsten Emig; Sahand Jamal Rahi; Robert L. Jaffe; Mehran Kardar

2011-03-30T23:59:59.000Z

214

Electromagnetic Casimir forces of parabolic cylinder and knife-edge geometries  

SciTech Connect

An exact calculation of electromagnetic scattering from a perfectly conducting parabolic cylinder is employed to compute Casimir forces in several configurations. These include interactions between a parabolic cylinder and a plane, two parabolic cylinders, and a parabolic cylinder and an ordinary cylinder. To elucidate the effect of boundaries, special attention is focused on the 'knife-edge' limit in which the parabolic cylinder becomes a half-plane. Geometrical effects are illustrated by considering arbitrary rotations of a parabolic cylinder around its focal axis, and arbitrary translations perpendicular to this axis. A quite different geometrical arrangement is explored for the case of an ordinary cylinder placed in the interior of a parabolic cylinder. All of these results extend simply to nonzero temperatures.

Graham, Noah [Department of Physics, Middlebury College, Middlebury, Vermont 05753 (United States); Shpunt, Alexander; Kardar, Mehran [Department of Physics, Massachusetts Institute of Technology, Cambridge, Massachusetts 02139 (United States); Emig, Thorsten [Laboratoire de Physique Theorique et Modeles Statistiques, CNRS UMR 8626, Bat. 100, Universite Paris-Sud, 91405 Orsay cedex (France); Rahi, Sahand Jamal [Department of Physics, Massachusetts Institute of Technology, Cambridge, Massachusetts 02139 (United States); Center for Studies in Physics and Biology, The Rockefeller University, 1230 York Street, New York, New York 10065 (United States); Jaffe, Robert L. [Department of Physics, Massachusetts Institute of Technology, Cambridge, Massachusetts 02139 (United States); Center for Theoretical Physics and Laboratory for Nuclear Science, Massachusetts Institute of Technology, Cambridge, Massachusetts 02139 (United States)

2011-06-15T23:59:59.000Z

215

Valve studies: Hydrogen fluoride monitoring of UF{sub 6} cylinder valves  

Science Conference Proceedings (OSTI)

Uranium hexafluoride (UF{sub 6}) cylinder valves have, like the cylinders, been in use and/or storage for periods ranging from 15 to 44 years. Visual inspection of the cylinders has shown that the extent of corrosion and the overall cylinder condition varies widely throughout the storage yards. One area of concern is the integrity of the cylinder valves. Visual inspection has found deposits which have been identified as radioactive material on or near the valves. These deposits suggest leakage of UF{sub 6} and may indicate valve degradation; however, these deposits may simply be residual material from cylinder filling operations.

Leedy, R.R.; Ellis, A.R.; Hoffmann, D.P.; Marsh, G.C. [and others

1996-08-01T23:59:59.000Z

216

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

217

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

218

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

219

Depletion modeling of liquid dominated geothermal reservoirs  

DOE Green Energy (OSTI)

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

Olsen, G.

1984-06-01T23:59:59.000Z

220

FAQ 24-Who is responsible for managing depleted uranium?  

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

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

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

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

Annual Energy Outlook 2012 (EIA)

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

222

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

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

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

223

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

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

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

224

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

225

Operation of a Four-Cylinder 1.9L Propane Fueled Homogeneous Charge Compression Ignition Engine: Basic Operating Characteristics and Cylinder-to-Cylinder Effects  

DOE Green Energy (OSTI)

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

2001-03-12T23:59:59.000Z

226

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

227

Electromagnetic Casimir forces of parabolic cylinder and knife-edge geometries  

E-Print Network (OSTI)

An exact calculation of electromagnetic scattering from a perfectly conducting parabolic cylinder is employed to compute Casimir forces in several configurations. These include interactions between a parabolic cylinder and ...

Graham, Noah

228

A modern depleted uranium manufacturing facility  

SciTech Connect

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

Zagula, T.A.

1995-07-01T23:59:59.000Z

229

Depletion effects of silicon deposition from methyltrichlorosilane  

DOE Green Energy (OSTI)

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

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

1992-10-01T23:59:59.000Z

230

Processing of mixed-waste compressed-gas cylinders on the Oak Ridge Reservation  

Science Conference Proceedings (OSTI)

To comply with restrictions on the storage of old compressed gas cylinders, the environmental management organization of Lockheed Martin Energy Systems must dispose of several thousand kilograms of compressed gases stored on the Oak Ridge Reservation (ORR) because the cylinders cannot be taken off-site for disposal in their current configuration. In the ORR Site Treatment Plan, a milestone is cited that requires repackaging and shipment off-site of 21 cylinders by September 30, 1997. A project was undertaken to first evaluate and then either recontainerize or neutralize these cylinders using a transportable compressed gas recontainerization skid (TCGRS), which was developed by Integrated Environmental Services of Atlanta. The transportable system can: (1) sample, analyze, and identify at the site the chemical and radiological content of each cylinder, even those with inoperable valves; (2) breach cylinders, when necessary, to release their contents into a containment chamber; and (3) either neutralize the gas or liquid contents within the containment chamber or transfer the gas or liquids to a new cylinder. The old cylinders and cylinder fragments were disposed of and the gases neutralized or transferred to new cylinders for transportation off-site for disposal. The entire operation to process the 21 cylinders took place in only 5 days once the system was approved for operation. The system performed as expected and can now be used to process the potentially thousands of more cylinders located across the US Department of Energy (DOE) complex that have not yet been declared surplus.

Morris, M.I.; Conley, T.B.; Osborne-Lee, I.W.

1998-01-01T23:59:59.000Z

231

Gas-lubricated seal for sealing between a piston and a cylinder wall  

DOE Patents (OSTI)

A piston-cylinder seal uses gas for a lubricant and has a runner supported on a gapless structure and placed in the space between the piston and the cylinder wall. The runner is deformed elastically under the influence of the operating pressures to follow and compensate for variations in the piston-cylinder fit and maintain a seal. 4 figs.

Hoult, D.P.

1985-09-10T23:59:59.000Z

232

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

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

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

233

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

234

FAQ 17-Where is uranium hexafluoride stored in the United States...  

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

Where is uranium hexafluoride stored in the United States? Where is uranium hexafluoride stored in the United States? Most of the depleted UF6 accumulated since the 1940s is stored...

235

DUF6 EIS Public Comment Form  

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

Public Comment Form Public Comment Form The public comment period for the Depleted UF6 Supplemental Analysis is closed. The public comment form is no longer available. Sorry The...

236

DUF6 Conversion Facility EIS Schedule  

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

Depleted UF6 Conversion Facility EISs Schedule The final EISs for the DUF6 Conversion Facilities have been completed, and are available through this web site. The RODs are...

237

Documents: Cost Analysis  

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

Analysis Search Documents: Search PDF Documents View a list of all documents Cost Analysis PDF Icon Summary of the Cost Analysis Report for the Long-term Management of Depleted UF6...

238

Mailing Services  

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

Mailing Services Mailing Services Use the form below to add your name to the Depleted UF6 Mailing List. First Name: Last Name: Organization: Address: City: State: Postal Code:...

239

Final report on PCRV thermal cylinder axial tendon failures  

SciTech Connect

The post-test examination of the failed tendons from the PCRV thermal cylinder experiment has been concluded. Failures in the wires are attributed to stress-corrosion cracking. The cause of tendon failures has not been unequivocably established, but they may have been due to nitrates in the duct. The wires employed in the manufacture of the tendons will crack in less than 72 hr in a 0.2 M solution of ammonium nitrate at 70$sup 0$C. The quality of the wires is poor, and surface cracks were detected. These could have acted as concentrating sites for both stress and the deleterious contaminants. It is believed that the factors that led to the failures in the thermal cylinder experiment were unique. An improper formulation of the epoxy resin did not provide the tendon anchor plate seal that was desired; indeed, the improper formulation is responsible for the high level of nitrogen in the ducts of the failed tendons. (auth)

Canonico, D.A.; Griess, J.C.; Robinson, G.C.

1976-01-01T23:59:59.000Z

240

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,

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

Integrated hydraulic cooler and return rail in camless cylinder head  

SciTech Connect

An engine assembly may include a cylinder head defining an engine coolant reservoir, a pressurized fluid supply, a valve actuation assembly, and a hydraulic fluid reservoir. The valve actuation assembly may be in fluid communication with the pressurized fluid supply and may include a valve member displaceable by a force applied by the pressurized fluid supply. The hydraulic fluid reservoir may be in fluid communication with the valve actuation assembly and in a heat exchange relation to the engine coolant reservoir.

Marriott, Craig D. (Clawson, MI); Neal, Timothy L. (Ortonville, MI); Swain, Jeff L. (Flushing, MI); Raimao, Miguel A. (Colorado Springs, CO)

2011-12-13T23:59:59.000Z

242

Lithium Depletion of Nearby Young Stellar Associations  

E-Print Network (OSTI)

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

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

2008-08-26T23:59:59.000Z

243

Wave runup on cylinders subject to deep water random waves  

E-Print Network (OSTI)

The accurate prediction of wave runup on deepwater offshore platform columns is of great importance for design engineers. Although linear predictive models are commonly used in the design and analysis process, many of the important effects are of higher order, and thus can only be accounted for by complex nonlinear models that better reflect the physics of the problem. This study presents a two-parameter Weibull distribution function that utilizes empirical coefficients to model the surface wave runup. Laboratory measurements of irregular waves interfering with vertical platform cylinders were used to obtain the Weibull coefficients necessary for the analytical model. Six data sets with different configurations where the wave elevation 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 and spectral analysis were utilized to characterize and interpret the time series data. The analysis focused on interpreting the tails of the probability distributions by carefully fitting the analytical model to the measured model data. The main conclusion of this study is that the two-parameter Weibull model can be used to accurately model the wave runup on platform cylinders for the experimental data investigated in this study.

Indrebo, Ann Kristin

2001-01-01T23:59:59.000Z

244

Natural Gas Vehicle Cylinder Safety, Training and Inspection Project  

DOE Green Energy (OSTI)

Under the auspices of the National Energy Technology Laboratory and the US Department of Energy, the Clean Vehicle Education Foundation conducted a three-year program to increase the understanding of the safe and proper use and maintenance of vehicular compressed natural gas (CNG) fuel systems. High-pressure fuel systems require periodic inspection and maintenance to insure safe and proper operation. The project addressed the needs of CNG fuel containers (cylinders) and associated high-pressure fuel system components related to existing law, codes and standards (C&S), available training and inspection programs, and assured coordination among vehicle users, public safety officials, fueling station operators and training providers. The program included a public and industry awareness campaign, establishment and administration of a cylinder inspector certification training scholarship program, evaluation of current safety training and testing practices, monitoring and investigation of CNG vehicle incidents, evaluation of a cylinder recertification program and the migration of CNG vehicle safety knowledge to the nascent hydrogen vehicle community.

Hank Seiff

2008-12-31T23:59:59.000Z

245

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

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

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

246

Numerical study of error propagation in Monte Carlo depletion simulations.  

E-Print Network (OSTI)

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

Wyant, Timothy Joseph

2012-01-01T23:59:59.000Z

247

DOE Selects Contractor for Depleted Hexafluoride Conversion Project...  

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

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

248

Health Risks Associated with Disposal of Depleted Uranium  

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

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

249

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

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

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

250

Application of thermal depletion model to geothermal reservoirs...  

Open Energy Info (EERE)

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

251

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

252

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).

253

Analysis of Hydrogen Depletion Using a Scaled Passive Autocatalytic Recombiner  

DOE Green Energy (OSTI)

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

Blanchat, T.K.; Malliakos, A.

1998-10-28T23:59:59.000Z

254

Analysis of Thermal Induction Plasmas between Coaxial Cylinders  

Science Conference Proceedings (OSTI)

A previously derived approximate solution of the one?dimensional energy?balance equation for steady thermal induction plasmas is applied to the case of an annular plasma contained between coaxial cylinders. It is assumed that heat conduction is the only loss mechanism and that both walls are at zero temperature. Charted material is presented to facilitate determination of heat loads to either wall and calculation of temperature distributions across the gap. Results for an atmospheric?pressure argon discharge are compared with both exact numerical calculations and with experimental data. With the former

H. U. Eckert

1972-01-01T23:59:59.000Z

255

Processing mixed-waste compressed-gas cylinders at the Oak Ridge Reservation  

Science Conference Proceedings (OSTI)

Until recently, several thousand kilograms of compressed gases were stored at the Oak Ridge Reservation (ORR), in Oak Ridge, Tennessee, because these cylinders could not be taken off-site in their state of configuration for disposal. Restrictions on the storage of old compressed-gas cylinders compelled the Waste Management Organization of Lockheed Martin Energy Systems, Inc. (LMES) to dispose of these materials. Furthermore, a milestone in the ORR Site Treatment Plan required repackaging and shipment off-site of 21 cylinders by September 30, 1997. A pilot project, coordinated by the Chemical Technology Division (CTD) at the Oak Ridge National Laboratory (ORNL), was undertaken to evaluate and recontainerize or neutralize these cylinders, which are mixed waste, to meet that milestone. Because the radiological component was considered to be confined to the exterior of the cylinder, the contents (once removed from the cylinder) could be handled as hazardous waste, and the cylinder could be handled as low-level waste (LLW). This pilot project to process 21 cylinders was important because of its potential impact. The successful completion of the project provides a newly demonstrated technology which can now be used to process the thousands of additional cylinders in inventory across the DOE complex. In this paper, many of the various aspects of implementing this project, including hurdles encountered and the lessons learned in overcoming them, are reported.

Morris, M.I.; Conley, T.B.; Osborne-Lee, I.W.

1998-05-01T23:59:59.000Z

256

Condition monitoring of internal leakage in modern water hydraulic cylinders using acoustic emission.  

E-Print Network (OSTI)

??This research aims to develop a sensitive method for condition monitoring of internal leakage in a modem water hydraulic cylinder by means of acoustic emission… (more)

Chen, Ping.

2009-01-01T23:59:59.000Z

257

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

258

Regulation of new depleted uranium uses.  

DOE Green Energy (OSTI)

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

Ranek, N. L.

2003-01-22T23:59:59.000Z

259

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 and a mixture of uranium and plutonium for use as a fresh blanket and 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 cathode is disposed about the outer anodic dissolution baskets. Uranium is deposited from the anode baskets 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 collection efficiency enhanced by increasing the electrode area and reducing the anode-cathode spacing for enhanced trapping and recovery of uranium dendrites scraped off of the cylindrical cathodes which may be greater in number than two.

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

1995-12-31T23:59:59.000Z

260

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

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

Modeling the fast fill process in natural gas vehicle storage cylinders  

DOE Green Energy (OSTI)

The on-board storage capacity of natural gas vehicles (NGVs) is a critical issue to the wide spread marketing of these alternate fueled vehicles. Underfilling of NGV cylinders, during fast fill (< 5 min.) charging operations, can occur at fueling stations, at ambient temperatures greater than 50{degrees}F or 60{degrees}F. The resulting reduced driving range of the vehicle is a serious obstacle which the gas industry is striving to overcome, without resorting to unnecessarily high fueling station pressures, or by applying extensive overpressurization of the cylinder during the fueling operation. Undercharged storage cylinders are a result of the elevated temperature which occurs in the NGV storage cylinder, due to compression and other processes which have not, to the author`s knowledge, been analyzed and documented to date. This paper presents a model and solution methodology which quantifies the cylinder undercharging phenomena which occurs during rapid (< 5 min.) fueling. The effects of heat transfer from the cylinder gas to its constraining walls and ambient are considered in the model analysis. The ramifications of the results on fueling station and cylinder designs are discussed. Suggestions are made for controlled experimental programs to verify the theoretical results, and for fueling station design studies which could minimize or eliminate cylinder underfilling.

Kountz, K.J.

1994-09-01T23:59:59.000Z

262

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

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

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

263

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.

264

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.

265

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.

266

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.

267

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,

268

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,

269

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

270

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

E-Print Network (OSTI)

tremendous flexibility to control the cylinder motion while decreasing the energy usage by utilizing and individual cylinder chamber pressure control for better energy saving. With a typical four-way directional energy usage. The programmable valve configuration used in this study is seen in Figure 1. Cylinder Valve

Yao, Bin

271

Natural phenomena evaluations of the K-25 site UF{sub 6} cylinder storage yards  

Science Conference Proceedings (OSTI)

The K-25 Site UF{sub 6} cylinder storage yards are used for the temporary storage of UF{sub 6} normal assay cylinders and long-term storage of other UF{sub 6} cylinders. The K-25 Site UF{sub 6} cylinder storage yards consist of six on-site areas: K-1066-B, K-1066-E, K-1066-F, K-1066-J, K-1066-K and K-1066-L. There are no permanent structures erected on the cylinder yards, except for five portable buildings. The operating contractor for the K-25 Site is preparing a Safety Analysis Report (SAR) to examine the safety related aspects of the K-25 Site UF{sub 6} cylinder storage yards. The SAR preparation encompasses many tasks terminating in consequence analysis for the release of gaseous and liquid UF{sub 6}, one of which is the evaluation of natural phenomena threats, such as earthquakes, floods, and winds. In support of the SAR, the six active cylinder storage yards were evaluated for vulnerabilities to natural phenomena, earthquakes, high winds and tornados, tornado-generated missiles, floods (local and regional), and lightning. This report summarizes those studies. 30 refs.

Fricke, K.E.

1996-09-15T23:59:59.000Z

272

Ozone depletion, greenhouse gases, and climate change: Proceedings  

SciTech Connect

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

1989-01-01T23:59:59.000Z

273

Experimental studies of unrestrained cylinders on an impermeable bottom under currents  

E-Print Network (OSTI)

Experimental studies were conducted to measure the motion of unrestrained cylinders with different diameters (0.048 m-0. 1 15 m), specific gravities (1.57-3.17) and aspect ratios (3.56-8.67), rolling on an impermeable, flat bottom under currents of velocities ranging from 0.3 m/s to 1.0 m/s. The currents in the flume of a uniform cross section (0.47 m x 0.52 m) were steady and uniform in velocity except near the bottom and the side walls. A video processing method was developed to document the linear and angular positions of the cylinders as a function of time. The experimental error encountered due to video resolution was studied and minimized through the use of a proper data sampling rate The terminal velocities of the cylinders are found to increase with an increase in current velocity. When the current velocity is above a superthreshold current velocity, the ratio of the terminal velocity to the current velocity (relative terminal velocity) seems to be around 0.70. The relative terminal velocities of the cylinders are found to be independent of diameter, aspect ratio and blockage ratio when the current velocity is greater than the superthreshold velocity. When the current velocity is greater than the superthreshold velocity, the relative terminal velocities of the cylinders are almost independent of specific gravity. The measurements show that the relative terminal velocities of cylinders with small specific gravities (1.57-1.71) range from 0.70-0.72, slightly above 0.70, while those of cylinders with large specific 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 not roll with pure rotation. Both steel and PVC cylinders experience back-slipping, where average angular velocity multiplied by the radius of the cylinder is greater than average linear center velocity in the x-direction.

Fenical, Scott William

1996-01-01T23:59:59.000Z

274

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

275

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

276

Depleted uranium as a backfill for nuclear fuel waste package  

DOE Patents (OSTI)

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

Forsberg, Charles W.

1997-12-01T23:59:59.000Z

277

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

278

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.

279

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

280

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

DOE Green Energy (OSTI)

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

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

Coal slurry combustion optimization on single cylinder engine  

DOE Green Energy (OSTI)

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

282

Study of laminar, unsteady piston-cylinder flows  

SciTech Connect

The present paper concerns numerical investigation of a piston-driven, axisymmetric flow in a pipe assembly containing a sudden expansion. The piston closes the larger of the two pipes. The impulsively starting intake flow is the topic of this investigation. Results of numerical calculations and laser-Doppler measurements are presented to provide an insight into the features of the flow. The calculation procedure employed in this study is based on a finite-volume method with staggered grids and SIMPLE algorithm for pressure-velocity coupling. The convection and diffusion fluxes in the Navier-Stokes equations are discretized with first order upwind and second order central differences, respectively. A fully implicit Euler scheme is used to discretize the temporal derivatives. The Navier-Stokes equations were suitably transformed to allow prediction of the flow within the inlet pipe and cylinder region simultaneously. Laser-Doppler measurements of both axial and radial velocity components were performed. Refractive index matching was used to eliminate the wall curvature effects. For each measuring point 20 cycles were measured, showing high repetition rates. Comparison of measured and predicted velocity profiles shows good agreement.

Stroell, H. [Wehrtechnische Dienststelle fuer Fernmeldewesen und Elektronik, Greding (Germany); Durst, F.; Peric, M. [Univ. Erlangen (Germany). Lehrstuhl fuer Stroemungsmechanik; Pereira, J.C.F. [Inst. Superior Tecnico, Lisboa (Portugal); Scheuerer, G. [Advanced Scientific Computing, Holzkirchen (Germany)

1993-12-01T23:59:59.000Z

283

Wave Forces on Offshore Structures: Nonlinear Wave Diffraction by Large Cylinders  

Science Conference Proceedings (OSTI)

A nonlinear theory of wave diffraction is presented and used to evaluate the forces exerted On a cylinder of large diameter. A perturbation technique has been used to solve the problem with the inclusion of second-order terms. Analytical ...

M. Rahman; H. S. Heaps

1983-12-01T23:59:59.000Z

284

Anomalous Near-Field Heat Transfer between a Cylinder and a Perforated Surface  

E-Print Network (OSTI)

We predict that the near-field radiative heat-transfer rate between a cylinder and a perforated surface depends nonmonotonically on their separation. This anomalous behavior, which arises due to evanescent-wave effects, ...

Rodriguez-Wong, Alejandro

285

Zeeman splitting of photonic angular momentum states in a gyromagnetic cylinder  

E-Print Network (OSTI)

We show that, under the presence of a static magnetic field, the photon eigenfrequencies of a circular gyromagnetic cylinder experience a splitting that is proportional to the angular momentum density of light at the ...

Dong, Hui Yuan

286

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

287

A Two-Cylinder Model of Cumulus Cells and Its Application in Computing Cumulus Transports  

Science Conference Proceedings (OSTI)

A two-cylinder model suitable for computing vertical transports in cumulus cells is formulated. The model includes explicit computation of perturbation pressure and allows the study of the evolution of raindrop size spectra. Sensitivity tests ...

Man Kong Yau

1980-11-01T23:59:59.000Z

288

Characterization of in-cylinder techniques for thermal management of diesel aftertreatment  

DOE Green Energy (OSTI)

One challenge in meeting emission regulations with catalytic aftertreatment systems is maintaining the proper catalyst temperatures that enable the catalytic devices to perform the emissions reduction. In this study, in-cylinder techniques are used to actively control the temperature of a catalyzed diesel particulate filter (DPF) in order to raise the DPF temperature to induce particulate oxidation. The performance of four strategies is compared for two different starting DPF temperatures (150 C and 300 C) on a 4-cylinder, 1.7-liter diesel engine. The four strategies include: (1) addition of extra fuel injection early in the combustion cycle for all four cylinders, (2) addition of extra fuel injection late in the combustion cycle for all four cylinders, (3) operating one-cylinder with extra fuel injection early in the combustion cycle, and (4) operating one-cylinder with extra fuel injection late in the combustion cycle. In cases (3) and (4), the cylinder operating with extra fuel injection is changed frequently to avoid oil dilution complications. In addition to the in-cylinder strategies, an in-pipe fuel addition technique for thermal management was studied for comparison. Results show that at starting temperatures above 300 C, late cycle injection strategies that cause temperature rise from exotherms created by unburned fuel components result in higher temperature rise for a given fuel penalty. At the low temperature of 150 C, early injection strategies that create temperature rise from both combustion and light reductant exotherms are preferred due to the inability of the catalyst to oxidize unburned fuel from late injection strategies.

Parks, II, James E [ORNL; Huff, Shean P [ORNL; Kass, Michael D [ORNL; Storey, John Morse [ORNL

2007-01-01T23:59:59.000Z

289

Numerical modeling of interaction of a current with a circular cylinder near a rigid bed  

Science Conference Proceedings (OSTI)

The numerical modeling of 2D turbulent flow around a smooth horizontal circular cylinder near a rigid bed with gap ratio G/D=0.3 at Reynolds number Re"D=9500 is investigated. Ansys^(R) 10.0-FLOTRAN program package is used to solve the governing equations ... Keywords: Circular cylinder, Numerical model, Particle image velocimetry, Steady flow, Strouhal number, Velocity field

M. Salih Kirkgoz; A. Alper Oner; M. Sami Akoz

2009-11-01T23:59:59.000Z

290

Extending operating range of a homogeneous charge compression ignition engine via cylinder deactivation  

DOE Patents (OSTI)

An HCCI engine has the ability to operate over a large load range by utilizing a lower cetane distillate diesel fuel to increase ignition delay. This permits more stable operation at high loads by avoidance of premature combustion before top dead center. During low load conditions, a portion of the engines cylinders are deactivated so that the remaining cylinders can operate at a pseudo higher load while the overall engine exhibits behavior typical of a relatively low load.

Hergart, Carl-Anders (Peoria, IL); Hardy, William L. (Peoria, IL); Duffy, Kevin P. (Metamora, IL); Liechty, Michael P. (Chillicothe, IL)

2008-05-27T23:59:59.000Z

291

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

292

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

293

Low-cost, low-weight CNG cylinder development. Final report  

DOE Green Energy (OSTI)

This program was established to develop and commercialize new high-strength steel-lined, composite hoop-wrapped compressed natural gas (CNG) cylinders for vehicular applications. As much as 70% of the cost of natural gas vehicles can be related to on-board natural gas storage costs. The cost and weight targets for this program represent significant savings in each characteristic when compared to comparable containers available at the initiation of the program. The program objectives were to optimize specific weight and cost goals, yielding CNG cylinders with dimensions that should, allowing for minor modifications, satisfy several vehicle market segments. The optimization process encompassed material, design, and process improvement. In optimizing the CNG cylinder design, due consideration was given to safety aspects relative to national, international, and vehicle manufacturer cylinder standards and requirements. The report details the design and development effort, encompassing plant modifications, material selection, design issues, tooling development, prototype development, and prototype testing. Extenuating circumstances prevented the immediate commercialization of the cylinder designs, though significant progress was made towards improving the cost and performance of CNG cylinders. A new low-cost fiber was successfully employed while the weight target was met and the cost target was missed by less than seven percent.

Richards, Mark E.; Melford, K.; Wong, J.; Gambone, L.

1999-09-01T23:59:59.000Z

294

Lithium depletion and the rotational history of exoplanet host stars  

E-Print Network (OSTI)

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

Jerome Bouvier

2008-08-28T23:59:59.000Z

295

The depleted hydrogen atoms in chemical graph theory  

Science Conference Proceedings (OSTI)

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

Lionello Pogliani

2008-12-01T23:59:59.000Z

296

CRDIAC: Coupled Reactor Depletion Instrument with Automated Control  

SciTech Connect

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

Steven K. Logan

2012-08-01T23:59:59.000Z

297

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

298

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,

299

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

300

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

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

Depletion-induced structure and dynamics in bimodal colloidal suspensions.  

Science Conference Proceedings (OSTI)

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

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

2011-05-03T23:59:59.000Z

302

Accounting for Depletion of Oil and Gas Resources in Malaysia  

Science Conference Proceedings (OSTI)

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

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

2012-12-15T23:59:59.000Z

303

CO depletion --- An evolutionary tracer for molecular clouds  

E-Print Network (OSTI)

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

Liu, Tie; Zhang, Huawei

2013-01-01T23:59:59.000Z

304

In-cylinder pressure and inter-cycle variability analysis for a compression ignition engine : Bayesian approaches.  

E-Print Network (OSTI)

??This thesis introduced Bayesian statistics as an analysis technique to isolate resonant frequency information in in-cylinder pressure signals taken from internal combustion engines. Applications of… (more)

Bodisco, Timothy Alexis

2013-01-01T23:59:59.000Z

305

Method and apparatus for reconstructing in-cylinder pressure and correcting for signal decay  

Science Conference Proceedings (OSTI)

A method comprises steps for reconstructing in-cylinder pressure data from a vibration signal collected from a vibration sensor mounted on an engine component where it can generate a signal with a high signal-to-noise ratio, and correcting the vibration signal for errors introduced by vibration signal charge decay and sensor sensitivity. The correction factors are determined as a function of estimated motoring pressure and the measured vibration signal itself with each of these being associated with the same engine cycle. Accordingly, the method corrects for charge decay and changes in sensor sensitivity responsive to different engine conditions to allow greater accuracy in the reconstructed in-cylinder pressure data. An apparatus is also disclosed for practicing the disclosed method, comprising a vibration sensor, a data acquisition unit for receiving the vibration signal, a computer processing unit for processing the acquired signal and a controller for controlling the engine operation based on the reconstructed in-cylinder pressure.

Huang, Jian

2013-03-12T23:59:59.000Z

306

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

307

Externally pressurized porous cylinder for multiple surface aerosol generation and method of generation  

DOE Patents (OSTI)

A nebulizer is described for generating aerosol having small droplet sizes and high efficiency at low sample introduction rates. The nebulizer has a cylindrical gas permeable active surface. A sleeve is disposed around the cylinder and gas is provided from the sleeve to the interior of the cylinder formed by the active surface. In operation, a liquid is provided to the inside of the gas permeable surface. The gas contacts the wetted surface and forms small bubbles which burst to form an aerosol. Those bubbles which are large are carried by momentum to another part of the cylinder where they are renebulized. This process continues until the entire sample is nebulized into aerosol sized droplets. 2 figs.

Apel, C.T.; Layman, L.R.; Gallimore, D.L.

1988-05-10T23:59:59.000Z

308

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

Science Conference Proceedings (OSTI)

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

2013-04-10T23:59:59.000Z

309

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

310

Deformation of a thin, elastic plate to a deep parabolic cylinder  

DOE Green Energy (OSTI)

Equations governing the elastic deformation of thin plates through large displacements to deep parabolic cylinders are presented and solved. The solution consists of expressions for a spatially distributed surface pressure and uniform rim loads which, when applied to the plate, produce the specified, deep parabolic cylindrical shape. These forming loads are written in dimensionless form for parabolic cylinders of arbitrary focal length and arbitrary rim to rim aperture. Numerical results are presented and limiting values are discussed. The solution and results find immediate application to mechanical forming and adhesive retention of parabolic solar collector components.

Reuter, R.C. Jr.; Wilson, R.K.

1982-02-01T23:59:59.000Z

311

Selection of a management strategy for depleted uranium hexafluoride  

Science Conference Proceedings (OSTI)

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

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

1995-09-06T23:59:59.000Z

312

Numerical prediction of aerodynamic characteristics of prismatic cylinder by finite element method with Spalart-Allmaras turbulence model  

Science Conference Proceedings (OSTI)

Aerodynamic characteristic of prismatic cylinders is numerically investigated by using finite element method with Spalart-Allmaras turbulence model. The developed model is verified against the available experimental and numerical results for turbulent ... Keywords: Aerodynamic characteristic, Afterbody shape, Finite element method, Prismatic cylinder, Turbulent flow, Unsteady S-A model

Yan Bao; Dai Zhou; Cheng Huang; Qier Wu; Xiang-qiao Chen

2011-02-01T23:59:59.000Z

313

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

314

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

315

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

316

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

317

The Icing of an Unheated, Nonrotating Cylinder. Part I: A Simulation Model  

Science Conference Proceedings (OSTI)

A model is described which simulates icing on an unheated, non-rotating cylinder. Both rime and glaze ice can be accounted for. The model computes the thermodynamic conditions and the initial icing rate as a function of angle around the upstream ...

E. P. Lozowski; J. R. Stallabrass; P. F. Hearty

1983-12-01T23:59:59.000Z

318

On the Cylinder Collapse Problem, Mixing, and the Merger of Isolated Eddies  

Science Conference Proceedings (OSTI)

The Rossby adjustment of an initially circular column of water, the so-called collapse of a cylinder, continues to be a widely used method for forming lenslike eddies in the laboratory. Here, we consider the structure of an eddy so formed as well ...

William K. Dewar; Peter D. Killworth

1990-10-01T23:59:59.000Z

319

Finite element lattice Boltzmann simulations of free surface flow in a concentric cylinder  

Science Conference Proceedings (OSTI)

The annular centrifugal contactor is a compact mixer/centrifuge device designed for liquid-liquid extraction operations in processes for recycling nuclear fuel. The flow in the annulus of a centrifugal contactor is similar to the Taylor vortex flow with ... Keywords: Concentric cylinder, Finite element method, Free surface flow, Lattice Boltzmann method

Kent E. Wardle; Taehun Lee

2013-01-01T23:59:59.000Z

320

The Icing of an Unheated, Nonrotating Cylinder. Part II. Icing Wind Tunnel Experiments  

Science Conference Proceedings (OSTI)

An experimental investigation of icing on non-rotating cylinders, under both wet and dry conditions was undertaken. Airspeeds of 30, 61 and 122 m s?1 appropriate to aircraft icing, liquid water contents of 0.4, 0.8 and 1.2 g m?3 and temperatures ...

E. P. Lozowski; J. R. Stallabrass; P. F. Hearty

1983-12-01T23:59:59.000Z

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.


321

Attainable Burnup in a LIFE Engine Loaded with Depleted Uranium  

Science Conference Proceedings (OSTI)

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

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

2009-11-30T23:59:59.000Z

322

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

323

Ozone-depleting-substance control and phase-out plan  

SciTech Connect

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

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

1994-07-01T23:59:59.000Z

324

The scale analysis sequence for LWR fuel depletion  

Science Conference Proceedings (OSTI)

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

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

1991-01-01T23:59:59.000Z

325

Numerical study of error propagation in Monte Carlo depletion simulations  

Science Conference Proceedings (OSTI)

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

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

2012-07-01T23:59:59.000Z

326

Sampling Plan for Assaying Plates Containing Depleted or Normal Uranium  

Science Conference Proceedings (OSTI)

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

Ivan R. Thomas

2011-11-01T23:59:59.000Z

327

On the Presence of Depleted Zones in Platinum  

SciTech Connect

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

Attardo, M J; Galligan, J M

1966-08-05T23:59:59.000Z

328

Prototype Tests for the Recovery and Conversion of UF6 Chemisorbed in NaF Traps for the Molten Salt Reactor Remediation Project  

SciTech Connect

The remediation of the Molten Salt Reactor Experiment (MSRE) site includes the removal of about 37 kg of uranium. Of that inventory, about 23 kg have already been removed from the piping system and chemisorbed in 25 NaF traps. This material is being stored in Building 3019. The planned recovery of -11 kg of uranium from the fuel salt will generate another 15 to 19 NaF traps. The remaining 2 to 3 kg of uranium are present in activated charcoal beds, which are also scheduled to be removed from the reactor site. Since all of these materials (NaF traps and the uranium-laden charcoal) are not suitable for long-term storage, they will be converted to a chemical form [uranium oxide], which is suitable for long-term storage. This document describes the process that will be used to recover and convert the uranium in the NaF traps into a stable oxide for long-term storage. Included are a description of the process, equipment, test results, and lessons learned. The process was developed for remote operation in a hot cell. Lessons learned from the prototype testing were incorporated into the process design.

Del Cul, G.D.; Icenhour, A.S.; Simmons, D.W.

2000-04-01T23:59:59.000Z

329

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

330

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

331

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

332

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

Science Conference Proceedings (OSTI)

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

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

2010-09-30T23:59:59.000Z

333

In-cylinder gas velocity measurements comparing crankcase and blower scavenging in a fired two-stroke cycle engine  

Science Conference Proceedings (OSTI)

The in-cylinder flow field of a Schnuerle (loop) scavenged two-stroke engine has been examined under conditions simulating both blower and crankcase driven scavenging. Measurements of the radial component of velocity were obtained along the cylinder centerline during fired operation at delivery ratios of 0.4, 0.6, and 0.8. Both mean velocity profiles and root mean square velocity fluctuations near top center show a strong dependence on the scavenging method. Complementary in-cylinder pressure measurements indicate that combustion performance is better under blower driven scavenging for the engine geometry studied.

Miles, P.C.; Green, R.M.; Witze, P.O.

1994-01-01T23:59:59.000Z

334

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

335

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

336

Electromagnetic energy within a magnetic infinite cylinder and scattering properties for oblique incidence  

E-Print Network (OSTI)

In this work we analytically calculate the time-averaged electromagnetic energy stored inside a nondispersive magnetic isotropic cylinder which is obliquely irradiated by an electromagnetic plane wave. An expression for the optical-absorption efficiency in terms of the magnetic internal coefficients is also obtained. In the low absorption limit, we derive a relation between the normalized internal energy and the optical-absorption efficiency which is not affected by the magnetism and the incidence angle. This mentioned relation, indeed, seems to be independent on the shape of the scatterer. This universal aspect of the internal energy is connected to the transport velocity and consequently to the diffusion coefficient in the multiple scattering regime. Magnetism favors high internal energy for low size parameter cylinders, which leads to a low diffusion coefficient for electromagnetic propagation in 2D random media.

Tiago Jose Arruda; Alexandre Souto Martinez

2010-10-14T23:59:59.000Z

337

A rotating cylinder in an asymptotically locally anti-de Sitter background  

E-Print Network (OSTI)

A family of exact solutions is presented which represents a rigidly rotating cylinder of dust in a background with a negative cosmological constant. The interior of the infinite cylinder is described by the Godel solution. An exact solution for the exterior solution is found which depends both on the rotation of the interior and on its radius. For values of these parameters less than a certain limit, the exterior solution is shown to be locally isomorphic to the Linet-Tian solution. For values larger than another limit, it is shown that the exterior solution extends into a region which contains closed timelike curves. At large distances from the source, the space-time is shown to be asymptotic locally to anti-de Sitter space.

J. B. Griffiths; N. O. Santos

2010-03-18T23:59:59.000Z

338

Analytical solution for unsteady thermal stresses in an infinite cylinder composed of two materials  

SciTech Connect

An exact analytical solution for unsteady thermal stresses in an infinitely long solid composite cylinder is presented. The unsteady temperature field is determined following Ozisik's (1980) treatment, but a more general solution is achieved by the present approach by considering a heat convection situation at the outer boundary. The plane stress and plane strain states are considered next, and the thermal stresses are evaluated. Results are provided as dimensionless plots for several combinations of thermal and mechanical parameters of practical interest. 6 references.

Pardo, E.; Sanchez Sarmiento, G.; Laura, P.A.A.; Gutierrez, R.H.

1987-01-01T23:59:59.000Z

339

Releases of UF{sub 6} to the atmosphere after a potential fire in a cylinder storage yard  

Science Conference Proceedings (OSTI)

Uranium hexafluoride (UF{sub 6}), a toxic material, is stored in just over 6200 cylinders at the K-25 site in Oak Ridge, Tennessee. The safety analysis report (SAR) for cylinder yard storage operations at the plant required the development of accident scenarios for the potential release of UF{sub 6} to the atmosphere. In accordance with DOE standards and guidance, the general approach taken in this SAR was to examine the functions and contents of the cylinder storage yards to determine whether safety-significant hazards were present for workers in the immediate vicinity, workers on-site, the general public off-site, or the environment. and to evaluate the significance of any hazards that were found. A detailed accident analysis was performed to determine a set of limiting accidents that have potential for off-site consequences. One of the limiting accidents identified in the SAR was the rupture of a cylinder engulfed in a fire.

Lombardi, D.A.; Williams, W.R.; Anderson, J.C. [and others

1997-06-01T23:59:59.000Z

340

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

E-Print Network (OSTI)

Saturated permeability is likely a good method for characterizing the susceptibility of portland cement concrete to various forms of degradation; although no widely accepted test exists to measure this property. The hollow cylinder dynamic pressurization test is a potential solution for measuring concrete permeability. The hollow cylinder dynamic pressurization (HDP) test is compared with the radial flow through (RFT) test and the solid cylinder dynamic pressurization (SDP) test to assess the accuracy and reliability of the HDP test. The three test methods, mentioned above, were used to measure the permeability of Vycor glass and portland cement paste and the results of the HDP test were compared with the results from the SDP and RFT tests. When the HDP and RFT test results were compared, the measured difference between the mean values of the two tests was 40% for Vycor glass and 47% for cement paste. When the HDP and SDP tests results were compared, the measured difference with Vycor glass was 53%. The cement paste permeability values could not be compared in the same manner since they were tested at various ages to show the time dependency of permeability in cement paste. The results suggest good correlation between the HDP test and both the SDP and RFT tests. Furthermore, good repeatability was shown with low coefficients of variation in all test permutations. Both of these factors suggest that the new HDP test is a valid tool for measuring the permeability of concrete materials.

Jones, Christopher Andrew

2008-08-01T23:59:59.000Z

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

Tribological evaluation of piston skirt/cylinder liner contact interfaces under boundary lubrication conditions.  

DOE Green Energy (OSTI)

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

342

Chemical reactions of UF{sub 6} with water on ingress to damaged model 48X 10 ton cylinder  

Science Conference Proceedings (OSTI)

Chemistry studies of the effects of water flooding in Model 48X 10-ton UF{sub 6} storage cylinders, as a result of impact fractures, were conducted to support the Safety Analysis Report for Packaging (SARP) review of the Paducah Tiger Overpack for transportation of those cylinders. The objectives of the study were to determine the maximum amount of water that could be admitted to the interior of such a damaged cylinder, the resulting geometries and chemical compositions from reactions of water with the UF{sub 6} contents of the cylinder, and the end-state water moderated and reflected configurations for input to nuclear criticality safety analyses. The case identified for analysis was the flooding of the inside of a cylinder, submerged horizontally in 3 ft of water. The flooding was driven by an initial pressure drop of 13 psig, through an assumed fracture (1/32 in. wide {times} 1/2 in. deep {times} 18 in. long) in the barrel of the cylinder. During the initial addition of water, transient back pressures occur from the effects of the heats of reaction and solution at the water/UF{sub 6} interface, with some chugging as more water is added to alternately coot the reaction surface and then heat it again as the added water reacts with more UF{sub 6}.

Rothman, A.B.

1996-02-01T23:59:59.000Z

343

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

344

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

345

Transpassive electrodissolution of depleted uranium in alkaline electrolytes  

SciTech Connect

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

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

1998-03-01T23:59:59.000Z

346

Kr ion irradiation study of the depleted-uranium alloys.  

Science Conference Proceedings (OSTI)

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

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

2010-12-01T23:59:59.000Z

347

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.

348

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

SciTech Connect

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

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

2012-07-01T23:59:59.000Z

349

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

350

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

351

Characterization of Thermal Properties of Depleted Uranium Metal Microspheres  

E-Print Network (OSTI)

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

Humrickhouse, Carissa Joy

2012-05-01T23:59:59.000Z

352

Piston Bowl Optimization for RCCI Combustion in a Light-Duty Multi-Cylinder Engine  

Science Conference Proceedings (OSTI)

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

353

Forensics of Soot: Nanostructure as a Diagnostic of In-Cylinder Chemistry  

DOE Green Energy (OSTI)

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; Strzelec, Dr. Andrea [Texas A& M University; Toops, Todd J [ORNL; Daw, C Stuart [ORNL

2012-01-01T23:59:59.000Z

354

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 Velocimetry as used herein is identical to the techniques in use in Texas A&M University's Pulsed Laser Velocimetry Laboratory where the test facilities include a flow bench, a ND-YAG pulsed laser, and data acquistion equipment, consisting of a CCD camera and attendant PC's programmed to control the laser and camera, and to acquire and store the digitized data. The data can then be retrieved for analysis. The data was analyzed using an existing algorithm, the Cross Correlation Code. Full-field, fluid two-dimensional velocity around, about, and past the test specimens was obtained with the digital camera which captured the images of light reflected from seeds flowing within the fluid within a given time exposure time of 53.8 ms. The viewing field area (approximately 5 cm by 5 cm) was illuminated by two light sheets impinging on the test specimens from opposing sides at angles less than 90' from the horizontal. The impinging angles were selected to create the least amount of shading by the test specimen and the incident target on the test specimen was common to both light sheets so that they would superimpose on the target, thus reinforcing the illumination intensity. The two light sheets were created by splitting the pulsing beam into two beams, and then each beam directed with, and to, mirrors which were part of an optical train consisting of three cylindrical lenses which converted the beam into a light sheet 0.5 to 1.0mm thick and 5 cm wide. The test conditions had a range of from 0.043 to 0.0579 m/s for the average velocity of the fluid and a range of Reynolds number of 7142 to 8140. Given these test conditions, vector plots representing the flow fieldwere generated for one test run on each of the these specimens. The velocity component of the plotted vectors was derived from a scale within the plots. Thus, two-dimensional velocities could be read anywhere within the plots. A mix of quantitative and qualitative data was obtained for the one, two, three, and quad cylinder arrangement test specimens.

Martinez, Ramiro Serna

1994-01-01T23:59:59.000Z

355

Ion beam driven ion-acoustic waves in a plasma cylinder with negatively charged dust grains  

SciTech Connect

An ion beam propagating through a magnetized potassium plasma cylinder having negatively charged dust grains drives electrostatic ion-acoustic waves to instability via Cerenkov interaction. The phase velocity of sound wave increases with the relative density of negatively charged dust grains. The unstable wave frequencies and the growth rate increase, with the relative density of negatively charged dust grains. The growth rate of the unstable mode scales as one-third power of the beam density. The real part of frequency of the unstable mode increases with the beam energy and scales as almost the one-half power of the beam energy.

Sharma, Suresh C.; Walia, Ritu [Department of Physics, Maharaja Agrasen Institute of Technology, PSP Area Plot No.-1, Sector-22, Rohini, Delhi 110 086 (India); Sharma, Kavita [Department of Physics, Bhagwan Parshuram Institute of Technology, Sector-17, Rohini, New Delhi 110 089 (India)

2012-07-15T23:59:59.000Z

356

,"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"

357

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

358

Development of a Physics of Failure Model and Quantitative Assessment of the Fire Fatality Risk of Compressed Natural Gas Bus Cylinders.  

E-Print Network (OSTI)

??Title of Dissertation: DEVELOPMENT OF A PHYSICS OF FAILURE MODEL AND QUANTITATIVE ASSESSMENT OF THE FIRE FATALITY RISKS OF COMPRESSED NATURAL GAS BUS CYLINDERS The… (more)

Chamberlain, Samuel Seamore

2004-01-01T23:59:59.000Z

359

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

360

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

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

Reactivity Controlled Compression Ignition (RCCI) Combustion on a Multi-Cylinder Light-Duty Diesel Engine  

Science Conference Proceedings (OSTI)

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

362

Self-Assembly on a Cylinder: A Model System for Understanding the Constraint of Commensurability  

E-Print Network (OSTI)

A crystal lattice, when confined to the surface of a cylinder, must have a periodic structure that is commensurate with the cylinder circumference. This constraint can frustrate the system, leading to oblique crystal lattices or to structures with a chiral seam known as a "line slip" phase, neither of which are stable for isotropic particles in equilibrium on flat surfaces. In this study, we use molecular dynamics simulations to find the steady-state structure of spherical particles with short-range repulsion and long-range attraction far below the melting temperature. We vary the range of attraction using the Lennard-Jones and Morse potentials and find that a shorter-range attraction favors the line-slip. We develop a simple model based only on geometry and bond energy to predict when the crystal or line-slip phases should appear, and find reasonable agreement with the simulations. The simplicity of this model allows us to understand the influence of the commensurability constraint, an understanding that might be extended into the more general problem of self-assembling particles in strongly confined spaces.

D. A. Wood; C. D. Santangelo; A. D. Dinsmore

2013-07-02T23:59:59.000Z

363

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

364

An In-Cylinder Study of Soot and NO in a DI Diesel Engine. Final report  

DOE Green Energy (OSTI)

Clearly the reduction of NOx and particulate emissions remains a major challenge to Diesel engine manufacturers due to increasingly stringent emission standards in the US and other countries. The well documented NOx/particulate trade-off observed in Diesel engines makes the simultaneous reduction of both emissions particularly difficult for manufacturers to achieve. In an effort to provide an improved understanding of the fundamental processes which result in this trade-off, a program was carried out at Penn State to develop the appropriate engine facilities and laser diagnostics to permit in-cylinder studies of Diesel combustion and emissions production with the support of the Department of Energy Advanced Industrial Technology Division . This work has also been supported by the Cummins Engine Company, Lubrizol Corporation and the National Science Foundation. An optically accessible, direct injection, Diesel engine was constructed for these studies. The major objective of the, design of the engine was to maximize optical access under conditions representative of Diesel engine combustion in small bore, commercial engines. Intake air is preheated and boosted in pressure to make the in-cylinder conditions of heat release and pressure as realistic as possible. Another important objective of the design was flexibility in combustion chamber geometry to permit a variety of head and bowl geometries to be studied. In all the results reported in this report a square bowl was used to simplify the introduction of laser light sheets into the engine.

Litzinger, T.A.

1995-10-18T23:59:59.000Z

365

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

366

Contact stresses for closely conforming bodies: application to cylinders and spheres. Final report  

DOE Green Energy (OSTI)

Since worn wheels and rails contact conformally, the existing contact stress theories for nonconformal contact are not adequate. A general numerical method of solution for three dimensional frictionless, conformal, elastic contact problems is presented. The method is used to analyze the conformal contact of a sphere indenting a spherical seat and a cylinder indenting a cylindrical seat. The results of the sphere-spherical seat problem compared well with experimental data. Results of the cylinder-cylindrical seat problem were in close agreement to a known analytic solution of this problem. For both analyses, results compared favorably with Hertzian theory for problems with small contact regions. A method is given for defining the boundaries of the large contact regions, and for solving the associated governing singular integral equation of the first kind. A general iterative procedure is developed which converges to the true three dimensional contact region. In addition the solution to a non-Hertzian contact problem with a multiply connected contact region is solved; namely, the case of two spheres in contact where one of them has a surface defect or pit.

Woodward, W.; Paul, B.

1976-12-01T23:59:59.000Z

367

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

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

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

368

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

Science Conference Proceedings (OSTI)

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

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

2011-03-01T23:59:59.000Z

369

Sequestration of CO2 in a Depleted Oil Reservoir: An Overview  

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

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

370

Exact Solution for the Stokes Problem of an Infinite Cylinder in a Fluid with Harmonic Boundary Conditions at Infinity  

E-Print Network (OSTI)

We present an exact solution for the time-dependent Stokes problem of an infinite cylinder of radius r=a in a fluid with harmonic boundary conditions at infinity. This is a 3-dimensional problem but, because of translational invariance along the axis of the cylinder it effectively reduces to a 2-dimensional one. The Stokes problem being a linear reduction of the full Navier-Stokes equations, we show how to satisfy the no-slip boundary condition at the cylinder surface and the harmonic boundary condition at infinity, exhibit the full velocity field for radius r>a, and discuss the nature of the solutions for the specific case of air at sea level.

Andreas N. Vollmayr; Jan-Moritz P. Franosch; J. Leo van Hemmen

2008-03-31T23:59:59.000Z

371

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

Science Conference Proceedings (OSTI)

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

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

2012-07-01T23:59:59.000Z

372

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.

373

Three-Dimensional Descriptions Based on the Analysis of the Invariant and Quasi-Invariant Properties of Some Curved-Axis Generalized Cylinders  

Science Conference Proceedings (OSTI)

Abstract¿We address the recovery of object-level 3-D descriptions of some classes of curved-axis generalized cylinders. For this, the first part of the paper analyzes the projective properties of two common generic shapes, planar right constant generalized ... Keywords: Shape description, generalized cylinders, invariants, quasi-invariants, segmentation, grouping.

Mourad Zerroug; Ramakant Nevatia

1996-03-01T23:59:59.000Z

374

ORALLOY (93.2 235U) METAL CYLINDER WITH BERYLLIUM TOP REFLECTOR  

SciTech Connect

A variety of critical experiments were constructed of enriched uranium metal during the 1960s and 1970s at the Oak Ridge Critical Experiments Facility (ORCEF) in support of criticality safety operations at the Y-12 Plant. The purposes of these experiments included the evaluation of storage, casting, and handling limits for the Y-12 Plant and providing data for verification of calculation methods and cross-sections for nuclear criticality safety applications. These included solid cylinders of various diameters, annuli of various inner and outer diameters, two and three interacting cylinders of various diameters, and graphite and polyethylene reflected cylinders and annuli. Of the hundreds of delayed critical experiments, one experiment was comprised of a stack of approximately 7-inch-diameter metal discs. The bottom of the stack consisted of uranium with an approximate height of 4-1/8 inches. The top of the stack consisted of beryllium with an approximate height of 5-9/16 inches. This experiment was performed on August 20, 1963 by J. T. Mihalczo and R. G. Taylor (Ref. 1) with accompanying logbook. Both detailed and simplified model specifications are provided in this evaluation. This fast-spectra experiment was determined to represent an acceptable benchmark. The calculated eigenvalues for both the detailed and simple models are within approximately 0.5% of the benchmark values, but significantly greater than 3s from the benchmark value because the uncertainty in the benchmark is very small: ±0.0002 (1s). There is significant variability between results using different neutron cross section libraries, the greatest being a ?keff of ~0.65% . Unreflected and unmoderated experiments with the same highly enriched uranium metal parts were performed at the Oak Ridge Critical Experiments Facility in the 1960s and are evaluated in HEU MET FAST 051. Thin graphite reflected (2 inches or less) experiments also using the same highly enriched uranium metal parts are evaluated in HEU MET FAST 071. Polyethylene-reflected configurations are evaluated in HEU-MET-FAST-076. Highly enriched metal annuli with beryllium cores are evaluated in HEU-MET-FAST-059.

John D. Bess; Leland M. Montierth; Raymond Reed; John T. Mihalczo

2010-09-01T23:59:59.000Z

375

Self assembly of monodisperse CdS nano-cylinders with a pore  

E-Print Network (OSTI)

We present investigate the self assembly and growth of an array of $CdS$ nanotubes: a consequence of a fine balance of directed motion, diffusion and aggregation of reacting ${\\rm Cd^{+2}}$ and ${\\rm S^{-2}}$ ions. In a previous communication [J. Kiruthiga, A. Chatterji, J. Chem. Phys., {\\bf 138} 024905 (2013)], we identified the mechanism of a unexpected growth of a very uniform $CdS$ nano-cylinder from the end of a nano-channel. Furthermore, the cylinder had a pore along the axis but were closed at one end. This unique phenomenon of self assembly of {\\em monodisperse} CdS nano-cylinders had been observed in a rather simple experiment where two chambers containing 0.1 M ${\\rm Cd Cl_2}$ and 0.1 M ${\\rm Na_2 S}$ solutions were joined by an array of anodized aluminium oxide (AAO) nano-channels [A. Varghese, S. Datta, Phys. Rev. E., {\\bf 85}, 056104 (2012)]. Our previous study identified the principles governing the growth of a single nano-tube at the exit point of a single AAO-nano-channel. In this communication, we identify factors affecting the self-assembly process for nano-tubes growing out an array of closely spaced AAO nano-channel exits. Our model is not $Cd^{+2}$ or $S^{2-}$ specific, the experimental scheme can be extended to self assemble a general class of reacting-diffusing A and B ions with A (${\\rm Cd^{+2}}$) selectively migrating out from a nano-channel. In particular, we note that after the initial prolonged growth of nanotubes, there can arise a severe deficiency of B-ions (${\\rm S^{-2}}$) ions near the AAO-nano-channel exits, the points where the reaction and aggregation occurs to form the $CdS$ nanotube, thus impeding further growth of uniform CdS nano-tubes. Thereby we predict the necessary characteristics of reacting systems which can be self assembled using suitable adaptations of previous experiments.

Kiruthiga Jagadeesan; Apratim Chatterji

2013-10-25T23:59:59.000Z

376

Highly Enriched Uranium Metal Annuli and Cylinders with Polyethylene Reflectors and/or Internal Polyethylene Moderator  

SciTech Connect

A variety of critical experiments were constructed of enriched uranium metal during the 1960s and 1970s at the Oak Ridge Critical Experiments Facility in support of criticality safety operations at the Y-12 Plant. The purposes of these experiments included the evaluation of storage, casting, and handling limits for the Y-12 Plant and providing data for verification of calculation methods and cross-sections for nuclear criticality safety applications. These included solid cylinders of various diameters, annuli of various inner and outer diameters, two and three interacting cylinders of various diameters, and graphite and polyethylene reflected cylinders and annuli. Of the hundreds of delayed critical experiments, experiments of uranium metal annuli with and without polyethylene reflectors and with the central void region either empty or filled with polyethylene were evaluated under ICSBEP Identifier HEU-MET-FAST-076. The outer diameter of the uranium annuli varied from 9 to 15 inches in two-inch increments. In addition, there were uranium metal cylinders with diameters varying from 7 to 15 inches with complete reflection and reflection on one flat surface to simulate floor reflection. Most of the experiments were performed between February 1964 and April 1964. Five partially reflected (reflected on the top only) experiments were assembled in November 1967, but are judged by the evaluators not to be of benchmark quality. Twenty-four of the twenty-five experiments have been determined to have fast spectra. The only exception has a mixed spectrum. Analyses were performed in which uncertainty associated with five different parameters associated with the uranium parts and three associated with the polyethylene parts was evaluated. Included were uranium mass, height, diameter, isotopic content, and impurity content and polyethylene mass, diameter, and impurity content. There were additional uncertainties associated with assembly alignment, support structure, and the value for ßeff. In addition to the idealizations made by the experimenters (removal of a diaphragm), a few simplifications were also made to the benchmark models that resulted in a small bias and additional uncertainty. Simplifications included omission of the support structure, possible surrounding equipment, and the walls, floor, and ceiling of the experimental cell. Bias values that result from these simplifications were determined and associated uncertainty in the bias values were included in the overall uncertainty in benchmark keff values. Bias values ranged from 0.0002 ?k to 0.0093 ?k below the experimental value. Overall uncertainties range from ? 0.0002 to ? 0.0011. Major contributors to the overall uncertainty include uncertainty in the support structure and the polyethylene parts. A comparison of experimental, benchmark-model, and MCNP-model keff values is shown in Figure 1. The experimental keff values are derived from the original reactivities reported by the principal experimentalist. The benchmark-model keff values are the experimental keff values adjusted to account for biases that were introduced by removing the support structure and surroundings. The MCNP-model keff values are simply the values found from MCNP calculations using the benchmark specifications and ENDF/B-VI cross-section data. Figure 1. Comparison of Experimental, Benchmark-Model and MCNP-Model keff value. Calculated results for most of the experiments are

Tyler Sumner; J. Blair Briggs; Leland Montierth

2007-05-01T23:59:59.000Z

377

Fatigue of quasi-isotropic composite cylinders under tension-tension loading  

Science Conference Proceedings (OSTI)

A tension fatigue life prediction methodology based on a through-thickness damage accumulation model is used to predict the fatigue failure of composite coupon specimens. Its applicability to thin-walled cylindrical specimens is investigated by comparing the fatigue behavior of composite coupon specimens to that of composite thin-walled cylindrical specimens. AS4/3501-6 graphite-epoxy coupon specimens and thin-walled cylinder specimens with the same layup sequence of (0/+/- 45/90)s were tested under static and fatigue loading conditions. Reasonably good agreement is found between the measured and predicted lives of the coupon specimens. Although the ultimate stresses of coupon and cylindrical specimens are different, it is observed that their fatigue lives at the same percentage of ultimate stress are nearly identical, independent of the coupon edge effect. 23 refs.

Norman, T.L.; Civelek, T.S.; Prucz, J. (West Virginia Univ., Morgantown (United States))

1992-11-01T23:59:59.000Z

378

Rapid estimation of cylinder erosion rates in abrasive dust-laden streams  

Science Conference Proceedings (OSTI)

Erosion yield data for particular combinations of target and projectile materials (via laboratory experiments carried out with a narrow-size distribution over the important range of impact velocities and incidence angles), together with recently developed rational correlations for inertial impaction of suspended particles on a cylinder in high Reynolds number crossflow are used to provide a tractable framework for predicting the erosion rates of, say, heat exchanger tubes immersed in particle-laden streams of combustion products. Universal results are cast in terms of the following accessible parameters: sensitivity of erosion yield to projectile incident velocity and angle, ratio of mean particle size to the threshold size required for impaction on the cylindrical target, spread of the mainstream particle size distribution (here log-normal), and the characteristic slip Reynolds number for the critical size abrasive particle in the mainstream. Applications of the results are illustrated, and several generalizations are discussed.

Rosner, D.E.; Tandon, P.; Labowsky, M.J. [Yale Univ., New Haven, CT (United States)

1995-05-01T23:59:59.000Z

379

Geothermal Casimir phenomena for the sphere-plate and cylinder-plate configurations  

E-Print Network (OSTI)

We investigate the nontrivial interplay between geometry and temperature in the Casimir effect for the sphere-plate and cylinder-plate configurations. At low temperature, the thermal contribution to the Casimir force is dominated by this interplay, implying that standard approximation techniques such as the PFA are inapplicable even in the limit of small surface separation. Thermal fluctuations on scales of the thermal wavelength lead to a delocalization of the thermal force density at low temperatures. As a consequence, the temperature dependence strongly differs from naive expectations. Most prominently, thermal forces can develop non-monotonic behavior below a critical temperature. We perform a comprehensive study of such geothermal phenomena in these Casimir geometries, using analytical and numerical worldline techniques for Dirichlet scalar fluctuations.

Alexej Weber; Holger Gies

2010-03-17T23:59:59.000Z

380

Geothermal Casimir phenomena for the sphere-plate and cylinder-plate configurations  

E-Print Network (OSTI)

We investigate the nontrivial interplay between geometry and temperature in the Casimir effect for the sphere-plate and cylinder-plate configurations. At low temperature, the thermal contribution to the Casimir force is dominated by this interplay, implying that standard approximation techniques such as the PFA are inapplicable even in the limit of small surface separation. Thermal fluctuations on scales of the thermal wavelength lead to a delocalization of the thermal force density at low temperatures. As a consequence, the temperature dependence strongly differs from naive expectations. Most prominently, thermal forces can develop non-monotonic behavior below a critical temperature. We perform a comprehensive study of such geothermal phenomena in these Casimir geometries, using analytical and numerical worldline techniques for Dirichlet scalar fluctuations.

Weber, Alexej

2010-01-01T23:59:59.000Z

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.


381

Determining the temperature field for cylinder symmetrical heat conduction problems in unsteady heat conduction in finite space  

Science Conference Proceedings (OSTI)

This paper proposes to present a new method to calculate unsteady heat conduction for cylinder symmetrical geometry. We will investigate the situation where the temperature field and heat flux created around a heat source placed in finite space are determined. ... Keywords: Garbai's integral equation, Laplace transformation, determining the temperate field, district heating pipes, geothermal producing pipe, heat flux density, heat loss, heat pump

László Garbai; Szabolcs Méhes

2007-05-01T23:59:59.000Z

382

http://rcc.its.psu.edu/hpc Simulation of In-Cylinder Processes in Internal Combustion Engines  

E-Print Network (OSTI)

http://rcc.its.psu.edu/hpc Simulation of In-Cylinder Processes in Internal Combustion Engines into clean and efficient turbulent combustion remains imperative. A single grand challenge was identified in a 2006 DOE workshop on clean and efficient combustion of 21st century transportation fuels [1]: "The

Bjørnstad, Ottar Nordal

383

Evaluation of 2 Percent CrMoWV HP/LP Rotor Gap Forging for Single Cylinder Steam Turbine Use  

Science Conference Proceedings (OSTI)

There has been considerable industry interest in developing a single shaft rotor configuration that uses the same rotor in the high-pressure (HP) as well as the Low Pressure (LP) sections of a steam turbine. This report evaluates an HP/LP rotor forging for single cylinder steam turbines.

1998-11-24T23:59:59.000Z

384

Floodplain/wetland assessment of the effects of construction and operation ofa depleted uranium hexafluoride conversion facility at the Paducah, Kentucky,site.  

SciTech Connect

The U.S. Department of Energy (DOE) Depleted Uranium Hexafluoride (DUF{sub 6}) Management Program evaluated alternatives for managing its inventory of DUF{sub 6} and issued the ''Programmatic Environmental Impact Statement for Alternative Strategies for the Long-Term Management and Use of Depleted Uranium Hexafluoride'' (DUF{sub 6} PEIS) in April 1999 (DOE 1999). The DUF{sub 6} inventory is stored in cylinders at three DOE sites: Paducah, Kentucky; Portsmouth, Ohio; and East Tennessee Technology Park (ETTP), near Oak Ridge, Tennessee. In the Record of Decision for the DUF{sub 6} PEIS, DOE stated its decision to promptly convert the DUF{sub 6} inventory to a more stable chemical form. Subsequently, the U.S. Congress passed, and the President signed, the ''2002 Supplemental Appropriations Act for Further Recovery from and Response to Terrorist Attacks on the United States'' (Public Law No. 107-206). This law stipulated in part that, within 30 days of enactment, DOE must award a contract for the design, construction, and operation of a DUF{sub 6} conversion plant at the Department's Paducah, Kentucky, and Portsmouth, Ohio, sites, and for the shipment of DUF{sub 6} cylinders stored at ETTP to the Portsmouth site for conversion. This floodplain/wetland assessment has been prepared by DOE, pursuant to Executive Order 11988 (''Floodplain Management''), Executive Order 11990 (Protection of Wetlands), and DOE regulations for implementing these Executive Orders as set forth in Title 10, Part 1022, of the ''Code of Federal Regulations'' (10 CFR Part 1022 [''Compliance with Floodplain and Wetland Environmental Review Requirements'']), to evaluate potential impacts to floodplains and wetlands from the construction and operation of a conversion facility at the DOE Paducah site. Reconstruction of the bridge crossing Bayou Creek would occur within the Bayou Creek 100-year floodplain. Replacement of bridge components, including the bridge supports, however, would not be expected to result in measurable long-term changes to the floodplain. Approximately 0.16 acre (0.064 ha) of palustrine emergent wetlands would likely be eliminated by direct placement of fill material within Location A. Some wetlands that are not filled may be indirectly affected by an altered hydrologic regime, due to the proximity of construction, possibly resulting in a decreased frequency or duration of inundation or soil saturation and potential loss of hydrology necessary to sustain wetland conditions. Indirect impacts could be minimized by maintaining a buffer near adjacent wetlands. Wetlands would likely be impacted by construction at Location B; however, placement of a facility in the northern portion of this location would minimize wetland impacts. Construction at Location C could potentially result in impacts to wetlands, however placement of a facility in the southeastern portion of this location may best avoid direct impacts to wetlands. The hydrologic characteristics of nearby wetlands could be indirectly affected by adjacent construction. Executive Order 11990, ''Protection of Wetlands'', requires federal agencies to minimize the destruction, loss, or degradation of wetlands, and to preserve and enhance the natural and beneficial uses of wetlands. DOE regulations for implementing Executive Order 11990 as well as Executive Order 11988, ''Floodplain Management'', are set forth in 10 CFR Part 1022. Mitigation for unavoidable impacts may be developed in coordination with the appropriate regulatory agencies. Unavoidable impacts to wetlands that are within the jurisdiction of the USACE may require a CWA Section 404 Permit, which would trigger the requirement for a CWA Section 401 Water Quality Certification from the Commonwealth of Kentucky. A mitigation plan may be required prior to the initiation of construction. Cumulative impacts to floodplains and wetlands are anticipated to be negligible to minor under the proposed action, in conjunction with the effects of existing conditions and other activities. Habitat disturbance would involve settings commonly found i

Van Lonkhuyzen, R.

2005-09-09T23:59:59.000Z

385

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

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

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

386

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

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

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

387

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

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

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

388

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

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

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

389

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

SciTech Connect

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

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

1985-06-01T23:59:59.000Z

390

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

DOE Green Energy (OSTI)

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

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

1983-01-01T23:59:59.000Z

391

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

E-Print Network (OSTI)

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

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

2008-07-18T23:59:59.000Z

392

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

Science Conference Proceedings (OSTI)

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

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

2012-07-03T23:59:59.000Z

393

ZPR-3 Assembly 6F : A spherical assembly of highly enriched uranium, depleted uranium, aluminum and steel with an average {sup 235}U enrichment of 47 atom %.  

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 6 consisted of six phases, A through F. In each phase a critical configuration was constructed to simulate a very simple shape such as a slab, cylinder or sphere that could be analyzed with the limited analytical tools available in the 1950s. In each case the configuration consisted of a core region of metal plates surrounded by a thick depleted uranium metal reflector. The average compositions of the core configurations were essentially identical in phases A - F. ZPR-3 Assembly 6F (ZPR-3/6F), the final phase of the Assembly 6 program, simulated a spherical core with a thick depleted uranium reflector. ZPR-3/6F was designed as a fast reactor physics benchmark experiment with an average core {sup 235}U enrichment of approximately 47 at.%. Approximately 81.4% of the total fissions in this assembly occur above 100 keV, approximately 18.6% 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. 7 in the Cross Section Evaluation Working Group (CSEWG) Benchmark Specifications and has historically been used as a data validation benchmark assembly. Loading of ZPR-3/6F began in late December 1956, and the experimental measurements were performed in January 1957. The core consisted of highly enriched uranium (HEU) plates, depleted uranium plates, perforated aluminum plates and stainless steel plates loaded into aluminum 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 three columns of 0.125 in.-wide (3.175 mm) HEU plates, three columns of 0.125 in.-wide depleted uranium plates, nine columns of 0.125 in.-wide perforated aluminum plates and one column of stainless steel plates. The maximum length of each column of core material in a drawer was 9 in. (228.6 mm). Because of the goal to produce an approximately spherical core, core fuel and diluent column lengths generally varied between adjacent drawers and frequently within an individual drawer. The axial reflector consisted of depleted uranium plates and blocks loaded in the available space in the front (core) drawers, with the remainder loaded into back drawers behind the front drawers. The radial reflector consisted of blocks of depleted uranium loaded directly into the matrix tubes. The assembly geometry approximated a reflected sphere as closely as the square matrix tubes, the drawers and the shapes of fuel and diluent plates allowed. According to the logbook and loading records for ZPR-3/6F

Lell, R. M.; McKnight, R. D; Schaefer, R. W.; Nuclear Engineering Division

2010-09-30T23:59:59.000Z

394

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 the harsh conditions inside an engine, the Fiber Fabry-Perot Interferometer (FFPI) element was coated with gold and copper. The metal-protected fiber sensor was embedded into a small cut in the metal casing of the spark plug. At first, the sensing element was dipped in liquid gold and cured. Then the gold-coated fiber sensor was electroplated with copper. Finally, the metal-coated fiber sensor was embedded in the spark plug. The spark-plug-embedded FFPI sensor was monitored using a signal conditioning unit. Field tests were carried out in a 3-cylinder automotive engine with a piezoelectric pressure sensor as a reference transducer up to about 3500 rpm. The fiber optic sensor data generally matched those measured by the piezoelectric reference sensor. The use of a Vertical Cavity Surface Emitting Laser (VCSEL) diode as a light source in an FFPI optic sensor system was investigated. Reflected light from the FFPI sensing element was used to measure the optical path difference. With a 1550nm VCSEL as the light source in a 12mm cavity length Fiber Fabry-Perot Interferometer, spectral characteristics were examined to determine the proper combination of dc bias current, modulation current amplitude and modulation frequency. Single VCSEL operation and regular fringe patterns were achieved. The laser tuning was -41.2 GHz/mA and was determined from measurements of the shift in the spectral peak of the VCSEL diode output as a function of dc bias current. By testing the fringe movement as the FFPI sensor was heated, the temperature tuning coefficient for the optical length was determined to be 11 x 10-6 �ºC. The results of these experiments indicate that the use of VCSEL diode as a light source for the FFPI sensor offers a viable alternative to the use of Distributed Feedback (DFB) laser diodes for monitoring at a lower bias current and modulating current amplitude.

Bae, Taehan

2006-08-01T23:59:59.000Z

395

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

SciTech Connect

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

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

2012-01-01T23:59:59.000Z

396

Peak production in an oil depletion model with triangular field profiles  

E-Print Network (OSTI)

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

Stark, Dudley

397

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

Science Conference Proceedings (OSTI)

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

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

2007-07-01T23:59:59.000Z

398

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

SciTech Connect

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

Forsberg, C.W.

1997-07-07T23:59:59.000Z

399

Unsteady flow and heat transfer in a channel with a built-in tandem of rectangular cylinders  

Science Conference Proceedings (OSTI)

The incompressible unsteady flow past a channel with a pair of cylinders of rectangular cross section, placed in tandem normal to the flow, is investigated by numerical simulation. The objective is to evaluate the effect of cylinder separation distance, S/H, on the flow behavior and heat transfer on the channel walls, over a range of Reynolds numbers. Above a critical Reynolds number, these flows bifurcate to a time-periodic self-sustained oscillatory state. The results reveal for S/H = 2.0 three distinct flow patterns: steady flow (Re = 200), time-periodic oscillatory state (400 {le} Re {le} 800), and quasi-periodic oscillatory flow (Re = 1,000). For S/H 600.

Valencia, A. [Universidad de Chile, Santiago (Chile). Dept. de Ingenieria Mecanica

1996-05-10T23:59:59.000Z

400

Comparison of in-cylinder scavenging flows in a two-stroke cycle engine under motored and fired conditions  

Science Conference Proceedings (OSTI)

The in-cylinder flow field of a loop-scavenged, two-stroke engine has been characterized using laser Doppler velocimetry. The radial component of gas velocity was measured along the axis of the cylinder for both motored and fired operation. Measurements were obtained under conditions simulating both crankcase and external blower driven scavenging. Mean profiles of the radial velocity show marked differences in the global flow structure between motored and fired operation for both scavenging methods. These differences persist throughout the scavenging process and survive compression of the fresh charge. Root mean square (rms) velocity fluctuations near TDC were also determined, and significant differences between motored and fired operation are observed. The rms fluctuations are found to correlate well with the mean shear during compression.

Miles, P.C.; Green, R.M.; Witze, P.O.

1994-06-01T23:59:59.000Z

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.


401

2-dimensional numerical simulations for the wave-wake-body interactions around circular cylinders in motion near seabed  

E-Print Network (OSTI)

The 2-dimensional, viscous and incompressible flow past a circular cylinder is investigated by solving the Navier-stokes equation. solved using CFD (Computational Fluid These equations are numerically Dynamics) methods on an overlapping multiblock 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 experimental and numerical data, which confirmed the correctness and accuracy of the present method. The numerical computations successfully captured many important flow features for the various types of flow conditions. The present program code proves to be a powerful tool, by enabling the study of numerous interesting and useful research topics related to fluid-structure interactions, thereby, it will contribute to a better design of offshore structures.

Tavassoli, Armin

1999-01-01T23:59:59.000Z

402

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

DOE Green Energy (OSTI)

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

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

1977-01-01T23:59:59.000Z

403

Electrostatic Patch Effect in Cylindrical Geometry. I. Potential and Energy between Slightly Non-Coaxial Cylinders  

E-Print Network (OSTI)

We study the effect of any uneven voltage distribution on two close cylindrical conductors with parallel axes that are slightly shifted in the radial and by any length in the axial direction. The investigation is especially motivated by certain precision measurements, such as the Satellite Test of the Equivalence Principle (STEP). By energy conservation, the force can be found as the energy gradient in the vector of the shift, which requires determining potential distribution and energy in the gap. The boundary value problem for the potential is solved, and energy is thus found to the second order in the small transverse shift, and to lowest order in the gap to cylinder radius ratio. The energy consists of three parts: the usual capacitor part due to the uniform potential difference, the one coming from the interaction between the voltage patches and the uniform voltage difference, and the energy of patch interaction, entirely independent of the uniform voltage. Patch effect forces and torques in the cylindri...

Ferroni, Valerio

2010-01-01T23:59:59.000Z

404

Electrostatic Patch Effect in Cylindrical Geometry. I. Potential and Energy between Slightly Non-Coaxial Cylinders  

E-Print Network (OSTI)

We study the effect of any uneven voltage distribution on two close cylindrical conductors with parallel axes that are slightly shifted in the radial and by any length in the axial direction. The investigation is especially motivated by certain precision measurements, such as the Satellite Test of the Equivalence Principle (STEP). By energy conservation, the force can be found as the energy gradient in the vector of the shift, which requires determining potential distribution and energy in the gap. The boundary value problem for the potential is solved, and energy is thus found to the second order in the small transverse shift, and to lowest order in the gap to cylinder radius ratio. The energy consists of three parts: the usual capacitor part due to the uniform potential difference, the one coming from the interaction between the voltage patches and the uniform voltage difference, and the energy of patch interaction, entirely independent of the uniform voltage. Patch effect forces and torques in the cylindrical configuration are derived and analyzed in the next two parts of this work.

Valerio Ferroni; Alexander Silbergleit

2010-09-16T23:59:59.000Z

405

Hydrogen Cylinder Storage Array Explosion Evaluations at the High Flux Isotope Reactor  

DOE Green Energy (OSTI)

The safety analysis for a recently-installed cold neutron source at the High Flux Isotope Reactor (HFIR) involved evaluation of potential explosion consequences from accidental hydrogen jet releases that could occur from an array of hydrogen cylinders. The scope of the safety analysis involved determination of the release rate of hydrogen, the total quantity of hydrogen assumed to be involved in the explosion, the location of an ignition point or center of the explosion from receptors of interest, and the peak overpressure at the receptors. To evaluate the total quantity of hydrogen involved in the explosion, a 2D model was constructed of the jet concentration and a radial-axial integral over the jet cloud from the centerline to the flammability limit of 4% was used to determine the hydrogen mass to be used as a source term. The location of the point source was chosen as the peak of the jet centerline concentration profile. Consequences were assessed using a combination of three methods for estimating local overpressure as a function of explosion source strength and distance: the Baker-Strehlow method, the TNT-equivalence method, and the TNO method. Results from the explosions were assessed using damage estimates in screening tables for buildings and industrial equipment.

Cook, David Howard [ORNL; Griffin, Frederick P [ORNL; Hyman III, Clifton R [ORNL

2010-01-01T23:59:59.000Z

406

Applications of Nuclear Resonance Fluorescence  

Science Conference Proceedings (OSTI)

Nuclear Resonance Fluorescence (NRF) has the potential of addressing a wide variety of applications, which require isotopic and/or elemental information about a sample. We have investigated a variety of non-proliferation applications that may be addressed by NRF. From these applications, we have selected two, measuring uranium enrichment in UF6 cylinders and material verification in dismantlement, to investigate in more detail. Analytical models have been developed to evaluate these applications, and test measurements have been conducted to validate those models. We found that it is unlikely with current technology to address the requirements for UF6 cylinder enrichment measurements. In contrast, NRF is a very promising approach for material verification for dismantlement.

Warren, Glen A.; Detwiler, Rebecca S.; Peplowski, Patrick N.

2010-11-11T23:59:59.000Z

407

The Charge Induced on a Conducting Cylinder by a Point Charge and Its Application to the Measurement of Charge on Precipitation  

Science Conference Proceedings (OSTI)

The solution of the electrostatic boundary value problem for a point charge inside an infinite cylinder is applied to sensors employed in the measurement of charge on precipitation. With these devices the charge induced on a cylindrical segment ...

Andrew J. Weinheimer

1988-04-01T23:59:59.000Z

408

Robust design evolution and impact of In-Cylinder Pressure Sensors to combustion control and optimization : a systems and strategy perspective  

E-Print Network (OSTI)

In-Cylinder Pressure Sensors (ICPS) today are close to satisfying the robustness, performance and cost requirements for application to closed loop control and monitoring of production automotive engines. Using the Robust ...

Eftekhari Shahroudi, Kamran, 1965-

2008-01-01T23:59:59.000Z

409

Fig. 1. Artist's concept of the 1-D parabolic cylinder reflector. The re-flector has a parabolic shape in the short dimension and a flat profile in  

E-Print Network (OSTI)

Fig. 1. Artist's concept of the 1-D parabolic cylinder reflector. The re- flector has a parabolic [1]. A stationary linear parabolic reflector with a diameter of 1.6 m and a length of 2 m would

Ruf, Christopher

410

Modeling the performance of the piston ring-pack with consideration of non-axisymmetric characteristics of the power cylinder system in internal combustion engines  

E-Print Network (OSTI)

The performance of the piston ring-pack is directly associated with the friction, oil consumption, wear, and blow-by in internal combustion engines. Because of non-axisymmetric characteristics of the power cylinder system, ...

Liu, Liang, 1971-

2005-01-01T23:59:59.000Z

411

Charge Depleting:  

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

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

412

Charge Depleting:  

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

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

413

Charge Depleting:  

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

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

414

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

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

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

415

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

Science Conference Proceedings (OSTI)

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

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

2009-02-26T23:59:59.000Z

416

Summary of the Preliminary Analysis of Savannah River Depleted Uranium Trioxide  

SciTech Connect

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

NSTec Environmental Management

2010-10-13T23:59:59.000Z

417

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

E-Print Network (OSTI)

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

unknown authors

1999-01-01T23:59:59.000Z

418

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

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

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

419

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

Science Conference Proceedings (OSTI)

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

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

2007-01-22T23:59:59.000Z

420

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

SciTech Connect

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

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

2011-01-20T23:59:59.000Z

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.


421

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

E-Print Network (OSTI)

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

Stripling, Hayes Franklin

2013-08-01T23:59:59.000Z

422

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

Science Conference Proceedings (OSTI)

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

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

2009-11-01T23:59:59.000Z

423

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

SciTech Connect

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

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

1997-07-07T23:59:59.000Z

424

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

Science Conference Proceedings (OSTI)

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

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

2012-04-04T23:59:59.000Z

425

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

DOE Green Energy (OSTI)

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

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

2011-09-01T23:59:59.000Z

426

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

E-Print Network (OSTI)

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

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

1998-01-01T23:59:59.000Z

427

Detection of illicit HEU production in gaseous centrifuge enrichment plants using neutron counting techniques on product cylinders  

SciTech Connect

Innovative and novel safeguards approaches are needed for nuclear energy to meet global energy needs without the threat of nuclear weapons proliferation. Part of these efforts will include creating verification techniques that can monitor uranium enrichment facilities for illicit production of highly-enriched uranium (HEU). Passive nondestructive assay (NDA) techniques will be critical in preventing illicit HEU production because NDA offers the possibility of continuous and unattended monitoring capabilities with limited impact on facility operations. Gaseous centrifuge enrichment plants (GCEP) are commonly used to produce low-enriched uranium (LEU) for reactor fuel. In a GCEP, gaseous UF{sub 6} spins at high velocities in centrifuges to separate the molecules containing {sup 238}U from those containing the lighter {sup 235}U. Unfortunately, the process for creating LEU is inherently the same as HEU, creating a proliferation concern. Insuring that GCEPs are producing declared enrichments poses many difficult challenges. In a GCEP, large cascade halls operating thousands of centrifuges work together to enrich the uranium which makes effective monitoring of the cascade hall economically prohibitive and invasive to plant operations. However, the enriched uranium exiting the cascade hall fills product cylinders where the UF{sub 6} gas sublimes and condenses for easier storage and transportation. These product cylinders hold large quantities of enriched uranium, offering a strong signal for NDA measurement. Neutrons have a large penetrability through materials making their use advantageous compared to gamma techniques where the signal is easily attenuated. One proposed technique for detecting HEU production in a GCEP is using neutron coincidence counting at the product cylinder take off stations. This paper discusses findings from Monte Carlo N-Particle eXtended (MCNPX) code simulations that examine the feasibility of such a detector.

Freeman, Corey R [Los Alamos National Laboratory; Geist, William H [Los Alamos National Laboratory

2010-01-01T23:59:59.000Z

428

High-speed four-color infrared digital imaging for study in-cylinder processes in a di diesel engine  

SciTech Connect

The study was to investigate in-cylinder events of a direct injection-type diesel engine by using a new high-speed infrared (IR) digital imaging systems for obtaining information that was difficult to achieve by the conventional devices. For this, a new high-speed-dual-spectra infrared digital imaging system was developed to simultaneously capture two geometrically identical (in respective spectral) sets of IR images having discrete digital information in a (64x64) matrix at rates as high as over 1,800 frames/sec each with exposure period as short as 20 usec. At the same time, a new advanced four-color IR imaging system was constructed. The first two sets of spectral data were the radiation from water vapor emission bands to compute the distributions of temperature and specie in the gaseous mixture and the remaining two sets of data were to find the instantaneous temperature distribution over the cylinder surface. More than eight reviewed publications have been produced to report many new findings including: Distributions of Water Vapor and Temperature in a Flame; End Gas Images Prior to Onset of Knock; Effect of MTBE on Diesel Combustion; Impact of Oxygen Enrichment on In-cylinder Reactions; Spectral IR Images of Spray Plume; Residual Gas Distribution; Preflame Reactions in Diesel Combustion; Preflame Reactions in the End Gas of an SI Engine; Postflame Oxidation; and Liquid Fuel Layers during Combustion in an SI Engine. In addition, some computational analysis of diesel combustion was performed using KIVA-II program in order to compare results from the prediction and the measurements made using the new IR imaging diagnostic tool.

Rhee, K.T.

1995-07-12T23:59:59.000Z

429

Development and Testing of a 6-Cylinder HCCI Engine for Distributed Generation  

DOE Green Energy (OSTI)

This paper describes the technical approach for converting a Caterpillar 3406 natural gas spark ignited engine into HCCI mode. The paper describes all stages of the process, starting with a preliminary analysis that determined that the engine can be operated by preheating the intake air with a heat exchanger that recovers energy from the exhaust gases. This heat exchanger plays a dual role, since it is also used for starting the engine. For start-up, the heat exchanger is preheated with a natural gas burner. The engine is therefore started in HCCI mode, avoiding the need to handle the potentially difficult transition from SI or diesel mode to HCCI. The fueling system was modified by replacing the natural gas carburetor with a liquid petroleum gas (LPG) carburetor. This modification sets an upper limit for the equivalence ratio at {phi} {approx} 0.4, which is ideal for HCCI operation and guarantees that the engine will not fail due to knock. Equivalence ratio can be reduced below 0.4 for low load operation with an electronic control valve. Intake boosting has been a challenge, as commercially available turbochargers are not a good match for the engine, due to the low HCCI exhaust temperature. Commercial introduction of HCCI engines for stationary power will therefore require the development of turbochargers designed specifically for this mode of operation. Considering that no appropriate off-the-shelf turbocharger for HCCI engines exists at this time, we are investigating mechanical supercharging options, which will deliver the required boost pressure (3 bar absolute intake) at the expense of some reduction in the output power and efficiency. An appropriate turbocharger can later be installed for improved performance when it becomes available or when a custom turbocharger is developed. The engine is now running in HCCI mode and producing power in an essentially naturally aspirated mode. Current work focuses on developing an automatic controller for obtaining consistent combustion in the 6 cylinders. The engine will then be tested for 1000 hours to demonstrate durability. This paper presents intermediate progress towards development of an HCCI engine for stationary power generation and next steps towards achieving the project goals.

Flowers, D L; Martinez-Frias, J; Espinosa-Loza, F; Killingsworth, N; Aceves, S M; Dibble, R; Kristic, M; Bining, A

2005-07-12T23:59:59.000Z

430

Standard practice for evaluating and qualifying oil field and refinery corrosion inhibitors using the rotating cylinder electrode  

E-Print Network (OSTI)

1.1 This practice covers a generally accepted procedure to use the rotating cylinder electrode (RCE) for evaluating corrosion inhibitors for oil field and refinery applications in defined flow conditions. 1.2 The values stated in SI units are to be regarded as the standard. The values given in parentheses are for information only. 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

2006-01-01T23:59:59.000Z

431

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

Science Conference Proceedings (OSTI)

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

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

2011-02-01T23:59:59.000Z

432

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

E-Print Network (OSTI)

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

Keast, Craig L.

433

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

SciTech Connect

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

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

2012-07-01T23:59:59.000Z

434

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

SciTech Connect

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

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

2009-03-01T23:59:59.000Z

435

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

E-Print Network (OSTI)

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

Liolios, T E

1999-01-01T23:59:59.000Z

436

In-cylinder pressure characteristics of a CI engine using blends of diesel fuel and methyl esters of beef tallow  

Science Conference Proceedings (OSTI)

A Cummins N14-410 diesel engine was operated on 12 fuels produced by blending methyl tallowate, methyl soyate, and ethanol with no. 2 diesel fuel. Engine in-cylinder pressure data were used to evaluate engine performance. Peak cylinder pressures for each fuel blend at all engine speeds were lower than peak pressure for diesel fuel with the exception of the 80% diesel, 13% methyl tallowate, and 7% ethanol; and the 80% diesel, 6.5% methyl tallowate, 6.5% methyl soyate and 7% ethanol blends. The indicated mean effective pressure (IMEP) values for all fuel blends were less than for diesel fuel. The differences in IMEP values correlated with differences in power output of the engine. Similarly, maximum rates of pressure rise for most fuel blends were less than for diesel fuel. It was concluded that the fuel blends used in this study would have no detrimental long-term effects on engine performance, wear, and knock. 6 refs., 4 figs., 7 tabs.

Ali, Y.; Hanna, M.A.; Borg, J.E. [Univ. of Nebraska, Lincoln, NE (United States)

1996-05-01T23:59:59.000Z

437

X-ray diffraction study of residual stresses in metal-matrix composite-jacketed steel cylinders subjected to internal pressure. Final report  

Science Conference Proceedings (OSTI)

The study of aluminum/silicon carbide metal matrix composite (MMC)-jacketed steel structural components was made because of their light weight and high stiffness. Steel 'liner' cylinders were wrapped with MMC 'jackets' with an all-hoop layup and put through various degrees of hydraulic autofrettage and thermal soak. In this report, the results from our x-ray diffraction residual stress measurements on cylinders using a position-sensitive scintillation detection system are discussed. Our experimental results are compared with theoretical predictions from a model based on the elastic-plastic analysis of a thick-walled cylinder subjected to internal pressure. Interpretation of the interference effect caused by the MMC jacket on the steel liner is also discussed.

Lee, S.L.; Doxbeck, M.; Capsimalis, G.

1992-03-01T23:59:59.000Z

438

ZPR-3 Assembly 12 : A cylindrical assembly of highly enriched uranium, depleted uranium and graphite with an average {sup 235}U enrichment of 21 atom %.  

Science Conference Proceedings (OSTI)

Over a period of 30 years, more than a hundred Zero Power Reactor (ZPR) critical assemblies were constructed at Argonne National Laboratory. The ZPR facilities, ZPR-3, ZPR-6, ZPR-9 and ZPPR, were all fast critical assembly facilities. The ZPR critical assemblies were constructed to support fast reactor development, but data from some of these assemblies are also well suited for nuclear data validation and to form the basis for criticality safety benchmarks. A number of the Argonne ZPR/ZPPR critical assemblies have been evaluated as ICSBEP and IRPhEP benchmarks. Of the three classes of ZPR assemblies, engineering mockups, engineering benchmarks and physics benchmarks, the last group tends to be most useful for criticality safety. Because physics benchmarks were designed to test fast reactor physics data and methods, they were as simple as possible in geometry and composition. The principal fissile species was {sup 235}U or {sup 239}Pu. Fuel enrichments ranged from 9% to 95%. Often there were only one or two main core diluent materials, such as aluminum, graphite, iron, sodium or stainless steel. The cores were reflected (and insulated from room return effects) by one or two layers of materials such as depleted uranium, lead or stainless steel. Despite their more complex nature, a small number of assemblies from the other two classes would make useful criticality safety benchmarks because they have features related to criticality safety issues, such as reflection by soil-like material. ZPR-3 Assembly 12 (ZPR-3/12) was designed as a fast reactor physics benchmark experiment with an average core {sup 235}U enrichment of approximately 21 at.%. Approximately 68.9% of the total fissions in this assembly occur above 100 keV, approximately 31.1% 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. 9 in the Cross Section Evaluation Working Group (CSEWG) Benchmark Specifications and has historically been used as a data validation benchmark assembly. Loading of ZPR-3 Assembly 12 began in late Jan. 1958, and the Assembly 12 program ended in Feb. 1958. The core consisted of highly enriched uranium (HEU) plates, depleted uranium plates and graphite 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, seven columns of 0.125 in.-wide depleted uranium plates and seven columns of 0.125 in.-wide graphite plates. The length of each column was 9 in. (228.6 mm) in each half of the core. The graphite plates were included to produce a softer neutron spectrum that would be more character