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Note: This page contains sample records for the topic "reduce shell package" 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

Package Equivalent Reactor Networks as Reduced Order Models for...  

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

Package Equivalent Reactor Networks as Reduced Order Models for Use with CAPE-Open Compliant Simulations Description The Department of Energy's (DOE) National Energy Technology...

2

Double-shell tank waste retrieval survey package  

SciTech Connect

Westinghouse Hanford Company is seeking industry solutions to underground double-shell tank waste retrieval at the Hanford Site located in southeastern Washington. This is not a request for proposals; it is a request for information to facilitate continued discussion. Westinghouse Hanford Company will not reimburse any costs incurred for providing the information requested.

Berglin, E.J.

1995-12-01T23:59:59.000Z

3

Contaminant Release Data Package for Residual Waste in Single-Shell Hanford Tanks  

Science Conference Proceedings (OSTI)

The Hanford Federal Facility Agreement and Consent Order requires that a Resource Conservation and Recovery Act (RCRA) Facility Investigation report be submitted to the Washington State Department of Ecology. The RCRA Facility Investigation report will provide a detailed description of the state of knowledge needed for tank farm performance assessments. This data package provides detailed technical information about contaminant release from closed single-shell tanks necessary to support the RCRA Facility Investigation report. It was prepared by Pacific Northwest National Laboratory (PNNL) for CH2M HILL Hanford Group, Inc., which is tasked by the U.S. Department of Energy (DOE) with tank closure. This data package is a compilation of contaminant release rate data for residual waste in the four Hanford single-shell tanks (SSTs) that have been tested (C-103, C-106, C-202, and C-203). The report describes the geochemical properties of the primary contaminants of interest from the perspective of long-term risk to groundwater (uranium, technetium-99, iodine-129, chromium, transuranics, and nitrate), the occurrence of these contaminants in the residual waste, release mechanisms from the solid waste to water infiltrating the tanks in the future, and the laboratory tests conducted to measure release rates.

Deutsch, William J.; Cantrell, Kirk J.; Krupka, Kenneth M.

2007-12-01T23:59:59.000Z

4

Geochemical Processes Data Package for the Vadose Zone in the Single-Shell Tank Waste Management Areas at the Hanford Site  

SciTech Connect

This data package discusses the geochemistry of vadose zone sediments beneath the single-shell tank farms at the U.S. Department of Energy’s (DOE’s) Hanford Site. The purpose of the report is to provide a review of the most recent and relevant geochemical process information available for the vadose zone beneath the single-shell tank farms and the Integrated Disposal Facility. Two companion reports to this one were recently published which discuss the geology of the farms (Reidel and Chamness 2007) and groundwater flow and contamination beneath the farms (Horton 2007).

Cantrell, Kirk J.; Zachara, John M.; Dresel, P. Evan; Krupka, Kenneth M.; Serne, R. Jeffrey

2007-09-28T23:59:59.000Z

5

Recharge Data Package for Hanford Single-Shell Tank Waste Management Areas  

Science Conference Proceedings (OSTI)

Pacific Northwest National Laboratory (PNNL) assists CH2M HILL Hanford Group, Inc., in its preparation of the Resource Conservation and Recovery Act (RCRA) Facility Investigation report. One of the PNNL tasks is to use existing information to estimate recharge rates for past and current conditions as well as future scenarios involving cleanup and closure of tank farms. The existing information includes recharge-relevant data collected during activities associated with a host of projects, including those of RCRA, the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA), the CH2M HILL Tank Farm Vadose Zone Project, and the PNNL Remediation and Closure Science Project. As new information is published, the report contents can be updated. The objective of this data package was to use published data to provide recharge estimates for the scenarios being considered in the RCRA Facility Investigation. Recharge rates were estimated for areas that remain natural and undisturbed, areas where the vegetation has been disturbed, areas where both the vegetation and the soil have been disturbed, and areas that are engineered (e.g., surface barrier). The recharge estimates supplement the estimates provided by PNNL researchers in 2006 for the Hanford Site using additional field measurements and model analysis using weather data through 2006.

Fayer, Michael J.; Keller, Jason M.

2007-09-24T23:59:59.000Z

6

Geochemical Characterization Data Package for the Vadose Zone in the Single-Shell Tank Waste Management Areas at the Hanford Site  

SciTech Connect

This data package discusses the geochemistry of vadose zone sediments beneath the single-shell tank (SST) farms at the U.S. Department of Energy’s (DOE’s) Hanford Site. The purpose of the report is to provide a review of the most recent and relevant geochemical information available for the vadose zone beneath the SST farms and the Integrated Disposal Facility (IDF).

Cantrell, Kirk J.; Brown, Christopher F.; Serne, R. Jeffrey; Krupka, Kenneth M.

2008-01-07T23:59:59.000Z

7

Reduced Pressure Electron Beam Welding Evaluation Activities on a Ni-Cr-Mo Alloy for Nuclear Waste Packages  

SciTech Connect

The current waste package design for the proposed repository at Yucca Mountain Nevada, USA, employs gas tungsten arc welding (GTAW) in fabricating the waste packages. While GTAW is widely used in industry for many applications, it requires multiple weld passes. By comparison, single-pass welding methods inherently use lower heat input than multi-pass welding methods which results in lower levels of weld distortion and also narrower regions of residual stresses at the weld TWI Ltd. has developed a Reduced Pressure Electron Beam (RPEB) welding process which allows EB welding in a reduced pressure environment ({le} 1 mbar). As it is a single-pass welding technique, use of RPEB welding could (1) achieve a comparable or better materials performance and (2) lead to potential cost savings in the waste package manufacturing as compared to GTAW. Results will be presented on the initial evaluation of the RPEB welding on a Ni-Cr-Mo alloy (a candidate alloy for the Yucca Mountain waste packages) in the areas of (a) design and manufacturing simplifications, (b) material performance and (c) weld reliability.

Wong, F; Punshon, C; Dorsch, T; Fielding, P; Richard, D; Yang, N; Hill, M; DeWald, A; Rebak, R; Day, S; Wong, L; Torres, S; McGregor, M; Hackel, L; Chen, H-L; Rankin, J

2003-09-11T23:59:59.000Z

8

Radioactive waste disposal package  

DOE Patents (OSTI)

A radioactive waste disposal package comprising a canister for containing vitrified radioactive waste material and a sealed outer shell encapsulating the canister. A solid block of filler material is supported in said shell and convertible into a liquid state for flow into the space between the canister and outer shell and subsequently hardened to form a solid, impervious layer occupying such space.

Lampe, Robert F. (Bethel Park, PA)

1986-01-01T23:59:59.000Z

9

Data Package for Past and Current Groundwater Flow and Contamination beneath Single-Shell Tank Waste Management Areas  

Science Conference Proceedings (OSTI)

This appendix summarizes historic and recent groundwater data collected from the uppermost aquifer beneath the 200 East and 200 West Areas. Although the area of interest is the Hanford Site Central Plateau, most of the information discussed in this appendix is at the scale of individual single-shell tank waste management areas. This is because the geologic, and thus the hydraulic, properties and the geochemical properties (i.e., groundwater composition) are different in different parts of the Central Plateau.

Horton, Duane G.

2007-03-16T23:59:59.000Z

10

Package Equivalent Reactor Networks as Reduced Order Models for Use with CAPE-OPEN Compliant Simulation  

SciTech Connect

Engineering simulations of coal gasifiers are typically performed using computational fluid dynamics (CFD) software, where a 3-D representation of the gasifier equipment is used to model the fluid flow in the gasifier and source terms from the coal gasification process are captured using discrete-phase model source terms. Simulations using this approach can be very time consuming, making it difficult to imbed such models into overall system simulations for plant design and optimization. For such system-level designs, process flowsheet software is typically used, such as Aspen Plus® [1], where each component where each component is modeled using a reduced-order model. For advanced power-generation systems, such as integrated gasifier/gas-turbine combined-cycle systems (IGCC), the critical components determining overall process efficiency and emissions are usually the gasifier and combustor. Providing more accurate and more computationally efficient reduced-order models for these components, then, enables much more effective plant-level design optimization and design for control. Based on the CHEMKIN-PRO and ENERGICO software, we have developed an automated methodology for generating an advanced form of reduced-order model for gasifiers and combustors. The reducedorder model offers representation of key unit operations in flowsheet simulations, while allowing simulation that is fast enough to be used in iterative flowsheet calculations. Using high-fidelity fluiddynamics models as input, Reaction Design’s ENERGICO® [2] software can automatically extract equivalent reactor networks (ERNs) from a CFD solution. For the advanced reduced-order concept, we introduce into the ERN a much more detailed kinetics model than can be included practically in the CFD simulation. The state-of-the-art chemistry solver technology within CHEMKIN-PRO allows that to be accomplished while still maintaining a very fast model turn-around time. In this way, the ERN becomes the basis for high-fidelity kinetics simulation, while maintaining the spatial information derived from the geometrically faithful CFD model. The reduced-order models are generated in such a way that they can be easily imported into a process flowsheet simulator, using the CAPE-OPEN architecture for unit operations. The ENERGICO/CHEMKIN-PRO software produces an ERN-definition file that is read by a dynamically linked library (DLL) that can be easily linked to any CAPE-OPEN compliant software. The plug-in unitoperation module has been successfully demonstrated for complex ERNs of coal gasifiers, using both Aspen Plus and COFE process flowsheet simulators through this published CAPE-OPEN interface.

Meeks, E.; Chou, C. -P.; Garratt, T.

2013-03-31T23:59:59.000Z

11

Package downsizing: is it ethical?  

Science Conference Proceedings (OSTI)

Package downsizing is a practice where the package content is reduced without changing the package or the price of the product. In a market that is defined by ‘hyper-competition,’ package downsizing is often practiced by marketers to effect ... Keywords: Downsizing, Ethical, Package, Principle of equivalence

Omprakash K. Gupta; Sudhir Tandon; Sukumar Debnath; Anna S. Rominger

2007-04-01T23:59:59.000Z

12

Soy Package  

Science Conference Proceedings (OSTI)

Contains four (4) titles. Soy Package Food Science Health Nutrition Biochemistry Processing Soybeans Food Science & Technology Health - Nutrition - Biochemistry Processing Value Packages This Value Package includes:

13

Biodiesel Package  

Science Conference Proceedings (OSTI)

A special collection of books and CD-ROMS on the topic of biodiesel. Biodiesel Package Biofuels and Bioproducts and Biodiesel Biofuels - Bioproducts Value Packages AOCS Press This Value Package includes: ...

14

Borehole Data Package for RCRA Well 299-W22-47 at Single-Shell Tank Waste Management Area S-SX, Hanford Site, Washington  

SciTech Connect

One new Resource Conservation and Recovery Act (RCRA) groundwater assessment well was installed at single-shell tank Waste Management Area (WMA) S-SX in fiscal year (FY) 2005 to fulfill commitments for well installations proposed in Hanford Federal Facility Agreement and Consent Order, Milestone M-24-57 (2004). The need for the new well, well 299-W22-47, was identified during a data quality objectives process for establishing a RCRA/ Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA)/Atomic Energy Act (AEA) integrated 200 West and 200 East Area Groundwater Monitoring Network. This document provides a compilation of all available geologic data, spectral gamma ray logs, hydrogeologic data and well information obtained during drilling, well construction, well development, pump installation, aquifer testing, and sample collection/analysis activities. Appendix A contains the Well Summary Sheets, the Well Construction Summary Report, the geologist's Borehole Log, well development and pump installation records, and well survey results. Appendix B contains analytical results from groundwater samples collected during drilling. Appendix C contains complete spectral gamma ray logs and borehole deviation surveys.

Horton, Duane G.; Chamness, Mickie A.

2006-04-17T23:59:59.000Z

15

Multiple shell fusion targets  

DOE Patents (OSTI)

Multiple shell fusion targets for use with electron beam and ion beam implosion systems are described. The multiple shell targets are of the low-power type and use a separate relatively low Z, low density ablator at large radius for the outer shell, which reduces the focusing and power requirements of the implosion system while maintaining reasonable aspect ratios. The targets use a high Z, high density pusher shell placed at a much smaller radius in order to obtain an aspect ratio small enough to protect against fluid instability. Velocity multiplication between these shells further lowers the power requirements. Careful tuning of the power profile and intershell density results in a low entropy implosion which allows breakeven at low powers. For example, with ion beams as a power source, breakeven at 10-20 Terrawatts with 10 MeV alpha particles for imploding a multiple shell target can be accomplished.

Lindl, J.D.; Bangerter, R.O.

1975-10-31T23:59:59.000Z

16

The reduction of packaging waste  

Science Conference Proceedings (OSTI)

Nationwide, packaging waste comprises approximately one third of the waste being sent to our solid waste landfills. These wastes range from product and shipping containers made from plastic, glass, wood, and corrugated cardboard to packaging fillers and wraps made from a variety of plastic materials such as shrink wrap and polystyrene peanuts. The amount of packaging waste generated is becoming an important issue for manufacturers, retailers, and consumers. Elimination of packaging not only conserves precious landfill space, it also reduces consumption of raw materials and energy, all of which result in important economic and environmental benefits. At the US Department of Energy-Richland Field Office's (DOE-RL) Hanford Site as well as other DOE sites the generation of packaging waste has added importance. By reducing the amount of packaging waste, DOE also reduces the costs and liabilities associated with waste handling, treatment, storage, and disposal.

Raney, E.A.; McCollom, M.; Hogan, J.

1993-04-01T23:59:59.000Z

17

The reduction of packaging waste  

Science Conference Proceedings (OSTI)

Nationwide, packaging waste comprises approximately one third of the waste being sent to our solid waste landfills. These wastes range from product and shipping containers made from plastic, glass, wood, and corrugated cardboard to packaging fillers and wraps made from a variety of plastic materials such as shrink wrap and polystyrene peanuts. The amount of packaging waste generated is becoming an important issue for manufacturers, retailers, and consumers. Elimination of packaging not only conserves precious landfill space, it also reduces consumption of raw materials and energy, all of which result in important economic and environmental benefits. At the US Department of Energy-Richland Field Office`s (DOE-RL) Hanford Site as well as other DOE sites the generation of packaging waste has added importance. By reducing the amount of packaging waste, DOE also reduces the costs and liabilities associated with waste handling, treatment, storage, and disposal.

Raney, E.A.; McCollom, M.; Hogan, J.

1993-04-01T23:59:59.000Z

18

Lipid Analysis Package  

Science Conference Proceedings (OSTI)

A Lipid Value package of 5 different books. Lipid Analysis Package Methods and Analyses Methods - Analyses Books Value Packages Methods - Analyses Books Methods This Value Package includes:   ...

19

Optimal segmentation and packaging process  

DOE Patents (OSTI)

A process for improving packaging efficiency uses three dimensional, computer simulated models with various optimization algorithms to determine the optimal segmentation process and packaging configurations based on constraints including container limitations. The present invention is applied to a process for decontaminating, decommissioning (D&D), and remediating a nuclear facility involving the segmentation and packaging of contaminated items in waste containers in order to minimize the number of cuts, maximize packaging density, and reduce worker radiation exposure. A three-dimensional, computer simulated, facility model of the contaminated items are created. The contaminated items are differentiated. The optimal location, orientation and sequence of the segmentation and packaging of the contaminated items is determined using the simulated model, the algorithms, and various constraints including container limitations. The cut locations and orientations are transposed to the simulated model. The contaminated items are actually segmented and packaged. The segmentation and packaging may be simulated beforehand. In addition, the contaminated items may be cataloged and recorded.

Kostelnik, Kevin M. (Idaho Falls, ID); Meservey, Richard H. (Idaho Falls, ID); Landon, Mark D. (Idaho Falls, ID)

1999-01-01T23:59:59.000Z

20

Shell sort  

Science Conference Proceedings (OSTI)

... Probably "Computer Assembler by General Electric". Don Shell worked in the same building, but he was manager of the Systems Analysts. ...

2013-05-08T23:59:59.000Z

Note: This page contains sample records for the topic "reduce shell package" 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

Hollow spherical shell manufacture  

DOE Patents (OSTI)

A process for making a hollow spherical shell of silicate glass composition in which an aqueous suspension of silicate glass particles and an immiscible liquid blowing agent is placed within the hollow spherical cavity of a porous mold. The mold is spun to reduce effective gravity to zero and to center the blowing agent, while being heated so as to vaporize the immiscible liquid and urge the water carrier of the aqueous suspension to migrate into the body of the mold, leaving a green shell compact deposited around the mold cavity. The green shell compact is then removed from the cavity, and is sintered for a time and a temperature sufficient to form a silicate glass shell of substantially homogeneous composition and uniform geometry.

O' Holleran, Thomas P. (Belleville, MI)

1991-01-01T23:59:59.000Z

22

Hollow spherical shell manufacture  

DOE Patents (OSTI)

A process is disclosed for making a hollow spherical shell of silicate glass composition in which an aqueous suspension of silicate glass particles and an immiscible liquid blowing agent is placed within the hollow spherical cavity of a porous mold. The mold is spun to reduce effective gravity to zero and to center the blowing agent, while being heated so as to vaporize the immiscible liquid and urge the water carrier of the aqueous suspension to migrate into the body of the mold, leaving a green shell compact deposited around the mold cavity. The green shell compact is then removed from the cavity, and is sintered for a time and a temperature sufficient to form a silicate glass shell of substantially homogeneous composition and uniform geometry. 3 figures.

O' Holleran, T.P.

1991-11-26T23:59:59.000Z

23

Work Package Templates  

Science Conference Proceedings (OSTI)

Work Package Templates provides fossil plant maintenance personnel with assorted inspection, minor repair or overhaul templates for various pieces of plant equipment. This guide will assist plant maintenance personnel in improving the efficiency, reliability and reducing the maintenance costs for associated with maintenance on selected pieces of equipment.

2007-02-15T23:59:59.000Z

24

Functional Foods Package  

Science Conference Proceedings (OSTI)

Contains five (5) titles regarding functional foods. Functional Foods Package Health - Nutrition - Biochemistry Value Packages Nutrition Health Food Science Biochemistry This Value Package includes: ...

25

Packaging and Labeling  

Science Conference Proceedings (OSTI)

Packaging and Labeling. The Fair Packaging and Labeling Act (FPLA) and other Federal laws and regulations govern the ...

2013-05-17T23:59:59.000Z

26

An assessment of the value of retail ready packaging  

E-Print Network (OSTI)

Use of retail-ready packaging reduces the costs of replenishing store shelves by eliminating the labor of removing packaging materials and stocking individual items on shelves. While reducing costs for retailers, retail-ready ...

Jackson, Kathleen Anne

2008-01-01T23:59:59.000Z

27

RECLAMATION OF RADIOACTIVE MATERIAL PACKAGING COMPONENTS  

SciTech Connect

Radioactive material packages are withdrawn from use for various reasons; loss of mission, decertification, damage, replacement, etc. While the packages themselves may be decertified, various components may still be able to perform to their required standards and find useful service. The Packaging Technology and Pressurized Systems group of the Savannah River National Laboratory has been reducing the cost of producing new Type B Packagings by reclaiming, refurbishing, and returning to service the containment vessels from older decertified packagings. The program and its benefits are presented.

Abramczyk, G.; Nathan, S.; Loftin, B.; Bellamy, S.

2011-06-06T23:59:59.000Z

28

ElectronicPackaging  

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

Packaging Packaging Manufacturing Technologies The Electronic Packaging technologies in the Thin Film, Vacuum, and Packaging Department are a resource for all aspects of microelectronic packag- ing. From design and layout to fabrication of proto- type samples, the staff offers partners the opportu- nity for concurrent engineering and development of a variety of electronic packaging concepts. This includes assistance in selecting the most appropri- ate technology for manufacturing, analysis of per- formance characteristics and development of new and unique processes. Capabilities 1. Network Fabrication * Low Temperature Co-Fired Ceramic (LTCC) * Thick Film * Thin Film 2. Packaging and Assembly * Chip Level Packaging * MEMs Packaging * Hermetic Sealing * Surface Mount Technology

29

Optimal segmentation and packaging process  

DOE Patents (OSTI)

A process for improving packaging efficiency uses three dimensional, computer simulated models with various optimization algorithms to determine the optimal segmentation process and packaging configurations based on constraints including container limitations. The present invention is applied to a process for decontaminating, decommissioning (D and D), and remediating a nuclear facility involving the segmentation and packaging of contaminated items in waste containers in order to minimize the number of cuts, maximize packaging density, and reduce worker radiation exposure. A three-dimensional, computer simulated, facility model of the contaminated items are created. The contaminated items are differentiated. The optimal location, orientation and sequence of the segmentation and packaging of the contaminated items is determined using the simulated model, the algorithms, and various constraints including container limitations. The cut locations and orientations are transposed to the simulated model. The contaminated items are actually segmented and packaged. The segmentation and packaging may be simulated beforehand. In addition, the contaminated items may be cataloged and recorded. 3 figs.

Kostelnik, K.M.; Meservey, R.H.; Landon, M.D.

1999-08-10T23:59:59.000Z

30

Trans Labeling Package  

Science Conference Proceedings (OSTI)

A special collection of books and CD-ROMS on the topic of trans fat. Trans Labeling Package Health Nutrition Biochemistry Trans Health - Nutrition - Biochemistry Value Packages This Value Package includes: ...

31

Omega-3 Package  

Science Conference Proceedings (OSTI)

Contain two(2) titles. Omega-3 Package Health Nutrition Biochemistry Health - Nutrition - Biochemistry Value Packages Fish, Omega-3 and Human Health ...

32

Microelectronic device package with an integral window  

DOE Patents (OSTI)

An apparatus for packaging of microelectronic devices, including an integral window. The microelectronic device can be a semiconductor chip, a CCD chip, a CMOS chip, a VCSEL chip, a laser diode, a MEMS device, or a IMEMS device. The package can include a cofired ceramic frame or body. The package can have an internal stepped structure made of one or more plates, with apertures, which are patterned with metallized conductive circuit traces. The microelectronic device can be flip-chip bonded on the plate to these traces, and oriented so that the light-sensitive side is optically accessible through the window. A cover lid can be attached to the opposite side of the package. The result is a compact, low-profile package, having an integral window that can be hermetically-sealed. The package body can be formed by low-temperature cofired ceramic (LTCC) or high-temperature cofired ceramic (HTCC) multilayer processes with the window being simultaneously joined (e.g. cofired) to the package body during LTCC or HTCC processing. Multiple chips can be located within a single package. The cover lid can include a window. The apparatus is particularly suited for packaging of MEMS devices, since the number of handling steps is greatly reduced, thereby reducing the potential for contamination.

Peterson, Kenneth A. (Albuquerque, NM); Watson, Robert D. (Tijeras, NM)

2002-01-01T23:59:59.000Z

33

Borehole Data Package for Two RCRA Wells 299-W11-25B and 299-W11-46 at Single-Shell Tank Waste Management Area T, Hanford Site, Washington  

Science Conference Proceedings (OSTI)

One new Resource Conservation and Recovery Act (RCRA) groundwater monitoring and assessment well was installed at single-shell tank Waste Management Area (WMA) T in calendar year 2005 in partial fulfillment of commitments for well installations proposed in Hanford Federal Facility Agreement and Consent Order, Milestone M-24-57 (2004). The need for increased monitoring capability at this WMA was identified during a data quality objectives process for establishing a RCRA/Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA)/Atomic Energy Act (AEA) integrated 200 West and 200 East Area Groundwater Monitoring Network. The initial borehole, 299-W11-25B, was located about 20 ft from existing downgradient well 299 W11-39. The specific objective for the borehole was to determine the vertical distribution of contaminants in the unconfined aquifer at the northeast corner of WMA T. The permanent casing in borehole 299-W11-25B was damaged beyond repair during well construction and replacement borehole, 299-W11-46, was drilled about 10 ft from borehole 299-W11-25B (Figure 1). Borehole 299-W11-46 was completed as a RCRA monitoring well. This document provides a compilation of all available geologic data, geophysical logs, hydrogeologic data and well information obtained during drilling, well construction, well development, pump installation, groundwater sampling and analysis activities, and preliminary results of slug tests associated with wells 299-W11-25B and 299-W11-46. Appendix A contains geologists logs, Well Construction Summary Reports, Well Summary Sheets (as-built diagrams), and Well Development and Testing Data sheets. Appendix B contains the results of chemical analysis of groundwater samples. Appendix C contains complete spectral gamma-ray logs and borehole deviation surveys and Appendix D contains initial results of slug tests. The non-conformance report for borehole 299-W11-46 is provided in Appendix E.

Horton, Duane G.; Chamness, Mickie A.

2006-04-17T23:59:59.000Z

34

The design of algorithm translation package using UML  

Science Conference Proceedings (OSTI)

The aim of this project is to develop software called Algorithm Translation Package. The main purpose of this package is to automatically convert users' edited algorithm code in Malay Language into C source code. This package also reduces the users' ... Keywords: activity diagram, object oriented software development life cycle, unified modeling language, use Case diagram

Noraida Haji Ali; Masila Abdul Jalil; Mustafa Mat Deris

2005-02-01T23:59:59.000Z

35

The reduction of packaging waste  

Science Conference Proceedings (OSTI)

Nationwide, packaging waste comprises approximately one-third of the waste disposed in sanitary landfills. the US Department of Energy (DOE) generated close to 90,000 metric tons of sanitary waste. With roughly one-third of that being packaging waste, approximately 30,000 metric tons are generated per year. The purpose of the Reduction of Packaging Waste project was to investigate opportunities to reduce this packaging waste through source reduction and recycling. The project was divided into three areas: procurement, onsite packaging and distribution, and recycling. Waste minimization opportunities were identified and investigated within each area, several of which were chosen for further study and small-scale testing at the Hanford Site. Test results, were compiled into five ``how-to`` recipes for implementation at other sites. The subject of the recipes are as follows: (1) Vendor Participation Program; (2) Reusable Containers System; (3) Shrink-wrap System -- Plastic and Corrugated Cardboard Waste Reduction; (4) Cardboard Recycling ; and (5) Wood Recycling.

Raney, E.A.; Hogan, J.J.; McCollom, M.L.; Meyer, R.J.

1994-04-01T23:59:59.000Z

36

CH Packaging Operations Manual  

Science Conference Proceedings (OSTI)

This procedure provides instructions for assembling the CH Packaging Drum payload assembly, Standard Waste Box (SWB) assembly, Abnormal Operations and ICV and OCV Preshipment Leakage Rate Tests on the packaging seals, using a nondestructive Helium (He) Leak Test.

Washington TRU Solutions LLC

2005-06-13T23:59:59.000Z

37

Edible Oils Package  

Science Conference Proceedings (OSTI)

Contains four (4) titles regarding frying and edible oils. Edible Oils Package Food Science & Technology Health - Nutrition - Biochemistry Value Packages 1766A8D5F05863694E128DE1C47D07C3 This Value Package includes: ...

38

Why packages? The Windows tools  

E-Print Network (OSTI)

Why packages? The Windows tools A sample package Going further Package Development in Windows from August 13, 2008; updated November 23, 2012 1 of 45 #12;Why packages? The Windows tools A sample of packages 2 The Windows tools The main tools Missing pieces Installing the tools 3 A sample package Getting

Murdoch, Duncan

39

Ocean shell noises  

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

Ocean shell noises Name: Rick A Cazzato Location: NA Country: NA Date: NA Question: Why do you here noises when you put a ocean shell to your ear? Does this happen because of...

40

Secure Shell (SSH)  

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

Secure Shell (SSH) Name: Rutaiwan Status: Educator Age: 20s Location: NA Country: NA Date: June 2003 Question: What is the Secure Shell (SSH)? What is a strong and weak points of...

Note: This page contains sample records for the topic "reduce shell package" 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

Flammable gas double shell tank expert elicitation presentations (Part A and Part B)  

Science Conference Proceedings (OSTI)

This document is a compilation of presentation packages and white papers for the Flammable Gas Double Shell Tank Expert Elicitation Workshop {number_sign}2. For each presentation given by the different authors, a separate section was developed. The purpose for issuing these workshop presentation packages and white papers as a supporting document is to provide traceability and a Quality Assurance record for future reference to these packages.

Bratzel, D.R.

1998-04-17T23:59:59.000Z

42

CH Packaging Operations Manual  

Science Conference Proceedings (OSTI)

This procedure provides instructions forassembling the following CH packaging payload: Drum payload assembly Standard Waste Box (SWB) assembly Ten-Drum Overpack (TDOP)

Washington TRU Solutions LLC

2007-11-29T23:59:59.000Z

43

CH Packaging Operations Manual  

SciTech Connect

Introduction - This procedure provides instructions for assembling the following CH packaging payload: - Drum payload assembly - Standard Waste Box (SWB) assembly - Ten-Drum Overpack (TDOP).

Washington TRU Solutions

2002-03-04T23:59:59.000Z

44

CH Packaging Operations Manual  

SciTech Connect

Introduction - This procedure provides instructions forassembling the following CH packaging payload: Drum payload assembly Standard Waste Box (SWB) assembly Ten-Drum Overpack (TDOP)

Washington TRU Solutions LLC

2006-12-18T23:59:59.000Z

45

CH Packaging Operations Manual  

SciTech Connect

This procedure provides instructions forassembling the following CH packaging payload: Drum payload assembly Standard Waste Box (SWB) assembly Ten-Drum Overpack (TDOP)

Washington TRU Solutions LLC

2007-08-22T23:59:59.000Z

46

CH Packaging Operations Manual  

Science Conference Proceedings (OSTI)

Introduction - This procedure provides instructions for assembling the following CH packaging payload: -Drum payload assembly -Standard Waste Box (SWB) assembly -Ten-Drum Overpack (TDOP).

Washington TRU Solutions LLC

2003-06-26T23:59:59.000Z

47

CH Packaging Operations Manual  

SciTech Connect

Introduction - This procedure provides instructions forassembling the following CH packaging payload: Drum payload assembly Standard Waste Box (SWB) assembly Ten-Drum Overpack (TDOP)

Washington TRU Solutions LLC

2007-05-15T23:59:59.000Z

48

Next Generation Packaging  

Science Conference Proceedings (OSTI)

Feb 28, 2011 ... Creation and Manipulation of Aligned Nanowires for Packaging and Circuit ... Plastic deformation plays an important role in the control of ...

49

Packaged CHP System Assessment  

Science Conference Proceedings (OSTI)

The Packaged CHP System Assessment report provides an analysis of packaged combined heat and power (CHP) systems. The report summarizes and compares the technical characteristics of commercial product lines with electric power output up to 3,000 kWe.

2004-03-22T23:59:59.000Z

50

TRNSYS for windows packages  

SciTech Connect

TRNSYS 14.1 was released in 1994. This package represents a significant step forward in usability due to several graphical utility programs for DOS. These programs include TRNSHELL, which encapsulates TRNSYS functions, PRESIM, which allows the graphical creation of a simulation system, and TRNSED, which allows the easy sharing of simulations. The increase in usability leads to a decrease in the time necessary to prepare the simulation. Most TRNSYS users operate on PC computers with the Windows operating system. Therefore, the next logical step in increased usability was to port the current TRNSYS package to the Windows operating system. Several organizations worked on this conversion that has resulted in two distinct Windows packages. One package closely resembles the DOS version and includes TRNSHELL for Windows and PRESIM for Windows. The other package incorporates a general front-end, called IISIBat, that is a general simulation tool front-end. 8 figs.

Blair, N.J.; Beckman, W.A.; Klein, S.A.; Mitchell, J.W.

1996-09-01T23:59:59.000Z

51

Long-term Repository Benefits of Using Cermet Waste Packages  

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

Long-Term Benefits Long-Term Benefits Long-term Repository Benefits of Using Cermet Waste Packages A cermet waste package may improve the long-term performance of the YM repository by two mechanisms: reducing (1) the potential for nuclear criticality in the repository and (2) the long-term release rate of radionuclides from the waste package. In the natural environment, the centers of uranium ore deposits have remained intact for very long time periods while the outer edges of the ore deposit have degraded. A cermet waste package may operate in the same way. The sacrificial, slow degradation of the waste package and the DU oxide protects the SNF uranium dioxide in the interior of the package long after the package has failed. Page 2 of 4 Follow the link below to learn more about Cermets:

52

Type B Drum packages  

Science Conference Proceedings (OSTI)

The Type B Drum package is a container in which a single drum containing Type B quantities of radioactive material will be packaged for shipment. The Type B Drum containers are being developed to fill a void in the packaging and transportation capabilities of the US Department of Energy (DOE), as no double containment packaging for single drums of Type B radioactive material is currently available. Several multiple-drum containers and shielded casks presently exist. However, the size and weight of these containers present multiple operational challenges for single-drum shipments. The Type B Drum containers will offer one unshielded version and, if needed, two shielded versions, and will provide for the option of either single or double containment. The primary users of the Type B Drum container will be any organization with a need to ship single drums of Type B radioactive material. Those users include laboratories, waste retrieval facilities, emergency response teams, and small facilities.

Edwards, W.S.

1995-11-01T23:59:59.000Z

53

PDSF Shells and Startup Files  

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

Shells and Startup Files Shells and Startup Files PDSF Defined Environment When new users are added to the PDSF machines, the shell is set according to the user's request. You can...

54

CH Packaging Program Guidance  

SciTech Connect

The purpose of this document is to provide the technical requirements for preparation for use, operation, inspection, and maintenance of a Transuranic Package Transporter Model II (TRUPACT-II), a HalfPACT Shipping Package, and directly related components. This document complies with the minimum requirements as specified in TRUPACT-II Safety Analysis Report for Packaging (SARP), HalfPACT SARP, and Nuclear Regulatory Commission (NRC) Certificates of Compliance (C of C) 9218 and 9279, respectively. In the event there is a conflict between this document and the SARP or C of C, the SARP and/or C of C shall govern. C of Cs state: ''each package must be prepared for shipment and operated in accordance with the procedures described in Chapter 7.0, Operating Procedures, of the application.'' They further state: ''each package must be tested and maintained in accordance with the procedures described in Chapter 8.0, Acceptance Tests and Maintenance Program of the Application.'' Chapter 9.0 of the SAR P charges the WIPP Management and Operation (M&O) contractor with assuring packaging is used in accordance with the requirements of the C of C. Because the packaging is NRC-approved, users need to be familiar with 10 CFR 71.11. Any time a user suspects or has indications that the conditions of approval in the C of C were not met, the Carlsbad Field Office (CBFO) shall be notified immediately. CBFO will evaluate the issue and notify the NRC if required. This document details the instructions to be followed to operate, maintain, and test the TRUPACT-II and HalfPACT packaging. The intent of these instructions is to standardize these operations. All users will follow these instructions or equivalent instructions that assure operations are safe and meet the requirements of the SARPs.

Washington TRU Solutions LLC

2002-03-04T23:59:59.000Z

55

CH Packaging Program Guidance  

Science Conference Proceedings (OSTI)

The purpose of this document is to provide the technical requirements for preparation for use, operation, inspection, and maintenance of a Transuranic Package Transporter Model II (TRUPACT-II), a HalfPACT shipping package, and directly related components. This document complies with the minimum requirements as specified in the TRUPACT-II Safety Analysis Report for Packaging (SARP), HalfPACT SARP, and Nuclear Regulatory Commission (NRC) Certificates of Compliance (C of C) 9218 and 9279, respectively. In the event of a conflict between this document and the SARP or C of C, the C of C shall govern. The C of Cs state: ''each package must be prepared for shipment and operated in accordance with the procedures described in Chapter 7.0, Operating Procedures, of the application.'' They further state: ''each package must be tested and maintained in accordance with the procedures described in Chapter 8.0, Acceptance Tests and Maintenance Program of the Application.'' Chapter 9.0 of the SARP charges the WIPP management and operating (M&O) contractor with assuring packaging is used in accordance with the requirements of the C of C. Because the packaging is NRC-approved, users need to be familiar with 10 CFR 71.11. Any time a user suspects or has indications that the conditions of approval in the C of C were not met, the Carlsbad Field Office (CBFO) shall be notified immediately. CBFO will evaluate the issue and notify the NRC if required. This document provides the instructions to be followed to operate, maintain, and test the TRUPACT-II and HalfPACT packaging. The intent of these instructions is to standardize operations. All users will follow these instructions or equivalent instructions that assure operations are safe and meet the requirements of the SARPs.

Washington TRU Solutions LLC

2003-04-30T23:59:59.000Z

56

The ENSDF Java Package  

Science Conference Proceedings (OSTI)

A package of computer codes has been developed to process and display nuclear structure and decay data stored in the ENSDF (Evaluated Nuclear Structure Data File) library. The codes were written in an object-oriented fashion using the java language. This allows for an easy implementation across multiple platforms as well as deployment on web pages. The structure of the different java classes that make up the package is discussed as well as several different implementations.

Sonzogni, A.A. [National Nuclear Data Center, Brookhaven National Laboratory, Upton, NY 11973-5000 (United States)

2005-05-24T23:59:59.000Z

57

Multilayered microelectronic device package with an integral window  

DOE Patents (OSTI)

An apparatus for packaging of microelectronic devices is disclosed, wherein the package includes an integral window. The microelectronic device can be a semiconductor chip, a CCD chip, a CMOS chip, a VCSEL chip, a laser diode, a MEMS device, or a IMEMS device. The package can comprise, for example, a cofired ceramic frame or body. The package has an internal stepped structure made of a plurality of plates, with apertures, which are patterned with metallized conductive circuit traces. The microelectronic device can be flip-chip bonded on the plate to these traces, and oriented so that the light-sensitive side is optically accessible through the window. A cover lid can be attached to the opposite side of the package. The result is a compact, low-profile package, having an integral window that can be hermetically-sealed. The package body can be formed by low-temperature cofired ceramic (LTCC) or high-temperature cofired ceramic (HTCC) multilayer processes with the window being simultaneously joined (e.g. cofired) to the package body during LTCC or HTCC processing. Multiple chips can be located within a single package, according to some embodiments. The cover lid can include a window. The apparatus is particularly suited for packaging of MEMS devices, since the number of handling steps is greatly reduced, thereby reducing the potential for contamination. The integral window can further include a lens for optically transforming light passing through the window. The package can include an array of binary optic lenslets made integral with the window. The package can include an electrically-switched optical modulator, such as a lithium niobate window attached to the package, for providing a very fast electrically-operated shutter.

Peterson, Kenneth A. (Albuquerque, NM); Watson, Robert D. (Tijeras, NM)

2003-01-01T23:59:59.000Z

58

THE USE OF DIGITAL RADIOGRAPHY IN THE EVALUATION OF RADIOACTIVE MATERIALS PACKAGING PERFORMANCE TESTING  

Science Conference Proceedings (OSTI)

New designs of radioactive material shipping packages are required to be evaluated in accordance with 10 CFR Part 71, ''Packaging and Transportation of Radioactive Material''. This paper will discuss the use of digital radiography to evaluate the effects of the tests required by 10 CFR 71.71, Normal Conditions of Transport (NCT), and 10 CFR 71.73, Hypothetical Accident Conditions (HAC). One acceptable means of evaluating packaging performance is to subject packagings to the series of NCT and HAC tests. The evaluation includes a determination of the effect on the packaging by the conditions and tests. That determination has required that packagings be cut and sectioned to learn the actual effects on internal components. Digital radiography permits the examination of internal packaging components without sectioning a package. This allows a single package to be subjected to a series of tests. After each test, the package is digitally radiographed and the effects of particular tests evaluated. Radiography reduces the number of packages required for testing and also reduces labor and materials required to section and evaluate numerous packages. This paper will include a description of the digital radiography equipment used in the testing and evaluation of the 9977 and 9978 packages at SRNL. The equipment is capable of making a single radiograph of a full-sized package in one exposure. Radiographs will be compared to sectioned packages that show actual conditions compared to radiographic images.

May, C; Lawrence Gelder, L; Boyd Howard, B

2007-03-22T23:59:59.000Z

59

RH Packaging Program Guidance  

Science Conference Proceedings (OSTI)

The purpose of this program guidance document is to provide the technical requirements for use, operation, inspection, and maintenance of the RH-TRU 72-B Waste Shipping Package (also known as the "RH-TRU 72-B cask") and directly related components. This document complies with the requirements as specified in the RH-TRU 72-B Safety Analysis Report for Packaging (SARP), and Nuclear Regulatory Commission (NRC) Certificate of Compliance (C of C) 9212. If there is a conflict between this document and the SARP and/or C of C, the C of C shall govern. The C of C states: "...each package must be prepared for shipment and operated in accordance with the procedures described in Chapter 7.0, Operating Procedures, of the application." It further states: "...each package must be tested and maintained in accordance with the procedures described in Chapter 8.0, Acceptance Tests and Maintenance Program of the Application." Chapter 9.0 of the SARP tasks the Waste Isolation Pilot Plant (WIPP) Management and Operating (M&O) Contractor with assuring the packaging is used in accordance with the requirements of the C of C. Because the packaging is NRC-approved, users need to be familiar with Title 10 Code of Federal Regulations (CFR) §71.8, "Deliberate Misconduct." Any time a user suspects or has indications that the conditions of approval in the C of C were not met, the U.S. Department of Energy (DOE) Carlsbad Field Office (CBFO) shall be notified immediately. The CBFO will evaluate the issue and notify the NRC if required.In accordance with 10 CFR Part 71, "Packaging and Transportation of Radioactive Material," certificate holders, packaging users, and contractors or subcontractors who use, design, fabricate, test, maintain, or modify the packaging shall post copies of (1) 10 CFR Part 21, "Reporting of Defects and Noncompliance," regulations, (2) Section 206 of the Energy Reorganization Act of 1974, and (3) NRC Form 3, Notice to Employees. These documents must be posted in a conspicuous location where the activities subject to these regulations are conducted. This document details the instructions to be followed to operate, maintain, and test the RH-TRU 72-B packaging. This Program Guidance standardizes instructions for all users. Users shall follow these instructions or equivalent approved instructions. Following these instructions assures that operations meet the requirements of the SARP.

Washington TRU Solutions LLC

2008-01-12T23:59:59.000Z

60

RH Packaging Program Guidance  

Science Conference Proceedings (OSTI)

The purpose of this program guidance document is to provide the technical requirements for use, operation, inspection, and maintenance of the RH-TRU 72-B Waste Shipping Package and directly related components. This document complies with the requirements as specified in the RH-TRU 72-B Safety Analysis Report for Packaging (SARP), and Nuclear Regulatory Commission (NRC) Certificate of Compliance (C of C) 9212. If there is a conflict between this document and the SARP and/or C of C, the C of C shall govern. The C of C states: "...each package must be prepared for shipment and operated in accordance with the procedures described in Chapter 7.0, Operating Procedures, of the application." It further states: "...each package must be tested and maintained in accordance with the procedures described in Chapter 8.0, Acceptance Tests and Maintenance Program of the Application." Chapter 9.0 of the SARP tasks the Waste Isolation Pilot Plant (WIPP) Management and Operating (M&O) Contractor with assuring the packaging is used in accordance with the requirements of the C of C. Because the packaging is NRC-approved, users need to be familiar with 10 Code of Federal Regulations (CFR) §71.8, "Deliberate Misconduct." Any time a user suspects or has indications that the conditions of approval in the C of C were not met, the U.S. Department of Energy (DOE) Carlsbad Field Office (CBFO) shall be notified immediately. CBFO will evaluate the issue and notify the NRC if required. In accordance with 10 CFR Part 71, "Packaging and Transportation of Radioactive Material," certificate holders, packaging users, and contractors or subcontractors who use, design, fabricate, test, maintain, or modify the packaging shall post copies of (1) 10 CFR Part 21, "Reporting of Defects and Noncompliance," regulations, (2) Section 206 of the Energy Reorganization Act of 1974, and (3) NRC Form 3, Notice to Employees. These documents must be posted in a conspicuous location where the activities subject to these regulations are conducted. This document details the instructions to be followed to operate, maintain, and test the RH-TRU 72-B packaging. This Program Guidance standardizes instructions for all users. Users shall follow these instructions or equivalent approved instructions. Following these instructions assures that operations meet the requirements of the SARP.

Washington TRU Solutions LLC

2006-11-07T23:59:59.000Z

Note: This page contains sample records for the topic "reduce shell package" 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

CH Packaging Program Guidance  

Science Conference Proceedings (OSTI)

The purpose of this document is to provide the technical requirements for preparation for use, operation, inspection, and maintenance of a Transuranic Package Transporter Model II (TRUPACT-II), a HalfPACT shipping package, and directly related components. This document complies with the minimum requirements as specified in the TRUPACT-II Safety Analysis Report for Packaging (SARP), HalfPACT SARP, and U.S. Nuclear Regulatory Commission (NRC) Certificates of Compliance (C of C) 9218 and 9279, respectively. In the event of a conflict between this document and the SARP or C of C, the C of C shall govern. The C of Cs state: "each package must be prepared for shipment and operated in accordance with the procedures described in Chapter 7.0, Operating Procedures, of the application." They further state: "each package must be tested and maintained in accordance with the procedures described in Chapter 8.0, Acceptance Tests and Maintenance Program of the Application." Chapter 9.0 of the SARP charges the Waste Isolation Pilot Plant (WIPP) management and operating (M&O) contractor with assuring packaging is used in accordance with the requirements of the C of C. Because the packaging is NRC-approved, users need to be familiar with Title 10 Code of Federal Regulations (CFR) §71.8. Any time a user suspects or has indications that the conditions of approval in the C of C were not met, the Carlsbad Field Office (CBFO) shall be notified immediately. The CBFO will evaluate the issue and notify the NRC if required.

Washington TRU Solutions LLC

2005-02-28T23:59:59.000Z

62

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

63

Drop Tests for the 6M Specification Package Closure Investigation  

SciTech Connect

Results of tests of drum-type RAM packages employing conventional clamp-ring closures have caused concern within the DOE Complex over the Department of Transportation 6M Specification Package. To clarify these issues, the Savannah River Site's Radioactive Material Packaging Technology Group was commissioned to conduct a series of tests to determine the response of the clamp-ring closure to the regulatory Hypothetical Accident Condition drop tests, for packages at maximum allowable weight, 640 lb. Additionally, three enhanced closure designs were also tested: the Clamshell, plywood disk reinforcement, and J-Clip. The results of the tests showed that the standard closure was unable to retain its lid for both Center-of-Gravity-Over-Corner and Shallow-Angle cases, for the standard package, at its maximum allowed weight. Similar results were found for packages dropped from a reduced height. The Clamshell design provided the best performance of the enhanced closures.

Smith, A.C.

2003-10-02T23:59:59.000Z

64

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

65

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

66

Core-Shell Structured Magnetic Ternary Nanocubes  

DOE Green Energy (OSTI)

While transition metal-doped ferrite nanoparticles constitute an important class of soft magnetic nanomaterials with spinel structures, the ability to control the shape and composition would enable a wide range of applications in homogeneous or heterogeneous reactions such as catalysis and magnetic separation of biomolecules. This report describes novel findings of an investigation of core-shell structured MnZn ferrite nanocubes synthesized in organic solvents by manipulating the reaction temperature and capping agent composition in the absence of the conventionally-used reducing agents. The core-shell structure of the highly-monodispersed nanocubes (~20 nm) are shown to consist of an Fe3O4 core and an (Mn0.5Zn0.5)(Fe0.9, Mn1.1)O4 shell. In comparison with Fe3O4 and other binary ferrite nanoparticles, the core-shell structured nanocubes were shown to display magnetic properties regulated by a combination of the core-shell composition, leading to a higher coercivity (~350 Oe) and field-cool/zero-field-cool characteristics drastically different from many regular MnZn ferrite nanoparticles. The findings are discussed in terms of the unique core-shell composition, the understanding of which has important implication to the exploration of this class of soft magnetic nanomaterials in many potential applications such as magnetic resonance imaging, fuel cells, and batteries.

Wang, Lingyan; Wang, Xin; Luo, Jin; Wanjala, Bridgid N.; Wang, Chong M.; Chernova, Natalya; Engelhard, Mark H.; Liu, Yao; Bae, In-Tae; Zhong, Chuan-Jian

2010-12-01T23:59:59.000Z

67

The ENSDF_toolbox program package: tool for the evaluator of nuclear data  

E-Print Network (OSTI)

The program package for the work with the Evaluated Nuclear Structure Data File is discussed. The program shell designed for the unification of the process of the evaluation of the nuclear data is proposed. This program shell may be used in the regular work of the nuclear data evaluator and for common use by scientists and engineers who need the actual data about nuclear states and transitions from the ENSDF database.

Shulyak, G I

2010-01-01T23:59:59.000Z

68

The ENSDF_toolbox program package: tool for the evaluator of nuclear data  

E-Print Network (OSTI)

The program package for the work with the Evaluated Nuclear Structure Data File is discussed. The program shell designed for the unification of the process of the evaluation of the nuclear data is proposed. This program shell may be used in the regular work of the nuclear data evaluator and for common use by scientists and engineers who need the actual data about nuclear states and transitions from the ENSDF database.

G. I. Shulyak; A. A. Rodionov

2010-04-20T23:59:59.000Z

69

Hamiltonian spacetime dynamics with a spherical null-dust shell  

E-Print Network (OSTI)

We consider the Hamiltonian dynamics of spherically symmetric Einstein gravity with a thin null-dust shell, under boundary conditions that fix the evolution of the spatial hypersurfaces at the two asymptotically flat infinities of a Kruskal-like manifold. The constraints are eliminated via a Kuchar-type canonical transformation and Hamiltonian reduction. The reduced phase space $\\tilde\\Gamma$ consists of two disconnected copies of $R^4$, each associated with one direction of the shell motion. The right-moving and left-moving test shell limits can be attached to the respective components of right-hand-side and left-hand-side masses as configuration variables provides a global canonical chart on each component of $\\tilde\\Gamma$, and renders the Hamiltonian simple, but encodes the shell dynamics in the momenta in a convoluted way. Choosing the shell curvature radius and the "interior" mass as configuration variables renders the shell dynamics transparent in an arbitrarily specifiable stationary gauge "exterior" ...

Louko, J; Friedman, J L; Louko, Jorma; Whiting, Bernard F.; Friedman, John L.

1998-01-01T23:59:59.000Z

70

Packaging architecture: a critique of architectural commodification  

E-Print Network (OSTI)

The thesis develops a critique of architectural commodification in terms of common intellectual, technological, and economic developments that have shaped both modem architecture and cuisine since the French Enlightenment. Food and architecture's shared condition as packaged commodities provide the basis for Fridge, a computer animation that develops visual analogies between milk, the machine, packaging, and modem architecture. Constraints and architectural skills engaged in translating the critique into a computer animation that appeals to a general audience are discussed in terms of the medium's potential for broadening architectural theory's reach and reducing its isolation from computer graphics.

Pushpathadam, Thomas

1996-01-01T23:59:59.000Z

71

White LED with High Package Extraction Efficiency  

Science Conference Proceedings (OSTI)

The goal of this project is to develop a high efficiency phosphor converting (white) Light Emitting Diode (pcLED) 1-Watt package through an increase in package extraction efficiency. A transparent/translucent monolithic phosphor is proposed to replace the powdered phosphor to reduce the scattering caused by phosphor particles. Additionally, a multi-layer thin film selectively reflecting filter is proposed between blue LED die and phosphor layer to recover inward yellow emission. At the end of the project we expect to recycle approximately 50% of the unrecovered backward light in current package construction, and develop a pcLED device with 80 lm/W{sub e} using our technology improvements and commercially available chip/package source. The success of the project will benefit luminous efficacy of white LEDs by increasing package extraction efficiency. In most phosphor-converting white LEDs, the white color is obtained by combining a blue LED die (or chip) with a powdered phosphor layer. The phosphor partially absorbs the blue light from the LED die and converts it into a broad green-yellow emission. The mixture of the transmitted blue light and green-yellow light emerging gives white light. There are two major drawbacks for current pcLEDs in terms of package extraction efficiency. The first is light scattering caused by phosphor particles. When the blue photons from the chip strike the phosphor particles, some blue light will be scattered by phosphor particles. Converted yellow emission photons are also scattered. A portion of scattered light is in the backward direction toward the die. The amount of this backward light varies and depends in part on the particle size of phosphors. The other drawback is that yellow emission from phosphor powders is isotropic. Although some backward light can be recovered by the reflector in current LED packages, there is still a portion of backward light that will be absorbed inside the package and further converted to heat. Heat generated in the package may cause a deterioration of encapsulant materials, affecting the performance of both the LED die and phosphor, leading to a decrease in the luminous efficacy over lifetime. Recent studies from research groups at Rensselaer Polytechnic Institute found that, under the condition to obtain a white light, about 40% of the light is transmitted outward of the phosphor layer and 60% of the light is reflected inward.1,2 It is claimed that using scattered photon extraction (SPE) technique, luminous efficacy is increased by 60%. In this project, a transparent/translucent monolithic phosphor was used to replace the powdered phosphor layer. In the normal pcLED package, the powdered phosphor is mixed with silicone either to be deposited on the top of LED die forming a chip level conversion (CLC) white LED or to be casted in the package forming a volume conversion white LED. In the monolithic phosphors there are no phosphor powder/silicone interfaces so it can reduce the light scattering caused by phosphor particles. Additionally, a multi-layer thin film selectively reflecting filter is inserted in the white LED package between the blue LED die and phosphor layer. It will selectively transmit the blue light from the LED die and reflect the phosphor's yellow inward emission outward. The two technologies try to recover backward light to the outward direction in the pcLED package thereby improving the package extraction efficiency.

Yi Zheng; Matthew Stough

2008-09-30T23:59:59.000Z

72

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

73

CH Packaging Maintenance Manual  

SciTech Connect

This procedure provides instructions for performing inner containment vessel (ICV) and outer containment vessel (OCV) maintenance and periodic leakage rate testing on the following packaging seals and corresponding seal surfaces using a nondestructive helium (He) leak test. In addition, this procedure provides instructions for performing ICV and OCV structural pressure tests.

Washington TRU Solutions

2002-01-02T23:59:59.000Z

74

Waste disposal package  

DOE Patents (OSTI)

This is a claim for a waste disposal package including an inner or primary canister for containing hazardous and/or radioactive wastes. The primary canister is encapsulated by an outer or secondary barrier formed of a porous ceramic material to control ingress of water to the canister and the release rate of wastes upon breach on the canister. 4 figs.

Smith, M.J.

1985-06-19T23:59:59.000Z

75

Package for fragile objects  

SciTech Connect

A package for fragile objects such as radioactive fusion pellets of micron size shipped in mounted condition or unmounted condition with a frangible inner container which is supported in a second inner container which in turn is supported in a final outer container, the second inner container having recesses for supporting alternate design inner containers.

Burgeson, Duane A. (Ann Arbor, MI)

1977-01-01T23:59:59.000Z

76

Detailed Analysis of the Builder Option Packages for Climate Zones 3,4,5, and 6 for Texas' Senate Bill 5 Legislation for Reducing Pollution in Non-Attainment and Affected Areas  

E-Print Network (OSTI)

This report is a detailed description of the analysis completed on the Energy Star Builder Option Packages (BOPs) using the Energy Systems Laboratory’s (ESL) Code Compliant Test Suite of Tools. This report outlines the basic procedure, which was followed. A description of the Test Suite, along with a detailed explanation of the naming the procedure of the different runs is also a part of this report. A CD-ROM is also provided which has all the 137 runs, inputs and outputs, the window inputs and the summary spreadsheets. BOPs for climate zones 3,4,5 and 6 were submitted for approval to ESL on April 29,2002. It was stated that the suggested BOPs were 10 to 15% less consumptive than the IECC chapter 4/5 house. Analysis was done on these BOPs and the BOPs which were less consumptive than the standard house were posted on the ESL’s website. The same tables have also been included in this report along with the detailed spreadsheets.

Ahmad, M.; Haberl, J. S.

2003-01-01T23:59:59.000Z

77

Plutonium stabilization and packaging system  

Science Conference Proceedings (OSTI)

This document describes the functional design of the Plutonium Stabilization and Packaging System (Pu SPS). The objective of this system is to stabilize and package plutonium metals and oxides of greater than 50% wt, as well as other selected isotopes, in accordance with the requirements of the DOE standard for safe storage of these materials for 50 years. This system will support completion of stabilization and packaging campaigns of the inventory at a number of affected sites before the year 2002. The package will be standard for all sites and will provide a minimum of two uncontaminated, organics free confinement barriers for the packaged material.

NONE

1996-05-01T23:59:59.000Z

78

RH Packaging Program Guidance  

Science Conference Proceedings (OSTI)

The purpose of this program guidance document is to provide technical requirements for use, operation, inspection, and maintenance of the RH-TRU 72-B Waste Shipping Package and directly related components. This document complies with the requirements as specified in the RH-TRU 72-B Safety Analysis Report for Packaging (SARP), and Nuclear Regulatory Commission (NRC) Certificate of Compliance (C of C) 9212. If there is a conflict between this document and the SARP and/or C of C, the SARP and/or C of C shall govern. The C of C states: ''...each package must be prepared for shipment and operated in accordance with the procedures described in Chapter 7.0, ''Operating Procedures,'' of the application.'' It further states: ''...each package must be tested and maintained in accordance with the procedures described in Chapter 8.0, ''Acceptance Tests and Maintenance Program of the Application.'' Chapter 9.0 of the SARP tasks the Waste Isolation Pilot Plant (WIPP) Management and Operating (M&O) contractor with assuring the packaging is used in accordance with the requirements of the C of C. Because the packaging is NRC approved, users need to be familiar with 10 CFR {section} 71.11, ''Deliberate Misconduct.'' Any time a user suspects or has indications that the conditions of approval in the C of C were not met, the Carlsbad Field Office (CBFO) shall be notified immediately. CBFO will evaluate the issue and notify the NRC if required. This document details the instructions to be followed to operate, maintain, and test the RH-TRU 72-B packaging. This Program Guidance standardizes instructions for all users. Users shall follow these instructions. Following these instructions assures that operations are safe and meet the requirements of the SARP. This document is available on the Internet at: ttp://www.ws/library/t2omi/t2omi.htm. Users are responsible for ensuring they are using the current revision and change notices. Sites may prepare their own document using the word-for-word steps in th is document, in sequence, including Notes and cautions. Site specific information may be included as necessary. The document, and revisions, must then be submitted to CBFO at sitedocuments@wipp.ws for approval. A copy of the approval letter from CBFO shall be available for audit purposes. Users may develop site-specific procedures addressing preoperational activities, quality assurance (QA), hoisting and rigging, and radiation health physics to be used with the instructions contained in this document. Users may recommend changes to this document by submitting their recommendations (in writing) to the WIPP M&O Contractor RH Packaging Maintenance Engineer for evaluation. If approved, the change(s) will be incorporated into this document for use by ALL users. Before first use and every 12 months after, user sites will be audited to this document to ensure compliance. They will also be audited within one year from the effective date of revisions to this document.

Washington TRU Solutions, LLC

2003-08-25T23:59:59.000Z

79

NUCLEAR MATERIAL PACKAGING MANUAL  

E-Print Network (OSTI)

The enclosed copy ofdraft DOE Manual M44I.I, Nuclear Material Packaging Manual, is forwarded for your review and comment. This satisfies commitment 5.1-3 in Appendix o ofthe implementation plan (IP) for recommendation 2005-1, Nuclear Material Packaging. The next milestone in Section 5.1 ofthe 2005-1 IP is forwarding the manual to the DOE 2005-1 Technical Review Board (TRB) by April 30, 2006 to begin the final TRB review. Therefore, your comments are requested by April 21, 2006, in order to allow one week for resolution and updating the manual before it is sent to the TRB. Please contact me at 301-903-4407 ifyou have any questions. t

The Honorable; A. J. Eggenberger; M. Whitaker Dr-i

2006-01-01T23:59:59.000Z

80

Aquaculture information package  

DOE Green Energy (OSTI)

This package of information is intended to provide background information to developers of geothermal aquaculture projects. The material is divided into eight sections and includes information on market and price information for typical species, aquaculture water quality issues, typical species culture information, pond heat loss calculations, an aquaculture glossary, regional and university aquaculture offices and state aquaculture permit requirements. A bibliography containing 68 references is also included.

Boyd, T.; Rafferty, K.

1998-08-01T23:59:59.000Z

Note: This page contains sample records for the topic "reduce shell package" 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

Bash Shell | Argonne Leadership Computing Facility  

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

Bash Shell A popular shell provided with the operating system, bash is available as a login shell. To change your login shell use your ALCF personal account page. Version(s):...

82

Stability of charged thin shells  

SciTech Connect

In this article we study the mechanical stability of spherically symmetric thin shells with charge, in Einstein-Maxwell and Einstein-Born-Infeld theories. We analyze linearized perturbations preserving the symmetry, for shells around vacuum and shells surrounding noncharged black holes.

Eiroa, Ernesto F. [Instituto de Astronomia y Fisica del Espacio, C.C. 67, Suc. 28, 1428, Buenos Aires (Argentina); Departamento de Fisica, Facultad de Ciencias Exactas y Naturales, Universidad de Buenos Aires, Ciudad Universitaria Pab. I, 1428, Buenos Aires (Argentina); Simeone, Claudio [Departamento de Fisica, Facultad de Ciencias Exactas y Naturales, Universidad de Buenos Aires, Ciudad Universitaria Pab. I, 1428, Buenos Aires (Argentina); IFIBA, CONICET, Ciudad Universitaria Pab. I, 1428, Buenos Aires (Argentina)

2011-05-15T23:59:59.000Z

83

Mollusk Shell Nacre Ultrastructure Correlates with Environmental...  

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

Mollusk Shell Nacre Ultrastructure Correlates with Environmental Temperature and Pressure Mollusk Shell Nacre Ultrastructure Correlates with Environmental Temperature and Pressure...

84

Technology transfer package on seismic base isolation - Volume III  

Science Conference Proceedings (OSTI)

This Technology Transfer Package provides some detailed information for the U.S. Department of Energy (DOE) and its contractors about seismic base isolation. Intended users of this three-volume package are DOE Design and Safety Engineers as well as DOE Facility Managers who are responsible for reducing the effects of natural phenomena hazards (NPH), specifically earthquakes, on their facilities. The package was developed as part of DOE's efforts to study and implement techniques for protecting lives and property from the effects of natural phenomena and to support the International Decade for Natural Disaster Reduction. Volume III contains supporting materials not included in Volumes I and II.

NONE

1995-02-14T23:59:59.000Z

85

IN-PACKAGE CHEMISTRY ABSTRACTION  

Science Conference Proceedings (OSTI)

This report was developed in accordance with the requirements in ''Technical Work Plan for Postclosure Waste Form Modeling'' (BSC 2005 [DIRS 173246]). The purpose of the in-package chemistry model is to predict the bulk chemistry inside of a breached waste package and to provide simplified expressions of that chemistry as a function of time after breach to Total Systems Performance Assessment for the License Application (TSPA-LA). The scope of this report is to describe the development and validation of the in-package chemistry model. The in-package model is a combination of two models, a batch reactor model, which uses the EQ3/6 geochemistry-modeling tool, and a surface complexation model, which is applied to the results of the batch reactor model. The batch reactor model considers chemical interactions of water with the waste package materials, and the waste form for commercial spent nuclear fuel (CSNF) waste packages and codisposed (CDSP) waste packages containing high-level waste glass (HLWG) and DOE spent fuel. The surface complexation model includes the impact of fluid-surface interactions (i.e., surface complexation) on the resulting fluid composition. The model examines two types of water influx: (1) the condensation of water vapor diffusing into the waste package, and (2) seepage water entering the waste package as a liquid from the drift. (1) Vapor-Influx Case: The condensation of vapor onto the waste package internals is simulated as pure H{sub 2}O and enters at a rate determined by the water vapor pressure for representative temperature and relative humidity conditions. (2) Liquid-Influx Case: The water entering a waste package from the drift is simulated as typical groundwater and enters at a rate determined by the amount of seepage available to flow through openings in a breached waste package.

E. Thomas

2005-07-14T23:59:59.000Z

86

About the ZOOM minimization package  

SciTech Connect

A new object-oriented Minimization package is available for distribution in the same manner as CLHEP. This package, designed for use in HEP applications, has all the capabilities of Minuit, but is a re-write from scratch, adhering to modern C++ design principles. A primary goal of this package is extensibility in several directions, so that its capabilities can be kept fresh with as little maintenance effort as possible. This package is distinguished by the priority that was assigned to C++ design issues, and the focus on producing an extensible system that will resist becoming obsolete.

Fischler, M.; Sachs, D.; /Fermilab

2004-11-01T23:59:59.000Z

87

The Packaging Handbook -- A guide to package design  

Science Conference Proceedings (OSTI)

The Packaging Handbook is a compilation of 14 technical chapters and five appendices that address the life cycle of a packaging which is intended to transport radioactive material by any transport mode in normal commerce. Although many topics are discussed in depth, this document focuses on the design aspects of a packaging. The Handbook, which is being prepared under the direction of the US Department of Energy, is intended to provide a wealth of technical guidance that will give designers a better understanding of the regulatory approval process, preferences of regulators in specific aspects of packaging design, and the types of analyses that should be seriously considered when developing the packaging design. Even though the Handbook is concerned with all packagings, most of the emphasis is placed on large packagings that are capable of transporting large radioactive sources that are also fissile (e.g., spent fuel). These are the types of packagings that must address the widest range of technical topics in order to meet domestic and international regulations. Most of the chapters in the Handbook have been drafted and submitted to the Oak Ridge National Laboratory for editing; the majority of these have been edited. This report summarizes the contents.

Shappert, L.B.

1995-12-31T23:59:59.000Z

88

Drop Tests for the 6M Specification Package Closure Investigation  

SciTech Connect

Results of tests of drum-type RAM packages employing conventional clamp-ring closures have caused concern over the DOT 6M Specification Package. To clarify these issues, a series of tests were performed to determine the response of the clamp-ring closure to the regulatory Hypothetical Accident Condition (9m) drop tests, for packages at maximum allowable weight. Three enhanced closure designs were also tested: the Clamshell, plywood disk reinforcement, and J-Clip. The results of the tests showed that the standard closure was unable to retain the top for both Center-of-Gravity-Over-Corner and Shallow Angle cases, for the standard package, at its maximum allowed weight. Similar results were found for packages dropped from a reduced height. The Clamshell design provided the best performance of the enhanced closures. It was concluded that the closure ring design employed on the 6M is inadequate to retain the top during the regulatory test sequence, for packages at the maximum allowed weight. For large heavy packages, the Center-of-Gravity- Over-Corner case is more challenging than the Shallow Angle case. The Clamshell design securely retained the top for all HAC test cases, and prevented formation of any opening which could compromise fire test performance.

SMITH, AC

2004-04-30T23:59:59.000Z

89

Tritium waste package  

DOE Patents (OSTI)

A containment and waste package system for processing and shipping tritium xide waste received from a process gas includes an outer drum and an inner drum containing a disposable molecular sieve bed (DMSB) seated within outer drum. The DMSB includes an inlet diffuser assembly, an outlet diffuser assembly, and a hydrogen catalytic recombiner. The DMSB absorbs tritium oxide from the process gas and converts it to a solid form so that the tritium is contained during shipment to a disposal site. The DMSB is filled with type 4A molecular sieve pellets capable of adsorbing up to 1000 curies of tritium. The recombiner contains a sufficient amount of catalyst to cause any hydrogen add oxygen present in the process gas to recombine to form water vapor, which is then adsorbed onto the DMSB.

Rossmassler, Rich (Cranbury, NJ); Ciebiera, Lloyd (Titusville, NJ); Tulipano, Francis J. (Teaneck, NJ); Vinson, Sylvester (Ewing, NJ); Walters, R. Thomas (Lawrenceville, NJ)

1995-01-01T23:59:59.000Z

90

Tritium waste package  

DOE Patents (OSTI)

A containment and waste package system for processing and shipping tritium oxide waste received from a process gas includes an outer drum and an inner drum containing a disposable molecular sieve bed (DMSB) seated within outer drum. The DMSB includes an inlet diffuser assembly, an outlet diffuser assembly, and a hydrogen catalytic recombiner. The DMSB adsorbs tritium oxide from the process gas and converts it to a solid form so that the tritium is contained during shipment to a disposal site. The DMSB is filled with type 4A molecular sieve pellets capable of adsorbing up to 1000 curies of tritium. The recombiner contains a sufficient amount of catalyst to cause any hydrogen and oxygen present in the process gas to recombine to form water vapor, which is then adsorbed onto the DMSB.

Rossmassler, R.; Ciebiera, L.; Tulipano, F.J.; Vinson, S.; Walters, R.T.

1994-12-31T23:59:59.000Z

91

Tritium waste package  

DOE Patents (OSTI)

A containment and waste package system for processing and shipping tritium oxide waste received from a process gas includes an outer drum and an inner drum containing a disposable molecular sieve bed (DMSB) seated within the outer drum. The DMSB includes an inlet diffuser assembly, an outlet diffuser assembly, and a hydrogen catalytic recombiner. The DMSB absorbs tritium oxide from the process gas and converts it to a solid form so that the tritium is contained during shipment to a disposal site. The DMSB is filled with type 4A molecular sieve pellets capable of adsorbing up to 1000 curies of tritium. The recombiner contains a sufficient amount of catalyst to cause any hydrogen and oxygen present in the process gas to recombine to form water vapor, which is then adsorbed onto the DMSB. 1 fig.

Rossmassler, R.; Ciebiera, L.; Tulipano, F.J.; Vinson, S.; Walters, R.T.

1995-11-07T23:59:59.000Z

92

Status of PERST-5 package  

SciTech Connect

The methods and algorithms used in the PERST-5 package are described. This package is part of the MCU-5 code and is intended for neutron-physical calculation of the cells and parts of nuclear reactors using a generalized method of first collision probabilities.

Gomin, E. A.; Gurevich, M. I.; Kalugin, M. A.; Lazarenko, A. P.; Pryanichnikov, A. V., E-mail: prianik@adis.vver.kiae.ru; Sidorenko, V. D. [National Research Centre Kurchatov Institute (Russian Federation); Druzhinin, V. E. [Scientific and Research Institute of Nuclear Power Plant Operation (VNIIAES) (Russian Federation); Zhirnov, A. P.; Rozhdestvenskiy, I. M. [Scientific Research and Design Institute of Electrical Engineering (NIKIET) (Russian Federation)

2012-12-15T23:59:59.000Z

93

CDIAC catalog of numeric data packages and computer model packages  

Science Conference Proceedings (OSTI)

The Carbon Dioxide Information Analysis Center acquires, quality-assures, and distributes to the scientific community numeric data packages (NDPs) and computer model packages (CMPs) dealing with topics related to atmospheric trace-gas concentrations and global climate change. These packages include data on historic and present atmospheric CO{sub 2} and CH{sub 4} concentrations, historic and present oceanic CO{sub 2} concentrations, historic weather and climate around the world, sea-level rise, storm occurrences, volcanic dust in the atmosphere, sources of atmospheric CO{sub 2}, plants` response to elevated CO{sub 2} levels, sunspot occurrences, and many other indicators of, contributors to, or components of climate change. This catalog describes the packages presently offered by CDIAC, reviews the processes used by CDIAC to assure the quality of the data contained in these packages, notes the media on which each package is available, describes the documentation that accompanies each package, and provides ordering information. Numeric data are available in the printed NDPs and CMPs, in CD-ROM format, and from an anonymous FTP area via Internet. All CDIAC information products are available at no cost.

Boden, T.A. [Oak Ridge National Lab., TN (United States). Carbon Dioxide Information Analysis Center; O`Hara, F.M. Jr. [O`Hara (Fred M., Jr.), Oak Ridge, TN (US); Stoss, F.W. [Univ. of Tennessee, Knoxville, TN (US). Energy, Environment, and Resources Center

1993-05-01T23:59:59.000Z

94

Pre-Packaged Data Set List  

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

Pre-Packaged Data Sets You will need to RegisterSign In to Order Pre-Packaged Products. You must RegisterSign In to order Pre-Packaged Products. Close window....

95

A wind-shell interaction model for multipolar planetary nebulae  

E-Print Network (OSTI)

We explore the formation of multipolar structures in planetary and pre-planetary nebulae from the interaction of a fast post-AGB wind with a highly inhomogeneous and filamentary shell structure assumed to form during the final phase of the high density wind. The simulations were performed with a new hydrodynamics code integrated in the interactive framework of the astrophysical modeling package SHAPE. In contrast to conventional astrophysical hydrodynamics software, the new code does not require any programming intervention by the user for setting up or controlling the code. Visualization and analysis of the simulation data has been done in SHAPE without external software. The key conclusion from the simulations is that secondary lobes in planetary nebulae, such as Hubble 5 and K3-17, can be formed through the interaction of a fast low-density wind with a complex high density environment, such as a filamentary circumstellar shell. The more complicated alternative explanation of intermittent collimated outflow...

Steffen, W; Esquivel, A; Garcia-Segura, G; Garcia-Diaz, Ma T; Lopez, J A; Magnor, M

2013-01-01T23:59:59.000Z

96

Project EARTH-12-SHELL6: Shell Geoscience Laboratory (2)  

E-Print Network (OSTI)

an increasingly important topic with wide implications for exploitation of unconventional gas reserves, toxic) This studentship is funded by Shell and is part of a larger Shell-supported research project on shale-gas shale (subject to contract) The development of natural fracture systems in fine-grained sediments is becoming

Henderson, Gideon

97

June 2005 Proper Packaging Required to Maintain ...  

Science Conference Proceedings (OSTI)

... as follows: 1. Wrap in multiple layers of plastic bubble packaging material; 2 ... are another type of standard that is difficult to safely package. ...

2010-12-16T23:59:59.000Z

98

Review of SAR for Packaging Report  

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

This Packaging Review Guide (PRG) provides guidance for Department of Energy (DOE) review and approval of packagings to transport fissile and Type B quantities of radioactive material.

99

In-Package Chemistry Abstraction  

SciTech Connect

This report was developed in accordance with the requirements in ''Technical Work Plan for: Regulatory Integration Modeling and Analysis of the Waste Form and Waste Package'' (BSC 2004 [DIRS 171583]). The purpose of the in-package chemistry model is to predict the bulk chemistry inside of a breached waste package and to provide simplified expressions of that chemistry as function of time after breach to Total Systems Performance Assessment for the License Application (TSPA-LA). The scope of this report is to describe the development and validation of the in-package chemistry model. The in-package model is a combination of two models, a batch reactor model that uses the EQ3/6 geochemistry-modeling tool, and a surface complexation model that is applied to the results of the batch reactor model. The batch reactor model considers chemical interactions of water with the waste package materials and the waste form for commercial spent nuclear fuel (CSNF) waste packages and codisposed waste packages that contain both high-level waste glass (HLWG) and DOE spent fuel. The surface complexation model includes the impact of fluid-surface interactions (i.e., surface complexation) on the resulting fluid composition. The model examines two types of water influx: (1) the condensation of water vapor that diffuses into the waste package, and (2) seepage water that enters the waste package from the drift as a liquid. (1) Vapor Influx Case: The condensation of vapor onto the waste package internals is simulated as pure H2O and enters at a rate determined by the water vapor pressure for representative temperature and relative humidity conditions. (2) Water Influx Case: The water entering a waste package from the drift is simulated as typical groundwater and enters at a rate determined by the amount of seepage available to flow through openings in a breached waste package. TSPA-LA uses the vapor influx case for the nominal scenario for simulations where the waste package has been breached but the drip shield remains intact, so all of the seepage flow is diverted from the waste package. The chemistry from the vapor influx case is used to determine the stability of colloids and the solubility of radionuclides available for transport by diffusion, and to determine the degradation rates for the waste forms. TSPA-LA uses the water influx case for the seismic scenario, where the waste package has been breached and the drip shield has been damaged such that seepage flow is actually directed into the waste package. The chemistry from the water influx case that is a function of the flow rate is used to determine the stability of colloids and the solubility of radionuclides available for transport by diffusion and advection, and to determine the degradation rates for the CSNF and HLW glass. TSPA-LA does not use this model for the igneous scenario. Outputs from the in-package chemistry model implemented inside TSPA-LA include pH, ionic strength, and total carbonate concentration. These inputs to TSPA-LA will be linked to the following principle factors: dissolution rates of the CSNF and HLWG, dissolved concentrations of radionuclides, and colloid generation.

E. Thomas

2004-11-09T23:59:59.000Z

100

Managing Feedwater Heater Shell Thinning  

SciTech Connect

Thinning of feedwater heater (FWH) shells has become an important issue throughout the U.S. nuclear industry. The thinning occurs primarily in the vicinity of the extraction steam and drain inlet nozzles where two-phase steam/water mixtures enter the heater. The thinning can be general wall thinning over a large area or highly localized thinning in a limited area. Eventually, shell repairs become necessary to ensure integrity of the pressure boundary and personnel safety, and to restore compliance with the ASME pressure vessel code. Ideally, long-term monitoring of the thickness of FWH shells would allow for timely repairs before the wall thickness decreases below the ASME Code minimum wall thickness. However, since most plants did not start inspecting FWH shells until recently, the initial inspection may find shells that are thinned to near or below the ASME Code minimum wall thickness. Because the cost and manpower requirements for shell repairs can be significant, it is imperative that shell repairs provide a long-term solution and that they be implemented as a planned outage evolution. Accordingly, the approach to managing FWH shell thinning must provide sufficient advance warning of the need for repairs while ensuring safe operation until the permanent repair can be implemented. The approach outlined in this paper does both. Establish acceptance criteria to ensure safe, interim operation with thinned shells until a permanent repair can be implemented. Develop contingency plans for interim repairs should the inspections identify thinning below the interim acceptance criteria. Inspect FWH shells during a refueling outage or possibly during planned system outages or power reductions. If necessary, perform interim repairs to ensure safe operation until the next refueling outage. Develop and implement permanent repairs that will prevent shell thinning. (authors)

Simons, John W.; Keating, Robert B. [MPR Associates Inc., 140 Mustang Circle, Simpsonville, SC 29681 (United States)

2002-07-01T23:59:59.000Z

Note: This page contains sample records for the topic "reduce shell package" 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

Foam shell cryogenic ICF target  

SciTech Connect

A uniform cryogenic layer of DT fuel is maintained in a fusion target having a low density, small pore size, low Z rigid foam shell saturated with liquid DT fuel. Capillary action prevents gravitational slumping of the fuel layer. The saturated shell may be cooled to produce a solid fuel layer.

Darling, Dale H. (Pleasanton, CA)

1987-01-01T23:59:59.000Z

102

How is an egg shell formed?  

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

How is an egg shell formed? Name: Tim Location: NA Country: NA Date: NA Question: How is an egg shell formed? Replies: Egg shells are formed by a complex interaction between a...

103

Shell Solar | Open Energy Information  

Open Energy Info (EERE)

Solar Solar Jump to: navigation, search Name Shell Solar Place The Hague, Netherlands Zip 2501 AN Sector Solar Product Shell Solar is developing non-crystalline PV technology, notably CIS, following the sale of nearly all its crystalline silicon PV operations to SolarWorld in early 2006. References Shell Solar[1] Information About Partnership with NREL Partnership with NREL Yes Partnership Type Uses NREL Research Facilities Partnering Center within NREL National Center for Photovoltaics Partnership Year 2006 LinkedIn Connections CrunchBase Profile No CrunchBase profile. Create one now! This article is a stub. You can help OpenEI by expanding it. Shell Solar is a company located in The Hague, Netherlands . References ↑ "Shell Solar" Retrieved from

104

Packaging Review Guide for Reviewing Safety Analysis Reports for Packagings  

SciTech Connect

This Packaging Review Guide (PRG) provides guidance for Department of Energy (DOE) review and approval of packagings to transport fissile and Type B quantities of radioactive material. It fulfills, in part, the requirements of DOE Order 460.1B for the Headquarters Certifying Official to establish standards and to provide guidance for the preparation of Safety Analysis Reports for Packagings (SARPs). This PRG is intended for use by the Headquarters Certifying Official and his or her review staff, DOE Secretarial offices, operations/field offices, and applicants for DOE packaging approval. This PRG is generally organized at the section level in a format similar to that recommended in Regulatory Guide 7.9 (RG 7.9). One notable exception is the addition of Section 9 (Quality Assurance), which is not included as a separate chapter in RG 7.9. Within each section, this PRG addresses the technical and regulatory bases for the review, the manner in which the review is accomplished, and findings that are generally applicable for a package that meets the approval standards. This Packaging Review Guide (PRG) provides guidance for DOE review and approval of packagings to transport fissile and Type B quantities of radioactive material. It fulfills, in part, the requirements of DOE O 460.1B for the Headquarters Certifying Official to establish standards and to provide guidance for the preparation of Safety Analysis Reports for Packagings (SARPs). This PRG is intended for use by the Headquarters Certifying Official and his review staff, DOE Secretarial offices, operations/field offices, and applicants for DOE packaging approval. The primary objectives of this PRG are to: (1) Summarize the regulatory requirements for package approval; (2) Describe the technical review procedures by which DOE determines that these requirements have been satisfied; (3) Establish and maintain the quality and uniformity of reviews; (4) Define the base from which to evaluate proposed changes in scope and requirements of reviews; and (5) Provide the above information to DOE organizations, contractors, other government agencies, and interested members of the general public. This PRG was originally published in September 1987. Revision 1, issued in October 1988, added new review sections on quality assurance and penetrations through the containment boundary, along with a few other items. Revision 2 was published October 1999. Revision 3 of this PRG is a complete update, and supersedes Revision 2 in its entirety.

DiSabatino, A; Biswas, D; DeMicco, M; Fisher, L E; Hafner, R; Haslam, J; Mok, G; Patel, C; Russell, E

2007-04-12T23:59:59.000Z

105

TRU waste transportation package development  

SciTech Connect

Inventories of the transuranic wastes buried or stored at various US DOE sites are tabulated. The leading conceptual design of Type-B packaging for contact-handled transuranic waste is the Transuranic Package Transporter (TRUPACT), a large metal container comprising inner and outer tubular steel frameworks which are separated by rigid polyurethane foam and sheathed with steel plate. Testing of TRUPACT is reported. The schedule for its development is given. 6 figures. (DLC)

Eakes, R. G.; Lamoreaux, G. H.; Romesberg, L. E.; Sutherland, S. H.; Duffey, T. A.

1980-01-01T23:59:59.000Z

106

Cosan Shell JV | Open Energy Information  

Open Energy Info (EERE)

Jump to: navigation, search Name Cosan & Shell JV Place Brazil Product Brazil-based bioethanol manufacturing joint venture. References Cosan & Shell JV1 LinkedIn Connections...

107

Overview of Hanford Single Shell Tank (SST) Structural Integrity - 14023  

Science Conference Proceedings (OSTI)

To improve the understanding of the single-shell tanks (SSTs) integrity, Washington River Protection Solutions, LLC (WRPS), the USDOE Hanford Site tank contractor, developed an enhanced Single-Shell Tank Integrity Project (SSTIP) in 2009. An expert panel on SST integrity, consisting of various subject matters experts in industry and academia, was created to provide recommendations supporting the development of the project. This panel developed 33 recommendations in four main areas of interest: structural integrity, liner degradation, leak integrity and prevention, and mitigation of contamination migration, Seventeen of these recommendations were used to develop the basis for the M-45-10-1 Change Package for the Hanford Federal Agreement and Compliance Order, which is also known as the Tri-Party Agreement. The structural integrity of the tanks is a key element in completing the cleanup mission at the Hanford Site. There are eight primary recommendations related to the structural integrity of Hanford Single-Shell Tanks. Six recommendations are being implemented through current and planned activities. The structural integrity of the Hanford is being evaluated through analysis, monitoring, inspection, materials testing, and construction document review. Structural evaluation in the form of analysis is performed using modern finite element models generated in ANSYS. The analyses consider in-situ, thermal, operating loads and natural phenomena such as earthquakes. Structural analysis of 108 of 149 Hanford Single-Shell Tanks has concluded that the tanks are structurally sound and meet current industry standards. Analysis of the remaining Hanford Single-Shell Tanks is scheduled for FY2014. Hanford Single-Shell Tanks are monitored through a dome deflection program. The program looks for deflections of the tank dome greater than ? inch. No such deflections have been recorded. The tanks are also subjected to visual inspection. Digital cameras record the interior surface of the concrete tanks, looking for cracks and other surface conditions that may indicate signs of structural distress. The condition of the concrete and rebar of the Hanford Single-Shell Tanks is currently being tested and planned for additional activities in the near future. Concrete and rebar removed from the dome of a 65 year old tank was tested for mechanics properties and condition. Results indicated stronger than designed concrete with additional Petrographic examination and rebar completed. Material properties determined from previous efforts combined with current testing and construction document review will help to generate a database that will provide indication of Hanford Single-Shell Tank structural integrity.

Rast, Richard S.; Washenfelder, Dennis J.; Johnson, Jeremy M.

2013-11-14T23:59:59.000Z

108

Borehole Data Package for Four CY 2003 RCRA Wells 299-E27-4, 299-E27-21, 299-E27-22, and 299-E27-23 at Single-Shell Tank, Waste Management Area C, Hanford Site, Washington  

Science Conference Proceedings (OSTI)

Four new Resource Conservation and Recovery Act (RCRA) groundwater monitoring wells were installed at the single-shell tank farm Waste Management Area (WMA) C in fiscal year 2003 to fulfill commitments for well installations proposed in the draft Hanford Federal Facility Agreement and Consent Order milestone M-24-00. Well 299-E27-22, installed upgradient, was drilled through the entire uppermost unconfined aquifer to the basalt and wells 299-E27-4, 299-E27-21 and 299-E27-23 were drilled approximately 40 feet into the uppermost unconfined aquifer and installed downgradient of the WMA. Specific objectives for these wells include monitoring the impact, if any, that potential releases from inside the WMA may have on current groundwater conditions (i.e., improved network coverage) and differentiating upgradient groundwater contamination from contaminants released at the WMA. This report supplies the information obtained during drilling, characterization, and installation of the four new groundwater monitoring wells. This document also provides a compilation of hydrogeologic and well construction information obtained during drilling, well development, aquifer testing, and sample collection/analysis activities.

Williams, Bruce A.; Narbutovskih, Susan M.

2004-05-12T23:59:59.000Z

109

Optimum rotationally symmetric shells for flywheel rotors  

DOE Patents (OSTI)

A flywheel rim support formed from two shell halves. Each of the shell halves has a disc connected to the central shaft. A first shell element connects to the disc at an interface. A second shell element connects to the first shell element. The second shell element has a plurality of meridional slits. A cylindrical shell element connects to the second shell element. The cylindrical shell element connects to the inner surface of the flywheel rim. A flywheel rim support having a disc connected an outer diameter of a shaft. Two optimally shaped shell elements connect to the optimally shaped disc at an interface. The interface defines a discontinuity in a meridional slope of said support. A cylindrical shell element connects to the two shell elements. The cylindrical shell element has an outer surface for connecting to the inner surface of the flywheel rim. A flywheel rim casing includes an annular shell connected to the central shaft. The annular shell connects to the flywheel rim. A composite shell surrounds the shaft, annular shell and flywheel rim.

Blake, Henry W. (Oak Ridge, TN)

2000-01-01T23:59:59.000Z

110

Wafer-Package Test Mix for Optimal Defect Detection and Test Time Savings  

Science Conference Proceedings (OSTI)

Editor's note: For years, it has been common to run a test at wafer and then exactly thesame test again at package. This article shows how one company took adetailed look at the wafer/package test mix and adjusted it to reduce costwhile retaining quality.¿Rob ...

Peter C. Maxwell

2003-09-01T23:59:59.000Z

111

Insulative laser shell coupler  

DOE Patents (OSTI)

A segmented coaxial laser shell assembly having at least two water jacket sections, two pairs of interconnection half rings, a dialectric break ring, and a pair of threaded ring sections. Each water jacket section with an inner tubular section that defines an inner laser cavity with water paths adjacent to at least a portion of the exterior of the inner tubular section, and mating faces at the end of the water jacket section through which the inner laser cavity opens and which defines at least one water port therethrough in communication with the water jackets. The water paths also define in their external surface a circumferential notch set back from and in close proximity to the mating face. The dielectric break ring has selected thickness and is placed between, and in coaxial alignment with, the mating faces of two of the adjacent water jacket sections. The break ring also defines an inner laser cavity of the same size and shape as the inner laser cavity of the water jacket sections and at least one water passage through the break ring to communicate with at least one water port through the mating faces of the water jacket sections.

Arnold, Phillip A. (Livermore, CA); Anderson, Andrew T. (Livermore, CA); Alger, Terry W. (Tracy, CA)

1994-01-01T23:59:59.000Z

112

Package for integrated optic circuit and method  

DOE Patents (OSTI)

A structure and method for packaging an integrated optic circuit. The package comprises a first wall having a plurality of microlenses formed therein to establish channels of optical communication with an integrated optic circuit within the package. A first registration pattern is provided on an inside surface of one of the walls of the package for alignment and attachment of the integrated optic circuit. The package in one embodiment may further comprise a fiber holder for aligning and attaching a plurality of optical fibers to the package and extending the channels of optical communication to the fibers outside the package. In another embodiment, a fiber holder may be used to hold the fibers and align the fibers to the package. The fiber holder may be detachably connected to the package.

Kravitz, Stanley H. (26 Aspen Rd., Placitas, NM 87043); Hadley, G. Ronald (6012 Annapolis NE., Albuquerque, NM 87111); Warren, Mial E. (3825 Mary Ellen NE., Albuquerque, NM 87111); Carson, Richard F. (1036 Jewel Pl. NE., Albuquerque, NM 87123); Armendariz, Marcelino G. (1023 Oro Real NE., Albuquerque, NM 87123)

1998-01-01T23:59:59.000Z

113

Package for integrated optic circuit and method  

DOE Patents (OSTI)

A structure and method are disclosed for packaging an integrated optic circuit. The package comprises a first wall having a plurality of microlenses formed therein to establish channels of optical communication with an integrated optic circuit within the package. A first registration pattern is provided on an inside surface of one of the walls of the package for alignment and attachment of the integrated optic circuit. The package in one embodiment may further comprise a fiber holder for aligning and attaching a plurality of optical fibers to the package and extending the channels of optical communication to the fibers outside the package. In another embodiment, a fiber holder may be used to hold the fibers and align the fibers to the package. The fiber holder may be detachably connected to the package. 6 figs.

Kravitz, S.H.; Hadley, G.R.; Warren, M.E.; Carson, R.F.; Armendariz, M.G.

1998-08-04T23:59:59.000Z

114

Hanford Site radioactive hazardous materials packaging directory  

SciTech Connect

The Hanford Site Radioactive Hazardous Materials Packaging Directory (RHMPD) provides information concerning packagings owned or routinely leased by Westinghouse Hanford Company (WHC) for offsite shipments or onsite transfers of hazardous materials. Specific information is provided for selected packagings including the following: general description; approval documents/specifications (Certificates of Compliance and Safety Analysis Reports for Packaging); technical information (drawing numbers and dimensions); approved contents; areas of operation; and general information. Packaging Operations & Development (PO&D) maintains the RHMPD and may be contacted for additional information or assistance in obtaining referenced documentation or assistance concerning packaging selection, availability, and usage.

McCarthy, T.L.

1995-12-01T23:59:59.000Z

115

Work Packages for Site Support Service at Los Alamos National  

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

Work Packages for Site Support Service at Los Alamos National Work Packages for Site Support Service at Los Alamos National Laboratory-IG-0746 Work Packages for Site Support Service at Los Alamos National Laboratory-IG-0746 The Department of Energy's Los Alarnos National Laboratory (LANL) enhances global security by ensuring the safety and reliability of the U.S. nuclear weapons stockpile; developing technical solutioils to reduce the threat of weapons of mass destnlction; and solving problems related to energy, environn~ent,i nfrastructure, healtl~a, nd national security. Site support services at the Laboratory, iilcludiilg maintenance and repairs, are provided by the contractor KSL. Maintenance and repair work perfomled by KSL are controlled by the requirements of LANL Irnplementation Procedure IMP 300.2, Integrated Work Management for Work

116

Technology transfer package on seismic base isolation - Volume I  

Science Conference Proceedings (OSTI)

This Technology Transfer Package provides some detailed information for the U.S. Department of Energy (DOE) and its contractors about seismic base isolation. Intended users of this three-volume package are DOE Design and Safety Engineers as well as DOE Facility Managers who are responsible for reducing the effects of natural phenomena hazards (NPH), specifically earthquakes, on their facilities. The package was developed as part of DOE's efforts to study and implement techniques for protecting lives and property from the effects of natural phenomena and to support the International Decade for Natural Disaster Reduction. Volume I contains the proceedings of the Workshop on Seismic Base Isolation for Department of Energy Facilities held in Marina Del Rey, California, May 13-15, 1992.

NONE

1995-02-14T23:59:59.000Z

117

NIST Handbook 133 Checking the Net Contents of Packaged ...  

Science Conference Proceedings (OSTI)

... 4. Except for aerosol or other pressurized packages, open the sample packages, empty, clean, and dry them as appropriate for the packaging ...

2012-11-14T23:59:59.000Z

118

MODEL 9975 LIFE EXTENSION PACKAGE 1 - FINAL REPORT  

Science Conference Proceedings (OSTI)

Life extension package LE1 (9975-03382) was instrumented and subjected to a temperature/humidity environment that bounds KAMS package storage conditions for 92 weeks. During this time, the maximum fiberboard temperature was {approx}180 F, and was established by a combination of internal heat (12 watts) and external heat ({approx}142 F). The relative humidity external to the package was maintained at 80 %RH. This package was removed from test in November 2010 after several degraded conditions were observed during a periodic examination. These conditions included degraded fiberboard (easily broken, bottom layer stuck to the drum), corrosion of the drum, and separation of the air shield from the upper fiberboard assembly. Several tests and parameters were used to characterize the package components. Results from these tests generally indicate agreement between this full-scale shipping package and small-scale laboratory tests on fiberboard and O-ring samples. These areas of agreement include the rate of fiberboard weight loss, change in fiberboard thermal conductivity, fiberboard compression strength, and O-ring compression set. In addition, this package provides an example of the extent to which moisture within the fiberboard can redistribute in the presence of a temperature gradient such as might be created by a 12 watt internal heat load. Much of the moisture near the fiberboard ID surface migrated towards the OD surface, but there was not a significant axial moisture gradient during most of the test duration. Only during the last inspection period (i.e. after 92 weeks exposure during the second phase) did enough moisture migrate to the bottom fiberboard layers to cause saturation. A side effect of moisture migration is the leaching of soluble compounds from the fiberboard. In particular, the corrosion observed on the drum appears related primarily to the leaching and concentration of chlorides. In most locations, this attack appears to be general corrosion, with shallow attack of the drum surface. The primary areas susceptible to corrosion are weld/heat-affected zones. However, one corrosion location not immediately associated with a weld was tested for, and confirmed as having, throughwall penetration. An increase in the axial gap at the top of the package is also related to the migration of moisture within the fiberboard. As moisture redistributes within the package, a majority of the fiberboard loses moisture (on average) and shrinks axially. In addition, an increased moisture content of the bottom fiberboard layers locally reduces its compression strength, leading to compaction of those layers under the weight of the package internal components. In addition to these moisture-driven phenomena, the fiberboard will shrink due to slow pyrolysis in an elevated temperature/humidity environment. Under the collective influence of these effects, the axial gap in the LE1 package increased from an initial value of 0.58 inch and exceeded the 1 inch (maximum) criterion after approximately 18 weeks conditioning. The axial gap eventually reached 1.86 inches. Despite the degradation seen in several of the package components (drum, fiberboard, shield and O-rings), the package appears to have retained sufficient integrity to meet the functional requirements for storage in KAMS. This demonstrates a degree of robustness in the package design relative to the storage environment.

Daugherty, W.

2011-03-04T23:59:59.000Z

119

Semiclassical environment of collapsing shells  

E-Print Network (OSTI)

We explore in detail the semiclassical environment of collapsing shells of matter, and determine the semiclassical flux measured by a variety of observers. This study is a preliminary step in a broader investigation of thermodynamic properties of the geometry of collapsing objects. Specifically, in this paper we consider spherically symmetric null and timelike collapsing shells which form an event horizon, and calculate the flux measured by observers both inside and outside the shell, and both inside and outside the event horizon, and find nontrivial results in most of the cases. Additionally, we also investigate the environment of a shell which collapses but \\emph{does not} form a horizon, halting at some radius larger than the Schwarzschild radius, and find that such an object generically gives rise to a pulse of radiation which is sharply peaked as it travels inwards and is reflected at the origin, and eventually emerges from the shell in a "thermalized" form. Our results have potential consequences in addressing questions pertaining, e.g. to black hole entropy and backreaction.

Kinjal Banerjee; Aseem Paranjape

2009-09-25T23:59:59.000Z

120

Technical Data Package Standards Development Summit  

Science Conference Proceedings (OSTI)

Technical Data Package Standards Development Summit. Purpose: ... Breakout Groups (session will begin after lunch): · Data Delivery/Content. ...

2011-10-11T23:59:59.000Z

Note: This page contains sample records for the topic "reduce shell package" 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

One-to-Many Multimodal Fusion Package  

Science Conference Proceedings (OSTI)

The One-to-many Multimodal Fusion Package. Participants from the Iris Exchange (IREX) III Evaluation and the Multibiometrics ...

2012-04-05T23:59:59.000Z

122

Model Based Enterprise / Technical Data Package Summit ...  

Science Conference Proceedings (OSTI)

Page 1. NIST Technical Note 1753 Model Based Enterprise / Technical Data Package Summit Report Joshua Lubell Kenway ...

2012-10-22T23:59:59.000Z

123

MST: Organizations: Thin Film, Vacuum, and Packaging  

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

Processes & Services Electronic Fabrication Manufacturing Process Science & Technology Thin Film, Vacuum, & Packaging Organic Materials Ceramic & Glass Meso Manufacturing &...

124

Biodegradable hydrogel film for food packaging  

Science Conference Proceedings (OSTI)

Disposal of waste plastic packaging materials has raised a serious problem worldwide leading to environmental pollution due to the fact that most of the plastic packaging materials are generally non-biodegradable. In this article we have reported about ... Keywords: biodegradable, biopolymer, breathable, compost, hydrogel, packaging

Niladri Roy; Nabanita Saha; Petr Saha

2011-07-01T23:59:59.000Z

125

Principles of Package Design Bertrand Meyer  

E-Print Network (OSTI)

List(lastpage) Fig. 4. Structure of the Manuals. USER / \\ APPLICATION / PROGRAM / ~ PACKAGE ~ , ~ SYSTEM / (compiler Issues The programming language for writing a package should offer a structure corresponding a program structure ("class" in Simula and "package" in Ada) with three cate- gories of elements: data

Meyer, Bertrand

126

The todonotes package Henrik Skov Midtiby  

E-Print Network (OSTI)

The todonotes package Henrik Skov Midtiby henrikmidtiby@gmail.com December 25, 2009 Abstract The todonotes package allows you to insert to­do items in your docu- ment. At any point in the document a list.1 Usage . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 1.2 Package options

Hoffmann, Rolf

127

UML's Package Extension Mechanism: Taking a Closer Look at Package Merge  

E-Print Network (OSTI)

. Since package merge was designed specically to be able to structure the UML metamodel, it is not clearUML's Package Extension Mechanism: Taking a Closer Look at Package Merge by Alanna Pauline Zito #12;Abstract The UML 2 specication introduced the notion of package merge as a means of den- ing

128

On Closed Shells in Nuclei  

DOE R&D Accomplishments (OSTI)

It has been suggested in the past that special numbers of neutrons or protons in the nucleus form a particularly stable configuration.{sup1} The complete evidence for this has never been summarized, nor is it generally recognized how convincing this evidence is. That 20 neutrons or protons (Ca{sup40}) form a closed shell is predicted by the Hartree model. A number of calculations support this fact.{sup2} These considerations will not be repeated here. In this paper, the experimental facts indicating a particular stability of shells of 50 and 82 protons and of 50, 82, and 126 neutrons will be listed.

Mayer, M. G.

1948-02-00T23:59:59.000Z

129

Open Ended Microwave Oven for Packaging  

E-Print Network (OSTI)

A novel open waveguide cavity resonator is presented for the combined variable frequency microwave curing of bumps, underfills and encapsulants, as well as the alignment of devices for fast flip-chip assembly, direct chip attach (DCA) or wafer-scale level packaging (WSLP). This technology achieves radio frequency (RF) curing of adhesives used in microelectronics, optoelectronics and medical devices with potential simultaneous micron-scale alignment accuracy and bonding of devices. In principle, the open oven cavity can be fitted directly onto a flip-chip or wafer scale bonder and, as such, will allow for the bonding of devices through localised heating thus reducing the risk to thermally sensitive devices. Variable frequency microwave (VFM) heating and curing of an idealised polymer load is numerically simulated using a multi-physics approach. Electro-magnetic fields within a novel open ended microwave oven developed for use in micro-electronics manufacturing applications are solved using a de icated Yee sche...

Sinclair, K I; Desmulliez, M Y P; Goussetis, G; Bailey, C; Parrott, K; Sangster, A J

2008-01-01T23:59:59.000Z

130

Packaging and Transportation | Department of Energy  

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

Packaging and Transportation Packaging and Transportation Packaging and Transportation Packaging and Transportation Radiological shipments are accomplished safely. Annually, about 400 million hazardous materials shipments occur in the United States by rail, air, sea, and land. Of these shipments, about three million are radiological shipments. Since Fiscal Year (FY) 2004, EM has completed over 150,000 shipments of radioactive material/waste. Please click here to see Office of Packaging and Transportation Fiscal Year 2012 Annual Report. SUPPORTING PROGRAMS SAFE TRANSPORTATION OF RADIOLOGICAL SHIPMENTS Transportation Emergency Preparedness Program (TEPP) TEPP provides the tools for planning, training and exercises, and technical assistance to assist State and Tribal authorities in preparing for response

131

Transportation and packaging resource guide  

Science Conference Proceedings (OSTI)

The purpose of this resource guide is to provide a convenient reference document of information that may be useful to the U.S. Department of Energy (DOE) and DOE contractor personnel involved in packaging and transportation activities. An attempt has been made to present the terminology of DOE community usage as it currently exists. DOE`s mission is changing with emphasis on environmental cleanup. The terminology or nomenclature that has resulted from this expanded mission is included for the packaging and transportation user for reference purposes. Older terms still in use during the transition have been maintained. The Packaging and Transportation Resource Guide consists of four sections: Sect. 1, Introduction; Sect. 2, Abbreviations and Acronyms; Sect. 3, Definitions; and Sect. 4, References for packaging and transportation of hazardous materials and related activities, and Appendices A and B. Information has been collected from DOE Orders and DOE documents; U.S Department of Transportation (DOT), U.S. Environmental Protection Agency (EPA), and U.S. Nuclear Regulatory Commission (NRC) regulations; and International Atomic Energy Agency (IAEA) standards and other international documents. The definitions included in this guide may not always be a regulatory definition but are the more common DOE usage. In addition, the definitions vary among regulatory agencies. It is, therefore, suggested that if a definition is to be used in a regulatory or a legal compliance issue, the definition should be verified with the appropriate regulation. To assist in locating definitions in the regulations, a listing of all definition sections in the regulations are included in Appendix B. In many instances, the appropriate regulatory reference is indicated in the right-hand margin.

Arendt, J.W.; Gove, R.M.; Welch, M.J.

1994-12-01T23:59:59.000Z

132

Thick-Shell Nanocrystal Quantum Dots  

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

Thick-Shell Nanocrystal Quantum Dots Thick-Shell Nanocrystal Quantum Dots Thick-Shell Nanocrystal Quantum Dots Colloidal nanocrystal quantum dots comprising an inner core having an average diameter of at least 1.5 nm and an outer shell, where said outer shell comprises multiple monolayers, wherein at least 30% of the quantum dots have an on-time fraction of 0.80 or greater under continuous excitation conditions for a period of time of at least 10 minutes. Available for thumbnail of Feynman Center (505) 665-9090 Email Thick-Shell Nanocrystal Quantum Dots Colloidal nanocrystal quantum dots comprising an inner core having an average diameter of at least 1.5 nm and an outer shell, where said outer shell comprises multiple monolayers, wherein at least 30% of the quantum dots have an on-time fraction of 0.80 or greater under continuous

133

Shell Solar India | Open Energy Information  

Open Energy Info (EERE)

Shell Solar India Shell Solar India Place India Sector Solar Product Shell Solar India was created as Shell's solar energy business in India, but has been acquired by Indian privately-held company Environ Energy-Tech. References Shell Solar India[1] LinkedIn Connections CrunchBase Profile No CrunchBase profile. Create one now! This article is a stub. You can help OpenEI by expanding it. Shell Solar India is a company located in India . References ↑ "Shell Solar India" Retrieved from "http://en.openei.org/w/index.php?title=Shell_Solar_India&oldid=350910" Categories: Clean Energy Organizations Companies Organizations Stubs What links here Related changes Special pages Printable version Permanent link Browse properties 429 Throttled (bot load) Error 429 Throttled (bot load)

134

Thick-Shell Nanocrystal Quantum Dots  

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

Thick-Shell Nanocrystal Quantum Dots Thick-Shell Nanocrystal Quantum Dots Colloidal nanocrystal quantum dots comprising an inner core having an average diameter of at least 1.5 nm...

135

Waste Package Design Methodology Report  

Science Conference Proceedings (OSTI)

The objective of this report is to describe the analytical methods and processes used by the Waste Package Design Section to establish the integrity of the various waste package designs, the emplacement pallet, and the drip shield. The scope of this report shall be the methodology used in criticality, risk-informed, shielding, source term, structural, and thermal analyses. The basic features and appropriateness of the methods are illustrated, and the processes are defined whereby input values and assumptions flow through the application of those methods to obtain designs that ensure defense-in-depth as well as satisfy requirements on system performance. Such requirements include those imposed by federal regulation, from both the U.S. Department of Energy (DOE) and U.S. Nuclear Regulatory Commission (NRC), and those imposed by the Yucca Mountain Project to meet repository performance goals. The report is to be used, in part, to describe the waste package design methods and techniques to be used for producing input to the License Application Report.

D.A. Brownson

2001-09-28T23:59:59.000Z

136

Shell structures for biogas plants  

Science Conference Proceedings (OSTI)

The shell structures designed for biogas plants of the fixed-dome type by the Bremen Overseas Research and Development Association are described. Biogas digesters of the design described have been successfully tested in Rwanda and India without structural or contractural problems.

Sasse, L.

1982-01-01T23:59:59.000Z

137

FOAM DENSITY SENSITIVITY STUDY FOR THE 9977 PACKAGE  

SciTech Connect

Two layers of insulation fill the volume of the 9977 package between the drum liner and the shell. One of these layers is composed of General Plastics FR-3716 polyurethane foam (also known as Last-A-Foam{reg_sign}), poured through fill holes in the drum bottom and foamed in place. There was concern that the density of the foam insulating layer may vary due to the manufacturing process and that variations in foam density would compromise the safety basis of the package. Thus, a structural finite element analysis was performed to investigate this concern. The investigation examined the effect of replacing the material properties for the FR-3716 polyurethane foam, which has a density equal to 16 lb{sub m}/ft{sup 3}, with material properties of similar foam with varying densities through finite element analysis of hypothetical accident conditions (HAC) pertaining to impact conditions. The results showed that the functional performance of the containment vessel (CV) was not compromised under the conditions investigated.

Gorczyca, J; Tsu-Te Wu, T

2008-05-02T23:59:59.000Z

138

Dual shell reactor vessel: A pressure-balanced system for high pressure and temperature reactions  

Science Conference Proceedings (OSTI)

The main purpose of this work was to demonstrate the Dual Shell Pressure Balanced Vessel (DSPBV) as a safe and economical reactor for the hydrothermal water oxidation of hazardous wastes. Experimental tests proved that the pressure balancing piston and the leak detection concept designed for this project will work. The DSPBV was sized to process 10 gal/hr of hazardous waste at up to 399{degree}C (750{degree}F) and 5000 psia (34.5 MPa) with a residence time of 10 min. The first prototype reactor is a certified ASME pressure vessel. It was purchased by Innotek Corporation (licensee) and shipped to Pacific Northwest Laboratory for testing. Supporting equipment and instrumentation were, to a large extent, transported here from Battelle Columbus Division. A special air feed system and liquid pump were purchased to complete the package. The entire integrated demonstration system was assembled at PNL. During the activities conducted for this report, the leak detector design was tested on bench top equipment. Response to low levels of water in oil was considered adequate to ensure safety of the pressure vessel. Shakedown tests with water only were completed to prove the system could operate at 350{degree}C at pressures up to 3300 psia. Two demonstration tests with industrial waste streams were conducted, which showed that the DSPBV could be used for hydrothermal oxidation. In the first test with a metal plating waste, chemical oxygen demand, total organic carbon, and cyanide concentrations were reduced over 90%. In the second test with a munitions waste, the organics were reduced over 90% using H{sub 2}O{sub 2} as the oxidant.

Robertus, R.J.; Fassbender, A.G.; Deverman, G.S.

1995-03-01T23:59:59.000Z

139

Leveraging Available Data to Support Extension of Transportation Packages Service Life  

SciTech Connect

Data obtained from testing shipping package materials have been leveraged to support extending the service life of select shipping packages while in nuclear materials transportation. Increasingly, nuclear material inventories are being transferred to an interim storage location where they will reside for extended periods of time. Use of a shipping package to store nuclear materials in an interim storage location has become more attractive for a variety of reasons. Shipping packages are robust and have a qualified pedigree for their performance in normal operation and accident conditions within the approved shipment period and storing nuclear material within a shipping package results in reduced operations for the storage facility. However, the shipping package materials of construction must maintain a level of integrity as specified by the safety basis of the storage facility through the duration of the storage period, which is typically well beyond the one year transportation window. Test programs have been established to obtain aging data on materials of construction that are the most sensitive/susceptible to aging in certain shipping package designs. The collective data are being used to support extending the service life of shipping packages in both transportation and storage.

Dunn, K.; Abramczyk, G.; Bellamy, S.; Daugherty, W.; Hackney, B.; Hoffman, E.; Skidmore, E.; Stefek, T.

2012-06-12T23:59:59.000Z

140

Doc.381, 'Nose flutes and shell trumpets'  

E-Print Network (OSTI)

flutes and shell trumpets Translation of title Description (to be used in archive entry) Audio recording of nose flutes and shell trumpets, 15 min 51 seconds 1) Nose flute, fangofango - Copy of BBC recording (Library number 20468) made in December 1953... , recorded in July 1957, in Suva by the Fiji Broadcasting commission. Arranged recording [6.25-9.20] 4) Shell trumpet. Blowing of the triton shell or davui, at Rakiraki, Kadavu, October 1955. Arranged recording [9.34-9.56] 5) Shell trumpet. Blowing...

Roth, George Kingsley

Note: This page contains sample records for the topic "reduce shell package" 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

NFR TRIGA package design review report  

SciTech Connect

The purpose of this document is to compile, present and document the formal design review of the NRF TRIGA packaging. The contents of this document include: the briefing meeting presentations, package description, design calculations, package review drawings, meeting minutes, action item lists, review comment records, final resolutions, and released drawings. This design review required more than two meeting to resolve comments. Therefore, there are three meeting minutes and two action item lists.

Clements, M.D.

1994-08-26T23:59:59.000Z

142

Shell Morocco | Open Energy Information  

Open Energy Info (EERE)

Morocco Morocco Jump to: navigation, search Logo: Shell Morocco Name Shell Morocco Address Immeuble Le Zenith II Place Casablanca, Morocco Zip 20190 Product Production and Distribution of Lubricants for motorists and industries; Storage and Distribution of Oils and LPG; Marine and Aviation; Off-Shore Exploration Year founded 1922 Phone number +212 (0) 522 972727 Website http://www.shell.com/home/cont Coordinates 38.959732°, -77.3419799° Loading map... {"minzoom":false,"mappingservice":"googlemaps3","type":"ROADMAP","zoom":14,"types":["ROADMAP","SATELLITE","HYBRID","TERRAIN"],"geoservice":"google","maxzoom":false,"width":"600px","height":"350px","centre":false,"title":"","label":"","icon":"","visitedicon":"","lines":[],"polygons":[],"circles":[],"rectangles":[],"copycoords":false,"static":false,"wmsoverlay":"","layers":[],"controls":["pan","zoom","type","scale","streetview"],"zoomstyle":"DEFAULT","typestyle":"DEFAULT","autoinfowindows":false,"kml":[],"gkml":[],"fusiontables":[],"resizable":false,"tilt":0,"kmlrezoom":false,"poi":true,"imageoverlays":[],"markercluster":false,"searchmarkers":"","locations":[{"text":"","title":"","link":null,"lat":38.959732,"lon":-77.3419799,"alt":0,"address":"","icon":"","group":"","inlineLabel":"","visitedicon":""}]}

143

FAQS Qualification Card - NNSA Package Certification Engineer |  

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

NNSA Package Certification Engineer NNSA Package Certification Engineer FAQS Qualification Card - NNSA Package Certification Engineer A key element for the Department's Technical Qualification Programs is a set of common Functional Area Qualification Standards (FAQS) and associated Job Task Analyses (JTA). These standards are developed for various functional areas of responsibility in the Department, including oversight of safety management programs identified as hazard controls in Documented Safety Analyses (DSA). For each functional area, the FAQS identify the minimum technical competencies and supporting knowledge and skills for a typical qualified individual working in the area. FAQC-NNSAPackageCertificationEngineer.docx Description NNSA Package Certification Engineer Qualification Card

144

The Disappearing Package - Materials Technology @ TMS  

Science Conference Proceedings (OSTI)

Feb 25, 2013 ... The largest percentage of this—about 76 million tons—is attributable to consumer packaging. For More Information: Visit The Disappearing ...

145

CH Packaging Operations for High Wattage Waste  

Science Conference Proceedings (OSTI)

This document provides instructions for assembling the following CH packaging payload: Drum payload assembly Standard Waste Box (SWB) assembly Ten-Drum Overpack (TDOP)

Washington TRU Solutions LLC

2006-01-06T23:59:59.000Z

146

Volvo Logistics Corporation Returnable Packaging System.  

E-Print Network (OSTI)

?? This thesis is a study for analysing costs affected by packaging in a producing industry. The purpose is to develop a model that will… (more)

Beselin Hallberg, Jacob

2008-01-01T23:59:59.000Z

147

DL_POLY Molecular Simulation Package  

Science Conference Proceedings (OSTI)

Jan 8, 2008 ... DL_POLY is a general purpose serial and parallel molecular dynamics simulation package developed at Daresbury Laboratory by W. Smith, ...

148

FAQS Reference Guide – NNSA Package Certification Engineer  

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

This reference guide addresses the competency statements in the February 2009 edition of DOE-STD-1026-2009, NNSA Package Certification Engineer Functional Area Qualification Standard.

149

PRIDE Surveillance Projects Data Packaging Project Information Package Specification Version 1.1  

Science Conference Proceedings (OSTI)

Information Package Specification version 1.1 describes an XML document format called an information package that can be used to store information in information management systems and other information archives. An information package consists of package information, the context required to understand and use that information, package metadata that describes the information, and XML signatures that protect the information. The information package described in this specification was designed to store Department of Energy (DOE) and National Nuclear Security Administration (NNSA) information and includes the metadata required for that information: a unique package identifier, information marking that conforms to DOE and NNSA requirements, and access control metadata. It is an implementation of the Open Archival Information System (OAIS) Reference Model archival information package tailored to meet NNSA information storage requirements and designed to be used in the computing environments at the Y-12 National Security Complex and at other NNSA sites.

Kelleher, D. M.; Shipp, R. L.; Mason, J. D.

2010-08-31T23:59:59.000Z

150

PRIDE Surveillance Projects Data Packaging Project, Information Package Specification Version 1.0  

Science Conference Proceedings (OSTI)

This document contains a specification for a standard XML document format called an information package that can be used to store information and the context required to understand and use that information in information management systems and other types of information archives. An information package consists of packaged information, a set of information metadata that describes the packaged information, and an XML signature that protects the packaged information. The information package described in this specification was designed to be used to store Department of Energy (DOE) and National Nuclear Security Administration (NNSA) information and includes the metadata required for that information: a unique package identifier, information marking that conforms to DOE and NNSA requirements, and access control metadata. Information package metadata can also include information search terms, package history, and notes. Packaged information can be text content, binary content, and the contents of files and other containers. A single information package can contain multiple types of information. All content not in a text form compatible with XML must be in a text encoding such as base64. Package information is protected by a digital XML signature that can be used to determine whether the information has changed since it was signed and to identify the source of the information. This specification has been tested but has not been used to create production information packages. The authors expect that gaps and unclear requirements in this specification will be identified as this specification is used to create information packages and as information stored in information packages is used. The authors expect to issue revised versions of this specification as needed to address these issues.

Kelleher, D.M.; Shipp, R. L.; Mason, J. D.

2009-09-28T23:59:59.000Z

151

Shell India Pvt Ltd | Open Energy Information  

Open Energy Info (EERE)

India Pvt Ltd India Pvt Ltd Jump to: navigation, search Name Shell India Pvt. Ltd. Place New Delhi, Delhi (NCT), India Sector Services, Solar Product Delhi-based subsidiary of Royal Dutch Shell having interests in natural gas (LNG), liquefied petroleum gas (LPG), lubricants and bitumen. The firm also owns a Technology and financial shared services center. The firm is also operating in solar energy. References Shell India Pvt. Ltd.[1] LinkedIn Connections CrunchBase Profile No CrunchBase profile. Create one now! This article is a stub. You can help OpenEI by expanding it. Shell India Pvt. Ltd. is a company located in New Delhi, Delhi (NCT), India . References ↑ "Shell India Pvt. Ltd." Retrieved from "http://en.openei.org/w/index.php?title=Shell_India_Pvt_Ltd&oldid=350907"

152

Innovative Approaches to Large Component Packaging  

Science Conference Proceedings (OSTI)

Radioactive waste disposal often times requires creative approaches in packaging design, especially for large components. Innovative design techniques are required to meet the needs for handling, transporting, and disposing of these large packages. Large components (i.e., Reactor Pressure Vessel (RPV) heads and even RPVs themselves) require special packaging for shielding and contamination control, as well as for transport and disposal. WMG Inc designed and used standard packaging for RPV heads without control rod drive mechanisms (CRDMs) attached for five RPV heads and has also more recently met an even bigger challenge and developed the innovative Intact Vessel Head Transport System (IVHTS) for RPV heads with CRDMs intact. This packaging system has been given a manufacturer's exemption by the United States Department of Transportation (USDOT) for packaging RPV heads. The IVHTS packaging has now been successfully used at two commercial nuclear power plants. Another example of innovative packaging is the large component packaging that WMG designed, fabricated, and utilized at the West Valley Demonstration Project (WVDP). In 2002, West Valley's high-level waste vitrification process was shut down in preparation for D and D of the West Valley Vitrification Facility. Three of the major components of concern within the Vitrification Facility were the Melter, the Concentrate Feed Makeup Tank (CFMT), and the Melter Feed Holdup Tank (MFHT). The removal, packaging, and disposition of these three components presented significant radiological and handling challenges for the project. WMG designed, fabricated, and installed special packaging for the transport and disposal of each of these three components, which eliminated an otherwise time intensive and costly segmentation process that WVDP was considering. Finally, WMG has also designed and fabricated special packaging for both the Connecticut Yankee (CY) and San Onofre Nuclear Generating Station (SONGS) RPVs. This paper presents the approach that has been successfully used for planning, implementing, and preparing for the disposition of large components such as those mentioned previously. It addresses the major regulatory and design requirements for packaging, transporting, and disposing of these components. The specific topics that are covered include radiological characterization, shielding, packaging design, on-site handling and movement, off-site transportation options, a brief discussion on disposition, and lessons learned. (authors)

Freitag, A.; Hooper, M.; Posivak, E.; Sullivan, J. [WMG, Inc., Peekskill, NY 10566 (United States)

2006-07-01T23:59:59.000Z

153

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:

154

Shell boosts recovery at Kernridge  

Science Conference Proceedings (OSTI)

Since acquiring the Kernridge property in December 1979, Shell Oil Co. has drilled more than 1,800 wells and steadily increased production from 42,000 to 89,000 b/d of oil. Currently, the Kernridge Production Division of Shell California Production Inc. (SCPI), a newly formed subsidiary of Shell Oil Co., is operator for the property. The property covers approximately 35,000 mostly contiguous net acres, with production concentrated mainly on about 5,500 net acres. SCPI's four major fields in the area are the North and South Belridge, Lost Hills, and Antelope Hills. Most of the production comes from the North and South Belridge fields, which were previously held by the Belridge Oil Co. Productive horizons in the fields are the Tulare, Diatomite, Brown Shale, Antelope Shale, 64 Zone, and Agua sand. The Tulare and Diatomite are the two major reservoirs SCPI is developing. The Tulare, encountered between 400 and 1,300 ft, is made up of fine- to coarse-grained, unconsolidated sands with interbedded shales and silt stones and contains 13 /sup 0/ API oil. Using steam drive as the main recovery method, SCPI estimates an ultimate recovery from the Tulare formation of about 60% of the original 1 billion barrels in place. The Diatomite horizon, found between 800 and 3,500 ft and containing light, 28 /sup 0/ API oil, has high porosity (more than 60%), low permeability (less than 1 md), and natural fractures. Because of the Diatomite's low permeability, fracture stimulation is being used to increase well productivity. SCPI anticipates that approximately 5% of the almost 2 billion barrels of oil originally in place will be recovered by primary production.

Moore, S.

1984-01-01T23:59:59.000Z

155

Enduring Stockpile CMM Shell Inspection Plan (U)  

SciTech Connect

The slides are intended to serve as a high level summary of the CMM Shell Inspection Plan as presented to Pu Sustainment Legacy Pit Production IPT.

Montano, Joshua D. [Los Alamos National Laboratory; Flores, Randy A. [Los Alamos National Laboratory

2012-06-13T23:59:59.000Z

156

Core/Shell Nanophosphors for LED Lighting  

Science Conference Proceedings (OSTI)

Symposium, Symposium H: Advanced Ceramics. Presentation Title, Core/Shell Nanophosphors for LED Lighting. Author(s), Jinkyu Han, Gustavo Hirata, Jan B ...

157

Working and Net Available Shell Storage Capacity  

U.S. Energy Information Administration (EIA)

Containing storage capacity data for crude oil, petroleum products, and selected biofuels. The report includes tables detailing working and net available shell ...

158

Material with core-shell structure  

DOE Patents (OSTI)

Disclosed is a material having a composite particle, the composite particle including an outer shell and a core. The core is made from a lithium alloying material and the outer shell has an inner volume that is greater in size than the core of the lithium alloying material. In some instances, the outer mean diameter of the outer shell is less than 500 nanometers and the core occupies between 5 and 99% of the inner volume. In addition, the outer shell can have an average wall thickness of less than 100 nanometers.

Luhrs, Claudia (Rio Rancho, NM); Richard, Monique N. (Ann Arbor, MI); Dehne, Aaron (Maumee, OH); Phillips, Jonathan (Rio Rancho, NM); Stamm, Kimber L. (Ann Arbor, MI); Fanson, Paul T. (Brighton, MI)

2011-11-15T23:59:59.000Z

159

Experience in Using Fills for Spent Nuclear Fuel Waste Packages  

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

Fills for SNF Waste Packages Experience in Using Fills for Spent Nuclear Fuel Waste Packages The use of other fill materials in waste packages has been investigated by several...

160

Apparatus and methods for installing, removing and adjusting an inner turbine shell section relative to an outer turbine shell section  

DOE Patents (OSTI)

A turbine includes upper and lower inner shell sections mounting the nozzles and shrouds and which inner shell is supported by pins secured to a surrounding outer shell. To disassemble the turbine for access to the inner shell sections and rotor, an alignment fixture is secured to the lower outer shell section and has pins engaging the inner shell section. To disassemble the turbine, the inner shell weight is transferred to the lower outer shell section via the alignment fixture and cradle pins. Roller assemblies are inserted through access openings vacated by support pins to permit rotation of the lower inner shell section out of and into the lower outer shell section during disassembly and assembly. The alignment fixture includes adjusting rods for adjusting the inner shell axially, vertically, laterally and about a lateral axis. A roller over-cage is provided to rotate the inner shell and a dummy shell to facilitate assembly and disassembly in the field.

Leach, David (Niskayuna, NY); Bergendahl, Peter Allen (Scotia, NY); Waldo, Stuart Forrest (Salem, NC); Smith, Robert Leroy (Milford, OH); Phelps, Robert Kim (Milford, OH)

2001-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "reduce shell package" 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

A SHELL MODEL TURBULENT DYNAMO  

Science Conference Proceedings (OSTI)

Turbulent dynamo phenomena, observed almost everywhere in astrophysical objects and also in the laboratory in the recent VKS2 experiment, are investigated using a shell model technique to describe magnetohydrodynamic turbulence. Detailed numerical simulations at very high Rossby numbers ({alpha}{sup 2} dynamo) show that as the magnetic Reynolds number increases, the dynamo action starts working and different regimes are observed. The model, which displays different large-scale coherent behaviors corresponding to different regimes, is able to reproduce the magnetic field reversals observed both in a geomagnetic dynamo and in the VKS2 experiment. While rough quantitative estimates of typical times associated with the reversal phenomenon are consistent with paleomagnetic data, the analysis of the transition from oscillating intermittent through reversal and finally to stationary behavior shows that the nature of the reversals we observe is typical of {alpha}{sup 2} dynamos and completely different from VKS2 reversals. Finally, the model shows that coherent behaviors can also be naturally generated inside the many-mode dynamical chaotic model, which reproduces the complexity of fluid turbulence, as described by the shell technique.

Perrone, D.; Nigro, G.; Veltri, P. [Universita della Calabria, Dipartimento di Fisica and Centro Nazionale Interuniversitario Struttura della Materia, Unita di Cosenza, I-87030 Arcavacata di Rende (Italy)

2011-07-10T23:59:59.000Z

162

LEVERAGING AGING MATERIALS DATA TO SUPPORT EXTENSION OF TRANSPORTATION SHIPPING PACKAGES SERVICE LIFE  

SciTech Connect

Nuclear material inventories are increasingly being transferred to interim storage locations where they may reside for extended periods of time. Use of a shipping package to store nuclear materials after the transfer has become more common for a variety of reasons. Shipping packages are robust and have a qualified pedigree for performance in normal operation and accident conditions but are only certified over an approved transportation window. The continued use of shipping packages to contain nuclear material during interim storage will result in reduced overall costs and reduced exposure to workers. However, the shipping package materials of construction must maintain integrity as specified by the safety basis of the storage facility throughout the storage period, which is typically well beyond the certified transportation window. In many ways, the certification processes required for interim storage of nuclear materials in shipping packages is similar to life extension programs required for dry cask storage systems for commercial nuclear fuels. The storage of spent nuclear fuel in dry cask storage systems is federally-regulated, and over 1500 individual dry casks have been in successful service up to 20 years in the US. The uncertainty in final disposition will likely require extended storage of this fuel well beyond initial license periods and perhaps multiple re-licenses may be needed. Thus, both the shipping packages and the dry cask storage systems require materials integrity assessments and assurance of continued satisfactory materials performance over times not considered in the original evaluation processes. Test programs for the shipping packages have been established to obtain aging data on materials of construction to demonstrate continued system integrity. The collective data may be coupled with similar data for the dry cask storage systems and used to support extending the service life of shipping packages in both transportation and storage.

Dunn, K. [Savannah River National Laboratory; Bellamy, S. [Savannah River National Laboratory; Daugherty, W. [Savannah River National Laboratory; Sindelar, R. [Savannah River National Laboratory; Skidmore, E. [Savannah River National Laboratory

2013-08-18T23:59:59.000Z

163

A Graph Theory Package for Maple - CECM - Simon Fraser University  

E-Print Network (OSTI)

{jfarr,mahdad,skhodada,mmonagan}@cecm.sfu.ca. Abstract. We present a new graph theory package for Maple. The package is presently intended for teaching  ...

164

Applications of Cermets to Meet Operational Waste Package Requirements  

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

Operational Waste Package Requirements Applications of Cermets to Meet Operational Waste Package Requirements The cermet could meet three operational requirements for the waste...

165

Investigations into High Temperature Components and Packaging  

SciTech Connect

The purpose of this report is to document the work that was performed at the Oak Ridge National Laboratory (ORNL) in support of the development of high temperature power electronics and components with monies remaining from the Semikron High Temperature Inverter Project managed by the National Energy Technology Laboratory (NETL). High temperature electronic components are needed to allow inverters to operate in more extreme operating conditions as required in advanced traction drive applications. The trend to try to eliminate secondary cooling loops and utilize the internal combustion (IC) cooling system, which operates with approximately 105 C water/ethylene glycol coolant at the output of the radiator, is necessary to further reduce vehicle costs and weight. The activity documented in this report includes development and testing of high temperature components, activities in support of high temperature testing, an assessment of several component packaging methods, and how elevated operating temperatures would impact their reliability. This report is organized with testing of new high temperature capacitors in Section 2 and testing of new 150 C junction temperature trench insulated gate bipolar transistor (IGBTs) in Section 3. Section 4 addresses some operational OPAL-GT information, which was necessary for developing module level tests. Section 5 summarizes calibration of equipment needed for the high temperature testing. Section 6 details some additional work that was funded on silicon carbide (SiC) device testing for high temperature use, and Section 7 is the complete text of a report funded from this effort summarizing packaging methods and their reliability issues for use in high temperature power electronics. Components were tested to evaluate the performance characteristics of the component at different operating temperatures. The temperature of the component is determined by the ambient temperature (i.e., temperature surrounding the device) plus the temperature increase inside the device due the internal heat that is generated due to conduction and switching losses. Capacitors and high current switches that are reliable and meet performance specifications over an increased temperature range are necessary to realize electronics needed for hybrid-electric vehicles (HEVs), fuel cell (FC) and plug-in HEVs (PHEVs). In addition to individual component level testing, it is necessary to evaluate and perform long term module level testing to ascertain the effects of high temperature operation on power electronics.

Marlino, L.D.; Seiber, L.E.; Scudiere, M.B.; M.S. Chinthavali, M.S.; McCluskey, F.P.

2007-12-31T23:59:59.000Z

166

Packaging and Transportation Support at LANL CTMA 2012  

SciTech Connect

Operations Support Packaging and Transportation (OS-PT) supports LANL in various functions. Some highlights of the past year have been with the work relating to environmental remediation, type B packaging, non-DOT compliant transfers, and special permit training. The TA-21 remediation project was part of the ARRA funding that LANL received. The $212 million in funding was used to demolish 24 buildings at TA-21, excavate the lab's oldest waste disposal site, and install 16 groundwater monitoring wells. The project was completed ahead of schedule and under budget. More than 300 tons of metal was recycled and all the soil excavated from MDA-B was replaced with clean fill. OS-PT supported this projected by transporting more than 7 million pounds of waste to TA-54 Area G with an addendum to their TSD. Because of the public access on the transfer route, Los Alamos County restricted the transfer to happen from 2:00 AM to 4:00 AM. OS-PT conducted 8 transfers in support of this project. Some concerns included the contaminated trailers at receipt facilities when transferring filled Super Sacks. Future Super Sacks were over packed into new IP-2 Super Sacks before shipping. OS-PT is also supporting the remediation of TA-54 Area G. LANL has an agreement with the State of New Mexico to remove all TRU waste currently stored above ground from at Area G. OS-PT supports this initiative with transfers of TRU waste under LANL's TSD and support of TRU shipments to WIPP. Another project supported by our organization is gas cylinder/dewar recycling and remediation. We are focusing on reducing risk associated with unneeded gasses at LANL. To minimized excessive ordering, to save money and time, and to minimize hazards OS-PT is supporting a gas recycling program. This program will allow programmatic organization across LANL to share unused/unneeded gasses. Instead of old dewars being disposed of, OS-PT has began identifying these dewars and sending them for refurbishment. To date, this effort has saved LANL $450K and estimated saving for future efforts will be more than $1.5 million. Some Projects that are happening here at LANL are offsite source recovery, weapon component transfers, and isotope science production. There are specific packages that help support these projects for the shipment of related materials. OS-PT provides support to these packages to ensure they are and will be available to continue this support. The Areva 435-B Overpack will help the Offsite Source Recovery Project recover high activity gamma sources from various locations across the globe. The Safety Analysis for Packaging is scheduled for initial completion June of 2012. The DPP-1 package is designed to replace the Model FL, which was designed by Rocky Flats and began service in 1990. LANL has collaborated on package design with LLNL, Pantex, Y-12, and KCP. LANL is supporting LLNL on component fixture development. Testing to 10 CFR 71 is to be completed in the Fall of 2012 and scheduled for NA-174 approval in 2014. The SAFESHIELD package helps supports LANL's Isotope production projects. This package can transfer highly irradiated materials from LANL's accelerator to material processing facilities. LANL worked to renew the SAFESHEILD's Certification for 5 more years.

Salazar, Nick [Los Alamos National Laboratory

2012-06-08T23:59:59.000Z

167

Packaging and Transportation Support at LANL CTMA 2012  

SciTech Connect

Operations Support Packaging and Transportation (OS-PT) supports LANL in various functions. Some highlights of the past year have been with the work relating to environmental remediation, type B packaging, non-DOT compliant transfers, and special permit training. The TA-21 remediation project was part of the ARRA funding that LANL received. The $212 million in funding was used to demolish 24 buildings at TA-21, excavate the lab's oldest waste disposal site, and install 16 groundwater monitoring wells. The project was completed ahead of schedule and under budget. More than 300 tons of metal was recycled and all the soil excavated from MDA-B was replaced with clean fill. OS-PT supported this projected by transporting more than 7 million pounds of waste to TA-54 Area G with an addendum to their TSD. Because of the public access on the transfer route, Los Alamos County restricted the transfer to happen from 2:00 AM to 4:00 AM. OS-PT conducted 8 transfers in support of this project. Some concerns included the contaminated trailers at receipt facilities when transferring filled Super Sacks. Future Super Sacks were over packed into new IP-2 Super Sacks before shipping. OS-PT is also supporting the remediation of TA-54 Area G. LANL has an agreement with the State of New Mexico to remove all TRU waste currently stored above ground from at Area G. OS-PT supports this initiative with transfers of TRU waste under LANL's TSD and support of TRU shipments to WIPP. Another project supported by our organization is gas cylinder/dewar recycling and remediation. We are focusing on reducing risk associated with unneeded gasses at LANL. To minimized excessive ordering, to save money and time, and to minimize hazards OS-PT is supporting a gas recycling program. This program will allow programmatic organization across LANL to share unused/unneeded gasses. Instead of old dewars being disposed of, OS-PT has began identifying these dewars and sending them for refurbishment. To date, this effort has saved LANL $450K and estimated saving for future efforts will be more than $1.5 million. Some Projects that are happening here at LANL are offsite source recovery, weapon component transfers, and isotope science production. There are specific packages that help support these projects for the shipment of related materials. OS-PT provides support to these packages to ensure they are and will be available to continue this support. The Areva 435-B Overpack will help the Offsite Source Recovery Project recover high activity gamma sources from various locations across the globe. The Safety Analysis for Packaging is scheduled for initial completion June of 2012. The DPP-1 package is designed to replace the Model FL, which was designed by Rocky Flats and began service in 1990. LANL has collaborated on package design with LLNL, Pantex, Y-12, and KCP. LANL is supporting LLNL on component fixture development. Testing to 10 CFR 71 is to be completed in the Fall of 2012 and scheduled for NA-174 approval in 2014. The SAFESHIELD package helps supports LANL's Isotope production projects. This package can transfer highly irradiated materials from LANL's accelerator to material processing facilities. LANL worked to renew the SAFESHEILD's Certification for 5 more years.

Salazar, Nick [Los Alamos National Laboratory

2012-06-08T23:59:59.000Z

168

Refined computational models for laminated shells  

Science Conference Proceedings (OSTI)

This paper presents refined computational models for non homogeneous, deep, doubly curved shells. The theory is based on a kinematical approach in which the continuity conditions for displacements and shear stresses at layer interfaces and on the bounding ... Keywords: bending-torsion warping coupling, multilayered shells, piezoelectric laminates, shear-membrane refinements, stress computations, triangular C1-C1/2 finite element

M. Touratier

2002-01-01T23:59:59.000Z

169

Thick-shell nanocrystal quantum dots  

DOE Patents (OSTI)

Colloidal nanocrystal quantum dots comprising an inner core having an average diameter of at least 1.5 nm and an outer shell, where said outer shell comprises multiple monolayers, wherein at least 30% of the quantum dots have an on-time fraction of 0.80 or greater under continuous excitation conditions for a period of time of at least 10 minutes.

Hollingsworth, Jennifer A. (Los Alamos, NM); Chen, Yongfen (Eugene, OR); Klimov, Victor I. (Los Alamos, NM); Htoon, Han (Los Alamos, NM); Vela, Javier (Los Alamos, NM)

2011-05-03T23:59:59.000Z

170

National Defense University (NDU) Nomination Package Checklist  

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

- November 2012 - November 2012 National Defense University (NDU) Nomination Package Checklist SEND 2 COPIES OF THE NOMINATION PACKAGE TO THE NDU UNIVERSITY REGISTRAR'S OFFICE Each student nomination package must include the following items: NDU Student Nomination Form One official transcript (highest degree earned) One-page student biography or résumé (include education and career history) Two Letters of Recommendation World-Wide Travel Statement Statement of Purpose (No more than two pages) Signed National Defense University Privacy Act Statement Signed Education Release Form (if nominating agency requires copies of final student evaluation and/or transcript) SAC students must also include: Senior Acquisition Course Nomination Form

171

Argonne CNM Highlight: Complexity in Core-Shell Nanomagnets  

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

Complexity in Core-Shell Nanomagnets Magnetgic hysteresis of core-shell nanoparticles (curves) Magnetic hysteresis of core-shell Fe@Fe3O4 nanoparticles at 5 K under field cooling...

172

The Fireball integrated code package  

Science Conference Proceedings (OSTI)

Many deep-space satellites contain a plutonium heat source. An explosion, during launch, of a rocket carrying such a satellite offers the potential for the release of some of the plutonium. The fireball following such an explosion exposes any released plutonium to a high-temperature chemically-reactive environment. Vaporization, condensation, and agglomeration processes can alter the distribution of plutonium-bearing particles. The Fireball code package simulates the integrated response of the physical and chemical processes occurring in a fireball and the effect these processes have on the plutonium-bearing particle distribution. This integrated treatment of multiple phenomena represents a significant improvement in the state of the art for fireball simulations. Preliminary simulations of launch-second scenarios indicate: (1) most plutonium vaporization occurs within the first second of the fireball; (2) large non-aerosol-sized particles contribute very little to plutonium vapor production; (3) vaporization and both homogeneous and heterogeneous condensation occur simultaneously; (4) homogeneous condensation transports plutonium down to the smallest-particle sizes; (5) heterogeneous condensation precludes homogeneous condensation if sufficient condensation sites are available; and (6) agglomeration produces larger-sized particles but slows rapidly as the fireball grows.

Dobranich, D.; Powers, D.A.; Harper, F.T.

1997-07-01T23:59:59.000Z

173

Scattering Functions of Yolk-Shell Particles  

SciTech Connect

The single-particle small-angle scattering properties of the yolk-shell particle, a new type of core-shell particle with a mobile core within the hosting shell, are systematically investigated. The Debye spatial autocorrelation function, pair distance distribution function and intraparticle structure factor (form factor) are calculated and compared to the corresponding scattering functions of reference systems of hard sphere and concentric core-shell particles with identical sizes. Based on our theoretical calculations, we find that the broken centrosymmetry, originating from the mobility of the trapped yolk, results in an imaginary scattering amplitude. As a result, it contributes an additional destructive interference term which smears certain features present in the scattering functions of the reference systems. Based on our theoretical models, we present the prospect of jointly using small angle neutron and x-ray scattering techniques to quantitatively determine the structural characteristics of yolk-shell particles.

Li, Xin [ORNL] [ORNL; Liu, Kao-Hsiang [National Taiwan University] [National Taiwan University; Wu, Bin [ORNL] [ORNL; Sanchez-Diaz, Luis E [ORNL] [ORNL; Smith, Gregory Scott [ORNL] [ORNL; Chen, Wei-Ren [ORNL] [ORNL

2013-01-01T23:59:59.000Z

174

21-PWR WASTE PACKAGE WITH ABSORBER PLATES LOADING CURVE EVALUATION  

Science Conference Proceedings (OSTI)

The objective of this calculation is to evaluate the required minimum burnup as a function of initial pressurized water reactor (PWR) assembly enrichment that would permit loading of spent nuclear fuel into the 21 PWR waste package with absorber plates design as provided in Attachment IV. This calculation is an example of the application of the methodology presented in the ''Disposal Criticality Analysis Methodology Topical Report'' (YMP 2003). The scope of this calculation covers a range of enrichments from 0 through 5.0 weight percent U-235, and a burnup range of 0 through 45 GWd/MTU. Higher burnups were not necessary because 45 GWd/MTU was high enough for the loading curve determination. This activity supports the validation of the use of burnup credit for commercial spent nuclear fuel applications. The intended use of these results will be in establishing PWR waste package configuration loading specifications. Limitations of this evaluation are as follows: (1) The results are based on burnup credit for actinides and selected fission products as proposed in YMP (2003, Table 3-1) and referred to as the ''Principal Isotopes''. Any change to the isotope listing will have a direct impact on the results of this report. (2) The results are based on 1.5 wt% Gd in the Ni-Gd Alloy material and having no tuff inside the waste package. If the Gd loading is reduced or a process to introduce tuff inside the waste package is defined, then this report would need to be reevaluated based on the alternative materials. This calculation is subject to the ''Quality Assurance Requirements and Description'' (QARD) (DOE 2004) because it concerns engineered barriers that are included in the ''Q-List'' (BSC 2004k, Appendix A) as items important to safety and waste isolation.

J.M. Scaglione

2004-12-17T23:59:59.000Z

175

Potential benefits of solar reflective car shells: Cooler cabins...  

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

of solar reflective car shells: Cooler cabins, fuel savings and emission reductions Title Potential benefits of solar reflective car shells: Cooler cabins, fuel savings and...

176

Safety evaluation for packaging two plywood boxes  

Science Conference Proceedings (OSTI)

This safety evaluation for packaging evaluates and documents the ability of the plywood boxes listed below to meet the packaging requirements of WHC-CM-2-14, Hazardous Material Packaging and Shipping, for the onsite transfer of Type B radioactive material. Onsite transfer is the transport of hazardous materials on controlled routes confined to established limited areas and to portions of federally owned roadways to which public access is prohibited during transfer. The plywood boxes being used for this transport are PIN number PNLD-95-322 and PNLD-95-385. The contents being transported are wood, plastic, piping, rubber, and gloves. The source term was determined by nondestructive analysis and obtained from the solid waste storage/disposal record. Before the nondestructive analysis, the intention was to transport the boxes under WHC-SD-TP-SEP-020, Safety Evaluation for Packaging (Onsite) Plywood Box (WHC 1994), but Type B shipments are not included.

Flanagan, B.D.

1996-09-26T23:59:59.000Z

177

Radiation Level Changes at RAM Package Surfaces  

Science Conference Proceedings (OSTI)

This paper will explore design considerations required to meet the regulations that limit radiation level variations at external surfaces of radioactive material (RAM) packages. The radiation level requirements at package surfaces (e.g. TS-R-1 paragraphs 531 and 646) invoke not only maximum radiation levels, but also strict limits on the allowable increase in the radiation level during transport. This paper will explore the regulatory requirements by quantifying the amount of near surface movement and/or payload shifting that results in a 20% increase in the radiation level at the package surface. Typical IP-2, IP-3, Type A and Type B packaging and source geometries will be illustrated. Variations in surface radiation levels are typically the result of changes in the geometry of the surface due to an impact, puncture or crush event, or shifting and settling of radioactive contents.

Opperman, Erich [Washington Savannah River Company; Hawk, Mark B [ORNL; Kapoor, Ashok [U.S. Department of Energy, Office of Packaging and Transportation; Natali, Ronald [R. B. Natali Consulting, Inc.

2010-01-01T23:59:59.000Z

178

Waste Package Component Design Methodology Report  

Science Conference Proceedings (OSTI)

This Executive Summary provides an overview of the methodology being used by the Yucca Mountain Project (YMP) to design waste packages and ancillary components. This summary information is intended for readers with general interest, but also provides technical readers a general framework surrounding a variety of technical details provided in the main body of the report. The purpose of this report is to document and ensure appropriate design methods are used in the design of waste packages and ancillary components (the drip shields and emplacement pallets). The methodology includes identification of necessary design inputs, justification of design assumptions, and use of appropriate analysis methods, and computational tools. This design work is subject to ''Quality Assurance Requirements and Description''. The document is primarily intended for internal use and technical guidance for a variety of design activities. It is recognized that a wide audience including project management, the U.S. Department of Energy (DOE), the U.S. Nuclear Regulatory Commission, and others are interested to various levels of detail in the design methods and therefore covers a wide range of topics at varying levels of detail. Due to the preliminary nature of the design, readers can expect to encounter varied levels of detail in the body of the report. It is expected that technical information used as input to design documents will be verified and taken from the latest versions of reference sources given herein. This revision of the methodology report has evolved with changes in the waste package, drip shield, and emplacement pallet designs over many years and may be further revised as the design is finalized. Different components and analyses are at different stages of development. Some parts of the report are detailed, while other less detailed parts are likely to undergo further refinement. The design methodology is intended to provide designs that satisfy the safety and operational requirements of the YMP. Four waste package configurations have been selected to illustrate the application of the methodology during the licensing process. These four configurations are the 21-pressurized water reactor absorber plate waste package (21-PWRAP), the 44-boiling water reactor waste package (44-BWR), the 5 defense high-level radioactive waste (HLW) DOE spent nuclear fuel (SNF) codisposal short waste package (5-DHLWDOE SNF Short), and the naval canistered SNF long waste package (Naval SNF Long). Design work for the other six waste packages will be completed at a later date using the same design methodology. These include the 24-boiling water reactor waste package (24-BWR), the 21-pressurized water reactor control rod waste package (21-PWRCR), the 12-pressurized water reactor waste package (12-PWR), the 5 defense HLW DOE SNF codisposal long waste package (5-DHLWDOE SNF Long), the 2 defense HLW DOE SNF codisposal waste package (2-MC012-DHLW), and the naval canistered SNF short waste package (Naval SNF Short). This report is only part of the complete design description. Other reports related to the design include the design reports, the waste package system description documents, manufacturing specifications, and numerous documents for the many detailed calculations. The relationships between this report and other design documents are shown in Figure 1.

D.C. Mecham

2004-07-12T23:59:59.000Z

179

A Look In the Mirror: Attacks on Package Managers Author Names Removed for Anonymous Submission  

E-Print Network (OSTI)

for security. There is no protection of package metadata or the root metadata. Package Metadata An attacker can of the package in the package meta- data protects the package from tampering. Packages Resistance to metadata, the package metadata is protected from tam- pering. Packages The signature on the root metadata prevents

Hartman, John H.

180

Packaging material for thin film lithium batteries  

SciTech Connect

A thin film battery including components which are capable of reacting upon exposure to air and water vapor incorporates a packaging system which provides a barrier against the penetration of air and water vapor. The packaging system includes a protective sheath overlying and coating the battery components and can be comprised of an overlayer including metal, ceramic, a ceramic-metal combination, a parylene-metal combination, a parylene-ceramic combination or a parylene-metal-ceramic combination.

Bates, John B. (116 Baltimore Dr., Oak Ridge, TN 37830); Dudney, Nancy J. (11634 S. Monticello Rd., Knoxville, TN 37922); Weatherspoon, Kim A. (223 Wadsworth Pl., Oak Ridge, TN 37830)

1996-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "reduce shell package" 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

Example Performance Targets and Efficiency Packages Greensburg, Kansas (Presentation)  

SciTech Connect

This presentation shows the energy performance targets and efficiency packages for residential buildings in Greensburg, Kansas.

Anderson, R.

2008-01-01T23:59:59.000Z

182

Supplement V.F: Packages For Introduction to Java Programming  

E-Print Network (OSTI)

. · To protect classes. Packages provide protection so that the protected members of the classes are accessible of the package name and the file system directory structure. For the package named com.prenhall.mypackage, youSupplement V.F: Packages For Introduction to Java Programming By Y. Daniel Liang 1 Introduction

Liang, Y. Daniel

183

Supplement: Java Packages For Introduction to Java Programming  

E-Print Network (OSTI)

conveniently. Packages group related classes so that they can be easily distributed. To protect classes. Packages provide protection so that the protected members of the classes are accessible to the classes of the package name and the file system directory structure. For the package named com.prenhall.mypackage, you

Liang, Y. Daniel

184

THE PYTHON SHELL FOR THE ORBIT CODE  

Science Conference Proceedings (OSTI)

A development of a Python driver shell for the ORBIT simulation code is presented. The original ORBIT code uses the SuperCode shell to organize accelerator-related simulations. It is outdated, unsupported, and it is an obstacle to future code development. The necessity and consequences of replacing the old shell language are discussed. A set of core modules and extensions that are currently in PyORBIT are presented. They include particle containers, parsers for MAD and SAD lattice files, a Python wrapper for MPI libraries, space charge calculators, TEAPOT trackers, and a laser stripping extension module.

Shishlo, Andrei P [ORNL; Gorlov, Timofey V [ORNL; Holmes, Jeffrey A [ORNL

2009-01-01T23:59:59.000Z

185

Directory of certificiates of compliance for radioactive materials packages: Report of NRC approved packages. Revision 19, Volume 1  

SciTech Connect

This directory provides information on packagings approved by the U.S. Nuclear Regulatory Commission.

NONE

1996-10-01T23:59:59.000Z

186

Preferential CO Oxidation in Hydrogen: Reactivity of Core-Shell Nanoparticles  

Science Conference Proceedings (OSTI)

We report on the first-principles-guided design, synthesis, and characterization of core-shell nanoparticle (NP) catalysts made of a transition metal core (M ) Ru, Rh, Ir, Pd, or Au) covered with a ?1-2 monolayer thick shell of Pt atoms (i.e., a M@Pt core-shell NP). An array of experimental techniques, including X-ray diffraction, Fourier transform infrared spectroscopy, high resolution transmission electron microscopy, and temperature-programmed reaction, are employed to establish the composition of the synthesized NPs. Subsequent studies of these NPs’ catalytic properties for preferential CO oxidation in hydrogen-rich environments (PROX), combined with Density Functional Theory (DFT)-based mechanistic studies, elucidate important trends and provide fundamental understanding of the reactivity of Pt shells as a function of the core metal. Both the PROX activity and selectivity of several of these M@Pt core-shell NPs are significantly improved compared to monometallic and bulk nonsegregated bimetallic nanoalloys. Among the systems studied, Ru@Pt core-shell NPs exhibit the highest PROX activity, where the CO oxidation is complete by 30 °C (1000 ppm CO in H2). Therefore, despite their reduced Pt content, M@Pt core-shell NPs afford the design of more active PROX catalysts. DFT studies suggest that the relative differences in the catalytic activities for the various core-shell NPs originate from a combination of (i) the relative availability of CO-free Pt surface sites on the M@Pt NPs, which are necessary for O2 activation, and (ii) a hydrogen-mediated low-temperature CO oxidation process that is clearly distinct from the traditional bifunctional CO oxidation mechanism.

Nilekar, Anand U.; Alayoglu, Selim; Eichhorn, Bryan W.; Mavrikakis, Manos

2010-06-02T23:59:59.000Z

187

FLAMMABLE GAS DIFFUSION THROUGH SINGLE SHELL TANK (SST) DOMES  

DOE Green Energy (OSTI)

This report quantified potential hydrogen diffusion through Hanford Site Single-Shell tank (SST) domes if the SSTs were hypothetically sealed airtight. Results showed that diffusion would keep headspace flammable gas concentrations below the lower flammability limit in the 241-AX and 241-SX SST. The purpose of this document is to quantify the amount of hydrogen that could diffuse through the domes of the SSTs if they were hypothetically sealed airtight. Diffusion is assumed to be the only mechanism available to reduce flammable gas concentrations. The scope of this report is limited to the 149 SSTs.

MEACHAM, J.E.

2003-11-10T23:59:59.000Z

188

Working and Net Available Shell Storage Capacity  

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

Working and Net Available Shell Storage Capacity Working and Net Available Shell Storage Capacity With Data for September 2013 | Release Date: November 27, 2013 | Next Release Date: May 29, 2013 Previous Issues Year: September 2013 March 2013 September 2012 March 2012 September 2011 March 2011 September 2010 Go Containing storage capacity data for crude oil, petroleum products, and selected biofuels. The report includes tables detailing working and net available shell storage capacity by type of facility, product, and Petroleum Administration for Defense District (PAD District). Net available shell storage capacity is broken down further to show the percent for exclusive use by facility operators and the percent leased to others. Crude oil storage capacity data are also provided for Cushing, Oklahoma, an

189

Hanford Single-Shell Tank Integrity Program  

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

Operations Contract Hanford Single Hanford Single- -Shell Shell Hanford Single Hanford Single Shell Shell Tank Integrity Tank Integrity Program Program Herbert S Berman Herbert S Berman Herbert S. Berman Herbert S. Berman July 29, 2009 July 29, 2009 1 Page 1 Tank Operations Contract Introduction * The Hanford site's principle historic mission was plutonium production for the manufacture of nuclear weapons. * Between 1944 and 1988, the site operated nine graphite- moderated light-water production reactors to irradiate moderated, light-water, production reactors to irradiate fuel and produce plutonium. * Four large chemical separations plants were run to extract plutonium from the fuel, and a variety of laboratories, support facilities, and related infrastructure to support production

190

Subsiding Shells around Shallow Cumulus Clouds  

Science Conference Proceedings (OSTI)

In this study large-eddy simulations (LES) are used to gain more knowledge on the shell of subsiding air that is frequently observed around cumulus clouds. First, a detailed comparison between observational and numerical results is presented to ...

Thijs Heus; Harm J. J. Jonker

2008-03-01T23:59:59.000Z

191

How are electrons placed in shells...  

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

a look at our Periodic Table of Elements. Let's use oxygen as an example. Oxygen's electron configuration is: 1s2 2s2 2p4 This means that the first energy level (the K-shell)...

192

Nuclear Quadrupole Moments and Nuclear Shell Structure  

DOE R&D Accomplishments (OSTI)

Describes a simple model, based on nuclear shell considerations, which leads to the proper behavior of known nuclear quadrupole moments, although predictions of the magnitudes of some quadrupole moments are seriously in error.

Townes, C. H.; Foley, H. M.; Low, W.

1950-06-23T23:59:59.000Z

193

V-band Transmission and Reflection Grid Amplifier Packaged in Waveguide  

E-Print Network (OSTI)

for thermal management by allowing the heat sink to be mounted on one side of the grid array. It also reduces and cooling fan were used to remove heat from the chip. The temperature distribution across the grid aperture1 V-band Transmission and Reflection Grid Amplifier Packaged in Waveguide Chun-Tung Cheung1 , Roger

Rutledge, David B.

194

Experimental study of upper sd shell nuclei and evolution of sd-fp shell gap  

Science Conference Proceedings (OSTI)

The intruder orbitals from the fp shell play important role in the structure of nuclei around the line of stability in the upper sd shell. Experimentally we have studied {sup 35}Cl, {sup 30}P, {sup 36}Cl, {sup 37}Ar and {sup 34}Cl in this mass region using the INGA setup. Large basis cross-shell shell model calculations have indicated the need for change of the sd-fp energy gap for reliable reproduction of negative parity and high spin positive parity states. Indication of population of states of large deformation has been found in our data. Theoretical interpretation of these states has been discussed.

Sarkar, M. Saha [Saha Institute of Nuclear Physics, Kolkata - 700064 (India)

2012-06-27T23:59:59.000Z

195

Reduce Stress!  

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

Stress! Stress! x Take a break every hour. Do some relaxation or stretching exercises or talk with someone about topics unrelated to work. Give your body and mind a rest. x Massage your hands and forearms several times a day with a vitamin E lotion. The massage will improve circulation and break up adhesions. Since you can't touch a keyboard until the lotion is absorbed, it also enforces a good break. x Massage the muscles in your neck working your way down from the skull to the shoulders, applying more force to the larger muscles as you go down. x Periodically evaluate your environment for ways to reduce stress. Try to keep your desk uncluttered so you can always find things. Make sure programs are set up correctly on the computer, and see if you can use a macro program to reduce

196

ORISE Resources: Radiation Treatment Medication Package Inserts  

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

Radiation Treatment Medication Package Inserts Radiation Treatment Medication Package Inserts The Oak Ridge Institute for Science and Education (ORISE) maintains a repository of clinical information and data on calcium and zinc diethylenetriaminepentaacetic acid (DTPA) and ferric hexacyanoferrate, also known as Prussian Blue. Calcium-DTPA and zinc-DTPA are injectable chelating agents used to enhance the excretion of plutonium and other transuranics from the body. Prussian Blue binds to radioactive cesium and thallium in the stomach, thereby enhancing their excretion from the body. Package inserts are available for radiation treatment pharmaceuticals calcium-DTPA, zinc-DTPA and Radiogardase (Prussian Blue). To view these files, you will need the Adobe Acrobat Reader, which can be downloaded free from the Adobe Web site.

197

RADIOACTIVE MATERIAL PACKAGING TORQUE REQUIREMENTS COMPLIANCE  

Science Conference Proceedings (OSTI)

Shipping containers used to transport radioactive material (RAM) in commerce employ a variety of closure mechanisms. Often, these closure mechanisms require a specific amount of torque be applied to a bolt, nut or other threaded fastener. It is important that the required preload is achieved so that the package testing and analysis is not invalidated for the purpose of protecting the public. Torque compliance is a means of ensuring closure preload, is a major factor in accomplishing the package functions of confinement/containment, sub-criticality, and shielding. This paper will address the importance of applying proper torque to package closures, discuss torque value nomenclature, and present one methodology to ensure torque compliance is achieved.

Watkins, R.; Leduc, D.

2011-03-24T23:59:59.000Z

198

DEVELOPMENT OF THE H1700 SHIPPING PACKAGE  

SciTech Connect

The H1700 Package is based on the DOE-EM Certified 9977 Packaging. The H1700 will be certified by the Packaging Certification Division of the National Nuclear Security Administration for the shipment of plutonium by air by the United Stated Military both within the United States and internationally. The H1700 is designed to ship radioactive contents in assemblies of Radioisotope Thermoelectric Generators (RTGs) or arrangements of nested food-pack cans. The RTG containers are designed and tested to remain leaktight during transport, handling, and storage; however, their ability to remain leaktight during transport in the H1700 is not credited. This paper discusses the design and special operation of the H1700.

Abramczyk, G.; Loftin, B.; Mann, P.

2009-06-05T23:59:59.000Z

199

Horizontal Drop of 21- PWR Waste Package  

SciTech Connect

The objective of this calculation is to determine the structural response of the waste package (WP) dropped horizontally from a specified height. The WP used for that purpose is the 21-Pressurized Water Reactor (PWR) WP. The scope of this document is limited to reporting the calculation results in-terms of stress intensities. This calculation is associated with the WP design and was performed by the Waste Package Design group in accordance with the ''Technical Work Plan for: Waste Package Design Description for LA'' (Ref. 16). AP-3.12Q, ''Calculations'' (Ref. 1 1) is used to perform the calculation and develop the document. The sketches attached to this calculation provide the potential dimensions and materials for the 21-PWR WP design.

A.K. Scheider

2007-01-31T23:59:59.000Z

200

Engineered waste-package-system design specification  

Science Conference Proceedings (OSTI)

This report documents the waste package performance requirements and geologic and waste form data bases used in developing the conceptual designs for waste packages for salt, tuff, and basalt geologies. The data base reflects the latest geotechnical information on the geologic media of interest. The parameters or characteristics specified primarily cover spent fuel, defense high-level waste, and commercial high-level waste forms. The specification documents the direction taken during the conceptual design activity. A separate design specification will be developed prior to the start of the preliminary design activity.

Not Available

1983-05-01T23:59:59.000Z

Note: This page contains sample records for the topic "reduce shell package" 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

Energy Savings Measure Packages: Existing Homes  

SciTech Connect

This document presents the most cost effective Energy Savings Measure Packages (ESMP) for existing mixed-fuel and all electric homes to achieve 15% and 30% savings for each BetterBuildings grantee location across the US. These packages are optimized for minimum cost to homeowners for given source energy savings given the local climate and prevalent building characteristics (i.e. foundation types). Maximum cost savings are typically found between 30% and 50% energy savings over the reference home. The dollar value of the maximum annual savings varies significantly by location but typically amounts to $300 - $700/year.

Casey, S.; Booten, C.

2011-11-01T23:59:59.000Z

202

Installation package for concentrating solar collector panels  

DOE Green Energy (OSTI)

Northrup, Inc., has developed and delivered 300 square feet of Concentrating Solar Collector (ML Series) and Attitude Control System, under the direction of the National Aeronautics and Space Administration. The ''ML Series'' Solar Collector Panels comprise a complete package array consisting of collector panels using modified Fresnel Prismatic Lenses for a 10 to 1 concentrating ration, supporting framework, fluid manifolding and tracking drive system, in unassembled components for field erection. The Installation, Operation and Maintenance Manual, Warranty, List of Materials, Sub-Assembly drawings and Final Field Assembly Drawings are included in the package.

Not Available

1978-08-01T23:59:59.000Z

203

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

204

Cluster aspects of p-shell and sd-shell nuclei  

SciTech Connect

We report some topics on cluster structures studied by using a theoretical method of antisymmetrized molecular dynamics(AMD). Cluster features of p-shell and sd-shell nuclei are discussed. In particular, three alpha cluster structures in the excited states of {sup 12}C and {sup 14}C are focused. Dineutron correlations in neutron-rich nuclei are also discussed.

Kanada-En'yo, Y.; Kobayashi, F.; Suhara, T. [Department of Physics, Kyoto University, Kyoto 606-8502 (Japan); Kimura, M. [Creative Research Initiative ''Sousei'', Hokkaido University, Sapporo, Hokkaido 001-0021 (Japan); Taniguchi, Y. [RIKEN Nishina Center for Accelerator-Based Science, RIKEN, Wako, Saitama 351-0198 (Japan)

2011-05-06T23:59:59.000Z

205

SHIPMENT OF TWO DOE-STD-3013 CONTAINERS IN A 9977 TYPE B PACKAGE  

Science Conference Proceedings (OSTI)

The 9977 is a certified Type B Packaging authorized to ship uranium and plutonium in metal and oxide forms. Historically, the standard container for these materials has been the DOE-STD-3013 which was specifically designed for the long term storage of plutonium bearing materials. The Department of Energy has used the 9975 Packaging containing a single 3013 container for the transportation and storage of these materials. In order to reduce container, shipping, and storage costs, the 9977 Packaging is being certified for transportation and storage of two 3013 containers. The challenges and risks of this content and the 9977s ability to meet the Code of Federal Regulations for the transport of these materials are presented.

Abramczyk, G.; Bellamy, S.; Loftin, B.; Nathan, S.

2011-06-06T23:59:59.000Z

206

Safety analysis report for packaging: the ORNL DOT specification 6M - special form package  

SciTech Connect

The ORNL DOT Specification 6M - Special Form Package was fabricated at the Oak Ridge Nation al Laboratory (ORNL) for the transport of Type B solid non-fissile radioactive materials in special form. The package was evaluated on the basis of tests performed by the Dow Chemical Company, Rocky Flats Division, on the DOT-6M container and special form tests performed on a variety of stainless steel capsules at ORNL by Operations Division personnel. The results of these evaluations demonstrate that the package is in compliance with the applicable regulations for the transport of Type B quantities in special form of non-fissile radioactive materials.

Schaich, R.W.

1982-07-01T23:59:59.000Z

207

An issue paper on the use of hydrogen getters in transportation packaging  

DOE Green Energy (OSTI)

The accumulation of hydrogen is usually an undesirable occurrence because buildup in sealed systems pose explosion hazards under certain conditions. Hydrogen scavengers, or getters, can avert these problems by removing hydrogen from such environments. This paper provides a review of a number of reversible and irreversible getters that potentially could be used to reduce the buildup of hydrogen gas in containers for the transport of radioactive materials. In addition to describing getters that have already been used for such purposes, novel getters that might find application in future transport packages are also discussed. This paper also discusses getter material poisoning, the use of getters in packaging, the effects of radiation on getters, the compatibility of getters with packaging, design considerations, regulatory precedents, and makes general recommendations for the materials that have the greatest applicability in transport packaging. At this time, the Pacific Northwest National Laboratory composite getter, DEB [1,4-(phenylethylene)benzene] or similar polymer-based getters, and a manganese dioxide-based getter appear to be attractive candidates that should be further evaluated. These getters potentially can help prevent pressurization from radiolytic reactions in transportation packaging.

NIGREY,PAUL J.

2000-02-01T23:59:59.000Z

208

Developing an Instrumentation Package for in-Water Testing of Marine Hydrokinetic Energy Devices: Preprint  

DOE Green Energy (OSTI)

The ocean-energy industry is still in its infancy and device developers have provided their own equipment and procedures for testing. Currently, no testing standards exist for ocean energy devices in the United States. Furthermore, as prototype devices move from the test tank to in-water testing, the logistical challenges and costs grow exponentially. Development of a common instrumentation package that can be moved from device to device is one means of reducing testing costs and providing normalized data to the industry as a whole. As a first step, the U.S. National Renewable Energy Laboratory (NREL) has initiated an effort to develop an instrumentation package to provide a tool to allow common measurements across various ocean energy devices. The effort is summarized in this paper. First, we present the current status of ocean energy devices. We then review the experiences of the wind industry in its development of the instrumentation package and discuss how they can be applied in the ocean environment. Next, the challenges that will be addressed in the development of the ocean instrumentation package are discussed. For example, the instrument package must be highly adaptable to fit a large array of devices but still conduct common measurements. Finally, some possible system configurations are outlined followed by input from the industry regarding its measurement needs, lessons learned from prior testing, and other ideas.

Nelson, E.

2010-08-01T23:59:59.000Z

209

Removable inner turbine shell with bucket tip clearance control  

DOE Patents (OSTI)

A turbine includes a plurality of inner shell sections mounting first and second stage nozzle and shroud portions. The inner shell sections are pinned to an outer containment shell formed of sections to preclude circumferential movement of the inner shell relative to the outer shell and enable thermal expansion and contraction of the inner shell relative to the outer shell. Positive bucket tip clearance control is afforded by passing a thermal medium about the inner shell in heat transfer relation with the shrouds about the first and second stage bucket tips, the thermal medium being provided from a source of heating/cooling fluid independent of the turbine. Access is provided to the rotor and turbine buckets by removing the outer and inner shell sections.

Sexton, Brendan F. (Clifton Park, NY); Knuijt, Hans M. (Niskayuna, NY); Eldrid, Sacheverel Q. (Saratoga Springs, NY); Myers, Albert (Amsterdam, NY); Coneybeer, Kyle E. (Schenectady, NY); Johnson, David Martin (Ballston Lake, NY); Kellock, Iain R. (Clifton Park, NY)

2000-01-01T23:59:59.000Z

210

Installation package for the solaron solar subsystems  

DOE Green Energy (OSTI)

This package contains information that is intended to be a guide for installation, operation, and maintenance of the various Solaron Solar Subsystems. The subsystems consist of the following: collectors, storage, transport (air handler) and controller for heat pump and off-peak storage. Two prototype residential systems have been installed at Akron, Ohio, and Duffield, Virginia.

Not Available

1979-04-01T23:59:59.000Z

211

Installation package for a solar heating system  

DOE Green Energy (OSTI)

Installation information is presented for a solar heating system installed in Concho Indian School at El Reno, Oklahoma. This package includes a system Operation and Maintenance Manual, hardware brochures, schematics, system operating modes and drawings. The Solar Engineering and Equipment Company (SEECO) developed this prototype solar heating system consisting of the following subsystems: solar collectors, control and storage.

Not Available

1978-12-01T23:59:59.000Z

212

Advances Toward Inner-Shell Photo-Ionization X-Ray Lasing at 45 (Angstrom)  

Science Conference Proceedings (OSTI)

The inner-shell photo-ionization (ISPI) scheme requires photon energies at least high enough to photo-ionize the K-shell. {approx}286 eV, in the case of carbon. As a consequence of the higher cross-section, the inner-shell are selectively knocked out, leaving a hole state 1s2s{sup 2}2p{sup 2} in the singly charged carbon ion. This generates a population inversion to the radiatively connected state 1s{sup 2}2s{sup 2}2p in C+, leading to gain on the 1s-2p transition at 45 {angstrom}. The resonant character of the lasing transition in the single ionization state intrinsically allows much higher quantum efficiency compared to other schemes. Competing processes that deplete the population inversion include auto-ionization, Auger decay, and in particular collisional ionization of the outer-shell electrons by electrons generated during photo-ionization. These competing processes rapidly quench the gain. Consequently, the pump method must be capable of populating the inversion at a rate faster than the competing processes. This can be achieved by an ultra-fast, high intensity laser that is able to generate an ultra-fast, bright x-ray source. With current advances in the development of high-power, ultra-short pulse lasers it is possible to realize fast x-ray sources based that can deliver powerful pulses of light in the multiple hundred terawatt regime and beyond. They will discuss in greater detail concept, target design and a series of x-ray spectroscopy investigations they have conducted in order to optimize the absorber/x-ray converter--filter package.

Moon, S J; Weber, F A; Celliers, P M; Eder, D C

2002-07-18T23:59:59.000Z

213

Analysis of leakage magnetic problems in shell-form power transformer  

Science Conference Proceedings (OSTI)

The principles of minimized magnetic energy and voltage equilibrium have been combined with the finite element method to solve the leakage magnetic field problems coupled with an unknown ampere-turn distribution in the shell-form power transformer. Based on the leakage magnetic field calculated, the eddy current and circulating current losses in the coils are further computed. The calculated results are consistent with measured values for a model of a shell-form transformer. Above principles are applied to the windings design of a 50MVA three-phase prototype shell-form power transformer. The calculated results show that the largest circulating current in strands of the low-voltage coils near two ends of each phase winding is greatly reduced to 11% from 98% of the rated current in each strand by placing the copper-shielding on these ends.

Cui Xiang; Yuan Jinsha [North China Electric Power Univ., Baoding, Hebei (China). Dept. of Electrical Engineering; Zhang Guoqiang; Zhang Yuanlu; Hu Qifan [Baoding Tian Wei Group Co., Ltd., Baoding, Hebei (China). Div. of Large Power Transformer

1997-03-01T23:59:59.000Z

214

NNSA PACKAGE CERTIFICATION ENGINEER QUALIFICATION STANDARD REFERENCE GUIDE  

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

NNSA Package NNSA Package Certification Engineer Qualification Standard Reference Guide FEBRUARY 2010 This page is intentionally blank. i Table of Contents LIST OF FIGURES ...................................................................................................................... ii LIST OF TABLES ........................................................................................................................ ii ACRONYMS ................................................................................................................................ iii PURPOSE...................................................................................................................................... 1 SCOPE ...........................................................................................................................................

215

Package Safety Analysis Assessment for Sludge Transportation System  

SciTech Connect

This package safety analysis assessment demonstrates that the Sludge Transportation System meets the acceptance criteria for an equivalent package as specified in DOE/RL-2001-36, Hanford Sitewide Transportation Safety Document for onsite shipment.

ROMANO, T.

2003-03-19T23:59:59.000Z

216

The C-Cat Wordnet Package: An Open Source Package for modifying andapplying Wordnet  

Science Conference Proceedings (OSTI)

We present the C-Cat Wordnet package, an open source library for using and modifying Wordnet. The package includes four key features: an API for modifying Synsets; implementations of standard similarity metrics, implementations of well known Word Sense Disambiguation algorithms, and an implementation of the Castanet algorithm. The library is easily extendible and usable in many runtime environments. We demonstrate it's use on two standard Word Sense Disambiguation tasks and apply the Castanet algorithm to a corpus.

Stevens, K; Huang, T; Buttler, D

2011-09-16T23:59:59.000Z

217

Safety Evaluation for Packaging 101-SY Hydrogen Mitigation Mixer Pump package  

DOE Green Energy (OSTI)

This Safety Evaluation for Packaging (SEP) provides analysis and considered necessary to approve a one-time transfer of the 101-SY Hydrogen Mitigation Mixer Pump (HMMP). This SEP will demonstrate that the transfer of the HMMP in a new shipping container will provide an equivalent degree of safety as would be provided by packages meeting US Department of Transportation (DOT)/US Nuclear Regulatory Commission (NRC) requirements. This fulfills onsite, transportation requirements implemented by WHC-CM-2-14.

Carlstrom, R.F.

1994-10-05T23:59:59.000Z

218

Inner shell radial pin geometry and mounting arrangement  

DOE Patents (OSTI)

Circumferentially spaced arrays of support pins are disposed through access openings in an outer turbine shell and have projections received in recesses in forward and aft sections of an inner turbine shell supported from the outer shell. The projections have arcuate sides in a circumferential direction affording line contacts with the side walls of the recesses and are spaced from end faces of the recesses, enabling radial and axial expansion and contraction of the inner shell relative to the outer shell. All loads are taken up in a tangential direction by the outer shell with the support pins taking no radial loadings.

Leach, David (Niskayuna, NY); Bergendahl, Peter Allen (Scotia, NY)

2002-01-01T23:59:59.000Z

219

Working and Net Available Shell Storage Capacity  

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

Working and Net Available Shell Working and Net Available Shell Storage Capacity November 2013 With Data as of September 30, 2013 Independent Statistics & Analysis www.eia.gov U.S. Department of Energy Washington, DC 20585 U.S. Energy Information Administration | Working and Net Available Shell Storage Capacity as of September 30, 2013 This report was prepared by the U.S. Energy Information Administration (EIA), the statistical and analytical agency within the U.S. Department of Energy. By law, EIA's data, analyses, and forecasts are independent of approval by any other officer or employee of the United States Government. The views in this report therefore should not be construed as representing those of the Department of Energy or

220

Safety analysis report for packaging (onsite) steel drum  

SciTech Connect

This Safety Analysis Report for Packaging (SARP) provides the analyses and evaluations necessary to demonstrate that the steel drum packaging system meets the transportation safety requirements of HNF-PRO-154, Responsibilities and Procedures for all Hazardous Material Shipments, for an onsite packaging containing Type B quantities of solid and liquid radioactive materials. The basic component of the steel drum packaging system is the 208 L (55-gal) steel drum.

McCormick, W.A.

1998-09-29T23:59:59.000Z

Note: This page contains sample records for the topic "reduce shell package" 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

Pb-free Solders and Emerging Interconnect and Packaging ...  

Science Conference Proceedings (OSTI)

In this Symposium, emerging interconnect and packaging technologies and insights into existing materials and technologies, including Pb-free, Pb-

222

DOE M 441.1-1, Nuclear Material Packaging Manual  

Directives, Delegations, and Requirements

The manual provides detailed packaging requirements for protecting workers from exposure to nuclear materials stored outside of an approved engineered ...

2008-03-07T23:59:59.000Z

223

Radio emission from shell-type supernova remnants  

E-Print Network (OSTI)

The evolution of the radio emission of shell-type Supernova remnants (SNRs) is modeled within the framework of the simple and commonly used assumptions that the mechanism of diffusive shock acceleration (DSA) is responsible for generating radio emitting electrons and that the magnetic field is the typical interstellar field compressed at the shock. It is considered that electrons are injected into the mechanism in test-particle regime directly from the high energy tail of the downstream Maxwellian distribution function. The model can be applied to most of the observed SNRs. It is shown that the model successfully explains the many averaged observational properties of evolved shell-type SNRs. In particular, the radio surface brightness ($\\Sigma$) evolves with diameter as $\\sim D^{-(0.3 \\div 0.5)}$, while the bounding shock is strong (Mach number is ${\\mathcal M} \\geq10$), followed by steep decrease (steeper than $\\sim D^{-4.5}$) for ${\\cal M} environmental parameters strongly reduce the usefulness of $\\Sigma - D$ relations as a tool for determining the distances to SNRs. The model predicts no radio emission from SNRs in the late radiative stage of evolution and the existence of radio-quiet but relatively active SNRs is possible. Our model easily explains very large-diameter radio sources such as the Galactic Loops and the candidates for Hypernova radio remnants. The model predicts that most of the observed SNRs are located in a tenuous phase of the ISM. From the comparison of the model results with the statistics of evolved shell-type SNRs, we were able to estimate the fraction of electrons accelerated from the thermal pool in the range $(3\\div 11) \\times 10^{- 4}$.

Abdul Asvarov

2006-08-03T23:59:59.000Z

224

JAVA SWING-BASED PLOTTING PACKAGE RESIDING WITHIN XAL  

Science Conference Proceedings (OSTI)

A data plotting package residing in the XAL tools set is presented. This package is based on Java SWING, and therefore it has the same portability as Java itself. The data types for charts, bar-charts, and color-surface plots are described. The algorithms, performance, interactive capabilities, limitations, and the best usage practices of this plotting package are discussed.

Shishlo, Andrei P [ORNL; Chu, Paul [Stanford University; Pelaia II, Tom [ORNL

2007-01-01T23:59:59.000Z

225

CXXR and Add-on Packages Andrew Runnalls  

E-Print Network (OSTI)

collection (i.e. missing PROTECT()/UNPROTECT()). After fixing these problems, three of the four packages (i.e. missing PROTECT()/UNPROTECT()). After fixing these problems, three of the four packagesCXXR and Add-on Packages Andrew Runnalls School of Computing, University of Kent, UK #12;Outline 1

Kent, University of

226

ALTERNATE MATERIALS IN DESIGN OF RADIOACTIVE MATERIAL PACKAGES  

SciTech Connect

This paper presents a summary of design and testing of material and composites for use in radioactive material packages. These materials provide thermal protection and provide structural integrity and energy absorption to the package during normal and hypothetical accident condition events as required by Title 10 Part 71 of the Code of Federal Regulations. Testing of packages comprising these materials is summarized.

Blanton, P.; Eberl, K.

2010-07-09T23:59:59.000Z

227

A charged rotating cylindrical shell 1  

E-Print Network (OSTI)

We give an example of a spacetime having an infinite thin rotating cylindrical shell constituted by a charged perfect fluid as a source. As the interior of the shell the Bonnor–Melvin universe is considered, while its exterior is represented by Datta– Raychaudhuri spacetime. We discuss the energy conditions and we show that our spacetime contains closed timelike curves. Trajectories of charged test particles both inside and outside the cylinder are also examined. Expression for the angular velocity of a circular motion inside the cylinder is given.

P. Klepá?; J. Horsk´y

2003-01-01T23:59:59.000Z

228

Optical Properties of Gold Pyramidal Shells  

Science Conference Proceedings (OSTI)

We present an investigation of the optical properties of gold pyramidal shell nanoparticles. Theory shows a multiresonance spectrum at near-infrared wavelengths that is consistent with the measured extinction spectra of particles that are fabricated using a soft-lithography technique. In addition to electric dipole and electric quadrupole resonances, the calculations identify an unusual plasmon mode, which involves oscillation of the polarization perpendicular to the direction of both the incident polarization and wave vector. We show that this TE-like resonance can be suppressed by truncating the tip of the pyramid or by increasing the shell thickness without adversely affecting the in-plane dipole and quadrupole resonances.

Shuford, Kevin L [ORNL; Lee, Jeunghoon [Northwestern University, Evanston; Odom, Teri [Northwestern University, Evanston; Schatz, George C. [Northwestern University, Evanston

2008-01-01T23:59:59.000Z

229

DEVELOPMENT OF THE BULK TRITIUM SHIPPING PACKAGING  

SciTech Connect

A new radioactive shipping packaging for transporting bulk quantities of tritium, the Bulk Tritium Shipping Package (BTSP), has been designed for the Department of Energy (DOE) as a replacement for a package designed in the early 1970s. This paper summarizes significant design features and describes how the design satisfies the regulatory safety requirements of the Code of Federal Regulations and the International Atomic Energy Agency. The BTSP design incorporates many improvements over its predecessor by implementing improved testing, handling, and maintenance capabilities, while improving manufacturability and incorporating new engineered materials. This paper also discusses the results from testing of the BTSP to 10 CFR 71 Normal Conditions of Transport and Hypothetical Accident Condition events. The programmatic need of the Department of Energy (DOE) to ship bulk quantities of tritium has been satisfied since the late 1970s by the UC-609 shipping package. The current Certificate of Conformance for the UC-609, USA/9932/B(U) (DOE), will expire in late 2011. Since the UC-609 was not designed to meet current regulatory requirements, it will not be recertified and thereby necessitates a replacement Type B shipping package for continued DOE tritium shipments in the future. A replacement tritium packaging called the Bulk Tritium Shipping Package (BTSP) is currently being designed and tested by Savannah River National Laboratory (SRNL). The BTSP consists of two primary assemblies, an outer Drum Assembly and an inner Containment Vessel Assembly (CV), both designed to mitigate damage and to protect the tritium contents from leaking during the regulatory Hypothetical Accident Condition (HAC) events and during Normal Conditions of Transport (NCT). During transport, the CV rests on a silicone pad within the Drum Liner and is covered with a thermal insulating disk within the insulated Drum Assembly. The BTSP packaging weighs approximately 500 lbs without contents and is 50-1/2 inches high by 24-1/2 inches in outside diameter. With contents the gross weight of the BTSP is 650 lbs. The BTSP is designed for the safe shipment of 150 grams of tritium in a solid or gaseous state. To comply with the federal regulations that govern Type B shipping packages, the BTSP is designed so that it will not lose tritium at a rate greater than the limits stated in 10CFR 71.51 of 10{sup -6} A2 per hour for the 'Normal Conditions of Transport' (NCT) and an A2 in 1 week under 'Hypothetical Accident Conditions' (HAC). Additionally, since the BTSP design incorporates a valve as part of the tritium containment boundary, secondary containment features are incorporated in the CV Lid to protect against gas leakage past the valve as required by 10CFR71.43(e). This secondary containment boundary is designed to provide the same level of containment as the primary containment boundary when subjected to the HAC and NCT criteria.

Blanton, P.; Eberl, K.

2008-09-14T23:59:59.000Z

230

OVERVIEW OF HANFORD SINGLE SHELL TANK (SST) STRUCTURAL INTEGRITY - 12123  

SciTech Connect

To improve the understanding of the single-shell tanks (SSTs) integrity, Washington River Protection Solutions, LLC (WRPS), the USDOE Hanford Site tank contractor, developed an enhanced Single-Shell Tank Integrity Project in 2009. An expert panel on SST integrity, consisting of various subject matters experts in industry and academia, was created to provide recommendations supporting the development of the project. This panel developed 33 recommendations in four main areas of interest: structural integrity, liner degradation, leak integrity and prevention, and mitigation of contamination migration. Seventeen of these recommendations were used to develop the basis for the M-45-10-1 Change Package for the Hanford Federal Agreement and Compliance Order, which is also known as the Tri-Party Agreement. The structural integrity of the tanks is a key element in completing the cleanup mission at the Hanford Site. There are eight primary recommendations related to the structural integrity of Hanford SSTs. Six recommendations are being implemented through current and planned activities. The structural integrity of the Hanford SSTs is being evaluated through analysis, monitoring, inspection, materials testing, and construction document review. Structural evaluation in the form of analysis is performed using modern finite element models generated in ANSYS{reg_sign} The analyses consider in-situ, thermal, operating loads and natural phenomena such as earthquakes. Structural analysis of 108 of 149 Hanford SSTs has concluded that the tanks are structurally sound and meet current industry standards. Analyses of the remaining Hanford SSTs are scheduled for FY2013. Hanford SSTs are monitored through a dome deflection program. The program looks for deflections of the tank dome greater than 1/4 inch. No such deflections have been recorded. The tanks are also subjected to visual inspection. Digital cameras record the interior surface of the concrete tank domes, looking for cracks and other surface conditions that may indicate signs of structural distress. The condition of the concrete and rebar of the Hanford SSTs is currently being tested and planned for additional activities in the near future. Concrete and rebar removed from the dome of a 65-year-old tank is being tested for mechanics properties and condition. Results indicated stronger than designed concrete with additional Petrographic examination and rebar testing ongoing. Material properties determined from previous efforts combined with current testing and construction document review will help to generate a database that will provide continuing indication of Hanford SST structural integrity.

RAST RS; RINKER MW; WASHENFELDER DJ; JOHNSON JB

2012-01-25T23:59:59.000Z

231

Micro- and Nano-Crystal Orientations in Shells  

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

Micro- and Nano-Crystal Orientations in Shells Micro- and Nano-Crystal Orientations in Shells Print Thursday, 12 April 2012 11:11 A research group from the University of Wisconsin...

232

Incorporation of silica into baroplastic core-shell nanoparticles  

E-Print Network (OSTI)

Core-shell baroplastics are nanophase materials that exhibit pressure-induced flow at low temperatures and high pressures. Core-shell baroplastics used in this work are comprised of a low Tg poly(butyl acrylate) (PBA) core ...

Hewlett, Sheldon A

2006-01-01T23:59:59.000Z

233

Handling and Packaging a Potentially Radiologically Contaminated Patient |  

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

Handling and Packaging a Potentially Radiologically Contaminated Handling and Packaging a Potentially Radiologically Contaminated Patient Handling and Packaging a Potentially Radiologically Contaminated Patient The purpose of this procedure is to provide guidance to EMS care providers for properly handling and packaging potentially radiologically contaminated patients. This procedure applies to Emergency Medical Service care providers who respond to a radioactive material transportation incident that involves potentially contaminated injuries. Handling and Packaging a Potentially Radiologically Contaminated Patient.docx More Documents & Publications Pre-Hospital Practices for Handling a Radiologically Contaminated Patient Emergency Response to a Transportation Accident Involving Radioactive Material Radioactive Materials Transportation and Incident Response

234

Handling and Packaging a Potentially Radiologically Contaminated Patient |  

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

Handling and Packaging a Potentially Radiologically Contaminated Handling and Packaging a Potentially Radiologically Contaminated Patient Handling and Packaging a Potentially Radiologically Contaminated Patient The purpose of this procedure is to provide guidance to EMS care providers for properly handling and packaging potentially radiologically contaminated patients. This procedure applies to Emergency Medical Service care providers who respond to a radioactive material transportation incident that involves potentially contaminated injuries. Handling and Packaging a Potentially Radiologically Contaminated Patient.docx More Documents & Publications Pre-Hospital Practices for Handling a Radiologically Contaminated Patient Medical Examiner/Coroner on the Handling of a Body/Human Remains that are Potentially Radiologically Contaminated

235

DOE-Idaho's Packaging and Transportation Perspective  

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

Idaho's Packaging and Idaho's Packaging and T t ti P ti Transportation Perspective Richard Provencher Manager DOE Idaho Operations Office DOE Idaho Operations Office Presented to the DOE National Transportation Stakeholders Forum Stakeholders Forum May 12, 2011 DOE's Idaho site ships and receives a wide variety of radioactive materials 2 Engineering Test Reactor vessel excavated, transported across the site and disposed 3 Navy SNF moved from wet to dry storage storage 4 5 Left: Contact-handled TRU shipments Right: A remote-handled TRU shipment Right: A remote handled TRU shipment 6 NAC spent nuclear fuel container on its trailer, prior to installation of its impact limiters 7 Examples of dry (CPP-603) and wet (CPP-666) storage in Idaho (CPP 666) storage in Idaho 8 INL's Materials and Fuels Complex Hot Fuel Examination

236

White LED with High Package Extraction Efficiency  

Office of Scientific and Technical Information (OSTI)

WHITE LED WITH HIGH PACKAGE WHITE LED WITH HIGH PACKAGE EXTRACTION EFFICIENCY Final Report Report Period Start Date: 10/01/2006 Report Period End Date: 09/30/2008 Authors: Yi Zheng and Matthew Stough Report Submission Date: November 2008 DOE Award Number: DE-FC26-06NT42935 Project Manager: Ryan Egidi OSRAM SYLVANIA Product Inc Central Research and Service Laboratory 71 Cherry Hill Dr., Beverly, MA 01915 2 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 an agency thereof, nor any of their employees, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness of any information, apparatus,

237

The Package Matters | Advanced Photon Source  

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

Disarming Deadly South American Hemorrhagic Fever Viruses Disarming Deadly South American Hemorrhagic Fever Viruses Pull-Chain "Polymer" Solves Puzzle of Complex Molecular Packing Discovering New Talents for Diamond Science Highlights Archives: 2013 | 2012 | 2011 | 2010 2009 | 2008 | 2007 | 2006 2005 | 2004 | 2003 | 2002 2001 | 2000 | 1998 | Subscribe to APS Science Highlights rss feed The Package Matters MARCH 23, 2010 Bookmark and Share Packing ammonia borane into mesoporous silica leads to a remarkable enhancement of the hydrogen storage properties. This image shows the molecular configuration of the packed ammonia borane (while spheres are hydrogen). When it comes to squeezing hydrogen out of ammonia borane the packaging matters, according to scientists from three U.S. Department of Energy national labs. Ammonia borane releases hydrogen with heating by a

238

Copper vapor laser modular packaging assembly  

DOE Patents (OSTI)

A modularized packaging arrangement for one or more copper vapor lasers and associated equipment is disclosed herein. This arrangement includes a single housing which contains the laser or lasers and all their associated equipment except power, water and neon, and means for bringing power, water, and neon which are necessary to the operation of the lasers into the container for use by the laser or lasers and their associated equipment.

Alger, Terry W. (Tracy, CA); Ault, Earl R. (Dublin, CA); Moses, Edward I. (Castro Valley, CA)

1992-01-01T23:59:59.000Z

239

Copper vapor laser modular packaging assembly  

DOE Patents (OSTI)

A modularized packaging arrangement for one or more copper vapor lasers and associated equipment is disclosed herein. This arrangement includes a single housing which contains the laser or lasers and all their associated equipment except power, water and neon, and means for bringing power, water, and neon which are necessary to the operation of the lasers into the container for use by the laser or lasers and their associated equipment. 2 figs.

Alger, T.W.; Ault, E.R.; Moses, E.I.

1992-12-01T23:59:59.000Z

240

Shape fluctuations of a spherical surfactant shell in a ...  

Science Conference Proceedings (OSTI)

Page 1. 1 Shape fluctuations of a spherical surfactant shell in a microemulsion ... Micelles are closed shape structures where the ...

2013-04-02T23:59:59.000Z

Note: This page contains sample records for the topic "reduce shell package" 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

Inorganic Shells for CZTS Nanocrystals With Enhanced Charge ...  

packing order, proximity, and surface chemistry to optimize the nanocrystals’ electrical properties. Specifically, the shells allow charge-carrying ...

242

System Specification for the Double Shell Tank (DST) System  

Science Conference Proceedings (OSTI)

This document establishes the functional, performance, design, development, interface and test requirements for the Double-Shell Tank System.

GRENARD, C.E.

2000-04-21T23:59:59.000Z

243

Fabrication of Highly Luminescent Graded Core/Shell ...  

Paul Alivisatos, Erik Scher, and Liberato Manna have grown graded shells on CdSe core nanorods. Traditional techniques have ...

244

Tank characterization for Double-Shell Tank 241-AP-102  

SciTech Connect

This document provides the characterization information and interprets the data for Double-Shell Tank AP-102.

DeLorenzo, D.S.; DiCenso, A.T.; Amato, L.C.; Weyns-Rollosson, M.I.; Smith, D.J. [Los Alamos Technical Associates, Inc., Kennewick, WA (United States); Simpson, B.C.; Welsh, T.L. [Westinghouse Hanford Co., Richland, WA (United States)

1994-08-01T23:59:59.000Z

245

Determing Degradation Of Fiberboard In The 9975 Shipping Package By Measuring Axial Gap  

SciTech Connect

Currently, thousands of model 9975 transportation packages are in use by the US Department of Energy (DOE); the design of which has been certified by DOE for shipment of Type B radioactive and fissile materials in accordance with Part 71, Title 10 Code of Federal Regulations (CFR), or 10 CFR 71, Packaging and Transportation of Radioactive Material. These transportation packages are also approved for the storage of DOE-STD-3013 containers at the Savannah River Site (SRS). As such, the 9975 has been continuously exposed to the service environment for a period of time greater than the approved transportation service life. In order to ensure the material integrity as specified in the safety basis, an extensive surveillance program is in place in K-Area Complex (KAC) to monitor the structural and thermal properties of the fiberboard of the 9975 shipping packages. The surveillance approach uses a combination of Non-Destructive Examination (NDE) field surveillance and Destructive Examination (DE) lab testing to validate the 9975 performance assumptions. The fiberboard in the 9975 is credited with thermal insulation, criticality control and resistance to crushing. During surveillance monitoring in KAC, an increased axial gap of the fiberboard was discovered on selected items packaged at Rocky Flats Environmental Technology Site (RFETS). Many of these packages were later found to contain excess moisture. Savannah River National Laboratory (SRNL) testing has resulted in a better understanding of the relationship between the fiberboard moisture level and compaction of the fiberboard under storage conditions and during transport. In laboratory testing, the higher moisture content has been shown to correspond to higher total compaction of fiberboard material and compaction rate. The fiberboard height is reduced by compression of the layers. This change is observed directly in the axial gap between the flange and the air shield. The axial gap measurement is made during the pre-use inspection or during the annual recertification process and is a screening measurement for changes in the fiberboard.

2013-08-01T23:59:59.000Z

246

Review of SAR for Packaging Report  

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

March 2010 March 2010 Standard Review Plan (SRP) E n v i r o n m e n t a l M a n a g e m e n t DOE - EM - SRP - 2010 2nd Edition Review of SAR for Packaging Report UCID-21218 Rev. 3 Packaging Review Guide for Reviewing Safety Analysis Reports for Packagings Revision 3 A. A. DiSabatino D. Biswas M. DeMicco L. E. Fischer R. S. Hafner L. B. Hagler J. J. Haslam G. C. Mok C. S. Patel E. W. Russell S. Sitaraman C. K. Syn J. Wen M. H. West LAWRENCE N A T I O N A L LABORATORY LIVERMORE February 2008 DISCLAIMER This document was prepared as an account of work sponsored by an agency of the United States government. Neither the United States government nor Lawrence Livermore National Security, LLC, nor any of their employees makes any warranty, expressed or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness of any information,

247

U-003:RPM Package Manager security update | Department of Energy  

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

03:RPM Package Manager security update 03:RPM Package Manager security update U-003:RPM Package Manager security update October 4, 2011 - 1:30pm Addthis PROBLEM: A vulnerability was reported in RPM Package Manager. A remote user can cause arbitrary code to be executed on the target user's system. PLATFORM: Version(s): 4.9.1.1 and prior versions. ABSTRACT: RPM Package Manager Header Validation Flaws Let Remote Users Execute Arbitrary Code. reference LINKS: RPM Package Manager Advisory RHSA-2011:1349-1 SecurityTracker Alert ID: 1026134 CVE-2011-3378 IMPACT ASSESSMENT: Medium Discussion: A remote user can create a specially crafted RPM package that, when queried or installed by the target user, will trigger a buffer overflow or memory corruption error and execute arbitrary code on the target system. The code

248

THERMAL PERFORMANCE OF RADIOACTIVE MATERIAL PACKAGES IN TRANSPORT CONFIGURATION  

SciTech Connect

Drum type packages are routinely used to transport radioactive material (RAM) in the U.S. Department of Energy (DOE) complex. These packages are designed to meet the federal regulations described in 10 CFR Part 71. The packages are transported in specially designed vehicles like Safe Secure Transport (SST) for safety and security. In the transport vehicles, the packages are placed close to each other to maximize the number of units in the vehicle. Since the RAM contents in the packagings produce decay heat, it is important that they are spaced sufficiently apart to prevent overheating of the containment vessel (CV) seals and the impact limiter to ensure the structural integrity of the package. This paper presents a simple methodology to assess thermal performance of a typical 9975 packaging in a transport configuration.

Gupta, N.

2010-03-04T23:59:59.000Z

249

Pseudo-Symmetry and Majorana Operators in pf-Shell  

SciTech Connect

The Majorana operator of the pseudo ds-shell preserves the SU-tilde(4) symmetry, and in a unified manner it reproduces reasonably well the ground state energies of the nine nuclei in this shell. The study of {beta} decay in the same shell provides further support for the SU-tilde(4) symmetry.

Valencia, J. P.; Wu, H. C. [Instituto de Fisica, Universidad de Antioquia, Medellin (Colombia)

2007-10-26T23:59:59.000Z

250

Constraints for system specifications for the double-shell and single-shell tank systems  

SciTech Connect

This is a supporting document for the Level 1 Double-Shell and Single-Shell System Specifications. The rationale for selection of specific regulatory constraining documents cited in the two system specifications is provided. many of the regulations have been implemented by the Project Hanford Management Contract procedures (HNF-PROs) and as such noted and traced back to their origins in State and Federal regulations.

SHAW, C.P.

1999-05-18T23:59:59.000Z

251

Reducing Drag and Oscillation of Spheres Used for Buoyancy in Oceanographic Moorings  

Science Conference Proceedings (OSTI)

Numerical and laboratory results of the drag characteristics are presented for different configurations of an underwater buoyancy package. It is shown that the drag and oscillation of an underwater sphere can be reduced substantially with the ...

Jane Hurley; Brad de Young; Christopher D. Williams

2008-10-01T23:59:59.000Z

252

The importance of thermal loading conditions to waste package performance at Yucca Mountain  

SciTech Connect

Temperature and relative humidity are primary environmental factors affecting waste package corrosion rates for the potential repository in the unsaturated zone at Yucca Mountain, Nevada. Under ambient conditions, the repository environment is quite humid. If relative humidity is low enough (<70%), corrosion will be minimal. Under humid conditions, corrosion is reduced if the temperature is low (<60 C). Using the V-TOUGH code, the authors model thermo-hydrological flow to investigate the effect of repository heat on temperature and relative humidity in the repository for a wide range of thermal loads. These calculations indicate that repository heat may substantially reduce relative humidity on the waste package, over hundreds of years for low thermal loads and over tens of thousands of year for high thermal loads. Temperatures associated with a given relative humidity decrease with increasing thermal load. Thermal load distributions can be optimized to yield a more uniform reduction in relative humidity during the boiling period.

Buscheck, T.A.; Nitao, J.J.

1994-10-01T23:59:59.000Z

253

Method of fabricating nested shells and resulting product  

DOE Patents (OSTI)

A multiple shell structure and a method of manufacturing such structure wherein a hollow glass microsphere is surface treated in an organosilane solution so as to render the shell outer surface hydrophobic. The surface treated glass shell is then suspended in the oil phase of an oil-aqueous phase dispersion. The oil phase includes an organic film-forming monomer, a polymerization initiator and a blowing agent. A polymeric film forms at each phase boundary of the dispersion and is then expanded in a blowing operation so as to form an outer homogeneously integral monocellular substantially spherical thermoplastic shell encapsulating an inner glass shell of lesser diameter.

Henderson, Timothy M. (Ann Arbor, MI); Kool, Lawrence B. (Ann Arbor, MI)

1982-01-01T23:59:59.000Z

254

BALLISTICS TESTING OF THE 9977 SHIPPING PACKAGE FOR STORAGE APPLICATIONS  

SciTech Connect

Radioactive materials are stored in a variety of locations throughout the DOE complex. At the Savannah River Site (SRS), materials are stored within dedicated facilities. Each of those facilities has a documented safety analysis (DSA) that describes accidents that the facility and the materials within it may encounter. Facilities at the SRS are planning on utilizing the certified Model 9977 Shipping Package as a long term storage package and one of these facilities required ballistics testing. Specifically, in order to meet the facility DSA, the radioactive materials (RAM) must be contained within the storage package after impact by a .223 caliber round. In order to qualify the Model 9977 Shipping Package for storage in this location, the package had to be tested under these conditions. Over the past two years, the Model 9977 Shipping Package has been subjected to a series of ballistics tests. The purpose of the testing was to determine if the 9977 would be suitable for use as a storage package at a Savannah River Site facility. The facility requirements are that the package must not release any of its contents following the impact in its most vulnerable location by a .223 caliber round. A package, assembled to meet all of the design requirements for a certified 9977 shipping configuration and using simulated contents, was tested at the Savannah River Site in March of 2011. The testing was completed and the package was examined. The results of the testing and examination are presented in this paper.

Loftin, B.; Abramczyk, G.; Koenig, R.

2012-06-06T23:59:59.000Z

255

THERMAL UPGRADING OF 9977 RADIOACTIVE MATERIAL (RAM) TYPE B PACKAGE  

Science Conference Proceedings (OSTI)

The 9977 package is a radioactive material package that was originally certified to ship Heat Sources and RTG contents up to 19 watts and it is now being reviewed to significantly expand its contents in support of additional DOE missions. Thermal upgrading will be accomplished by employing stacked 3013 containers, a 3013 aluminum spacer and an external aluminum sleeve for enhanced heat transfer. The 7th Addendum to the original 9977 package Safety Basis Report describing these modifications is under review for the DOE certification. The analyses described in this paper show that this well-designed and conservatively analyzed package can be upgraded to carry contents with decay heat up to 38 watts with some simple design modifications. The Model 9977 package has been designed as a replacement for the Department of Transportation (DOT) Fissile Specification 6M package. The 9977 package is a very versatile Type B package which is certified to transport and store a wide spectrum of radioactive materials. The package was analyzed quite conservatively to increase its usefulness and store different payload configurations. Its versatility is evident from several daughter packages such as the 9978 and H1700, and several addendums where the payloads have been modified to suit the Shipper's needs without additional testing.

Gupta, N.; Abramczyk, G.

2012-03-26T23:59:59.000Z

256

PACKAGING CERTIFICATION PROGRAM METHODOLOGY FOR DETERMINING DOSE RATES FOR SMALL GRAM QUANTITIES IN SHIPPING PACKAGINGS  

Science Conference Proceedings (OSTI)

The Small Gram Quantity (SGQ) concept is based on the understanding that small amounts of hazardous materials, in this case radioactive materials (RAM), are significantly less hazardous than large amounts of the same materials. This paper describes a methodology designed to estimate an SGQ for several neutron and gamma emitting isotopes that can be shipped in a package compliant with 10 CFR Part 71 external radiation level limits regulations. These regulations require packaging for the shipment of radioactive materials, under both normal and accident conditions, to perform the essential functions of material containment, subcriticality, and maintain external radiation levels within the specified limits. By placing the contents in a helium leak-tight containment vessel, and limiting the mass to ensure subcriticality, the first two essential functions are readily met. Some isotopes emit sufficiently strong photon radiation that small amounts of material can yield a large dose rate outside the package. Quantifying the dose rate for a proposed content is a challenging issue for the SGQ approach. It is essential to quantify external radiation levels from several common gamma and neutron sources that can be safely placed in a specific packaging, to ensure compliance with federal regulations. The Packaging Certification Program (PCP) Methodology for Determining Dose Rate for Small Gram Quantities in Shipping Packagings provides bounding shielding calculations that define mass limits compliant with 10 CFR 71.47 for a set of proposed SGQ isotopes. The approach is based on energy superposition with dose response calculated for a set of spectral groups for a baseline physical packaging configuration. The methodology includes using the MCNP radiation transport code to evaluate a family of neutron and photon spectral groups using the 9977 shipping package and its associated shielded containers as the base case. This results in a set of multipliers for 'dose per particle' for each spectral group. For a given isotope, the source spectrum is folded with the response for each group. The summed contribution from all isotopes determines the total dose from the RAM in the container.

Nathan, S.; Loftin, B.; Abramczyk, G.; Bellamy, S.

2012-05-09T23:59:59.000Z

257

DESTRUCTIVE EXAMINATION OF SHIPPING PACKAGE 9975-03431  

SciTech Connect

Destructive and non-destructive examinations have been performed on specified components of shipping package 9975-03431. For those attributes that were also measured during the field surveillance, no significant changes were observed. All observations and test results met identified criteria, or were collected for information and trending purposes. Except for modest corrosion of the lead shield (which is typical of these packages following several years service), no evidence of a degraded condition was found in this package. The Savannah River Site (SRS) stores packages containing plutonium (Pu) materials in the KArea Complex (KAC). The Pu materials are packaged per the DOE 3013 Standard and stored within Model 9975 shipping packages in KAC. The KAC facility DSA (Document Safety Analysis) credits the Model 9975 package to perform several safety functions, including criticality prevention, impact resistance, containment, and fire resistance to ensure the plutonium materials remain in a safe configuration during normal and accident conditions. The Model 9975 package is expected to perform its safety function for at least 12 years from initial packaging. The DSA recognizes the degradation potential for the materials of package construction over time in the KAC storage environment and requires an assessment of materials performance to validate the assumptions of the analysis and ultimately predict service life. As part of the comprehensive Model 9975 package surveillance program, destructive examination of package 9975-03431 was performed following field surveillance in accordance with Reference. Field surveillance of the Model 9975 package in KAC included nondestructive examination of the drum, fiberboard, lead shield and containment vessels. Results of the field surveillance are provided in Attachment 1.

Daugherty, W.

2012-05-30T23:59:59.000Z

258

Working and Net Available Shell Storage Capacity  

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

Net Available Shell Storage Capacity by PAD District as of September 30, 2013 Net Available Shell Storage Capacity by PAD District as of September 30, 2013 (Thousand Barrels) Commodity In Operation Idle 1 In Operation Idle 1 In Operation Idle 1 In Operation Idle 1 In Operation Idle 1 In Operation Idle 1 Refineries Crude Oil 17,334 831 21,870 1,721 86,629 3,468 4,655 174 39,839 1,230 170,327 7,424 Fuel Ethanol 174 - 175 1 289 - 134 - 92 - 864 1 Natural Gas Plant Liquids and Liquefied Refinery Gases 2 1,267 23 11,599 382 28,865 78 641 19 2,412 23 44,784 525 Propane/Propylene (dedicated)

259

Production of Hydrogen from Peanut Shells  

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

Production of Hydrogen from Peanut Shells Production of Hydrogen from Peanut Shells The goal of this project is the production of renewable hydrogen from agricultural residues, in the near-term time frame (~three years) and at a comparable cost to existing methane reforming technologies. The hydrogen produced will be blended with CNG and used to power a bus in Albany, GA. Our strategy is to produce hydrogen from biomass pyrolysis oils in conjunction with high value co-products. Activated carbon can be made from agricultural residues in a two- stage process: (1) slow pyrolysis of biomass to produce charcoal, and (2) high temperature processing to form activated carbon. The vapor by-products from the first step can be steam reformed into hydrogen. NREL has developed the technology for bio-

260

Flare Gas Recovery in Shell Canada Refineries  

E-Print Network (OSTI)

Two of Shell Canada's refineries have logged about six years total operating experience with modern flare gas recovery facilities. The flare gas recovery systems were designed to recover the normal continuous flare gas flow for use in the refinery fuel gas system. The system consists of liquid knock-out, compression, and liquid seal facilities. Now that the debugging-stage challenges have been dealt with, Shell Canada is more than satisfied with the system performance. A well-thought-out installation can today be safe, trouble-free, and attractive from an economic and environmental viewpoint. This paper highlights general guidelines for the sizing, design and operation of a refinery flare gas recovery facility.

Allen, G. D.; Wey, R. E.; Chan, H. H.

1983-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "reduce shell package" 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

Understanding Nuclei in the upper sd - shell  

E-Print Network (OSTI)

Nuclei in the upper-$sd$ shell usually exhibit characteristics of spherical single particle excitations. In the recent years, employment of sophisticated techniques of gamma spectroscopy has led to observation of high spin states of several nuclei near A$\\simeq$ 40. In a few of them multiparticle, multihole rotational states coexist with states of single particle nature. We have studied a few nuclei in this mass region experimentally, using various campaigns of the Indian National Gamma Array setup. We have compared and combined our empirical observations with the large-scale shell model results to interpret the structure of these nuclei. Indication of population of states of large deformation has been found in our data. This gives us an opportunity to investigate the interplay of single particle and collective degrees of freedom in this mass region.

M. Saha Sarkar; Abhijit Bisoi; Sudatta Ray; Ritesh Kshetri; S. Sarkar

2013-08-01T23:59:59.000Z

262

Compact shell solitons in K field theories  

Science Conference Proceedings (OSTI)

Some models providing shell-shaped static solutions with compact support (compactons) in 3+1 and 4+1 dimensions are introduced, and the corresponding exact solutions are calculated analytically. These solutions turn out to be topological solitons and may be classified as maps S{sup 3}{yields}S{sup 3} and suspended Hopf maps, respectively. The Lagrangian of these models is given by a scalar field with a nonstandard kinetic term (K field) coupled to a pure Skyrme term restricted to S{sup 2}, rised to the appropriate power to avoid the Derrick scaling argument. Further, the existence of infinitely many exact shell solitons is explained using the generalized integrability approach. Finally, similar models allowing for nontopological compactons of the ball type in 3+1 dimensions are briefly discussed.

Adam, C.; Klimas, P.; Sanchez-Guillen, J. [Departamento de Fisica de Particulas, Universidad de Santiago and Instituto Galego de Fisica de Altas Enerxias (IGFAE), E-15782 Santiago de Compostela (Spain); Wereszczynski, A. [Niels Bohr Institute, Copenhagen University, Blegdamsvej 17, DK-2100 Copenhagen O, Denmark and Institute of Physics, Jagiellonian University, Reymonta 4, Krakow, 30-059 (Poland)

2009-10-15T23:59:59.000Z

263

LED Chips and Packaging for 120 LPW SSL Component  

SciTech Connect

Cree has developed a new, high-efficiency, low-cost, light emitting diode (LED) lamp module that should be capable of replacing standard, halogen, fluorescent and metal halide lamps based on the total cost of ownership. White LEDs are produced by combining one or more saturated color LEDs with a phosphor or other light down-converting media to achieve white broad-band illumination. This two year project addressed LED chip and package efficiency improvements to establish a technology platform suitable for low-cost, high-efficiency commercial luminaires. Novel photonic-crystal LEDs were developed to improve the light extraction efficiency of blue GaN-based LEDs compared to the baseline technology. Improved packaging designs that reduced down-conversion and absorption related light losses, led to a higher overall LED efficiency. Specifically, blue LEDs were demonstrated with light output nearing 600 mW and an external quantum efficiency greater than 60 percent (using 1 mm2 chips at an operating current of 350 mA). The results were achieved using a novel, production capable photonic-crystal LED fabrication process. These LEDs formed the basis for a multi-chip white lamp module prototype, which provided 510 lumens light output at a correlated color temperature (CCT) of 3875 K and an operating current of 350 mA per 1mm2 chip. The overall conversion efficiency at 4100 K improved to ~ 65%. The resulting efficacy is 112 lumens per watt (LPW) â?? a 33% improvement over the start of the project. In addition, a proof-of-concept luminaire was demonstrated that provided a flux of 1700 lumens at a 3842 K CCT.

James Ibbetson

2009-09-30T23:59:59.000Z

264

Hydrogen Diffusion through Multiple Packaging Layers  

DOE Green Energy (OSTI)

For this scenario, hydrogen is generated in a container that is eventually stored within a drum or some type of long range storage container. When preparing for long-term storage, the hydrogen container (HC) is placed in a plastic bag (PB1). The PB1 is then placed inside an inner drum (ID). The ID is placed inside a plastic bag (PB2) which is then placed within an outer drum (OD). One or more ODs are then storage is a large container (LC). Filtered vents or vent holes are located on all the container barriers to prevent pressurization and allow gases to flow in and out of the HC. The LC is vented to the atmosphere with four vent paths for this example. The source of hydrogen generation for this study is not important. Any source that generates hydrogen in elemental form (i.e., H{sub 2}) is a candidate for the purposes of this generic evaluation. The released hydrogen accumulates inside the waste packaging. Depending on the permeability of the packaging layers, some of the accumulated hydrogen may diffuse out of the packaging layers and into the space surrounding the drums. Since the drums are confined in the LC, the hydrogen accumulates in the LC as it did inside the drums if venting of the LC does not occur. If accumulation in the LC is allowed without venting, the confinement is eventually breached or the hydrogen is consumed by reaction with other chemical species. One possible reaction is combustion with oxygen. Such a reaction can be explosive, and from this possibility arises the safety concern.

McAllister, J.; Mohiuddin, A.

2010-05-05T23:59:59.000Z

265

Initial waste package interaction tests: status report  

SciTech Connect

This report describes the results of some initial investigations of the effects of rock media on the release of simulated fission products from a sngle waste form, PNL reference glass 76-68. All tests assemblies contained a minicanister prepared by pouring molten, U-doped 76-68 glass into a 2-cm-dia stanless steel tube closed at one end. The tubes were cut to 2.5 to 7.5 cm in length to expose a flat glass surface rimmed by the canister wall. A cylindrical, whole rock pellet, cut from one of the rock materials used, was placed on the glass surface then both the canister and rock pellet were packed in the same type of rock media ground to about 75 ..mu..m to complete the package. Rock materials used were a quartz monzonite basalt and bedded salt. These packages were run from 4 to 6 weeks in either 125 ml digestion bombs or 850 ml autoclaves capable of direct solution sampling, at either 250 or 150/sup 0/C. Digestion bomb pressures were the vapor pressure of water, 600 psig at 250/sup 0/C, and the autoclaves were pressurized at 2000 psig with an argon overpressure. In general, the solution chemistry of these initial package tests suggests that the rock media is the dominant controlling factor and that rock-water interaction may be similar to that observed in some geothermal areas. In no case was uranium observed in solution above 15 ppB. The observed leach rates of U glass not in contact with potential sinks (rock surfaces and alteration products) have been observed to be considerably higher. Thus the use of leach rates and U concentrations observed from binary leach experiments (waste-form water only) to ascertain long-term environmental consequences appear to be quite conservative compared to actual U release in the waste package experiments. Further evaluation, however, of fission product transport behavior and the role of alteration phases as fission product sinks is required.

Shade, J.W.; Bradley, D.J.

1980-12-01T23:59:59.000Z

266

New lambda Bootis stars with a shell  

E-Print Network (OSTI)

We publish here the second part of our spectroscopic survey at high dispersion of some known and suspected lambda Bootis stars with a view to detecting circumstellar shell features. Eight stars of our sample exhibit such features. These stars are fast rotators, a result which is in line with Holweger and Rentzsch-Holm's study (1995). The analysis of the photometric data has allowed us to confirm the exclusion of a few stars misclassified from the lambda Bootis group.

B. Hauck; D. Ballereau; J. Chauville

1997-09-02T23:59:59.000Z

267

CRAD, Packaging and Transfer of Hazardous Materials and Materials of  

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

Packaging and Transfer of Hazardous Materials and Materials Packaging and Transfer of Hazardous Materials and Materials of National Security Interest Assessment Plan CRAD, Packaging and Transfer of Hazardous Materials and Materials of National Security Interest Assessment Plan Performance Objective: Verify that packaging and transportation safety requirements of hazardous materials and materials of national security interest have been established and are in compliance with DOE Orders 461.1 and 460.1B Criteria: Verify that safety requirements for the proper packaging and transportation of DOE/NNSA offsite shipments and onsite transfers of hazardous materials and for modal transport have been established [DOE O 460.1B, 1, "Objectives"]. Verify that the contractor transporting a package of hazardous materials is in compliance with the requirements of the Hazardous Materials

268

Waste Package Materials Performance Peer Review | Department of Energy  

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

Waste Package Materials Performance Peer Review Waste Package Materials Performance Peer Review Waste Package Materials Performance Peer Review A consensus peer review of the current technical basis and the planned experimental and modeling program for the prediction of the long-term performance of waste package materials being considered for use in a proposed repository at Yucca Mountain, Nevada. Waste Package Materials Performance Peer Review A Compilation of Special Topic Reports Wastepackagematerials_PPRP_final.pdf Evaluation of the Final Report: Waste Package Materials Performance Peer Review Panel Multi-Purpose_Canister_System_Evaluation.pdf More Documents & Publications Preliminary Report on Dual-Purpose Canister Disposal Alternatives (FY13) A Review of Stress Corrosion Cracking/Fatigue Modeling for Light Water

269

ADAPTING A CERTIFIED SHIPPING PACKAGE FOR STORAGE APPLICATIONS  

Science Conference Proceedings (OSTI)

For years shipping packages have been used to store radioactive materials at many DOE sites. Recently, the K-Area Material Storage facility at the Savannah River Site became interested in and approved the Model 9977 Shipping Package for use as a storage package. In order to allow the 9977 to be stored in the facility, there were a number of evaluations and modifications that were required. There were additional suggested modifications to improve the performance of the package as a storage container that were discussed but not incorporated in the design that is currently in use. This paper will discuss the design being utilized for shipping and storage, suggested modifications that have improved the storage configuration but were not used, as well as modifications that have merit for future adaptations for both the 9977 and for other shipping packages to be used as storage packages.

Loftin, B.; Abramczyk, G.

2012-06-05T23:59:59.000Z

270

Dilaton thin-shell wormholes supported by a generalized Chaplygin gas  

E-Print Network (OSTI)

In this article, we construct spherical thin-shell wormholes with charge in dilaton gravity. The exotic matter required for the construction is provided by a generalized Chaplygin gas. We study the stability under perturbations preserving the symmetry. We find that the increase of the coupling between the dilaton and the electromagnetic fields reduces the range of the parameters for which stable configurations are possible.

Cecilia Bejarano; Ernesto F. Eiroa

2011-06-30T23:59:59.000Z

271

Maintenance Work Package Planning Guidance for Fossil Power Plant Personnel  

Science Conference Proceedings (OSTI)

The work management process is one of the core business processes for operation and maintenance of fossil power plants. The preparation of work packages is a key element of this overall process. The purpose of this report is to provide guidance to power plant personnel regarding work package quality, by providing a consistent approach for administrative control, achieving an appropriate level-of-detail, ensuring an acceptable level-of-use, work package format, and application.

2005-12-21T23:59:59.000Z

272

A Finite Groups Package - CECM - Simon Fraser University  

E-Print Network (OSTI)

A Finite Groups Package. Vahid Dabbaghian-Abdoly and Greg Fee. The Centre for Experimental and Censtructiye Mathematics ICECH}. Introduction. As part of ...

273

CH Packaging Operations for High Wattage Waste at LANL  

Science Conference Proceedings (OSTI)

This procedure provides instructions for assembling the following CH packaging payload: Drum payload assembly Standard Waste Box (SWB) assembly Ten-Drum Overpack (TDOP).

Washington TRU Solutions LLC

2005-04-13T23:59:59.000Z

274

CH Packaging Operations for High Wattage Waste at LANL  

Science Conference Proceedings (OSTI)

This procedure provides instructions for assembling the following CH packaging payload: Drum payload assembly Standard Waste Box (SWB) assembly Ten-Drum Overpack (TDOP).

Washington TRU Solutions LLC

2005-04-04T23:59:59.000Z

275

Trans_package_Poster_Draft_8_7_12.indd  

National Nuclear Security Administration (NNSA)

breaking open or releasing radiation including: * Free-Drop Test * Puncture Test * Thermal Test Type B transportation packages that could be used to transport radioactive...

276

Energy-Big voltage, little package... | ornl.gov  

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

News DOE Pulse Media Contacts Media Mentions RSS Feeds News Home | ORNL | News | Story Tips SHARE Energy-Big voltage, little package Oak Ridge National Laboratory's new Stinger...

277

Interconnect Design and Reliability in Electronic Packages III  

Science Conference Proceedings (OSTI)

More than 400 test vehicles were assembled using ceramic and plastic BGAs, LCCs, .... still draws big attention among the electronic package manufacturers.

278

DOE-Idaho's Packaging and Transportation Perspective | Department...  

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

and Transportation Perspective Presented by Richard Provencher, Manager for the DOE Idaho Operations Office. DOE-Idaho's Packaging and Transportation Perspective More Documents...

279

A GAP package for computation with coherent configurations  

Science Conference Proceedings (OSTI)

We present a GAP package for computing with Schurian coherent configurations and their representations. Keywords: GAP, GRAPE, association scheme, centralizer ring, coherent configuration, permutation group, sage, semidefinite programming

Dmitrii V. Pasechnik; Keshav Kini

2010-09-01T23:59:59.000Z

280

PROJECT MANGEMENT PLAN EXAMPLES Prepare Detailed Work Packages...  

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

Work Packages Examples Example 71 8.2.5 Work Processes Work associated with nuclear safety functions will be planned, authorized, and performed following approved technical...

Note: This page contains sample records for the topic "reduce shell package" 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

Radiation Materials Science Package (2007), by Gary S. Was - TMS  

Science Conference Proceedings (OSTI)

Jul 11, 2008 ... Fundamentals of Radiation Materials Science is a high-level materials science book/CD package intended for graduate students and ...

282

graphicsQC-package Quality Control for Graphics Description Details  

E-Print Network (OSTI)

Description The package provides functions to generate graphics files, compare them with “model” files, and report the results. License GPL-2

Stephen Gardiner; Paul Murrell; Maintainer Paul Murrell; Stephen Gardiner

2009-01-01T23:59:59.000Z

283

September 27, 2000, DOE letter enclosing closure packages for...  

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

Other factors such as process efficiencies (including number of items in a batch), packaging configuration and worker risk also will be considered in determining individual...

284

Improvements to the SHDOM Radiative Transfer Modeling Package  

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

to the SHDOM Radiative Transfer Modeling Package K. F. Evans University of Colorado Boulder, Colorado W. J. Wiscombe National Aeronautics and Space Administration...

285

Water Rights Permit Package Application | Open Energy Information  

Open Energy Info (EERE)

Login | Sign Up Search Page Edit with form History Facebook icon Twitter icon Water Rights Permit Package Application Jump to: navigation, search GEOTHERMAL...

286

DOE O 460.1C, Packaging and Transportation Safety  

Directives, Delegations, and Requirements

The order establishes safety requirements for the proper packaging and transportation of DOE, including NNSA, offsite shipments and onsite transfers of ...

2010-05-14T23:59:59.000Z

287

Nuclear waste package fabricated from concrete  

Science Conference Proceedings (OSTI)

After the United States enacted the Nuclear Waste Policy Act in 1983, the Department of Energy must design, site, build and operate permanent geologic repositories for high-level nuclear waste. The Department of Energy has recently selected three sites, one being the Hanford Site in the state of Washington. At this particular site, the repository will be located in basalt at a depth of approximately 3000 feet deep. The main concern of this site, is contamination of the groundwater by release of radionuclides from the waste package. The waste package basically has three components: the containment barrier (metal or concrete container, in this study concrete will be considered), the waste form, and other materials (such as packing material, emplacement hole liners, etc.). The containment barriers are the primary waste container structural materials and are intended to provide containment of the nuclear waste up to a thousand years after emplacement. After the containment barriers are breached by groundwater, the packing material (expanding sodium bentonite clay) is expected to provide the primary control of release of radionuclide into the immediate repository environment. The loading conditions on the concrete container (from emplacement to approximately 1000 years), will be twofold; (1) internal heat of the high-level waste which could be up to 400/sup 0/C; (2) external hydrostatic pressure up to 1300 psi after the seepage of groundwater has occurred in the emplacement tunnel. A suggested container is a hollow plain concrete cylinder with both ends capped. 7 refs.

Pfeiffer, P.A.; Kennedy, J.M.

1987-03-01T23:59:59.000Z

288

Using the scalable nonlinear equations solvers package  

SciTech Connect

SNES (Scalable Nonlinear Equations Solvers) is a software package for the numerical solution of large-scale systems of nonlinear equations on both uniprocessors and parallel architectures. SNES also contains a component for the solution of unconstrained minimization problems, called SUMS (Scalable Unconstrained Minimization Solvers). Newton-like methods, which are known for their efficiency and robustness, constitute the core of the package. As part of the multilevel PETSc library, SNES incorporates many features and options from other parts of PETSc. In keeping with the spirit of the PETSc library, the nonlinear solution routines are data-structure-neutral, making them flexible and easily extensible. This users guide contains a detailed description of uniprocessor usage of SNES, with some added comments regarding multiprocessor usage. At this time the parallel version is undergoing refinement and extension, as we work toward a common interface for the uniprocessor and parallel cases. Thus, forthcoming versions of the software will contain additional features, and changes to parallel interface may result at any time. The new parallel version will employ the MPI (Message Passing Interface) standard for interprocessor communication. Since most of these details will be hidden, users will need to perform only minimal message-passing programming.

Gropp, W.D.; McInnes, L.C.; Smith, B.F.

1995-02-01T23:59:59.000Z

289

Safety evaluation for packaging CPC metal boxes  

Science Conference Proceedings (OSTI)

This Safety Evaluation for Packaging (SEP) provides authorization for the use of Container Products Corporation (CPC) metal boxes, as described in this document, for the interarea shipment of radioactive contaminated equipment and debris for storage in the Central Waste Complex (CWC) or T Plant located in the 200 West Area. Authorization is granted until November 30, 1995. The CPC boxes included in this SEP were originally procured as US Department of Transportation (DOT) Specification 7A Type A boxes. A review of the documentation provided by the manufacturer revealed the documentation did not adequately demonstrate compliance to the 4 ft drop test requirement of 49 CFR 173.465(c). Preparation of a SEP is necessary to document the equivalent safety of the onsite shipment in lieu of meeting DOT packaging requirements until adequate documentation is received. The equivalent safety of the shipment is based on the fact that the radioactive contents consist of contaminated equipment and debris which are not dispersible. Each piece is wrapped in two layers of no less than 4 mil plastic prior to being placed in the box which has an additional 10 mil liner. Pointed objects and sharp edges are padded to prevent puncture of the plastic liner and wrapping.

Romano, T.

1995-05-15T23:59:59.000Z

290

Environmental restoration risk-based prioritization work package planning and risk ranking methodology. Revision 2  

Science Conference Proceedings (OSTI)

This document presents the risk-based prioritization methodology developed to evaluate and rank Environmental Restoration (ER) work packages at the five US Department of Energy, Oak Ridge Field Office (DOE-ORO) sites [i.e., Oak Ridge K-25 Site (K-25), Portsmouth Gaseous Diffusion Plant (PORTS), Paducah Gaseous Diffusion Plant (PGDP), Oak Ridge National Laboratory (ORNL), and the Oak Ridge Y-12 Plant (Y-12)], the ER Off-site Program, and Central ER. This prioritization methodology was developed to support the increased rigor and formality of work planning in the overall conduct of operations within the DOE-ORO ER Program. Prioritization is conducted as an integral component of the fiscal ER funding cycle to establish program budget priorities. The purpose of the ER risk-based prioritization methodology is to provide ER management with the tools and processes needed to evaluate, compare, prioritize, and justify fiscal budget decisions for a diverse set of remedial action, decontamination and decommissioning, and waste management activities. The methodology provides the ER Program with a framework for (1) organizing information about identified DOE-ORO environmental problems, (2) generating qualitative assessments of the long- and short-term risks posed by DOE-ORO environmental problems, and (3) evaluating the benefits associated with candidate work packages designed to reduce those risks. Prioritization is conducted to rank ER work packages on the basis of the overall value (e.g., risk reduction, stakeholder confidence) each package provides to the ER Program. Application of the methodology yields individual work package ``scores`` and rankings that are used to develop fiscal budget requests. This document presents the technical basis for the decision support tools and process.

Dail, J.L.; Nanstad, L.D.; White, R.K.

1995-06-01T23:59:59.000Z

291

Tritium Permeation Estimate from APT and CLWR-TEF Waste Packages  

Science Conference Proceedings (OSTI)

The amount of tritium permeating out of waste containers has been estimated for the Accelerator Production of Tritium project (APT) and for the Commercial Light Water Reactor - Tritium Extraction Facility project (CLWR-TEF). The waste packages analyzed include the Aluminum, Window, Tungsten, Lead, and Steel packages for the APT project, and the overpack of extracted Tritium Producing Burnable Absorber Rods (TPBARs) for the CLWR-TEF project. All of the tritium contained in the waste was assumed to be available as a gas in the free volume inside the waste container at the beginning of disposal, and to then permeate the stainless steel waste container. From estimates of the tritium content of each waste form, the void or free volume of the package, disposal temperature and container geometry, the amount of tritium exiting the waste container by permeation was calculated. Two tritium permeation paths were considered separately: through the entire wall surface area and through the weld area only, the weld area having reduced thickness and significantly less surface area compared to the wall area. Permeation out of the five APT waste containers at 50 degrees Celsius is mainly through the welds, and at 100 degrees Celsius is through the permeation out of the entire wall surface area. The largest maximum offgas rate from an APT waste stream at 50 degrees Celsius (estimated disposal temperature) was 1.8E-6 Ci/year from the weld of the Window waste package, and the smallest maximum offgas rate was 3.7E-5 Ci/year from the weld of the Lead waste package. Permeation from the CLWR-TEF overpack at 40 degrees Celsius is mainly through the entire wall surface area, with a maximum offgas rate of 1.3E-5 Ci/year.

Clark, E.A.

1999-03-18T23:59:59.000Z

292

Wastepaper recycling in the packaging industry. (Latest citations from Packaging Science and Technology Abstracts database). Published Search  

Science Conference Proceedings (OSTI)

The bibliography contains citations concerning the reclamation and re-use of waste paper in the packaging industry. Uses of recycled papers include containers, paper manufacture, paperboard products, and other packaging applications. Economics, environmental impacts, legislation, and feasibility studies are included. Problems associated with recycling paper products, and comparisons with plastic products are also considered. Biodegradation of packaging materials is considered in separate bibliographies. (Contains 250 citations and includes a subject term index and title list.)

Not Available

1993-07-01T23:59:59.000Z

293

Thin Film Packaging Solutions for High Efficiency OLED Lighting Products  

Science Conference Proceedings (OSTI)

The objective of the 'Thin Film Packaging Solutions for High Efficiency OLED Lighting Products' project is to demonstrate thin film packaging solutions based on SiC hermetic coatings that, when applied to glass and plastic substrates, support OLED lighting devices by providing longer life with greater efficiency at lower cost than is currently available. Phase I Objective: Demonstrate thin film encapsulated working phosphorescent OLED devices on optical glass with lifetime of 1,000 hour life, CRI greater than 75, and 15 lm/W. Phase II Objective: Demonstrate thin film encapsulated working phosphorescent OLED devices on plastic or glass composite with 25 lm/W, 5,000 hours life, and CRI greater than 80. Phase III Objective: Demonstrate 2 x 2 ft{sup 2} thin film encapsulated working phosphorescent OLED with 40 lm/W, 10,000 hour life, and CRI greater than 85. This report details the efforts of Phase III (Budget Period Three), a fourteen month collaborative effort that focused on optimization of high-efficiency phosphorescent OLED devices and thin-film encapsulation of said devices. The report further details the conclusions and recommendations of the project team that have foundation in all three budget periods for the program. During the conduct of the Thin Film Packaging Solutions for High Efficiency OLED Lighting Products program, including budget period three, the project team completed and delivered the following achievements: (1) a three-year marketing effort that characterized the near-term and longer-term OLED market, identified customer and consumer lighting needs, and suggested prototype product concepts and niche OLED applications lighting that will give rise to broader market acceptance as a source for wide area illumination and energy conservation; (2) a thin film encapsulation technology with a lifetime of nearly 15,000 hours, tested by calcium coupons, while stored at 16 C and 40% relative humidity ('RH'). This encapsulation technology was characterized as having less than 10% change in transmission during the 15,000 hour test period; (3) demonstrated thin film encapsulation of a phosphorescent OLED device with 1,500 hours of lifetime at 60 C and 80% RH; (4) demonstrated that a thin film laminate encapsulation, in addition to the direct thin film deposition process, of a polymer OLED device was another feasible packaging strategy for OLED lighting. The thin film laminate strategy was developed to mitigate defects, demonstrate roll-to-roll process capability for high volume throughput (reduce costs) and to support a potential commercial pathway that is less dependent upon integrated manufacturing since the laminate could be sold as a rolled good; (5) demonstrated that low cost 'blue' glass substrates could be coated with a siloxane barrier layer for planarization and ion-protection and used in the fabrication of a polymer OLED lighting device. This study further demonstrated that the substrate cost has potential for huge cost reductions from the white borosilicate glass substrate currently used by the OLED lighting industry; (6) delivered four-square feet of white phosphorescent OLED technology, including novel high efficiency devices with 82 CRI, greater than 50 lm/W efficiency, and more than 1,000 hours lifetime in a product concept model shelf; (7) presented and or published more than twenty internal studies (for private use), three external presentations (OLED workshop-for public use), and five technology-related external presentations (industry conferences-for public use); and (8) issued five patent applications, which are in various maturity stages at time of publication. Delivery of thin film encapsulated white phosphorescent OLED lighting technology remains a challenging technical achievement, and it seems that commercial availability of thin, bright, white OLED light that meets market requirements will continue to require research and development effort. However, there will be glass encapsulated white OLED lighting products commercialized in niche markets during the 2008 calendar year. This commercializ

None

2008-06-30T23:59:59.000Z

294

Commercial Spent Nuclear Fuel Waste Package Misload Analysis  

Science Conference Proceedings (OSTI)

The purpose of this calculation is to estimate the probability of misloading a commercial spent nuclear fuel waste package with a fuel assembly(s) that has a reactivity (i.e., enrichment and/or burnup) outside the waste package design. The waste package designs are based on the expected commercial spent nuclear fuel assemblies and previous analyses (Macheret, P. 2001, Section 4.1 and Table 1). For this calculation, a misloaded waste package is defined as a waste package that has a fuel assembly(s) loaded into it with an enrichment and/or burnup outside the waste package design. An example of this type of misload is a fuel assembly designated for the 21-PWR Control Rod waste package being incorrectly loaded into a 21-PWR Absorber Plate waste package. This constitutes a misloaded 21-PWR Absorber Plate waste package, because the reactivity (i.e., enrichment and/or burnup) of a 21-PWR Control Rod waste package fuel assembly is outside the design of a 21-PWR Absorber Plate waste package. These types of misloads (i.e., fuel assembly with enrichment and/or burnup outside waste package design) are the only types that are evaluated in this calculation. This calculation utilizes information from ''Frequency of SNF Misload for Uncanistered Fuel Waste Package'' (CRWMS M&O 1998) as the starting point. The scope of this calculation is limited to the information available. The information is based on the whole population of fuel assemblies and the whole population of waste packages, because there is no information about the arrival of the waste stream at this time. The scope of this calculation deviates from that specified in ''Technical Work Plan for: Risk and Criticality Department'' (BSC 2002a, Section 2.1.30) in that only waste package misload is evaluated. The remaining issues identified (i.e., flooding and geometry reconfiguration) will be addressed elsewhere. The intended use of the calculation is to provide information and inputs to the Preclosure Safety Analysis Department. Before using the results of this calculation, the reader is cautioned to verify that the assumptions made in this calculation regarding the waste stream, the loading process, and the staging of the spent nuclear fuel assemblies are applicable.

A. Alsaed

2005-07-28T23:59:59.000Z

295

DESTRUCTIVE EXAMINATION OF SHIPPING PACKAGE 9975-02168  

Science Conference Proceedings (OSTI)

The Savannah River Site (SRS) stores packages containing plutonium (Pu) materials in the K-Area Complex (KAC). The Pu materials are packaged per the DOE 3013 Standard and stored within Model 9975 shipping packages in KAC. The KAC facility DSA (Document Safety Analysis) credits the Model 9975 package to perform several safety functions, including criticality prevention, impact resistance, containment, and fire resistance to ensure the plutonium materials remain in a safe configuration during normal and accident conditions. The Model 9975 package is expected to perform its safety function for at least 12 years from initial packaging. The DSA recognizes the degradation potential for the materials of package construction over time in the KAC storage environment and requires an assessment of materials performance to validate the assumptions of the analysis and ultimately predict service life. As part of the comprehensive Model 9975 package surveillance program, destructive examination of package 9975-02028 was performed following field surveillance in accordance with Reference. Field surveillance of the Model 9975 package in KAC included nondestructive examination of the drum, fiberboard, lead shield and containment vessels. Results of the field surveillance are provided in Attachment 1. Destructive and non-destructive examinations have been performed on specified components of shipping package 9975-02168. For those attributes that were also measured during the field surveillance, no significant changes were observed. Two conditions were identified that do not meet inspection criteria. These conditions are subject to additional investigation and disposition by the Surveillance Program Authority. The conditions include: (1) The lead shield was covered with a white corrosion layer, and (2) Fiberboard thermal conductivity in the axial direction exceeded the specified range. The Surveillance Program Authority was notified of these conditions and will document the findings by surveillance report. All other observations and test results met identified criteria, or were collected for information and trending purposes.

Daugherty, W.

2010-11-18T23:59:59.000Z

296

Method and Apparatus for Pasteurizing Shell Eggs Using Radio Frequency  

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

Method and Apparatus for Pasteurizing Shell Eggs Using Radio Frequency Method and Apparatus for Pasteurizing Shell Eggs Using Radio Frequency Heating" Inventors..--.. Christopher D. Brunkhorst, David J. Geveke, Andrew B. W. Bigley. This disclosure is directed to a system for pasteurizing shell eggs. The system includes an egg rotating assembly structured to rotate the egg, and electrodes that are in contact with the egg. The system is structured so that, as the rotating assembly rotates the egg, radio frequency energy is directed to the egg to pasteurize it. Nearly 200 million "shell eggs" are consumed in the United States (US) each day. "Shell eggs" are non-powdered conventional eggs that are naturally produced by hens. Shell eggs are among the most nutritious foods on earth and can be part of a healthy diet. However, some unbroken, clean, fresh

297

Graded core/shell semiconductor nanorods and nanorod barcodes  

DOE Patents (OSTI)

Graded core/shell semiconductor nanorods and shaped nanorods are disclosed comprising Group II-VI, Group III-V and Group IV semiconductors and methods of making the same. Also disclosed are nanorod barcodes using core/shell nanorods where the core is a semiconductor or metal material, and with or without a shell. Methods of labeling analytes using the nanorod barcodes are also disclosed.

Alivisatos, A. Paul (Oakland, CA); Scher, Erik C. (San Francisco, CA); Manna, Liberato (Lecce, IT)

2010-12-14T23:59:59.000Z

298

Graded core/shell semiconductor nanorods and nanorod barcodes  

DOE Patents (OSTI)

Graded core/shell semiconductor nanorods and shapped nanorods are disclosed comprising Group II-VI, Group III-V and Group IV semiconductors and methods of making the same. Also disclosed are nanorod barcodes using core/shell nanorods where the core is a semiconductor or metal material, and with or without a shell. Methods of labeling analytes using the nanorod barcodes are also disclosed.

Alivisatos, A. Paul; Scher, Erik C.; Manna, Liberato

2013-03-26T23:59:59.000Z

299

Mr. LDA: a flexible large scale topic modeling package using variational inference in MapReduce  

Science Conference Proceedings (OSTI)

Latent Dirichlet Allocation (LDA) is a popular topic modeling technique for exploring document collections. Because of the increasing prevalence of large datasets, there is a need to improve the scalability of inference for LDA. In this paper, we introduce ... Keywords: mapreduce, scalability, topic models

Ke Zhai; Jordan Boyd-Graber; Nima Asadi; Mohamad L. Alkhouja

2012-04-01T23:59:59.000Z

300

AGC-2 Graphite Preirradiation Data Package  

SciTech Connect

The NGNP Graphite R&D program is currently establishing the safe operating envelope of graphite core components for a Very High Temperature Reactor (VHTR) design. The program is generating quantitative data necessary for predicting the behavior and operating performance of the new nuclear graphite grades. To determine the in-service behavior of the graphite for pebble bed and prismatic designs, the Advanced Graphite Creep (AGC) experiment is underway. This experiment is examining the properties and behavior of nuclear grade graphite over a large spectrum of temperatures, neutron fluences and compressive loads. Each experiment consists of over 400 graphite specimens that are characterized prior to irradiation and following irradiation. Six experiments are planned with the first, AGC-1, currently being irradiated in the Advanced Test Reactor (ATR) and pre-irradiation characterization of the second, AGC-2, completed. This data package establishes the readiness of 512 specimens for assembly into the AGC-2 capsule.

David Swank; Joseph Lord; David Rohrbaugh; William Windes

2012-10-01T23:59:59.000Z

Note: This page contains sample records for the topic "reduce shell package" 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

Packaging and Transportation of Additional Neptunium Oxide  

Science Conference Proceedings (OSTI)

The Savannah River Site's HB-Line Facility completed a second neptunium oxide production campaign in which nine (9) additional cans of neptunium oxide were produced and shipped to the Idaho National Laboratory and Oak Ridge National Laboratory in the 9975 shipping container. These additional cans were from a different feed solution than the first fifty (50) cans of neptunium oxide that were previously produced and shipped via a Letter of Amendment to the 9975 Safety Analysis Report for Packaging (SARP) content table. This paper will address the challenges associated with demonstrating the neptunium oxide produced from the additional feed solution was equivalent to the original neptunium oxide and within the content description of the Letter of Amendment.

Watkins, R.; Jordan, J.; Hensel, S.

2010-05-05T23:59:59.000Z

302

Laser diode package with enhanced cooling  

Science Conference Proceedings (OSTI)

A laser diode package assembly includes a reservoir filled with a fusible metal in close proximity to a laser diode. The fusible metal absorbs heat from the laser diode and undergoes a phase change from solid to liquid during the operation of the laser. The metal absorbs heat during the phase transition. Once the laser diode is turned off, the liquid metal cools off and resolidifies. The reservoir is designed such that that the liquid metal does not leave the reservoir even when in liquid state. The laser diode assembly further includes a lid with one or more fin structures that extend into the reservoir and are in contact with the metal in the reservoir.

Deri, Robert J.; Kotovsky, Jack; Spadaccini, Christopher M.

2012-06-26T23:59:59.000Z

303

Laser diode package with enhanced cooling  

Science Conference Proceedings (OSTI)

A laser diode package assembly includes a reservoir filled with a fusible metal in close proximity to a laser diode. The fusible metal absorbs heat from the laser diode and undergoes a phase change from solid to liquid during the operation of the laser. The metal absorbs heat during the phase transition. Once the laser diode is turned off, the liquid metal cools off and resolidifies. The reservoir is designed such that that the liquid metal does not leave the reservoir even when in liquid state. The laser diode assembly further includes a lid with one or more fin structures that extend into the reservoir and are in contact with the metal in the reservoir.

Deri, Robert J. (Pleasanton, CA); Kotovsky, Jack (Oakland, CA); Spadaccini, Christopher M. (Oakland, CA)

2012-06-12T23:59:59.000Z

304

AMPX-77 Phase 1 certification package  

Science Conference Proceedings (OSTI)

The AMPX-77 Phase 1 modules have been certified. AMPX-77 is a modular code system for generating coupled multigroup neutron-gamma cross section libraries from Evaluated Nuclear Data Files (ENDF/B). All basic cross-section data are input from the formats used by the ENDF/B, and output can be obtained from a variety of formats, included in its own internal and very general formats, along with a variety of other useful formats used by major transport, diffusion theory, and Monte Carlo codes. Processing is provided for both neutron and gamma-ray data. The AMPX-77 code system will be used at SRS to perform critical calculations related to nuclear criticality safety. The AMPX-77 modular codes system contains forty-seven separate modules. For the certification process, the 47 modules have been divided into three groups or phases. This Certification Package is for the Phase 1 modules: BONAMI, LAPHNGAS, MALOCS, NITAWL, ROLAIDS, SMUG, and XSDRNPM.

Niemer, K.A.

1994-03-01T23:59:59.000Z

305

KENO V.a certification package  

Science Conference Proceedings (OSTI)

KENO V.a has been certified. KENO V.a is a multigroup Monte Carlo criticality program used to calculate the k-effective of a 3-D system. It is part of the SCALE modular code system for performing Standardized Computer Analyses for Licensing Evaluation. SCALE was developed for the Nuclear Regulatory Commission to satisfy a need for a standardized method of analysis for the evaluation of nuclear fuel facility and package designs. In its present form, the system has the capability to perform criticality, shielding, and heat transfer analyses using well established functional modules tailored to the SCALE system. KENO V.a will be used at SRS to perform critical calculations related to nuclear criticality safety.

Niemer, K.A.

1994-04-01T23:59:59.000Z

306

The Impact of Maintenance on Packaged Unitary Equipment  

Science Conference Proceedings (OSTI)

This report summarizes the findings of a two-year study of the energy and demand impacts of maintenance on rooftop packaged heating and cooling equipment. The purpose of the project was to determine if energy consumption and peak demand reductions could be reliably obtained through the implementation of proper maintenance on unitary packaged equipment in the three to ten ton range.

1997-05-29T23:59:59.000Z

307

An Assessment Model on Green Degree of Biodegradable Packaging Materials  

Science Conference Proceedings (OSTI)

An assessment model of green degree of biodegradable packaging materials is built. The first-order assessment indexes are composed of environmental properties, energy properties, resource properties and economy and the second order assessment index are ... Keywords: packaging materials, analytic hierarchy process, life cycle assessment

Xiaoming Zuo; Zhaomei Xu

2010-03-01T23:59:59.000Z

308

Development of an Air Transport Type A Fissile Package  

SciTech Connect

This paper presents the summary of testing by the Savannah River National Laboratory (SRNL) to support development of a light weight (<140 lbs) air transport qualified Type A Fissile Packaging. The package design incorporates features and materials specifically designed to minimize packaging weight. The light weight package is being designed to provide confinement to the contents when subjected to the normal and hypothetical conditions required of an air transportable Type A Fissile radioactive material shipping package. The objective of these tests was to provide design input to the final design for the LORX Type A Fissile Air Transport Packaging when subjected to the performance requirements of the drop, crush and puncture probe test of 10CFR71. The post test evaluation of the prototype packages indicates that all of the tested designs would satisfactorily confine the content within the packaging. The differences in the performance of the prototypes varied significantly depending on the core materials and their relative densities. Information gathered from these tests is being used to develop the final design for the Department of Homeland Security.

Blanton, P.; Ebert, K.

2011-07-13T23:59:59.000Z

309

Working and Net Available Shell Storage Capacity as of March...  

Gasoline and Diesel Fuel Update (EIA)

includes tables detailing working and net available shell storage capacity by type of facility, product, and Petroleum Administration for Defense District (PAD District). Net...

310

Working and Net Available Shell Storage Capacity as of ...  

U.S. Energy Information Administration (EIA)

It includes three tables detailing working and net available shell storage capacity by facility type, product, and PAD District as of September 30, 2010.

311

Optimization the Preparation of Activated Carbon Form Walnut Shell ...  

Science Conference Proceedings (OSTI)

The study supported the potentiality of comprehensive utilization of walnut shell and the ... An Experimental Investigation of a Flue Gas Recirculation System for ...

312

Nondestructive Evaluation: Structural Health Monitoring for Heat Exchanger Shells  

Science Conference Proceedings (OSTI)

The heat exchanger shell is a pressure vessel that surrounds and encloses a tube bundle. The shell is susceptible to corrosion and wear, which originates from the inside of the vessel and is caused by steam impingement and flow conditions. The shells are nominally 30 to 50 ft (9.1 to 15.2 m) in length and 30 to 60 in. (76.2 to 152.4 cm) in diameter; the wall thickness is approximately 0.75 in. (1.91 cm). Ultrasonic thickness readings are currently performed on distinct regions on the shell wall to suppor...

2008-03-14T23:59:59.000Z

313

Absence of Embedded Mass Shells: Cerenkov Radiation and Quantum Friction  

E-Print Network (OSTI)

We show that, in a model where a non-relativistic particle is coupled to a quantized relativistic scalar Bose field, the embedded mass shell of the particle dissolves in the continuum when the interaction is turned on, provided the coupling constant is sufficiently small. More precisely, under the assumption that the fiber eigenvectors corresponding to the putative mass shell are differentiable as functions of the total momentum of the system, we show that a mass shell could exist only at a strictly positive distance from the unperturbed embedded mass shell near the boundary of the energy-momentum spectrum.

W. De Roeck; J. Froehlich; A. Pizzo

2010-01-05T23:59:59.000Z

314

Core-Shell Type Nanowires for Electrodes of Flexible ...  

Science Conference Proceedings (OSTI)

Abstract Scope, Highly conductive oxide core-thin anode material shell nanowire ... yet flexible electrode with large surface area and high electric conductivity, ...

315

STATEMENT OF CONSIDERATIONS REQUEST BY SHELL SOLAR SYSTEMS, LP...  

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

As set out ins the attached waiver petition and in subsequent discussions with DOE Patent Counsel, Shell Solar Systems, LP (SSI) has requested an advance waiver of domestic...

316

Gulf Coast (PADD 3) Shell Storage Capacity at Operable Refineries  

U.S. Energy Information Administration (EIA)

Propane/Propylene: 4,376: 3,520: 3,565-----1982-2013: ... Notes: Shell storage capacity is the design capacity of the tank. See Definitions, Sources, ...

317

Working and Net Available Shell Storage Capacity as of ...  

U.S. Energy Information Administration (EIA)

Revision to Working and Net Available Shell Storage Capacity as of September 30, 2010 . Crude oil storage capacity data at tank farms reported for PAD District 2 and ...

318

Shell Solar GmbH formerly Siemens und Shell Solar GmbH | Open Energy  

Open Energy Info (EERE)

GmbH formerly Siemens und Shell Solar GmbH GmbH formerly Siemens und Shell Solar GmbH Jump to: navigation, search Name Shell Solar GmbH (formerly Siemens und Shell Solar GmbH) Place Munich, Bavaria, Germany Zip 80807 Sector Solar Product Manufacturer and distributor of solar energy equipment and products. Coordinates 48.136415°, 11.577531° Loading map... {"minzoom":false,"mappingservice":"googlemaps3","type":"ROADMAP","zoom":14,"types":["ROADMAP","SATELLITE","HYBRID","TERRAIN"],"geoservice":"google","maxzoom":false,"width":"600px","height":"350px","centre":false,"title":"","label":"","icon":"","visitedicon":"","lines":[],"polygons":[],"circles":[],"rectangles":[],"copycoords":false,"static":false,"wmsoverlay":"","layers":[],"controls":["pan","zoom","type","scale","streetview"],"zoomstyle":"DEFAULT","typestyle":"DEFAULT","autoinfowindows":false,"kml":[],"gkml":[],"fusiontables":[],"resizable":false,"tilt":0,"kmlrezoom":false,"poi":true,"imageoverlays":[],"markercluster":false,"searchmarkers":"","locations":[{"text":"","title":"","link":null,"lat":48.136415,"lon":11.577531,"alt":0,"address":"","icon":"","group":"","inlineLabel":"","visitedicon":""}]}

319

Characterization of the corrosion behavior of the carbon steel liner in Hanford Site single-shell tanks  

SciTech Connect

Six safety initiatives have been identified for accelerating the resolution of waste tank safety issues and closure of unreviewed safety questions. Safety Initiative 5 is to reduce safety and environmental risk from tank leaks. Item d of Safety Initiative 5 is to complete corrosion studies of single-shell tanks to determine failure mechanisms and corrosion control options to minimize further degradation by June 1994. This report has been prepared to fulfill Safety Initiative 5, Item d. The corrosion mechanisms that apply to Hanford Site single-shell tanks are stress corrosion cracking, pitting/crevice corrosion, uniform corrosion, hydrogen embrittlement, and microbiologically influenced corrosion. The corrosion data relevant to the single-shell tanks dates back three decades, when results were obtained from in-situ corrosion coupons in a few single-shell tanks. Since that time there have been intertank transfers, evaporation, and chemical alterations of the waste. These activities have changed the character and the present composition of the waste is not well characterized. All conclusions and recommendations are made in the absence of relevant laboratory experimental data and tank inspection data. The report attempts to identify the failure mechanisms by a literature survey of carbon steel data in environments similar to the single-shell tank wastes, and by a review of the work performed at the Savannah River Site where similar wastes are stored in similar carbon steel tanks. Based on these surveys, and in the absence of data specific to Hanford single-shell tanks, it may be concluded that the single-shell tanks identified as leakers failed primarily by stress corrosion cracking due to the presence of high nitrate/low hydroxide wastes and residual stresses. In addition, some failures may be attributed to pitting under crevices in low hydroxide locations.

Anantatmula, R.P.; Schwenk, E.B. [Westinghouse Hanford Co., Richland, WA (United States); Danielson, M.J. [Pacific Northwest Lab., Richland, WA (United States)

1994-06-01T23:59:59.000Z

320

Multistable and morphing corrugated shell structures  

E-Print Network (OSTI)

to their popularity for , i.a., cheap roofing, 0 1' their use as a layer in sandwich structures, e.g., cardboard packaging, as shown in F ig. 1.1. Moving upwards in complexity. from simple stm ctures, machinery consists of a series of such structures connected... by hinges, rods, sliders 8c. to provide the relevant degrees of freedom, and driven by actuators such as motors , pneumatic 0 1' hydraulic pistons. The result is a complex system of many components , each of which is critical to the perfor­ mance...

Norman, Alexander David

2009-06-09T23:59:59.000Z

Note: This page contains sample records for the topic "reduce shell package" 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

Packaging Research and Routing Optimization - Research Area - National  

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

Packaging Research Packaging Research The Packaging Research Facility conducts research for DOE National Nuclear Security Administration, as well as for commercial customers. The facility specializes in testing packaging systems for the transportation of nuclear fuel. Once a package design has been successfully tested, it can then be certified by one of several regulatory authorities, usually DOE, the National Nuclear Security Administration, or the Nuclear Regulatory Commission, for use on the road. Welcome EESD Programs EES Directorate ORNL Web Contact Disclaimer Oak Ridge National Laboratory is a national multi-program research and development facility managed by UT-Battelle, LLC for the U.S. Department of Energy UT-Battelle, LLC U.S. Department of Energy Contact Scott Ludwig

322

COMPARISON OF RESPONSE OF 9977 TEST PACKAGES TO ANALYTICAL RESULTS  

Science Conference Proceedings (OSTI)

Each of the hypothetical accident test cases for the 9977 prototypes was included in the battery of finite element structural analyses performed for the package. Comparison of the experimental and analytical results provides a means of confirming that the analytical model correctly represents the physical behavior of the package. The ability of the analytical model to correctly predict the performance of the foam overpack material for the crush test is of particular interest. The dissipation of energy in the crushing process determines the deceleration of the package upon impact and the duration of the impact. In addition, if the analytical model correctly models the foam behavior, the predicted deformation of the package will match that measured on the test articles. This study compares the deformations of the test packages with the analytical predictions. In addition, the impact acceleration and impact duration for the test articles are compared with those predicted by the analyses.

Smith, A; Tsu-Te Wu, T

2007-12-05T23:59:59.000Z

323

Development of an Automated Pit Packaging System for Pantex  

E-Print Network (OSTI)

Sandia National Laboratories is developing a system that uses robots to package pits at Pantex in the AT-400A pit storage and transportation container. This report will give an overview of the AT-400A packaging process, and the parts of the overall AT-400A packaging operation that will be performed robotically. The process employed to move from development in the laboratory at Sandia to production use at Pantex will be described. Finally, important technology components being developed for and incorporated into the robotic system will be described. ____________________________________________________________________________ 2 Development of an Automated Pit Packaging System for Pantex Intentionally Left Blank ______________________________________________________________________________ Development of an Automated Pit Packaging System for Pantex 3 Contents 1. Introduction........................................................................................................... 7 ...

Jill Fahrenholtz Manufacturing; System For Pantex; Jill C. Fahrenholtz

1997-01-01T23:59:59.000Z

324

Drop Tests of 325 Pound 6M Specification Packages  

Science Conference Proceedings (OSTI)

Testing of 6M specification packages, performed in response to concerns over the integrity of the clamp-ring closure, showed that the clamp-ring was unable to retain the top in thirty foot drop tests of packages having the maximum allowed weight (290 kg or 640 lb). To determine if the clamp-ring closure was adequate for packages with lower contents weight, a series of tests were performed on packages weighing 147 kg (325 lb) at a range of impact angles. The results showed that the standard clamp-ring closure was unable to retain the top in tests of standard 6M packages weighing 147 kg (325 lb). A test employing a plywood disk enhanced closure with impact at 6.5 degrees retained its top successfully.

SMITH, AC

2004-04-30T23:59:59.000Z

325

FINITE ELEMENT ANALYSIS OF BULK TRITIUM SHIPPING PACKAGE  

SciTech Connect

The Bulk Tritium Shipping Package was designed by Savannah River National Laboratory. This package will be used to transport tritium. As part of the requirements for certification, the package must be shown to meet the scenarios of the Hypothetical Accident Conditions (HAC) defined in Code of Federal Regulations Title 10 Part 71 (10CFR71). The conditions include a sequential 30-foot drop event, 30-foot dynamic crush event, and a 40-inch puncture event. Finite Element analyses were performed to support and expand upon prototype testing. Cases similar to the tests were evaluated. Additional temperatures and orientations were also examined to determine their impact on the results. The peak stress on the package was shown to be acceptable. In addition, the strain on the outer drum as well as the inner containment boundary was shown to be acceptable. In conjunction with the prototype tests, the package was shown to meet its confinement requirements.

Jordan, J.

2010-06-02T23:59:59.000Z

326

Effects of mixed waste simulants on transportation packaging plastic components  

Science Conference Proceedings (OSTI)

The purpose of hazardous and radioactive materials packaging is to, enable these materials to be transported without posing a threat to the health or property of the general public. To achieve this aim, regulations have been written establishing general design requirements for such packagings. While no regulations have been written specifically for mixed waste packaging, regulations for the constituents of mixed wastes, i.e., hazardous and radioactive substances, have been codified. The design requirements for both hazardous and radioactive materials packaging specify packaging compatibility, i.e., that the materials of the packaging and any contents be chemically compatible with each other. Furthermore, Type A and Type B packaging design requirements stipulate that there be no significant chemical, galvanic, or other reaction between the materials and contents of the package. Based on these requirements, a Chemical Compatibility Testing Program was developed in the Transportation Systems Department at Sandia National Laboratories (SNL). The program, supported by the US Department of Energy`s (DOE) Transportation Management Division, EM-261 provides the means to assure any regulatory body that the issue of packaging material compatibility towards hazardous and radioactive materials has been addressed. In this paper, we describe the general elements of the testing program and the experimental results of the screening tests. The implications of the results of this testing are discussed in the general context of packaging development. Additionally, we present the results of the first phase of this experimental program. This phase involved the screening of five candidate liner and six seal materials against four simulant mixed wastes.

Nigrey, P.J.; Dickens, T.G.

1994-12-31T23:59:59.000Z

327

Packaging, Transportation, and Disposal Logistics for Large Radioactively Contaminated Reactor Decommissioning Components  

Science Conference Proceedings (OSTI)

The packaging, transportation and disposal of large, retired reactor components from operating or decommissioning nuclear plants pose unique challenges from a technical as well as regulatory compliance standpoint. In addition to the routine considerations associated with any radioactive waste disposition activity, such as characterization, ALARA, and manifesting, the technical challenges for large radioactively contaminated components, such as access, segmentation, removal, packaging, rigging, lifting, mode of transportation, conveyance compatibility, and load securing require significant planning and execution. In addition, the current regulatory framework, domestically in Titles 49 and 10 and internationally in TS-R-1, does not lend itself to the transport of these large radioactively contaminated components, such as reactor vessels, steam generators, reactor pressure vessel heads, and pressurizers, without application for a special permit or arrangement. This paper addresses the methods of overcoming the technical and regulatory challenges. The challenges and disposition decisions do differ during decommissioning versus component replacement during an outage at an operating plant. During decommissioning, there is less concern about critical path for restart and more concern about volume reduction and waste minimization. Segmentation on-site is an available option during decommissioning, since labor and equipment will be readily available and decontamination activities are routine. The reactor building removal path is also of less concern and there are more rigging/lifting options available. Radionuclide assessment is necessary for transportation and disposal characterization. Characterization will dictate the packaging methodology, transportation mode, need for intermediate processing, and the disposal location or availability. Characterization will also assist in determining if the large component can be transported in full compliance with the transportation and disposal regulations and criteria or if special authorizations must be granted to transport and/or dispose. The U.S. DOT routinely issues special permits for large components where compliance with regulatory or acceptance criteria is impractical or impossible to meet. Transportation and disposal safety must be maintained even under special permits or authorizations. For example, if transported un-packaged, performance analysis must still be performed to assess the ability of the large component's outer steel shell to contain the internal radioactive contamination under normal transportation conditions and possibly incidence normal to transportation. The dimensions and weight of a large component must be considered when determining the possible modes of transportation (rail, water, or highway). At some locations, rail and/or barge access is unavailable. Many locations that once had an active rail spur to deliver new construction materials and components have let the spur deteriorate to the point that repair and upgrade of the spur is no longer economically feasible. Barge slips that have not been used since new plant construction require significant repair and/or dredging. Short on-site haul routes must be assessed for surface and subsurface conditions, as well as longer off-site routes. Off-site routes require clearance approvals from the regulatory authorities or, in the case of rail transport, the rail lines. Significant engineering planning and analysis must be performed during the pre-mobilization. In conclusion, the packaging, transportation, and disposal of large, oversized radioactively contaminated components removed during plant decommissioning is complex. However, over the last 15 years, a 100 or more components have been safely and compliantly packaged and transported for processing and/or disposal.

Lewis, Mark S. [EnergySolutions: 140 Stoneridge Drive, Columbia, SC 29210 (United States)

2008-01-15T23:59:59.000Z

328

Technical Review Report for the Mound 1KW Package Safety Analysis Report for Packaging Addendum No. 1, through Revision b  

SciTech Connect

This Technical Review Report (TRR) documents the review, performed by the Lawrence Livermore National Laboratory (LLNL) staff, at the request of the U.S. Department of Energy (DOE), on the 'Mound 1KW Package Safety Analysis Report for Packaging, Addendum No. 1, Revision b', dated May 2007 (Addendum 1). The Mound 1KW Package is certified by DOE Certificate of Compliance (CoC) number USA/9516/B(U)F-85 for the transportation of Type B quantities of plutonium heat source material. The safety analysis of the package is documented in the 'Safety Analysis Report for Packaging (SARP) for the Mound 1KW Package' (i.e., the Mound 1KW SARP, or the SARP). Addendum 1 incorporates a new fueled capsule assembly payload. The following changes have been made to add this payload: (1) The primary containment vessel (PCV) will be of the same design, but will increase in height to 11.16 in.; (2) A new graphite support block will be added to support up to three fueled capsule assemblies per package; (3) The cutting groove height on the secondary containment vessel (SCV) will be heightened to accommodate the taller PCV; and (4) A 3.38 in. high graphite filler block will be placed on top of the PCV. All other packaging features, as described in the Mound 1KW SARP [3], remain unchanged. This report documents the LLNL review of Addendum 1[1]. The specific review for each SARP Chapter is documented herein.

DiSabatino, A; West, M; Hafner, R; Russell, E

2007-10-04T23:59:59.000Z

329

MEE 452: Example 3-2 ShellShell--andand--Tube Heat Exchanger Analysis:Tube Heat Exchanger Analysis  

E-Print Network (OSTI)

minmaxminmax min ,;; ,min)()( C C NTU C UA NTU TC q q q CCCcmCcmC UA CHCpCHpH #12;Tube arrangement in shell

Kostic, Milivoje M.

330

Integrating Volume Reduction and Packaging Alternatives to Achieve Cost Savings for Low Level Waste Disposal at the Rocky Flats Environmental Technology Site  

Science Conference Proceedings (OSTI)

In order to reduce costs and achieve schedules for Closure of the Rocky Flats Environmental Technology Site (RFETS), the Waste Requirements Group has implemented a number of cost saving initiatives aimed at integrating waste volume reduction with the selection of compliant waste packaging methods for the disposal of RFETS low level radioactive waste (LLW). Waste Guidance Inventory and Shipping Forecasts indicate that over 200,000 m3 of low level waste will be shipped offsite between FY2002 and FY2006. Current projections indicate that the majority of this waste will be shipped offsite in an estimated 40,000 55-gallon drums, 10,000 metal and plywood boxes, and 5000 cargo containers. Currently, the projected cost for packaging, shipment, and disposal adds up to $80 million. With these waste volume and cost projections, the need for more efficient and cost effective packaging and transportation options were apparent in order to reduce costs and achieve future Site packaging a nd transportation needs. This paper presents some of the cost saving initiatives being implemented for waste packaging at the Rocky Flats Environmental Technology Site (the Site). There are many options for either volume reduction or alternative packaging. Each building and/or project may indicate different preferences and/or combinations of options.

Church, A.; Gordon, J.; Montrose, J. K.

2002-02-26T23:59:59.000Z

331

DETECTION OF DRUGSTORE BEETLES IN 9975 PACKAGES USING ACOUSTIC EMISSIONS  

SciTech Connect

This report documents the initial feasibility tests performed using a commercial acoustic emission instrument for the purpose of detecting beetles in Department of Energy 9975 shipping packages. The device selected for this testing was a commercial handheld instrument and probe developed for the detection of termites, weevils, beetles and other insect infestations in wooden structures, trees, plants and soil. The results of two rounds of testing are presented. The first tests were performed by the vendor using only the hand-held instrument’s indications and real-time operator analysis of the audio signal content. The second tests included hands-free positioning of the instrument probe and post-collection analysis of the recorded audio signal content including audio background comparisons. The test results indicate that the system is promising for detecting the presence of drugstore beetles, however, additional work would be needed to improve the ease of detection and to automate the signal processing to eliminate the need for human interpretation. Mechanisms for hands-free positioning of the probe and audio background discrimination are also necessary for reliable detection and to reduce potential operator dose in radiation environments.

Shull, D.

2013-03-04T23:59:59.000Z

332

Unconventional Staging Package Selection Leads to Cost Savings  

SciTech Connect

In late 2010, U.S. Department of Energy (DOE) Deputy Secretary of Energy, Daniel Poneman, directed that an analysis be conducted on the U-233 steel-clad, Zero Power Reactor (ZPR) fuel plates that were stored at Oak Ridge National Laboratory (ORNL), focusing on cost savings and any potential DOE programmatic needs for the special nuclear material (SNM). The NA-162 Nuclear Criticality Safety Program requested retention of these fuel plates for use in experiments at the Nevada National Security Site (NNSS). A Secretarial Initiative challenged ORNL to make the first shipment to the NNSS by the end of the 2011 calendar year, and this effort became known as the U-233 Project Accelerated Shipping Campaign. To meet the Secretarial Initiative, National Security Technologies, LLC (NSTec), the NNSS Management and Operations contractor, was asked to facilitate the receipt and staging of the U-233 fuel plates in the Device Assembly Facility (DAF). Because there were insufficient staging containers available for the fuel plates, NSTec conducted an analysis of alternatives. The project required a staging method that would reduce the staging footprint while addressing nuclear criticality safety and radiation exposure concerns. To accommodate an intermediate staging method of approximately five years, the NSTec project team determined that a unique and unconventional staging package, the AT-400R, was available to meet the project requirements. By using the AT-400R containers, NSTec was able to realize a cost savings of approximately $10K per container, a total cost savings of nearly $450K.

,

2012-06-07T23:59:59.000Z

333

Growth and photoluminescence of self-catalyzed GaP/GaNP core/shell nanowires on Si(111) by gas source molecular beam epitaxy  

Science Conference Proceedings (OSTI)

We report a study on self-catalyzed GaP/GaNP core/shell nanowires (NWs) grown on Si(111) by gas-source molecular beam epitaxy. Scanning electron microscopy images show that vertical and uniform GaP NWs and GaP/GaNP core/shell NWs are grown on Si(111). The density ranges from {approx}1 x 10{sup 7} to {approx}5 x 10{sup 8} cm{sup -2} across the substrate. Typical diameters are {approx}110 nm for GaP NWs and {approx}220 nm for GaP/GaNP NWs. Room temperature photoluminescence (PL) signal from the GaP/GaNP core/shell NWs confirms that N is incorporated in the shell and the average N content is {approx}0.9%. The PL low-energy tail is significantly reduced, compared to bulk GaNP.

Kuang, Y. J. [Department of Physics, University of California, San Diego, La Jolla, California 92093 (United States); Sukrittanon, S. [Graduate Program of Material Science and Engineering, University of California, San Diego, La Jolla, California 92093 (United States); Li, H. [Department of Electrical and Computer Engineering, University of California, San Diego, La Jolla, California 92093 (United States); Tu, C. W. [Graduate Program of Material Science and Engineering, University of California, San Diego, La Jolla, California 92093 (United States); Department of Electrical and Computer Engineering, University of California, San Diego, La Jolla, California 92093 (United States)

2012-01-30T23:59:59.000Z

334

terms Package — FiPy 3.0.1-dev157-g518df83 documentation  

Science Conference Proceedings (OSTI)

... steppers Package. Next topic. tests Package. This Page. Show Source. Quick search. Enter search terms or a module, class or function name. Contact ...

2013-08-30T23:59:59.000Z

335

High Rayleigh number thermal convection in volumetrically heated spherical shells  

E-Print Network (OSTI)

parameterizations for the average temperature of the shell and for the temperature jump across the thermal boundary properties, cores and overlying shells (e.g., silicate mantles or ice layers) of rocky planets and icy moons, including the rheology of the material, the presence of phase transitions, and the mode of heating

Tackley, Paul J.

336

Pre-release plastic packaging of MEMS and IMEMS devices  

DOE Patents (OSTI)

A method is disclosed for pre-release plastic packaging of MEMS and IMEMS devices. The method can include encapsulating the MEMS device in a transfer molded plastic package. Next, a perforation can be made in the package to provide access to the MEMS elements. The non-ablative material removal process can include wet etching, dry etching, mechanical machining, water jet cutting, and ultrasonic machining, or any combination thereof. Finally, the MEMS elements can be released by using either a wet etching or dry plasma etching process. The MEMS elements can be protected with a parylene protective coating. After releasing the MEMS elements, an anti-stiction coating can be applied. The perforating step can be applied to both sides of the device or package. A cover lid can be attached to the face of the package after releasing any MEMS elements. The cover lid can include a window for providing optical access. The method can be applied to any plastic packaged microelectronic device that requires access to the environment, including chemical, pressure, or temperature-sensitive microsensors; CCD chips, photocells, laser diodes, VCSEL's, and UV-EPROMS. The present method places the high-risk packaging steps ahead of the release of the fragile portions of the device. It also provides protection for the die in shipment between the molding house and the house that will release the MEMS elements and subsequently treat the surfaces.

Peterson, Kenneth A. (Albuquerque, NM); Conley, William R. (Tijeras, NM)

2002-01-01T23:59:59.000Z

337

Pre-release plastic packaging of MEMS and IMEMS devices  

Science Conference Proceedings (OSTI)

A method is disclosed for pre-release plastic packaging of MEMS and IMEMS devices. The method can include encapsulating the MEMS device in a transfer molded plastic package. Next, a perforation can be made in the package to provide access to the MEMS elements. The non-ablative material removal process can include wet etching, dry etching, mechanical machining, water jet cutting, and ultrasonic machining, or any combination thereof. Finally, the MEMS elements can be released by using either a wet etching or dry plasma etching process. The MEMS elements can be protected with a parylene protective coating. After releasing the MEMS elements, an anti-stiction coating can be applied. The perforating step can be applied to both sides of the device or package. A cover lid can be attached to the face of the package after releasing any MEMS elements. The cover lid can include a window for providing optical access. The method can be applied to any plastic packaged microelectronic device that requires access to the environment, including chemical, pressure, or temperature-sensitive microsensors; CCD chips, photocells, laser diodes, VCSEL's, and UV-EPROMS. The present method places the high-risk packaging steps ahead of the release of the fragile portions of the device. It also provides protection for the die in shipment between the molding house and the house that will release the MEMS elements and subsequently treat the surfaces.

Peterson, Kenneth A. (Albuquerque, NM); Conley, William R. (Tijeras, NM)

2002-01-01T23:59:59.000Z

338

Application to Export Electric Energy OE Doc No. EA-339-A Shell...  

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

Energy OE Doc No. EA-339-A Shell Energy North America (US), L.P. Application from Shell Energy to export electric energy to Canada. EA-339-A Shell Energy (CN).pdf More...

339

EA-339-A Shell Energy North America (US), L.P. | Department of...  

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

North America (US), L.P. EA-339-A Shell Energy North America (US), L.P. Order authorizing Shell Energy to export electric energy to Canada. EA-339-A Shell Energy (CN).pdf...

340

EA-339 Shell Energy North America (US), L.P. | Department of...  

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

North America (US), L.P. EA-339 Shell Energy North America (US), L.P. Order authorizing Shell Energy North America (US), L.P. to export electric energy to Canada EA-339 Shell...

Note: This page contains sample records for the topic "reduce shell package" 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

EA-338 Shell Energy North America (US), L.P. | Department of...  

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

North America (US), L.P. EA-338 Shell Energy North America (US), L.P. Order authorizing Shell Energy North America (US), L.P. to export electric energy to Mexico EA-338 Shell...

342

EA-338-A Shell Energy North America (US), L.P. | Department of...  

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

Shell Energy North America (US), L.P. Order authorizing Shell Energy to export electric energy to Mexico. EA-338-A Shell Energy (MX).pdf More Documents & Publications Application...

343

SPR Awards Exchange Contract to Shell Trading | Department of Energy  

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

Awards Exchange Contract to Shell Trading Awards Exchange Contract to Shell Trading SPR Awards Exchange Contract to Shell Trading May 10, 2007 - 12:55pm Addthis Deliveries to Begin in August WASHINGTON, DC - The U.S. Department of Energy (DOE) today awarded a contract to Shell Trading for exchange of 8.7 million barrels of royalty oil produced from the Gulf Coast for crude oil meeting the quality specifications of the Strategic Petroleum Reserve (SPR). The exchange oil will be delivered to two SPR sites, West Hackberry, Louisiana and Bryan Mound, Texas. The offer submitted by Shell Trading represented the highest value of specification-grade oil for the Reserve. Deliveries are expected to begin in August 2007 at a modest rate of approximately 50,000 barrels per day for a period of six months. The contract terms apply royalty-in-kind exchange provisions that require

344

A Shell Theory for Chiral Single-Wall Carbon Nanotubes  

E-Print Network (OSTI)

In this paper, we propose a characterization of the mechanical response of the linearly elastic shell we associate to a single-wall carbon nanotube of arbitrary chirality. In Bajaj et al. 2013, we gave such a characterization in the case of zigzag and armchair nanotubes; in particular, we showed that the orthotropic response we postulated for the associated shells is to become isotropic in the graphene-limit, that is, when the shell radius grows bigger and bigger. Here we give an explicit recipe to construct the generally anisotropic response of the shell associated to a nanotube of any chirality in terms of the response of the shell associated to a related zigzag or armchair nanotube. The expected coupling of mechanical effects that anisotropy entrains is demonstrated in the case of a torsion problem, where the axial extension accompanying twist is determined analytically and found in good agreement with the available experimental data.

Antonino Favata; Paolo Podio-Guidugli

2013-06-28T23:59:59.000Z

345

Stabilization of the resistive shell mode in tokamaks  

Science Conference Proceedings (OSTI)

The stability of current-driven external-kink modes is investigated in a tokamak plasma surrounded by an external shell of finite electrical conductivity. According to conventional theory, the ideal mode can be stabilized by placing the shell sufficiently close to the plasma, but the non-rotating ``resistive shell mode,`` which grows on the characteristic L/R time of the shell, always persists. It is demonstrated, using both analytic and numerical techniques, that a combination of strong edge plasma rotation and dissipation somewhere inside the plasma is capable of stabilizing the resistive shell mode. This stabilization mechanism does not necessarily depend on toroidicity or presence of resonant surfaces inside the plasma.

Fitzpatrick, R.; Aydemir, A.

1995-02-01T23:59:59.000Z

346

Hanford double shell tank corrosion monitoring instrument tree prototype  

Science Conference Proceedings (OSTI)

High-level nuclear wastes at the Hanford site are stored underground in carbon steel double-shell and single-shell tanks (DSTs and SSTs). The installation of a prototype corrosion monitoring instrument tree into DST 241-A-101 was completed in December 1995. The instrument tree has the ability to detect and discriminate between uniform corrosion, pitting, and stress corrosion cracking (SCC) through the use of electrochemical noise measurements and a unique stressed element, three-electrode probe. The tree itself is constructed of AISI 304L stainless steel (UNS S30403), with probes in the vapor space, vapor/liquid interface and liquid. Successful development of these trees will allow their application to single shell tanks and the transfer of technology to other US Department of Energy (DOE) sites. Keywords: Hanford, radioactive waste, high-level waste tanks, electrochemical noise, probes, double-shell tanks, single-shell tanks, corrosion.

Nelson, J.L.; Edgemon, G.L.; Ohl, P.C.

1995-11-01T23:59:59.000Z

347

Pemex to acquire interest in Shell Texas refinery  

Science Conference Proceedings (OSTI)

This paper reports that Petroleos Mexicanos and Shell Oil Co. have signed a memorandum of understanding to form a joint refining venture involving Shell's 225,000 b/d Deer Park, Tex., refinery. Under the agreement, Mexico's state owned oil company is to purchase a 50% interest in the refinery, and Shell is to sell Pemex unleaded gasoline on a long term basis. Under the venture, Shell and Pemex plan to add undisclosed conversion and upgrading units tailored to process heavy Mexican crude. The revamp will allow Pemex to place more than 100,000 b/d of Mayan heavy crude on the U.S. market. Mayan accounts for 70% of Mexico's crude oil exports. In turn, Shell will sell Pemex as much as 45,000 b/d of unleaded gasoline to help meet Mexico's rapidly growing demand.

Not Available

1992-08-31T23:59:59.000Z

348

Aging and Phase Stability of Waste Package Outer Barrier  

Science Conference Proceedings (OSTI)

This report was prepared in accordance with ''Technical Work Plan for: Regulatory Integration Modeling and Analysis of the Waste Form and Waste Package'' (BSC 2004 [DIRS 171583]). This report provides information on the phase stability of Alloy 22, the current waste package outer barrier material. The goal of this model is to determine whether the single-phase solid solution is stable under repository conditions and, if not, how fast other phases may precipitate. The aging and phase stability model, which is based on fundamental thermodynamic and kinetic concepts and principles, will be used to provide predictive insight into the long-term metallurgical stability of Alloy 22 under relevant repository conditions. The results of this model are used by ''General Corrosion and Localized Corrosion of Waste Package Outer Barrier'' as reference-only information. These phase stability studies are currently divided into three general areas: Tetrahedrally close-packed (TCP) phase and carbide precipitation in the base metal; TCP and carbide precipitation in welded samples; and Long-range ordering reactions. TCP-phase and carbide precipitates that form in Alloy 22 are generally rich in chromium (Cr) and/or molybdenum (Mo) (Raghavan et al. 1984 [DIRS 154707]). Because these elements are responsible for the high corrosion resistance of Alloy 22, precipitation of TCP phases and carbides, especially at grain boundaries, can lead to an increased susceptibility to localized corrosion in the alloy. These phases are brittle and also tend to embrittle the alloy (Summers et al. 1999 [DIRS 146915]). They are known to form in Alloy 22 at temperatures greater than approximately 600 C. Whether these phases also form at the lower temperatures expected in the repository during the 10,000-year regulatory period must be determined. The kinetics of this precipitation will be determined for both the base metal and the weld heat-affected zone (HAZ). The TCP phases (P, {mu}, and {sigma}) are present in the weld metal in the as-welded condition. It may be possible to eliminate these phases through a solution anneal heat treatment, but that may not be possible for the closure weld because the spent nuclear fuel cladding cannot be heated to more than 350 C. The effects of any stress mitigation techniques (such as laser peening or solution heat treating) that may be used to reduce the tensile stresses on the closure welds must also be determined. Cold-work will cause an increase in dislocation density, and such an increase in dislocation density may cause an increase in diffusion rates that control precipitation kinetics (Porter et al. 1992 [DIRS 161265]; Tawancy et al. 1983 [DIRS 104991]). Long-range order (LRO) occurs in nickel (Ni)-Cr-Mo alloys (such as Alloy 22) at temperatures less than approximately 600 C. This ordering has been linked to an increased susceptibility of Ni-Cr-Mo alloys to stress corrosion cracking and hydrogen embrittlement (Tawancy et al. 1983 [DIRS 104991]). These analyses provide information on the rate at which LRO may occur in Alloy 22 under repository conditions. Determination of the kinetics of transformations through experimental techniques requires that the transformations being investigated be accelerated due to the fact that the expected service life is at least 10,000 years. Phase transformations are typically accelerated through an increase in temperature. The rate of transformation is determined at the higher temperature and is extrapolated to the lower temperatures of interest.

F. Wong

2004-09-28T23:59:59.000Z

349

FFTF railroad tank car safety evaluation for packaging  

SciTech Connect

This Safety Evaluation for Packaging (SEP) provides evaluations necessary to approve transfer of the 8,000 gallon Liquid Waste Tank Car (LWTC) from the Fast Flux Test Facility (FFTF) to the 200 Areas. This SEP will demonstrate that the transfer cif the LWTC will provide an equivalent degree of safety as would be provided by packages meeting U.S. Department of Transportation (DOT) requirements. This fulfills onsite transportation requirements implemented in the Hazardous Material Packaging and Shipping, WHC-CM-2-14.

Romano, T.

1996-10-25T23:59:59.000Z

350

CH Packaging Operations for High Wattage Waste at LANL  

SciTech Connect

This procedure provides instructions for assembling the following contact-handled (CH) packaging payloads: - Drum payload assembly - Standard Waste Box (SWB) assembly - Ten-Drum Overpack (TDOP) In addition, this procedure also provides operating instructions for the TRUPACT-II CH waste packaging. This document also provides instructions for performing ICV and OCV preshipment leakage rate tests on the following packaging seals, using a nondestructive helium (He) leak test: - ICV upper main O-ring seal - ICV outer vent port plug O-ring seal - OCV upper main O-ring seal - OCV vent port plug O-ring seal.

Washington TRU Solutions LLC

2003-03-21T23:59:59.000Z

351

CH Packaging Operations for High Wattage Waste at LANL  

Science Conference Proceedings (OSTI)

This procedure provides instructions for assembling the following contact-handled (CH) packaging payloads: - Drum payload assembly - Standard Waste Box (SWB) assembly - Ten-Drum Overpack (TDOP) In addition, this procedure also provides operating instructions for the TRUPACT-II CH waste packaging. This document also provides instructions for performing ICV and OCV preshipment leakage rate tests on the following packaging seals, using a nondestructive helium (He) leak test: - ICV upper main O-ring seal - ICV outer vent port plug O-ring seal - OCV upper main O-ring seal - OCV vent port plug O-ring seal.

Washington TRU Solutions LLC

2002-12-18T23:59:59.000Z

352

CH Packaging Operations for High Wattage Waste at LANL  

Science Conference Proceedings (OSTI)

This procedure provides instructions for assembling the following contact-handled (CH) packaging payloads: - Drum payload assembly - Standard Waste Box (SWB) assembly - Ten-Drum Overpack (TDOP) In addition, this procedure also provides operating instructions for the TRUPACT-II CH waste packaging. This document also provides instructions for performing ICV and OCV preshipment leakage rate tests on the following packaging seals, using a nondestructive helium (He) leak test: - ICV upper main O-ring seal - ICV outer vent port plug O-ring seal - OCV upper main O-ring seal - OCV vent port plug O-ring seal.

Washington TRU Solutions LLC

2003-08-28T23:59:59.000Z

353

CH Packaging Operations for High Wattage Waste at LANL  

SciTech Connect

This procedure provides instructions for assembling the following contact-handled (CH) packaging payloads: - Drum payload assembly - Standard Waste Box (SWB) assembly - Ten-Drum Overpack (TDOP) In addition, this procedure also provides operating instructions for the TRUPACT-II CH waste packaging. This document also provides instructions for performing ICV and OCV preshipment leakage rate tests on the following packaging seals, using a nondestructive helium (He) leak test: - ICV upper main O-ring seal - ICV outer vent port plug O-ring seal - OCV upper main O-ring seal - OCV vent port plug O-ring seal.

Washington TRU Solutions LLC

2003-05-06T23:59:59.000Z

354

Development of an automated pit packaging system for Pantex  

Science Conference Proceedings (OSTI)

Sandia National Laboratories is developing a system that uses robots to package pits at Pantex in the AT-400A pit storage and transportation container. This report will give an overview of the AT-400A packaging process, and the parts of the overall AT-400A packaging operation that will be performed robotically. The process employed to move from development in the laboratory at Sandia to production use at Pantex will be described. Finally, important technology components being developed for and incorporated into the robotic system will be described. 7 refs., 9 figs.

Fahrenholtz, J.C.

1997-09-01T23:59:59.000Z

355

A Windows based graphical package for symmetrical components analysis  

Science Conference Proceedings (OSTI)

A Microsoft{reg_sign} Windows{trademark} graphical package to facilitate the teaching and learning of symmetrical component is described in this paper. This package is written in Microsoft Visual Basic 3.0. This software calculates and displays graphically, the ABC sequence and the corresponding symmetrical component phasors. Students can manipulate the graphical displays by keyboard input or by mouse operation. The objective of this package is to help the students to better understand the various aspects of symmetrical components` analysis through a user-friendly Graphical User Interface (GUI).

Yu, D.C.; Chen, D.; Ramasamy, S. [Univ. of Wisconsin, Milwaukee, WI (United States); Flinn, D.G. [Cooper Power System, Franksville, WI (United States)

1995-11-01T23:59:59.000Z

356

Sitewide railroad ties volatile organic package  

SciTech Connect

The initial GC/MS calibration and continuing calibration met all protocols. The calibration working standard is made from 9 separate mixes. One of the mixes (Restek semivolatile mix 3) was doubled, increasing the calibration concentration curve by a factor of two. None of the compounds of interest were affected, and all of the forms have been adjusted. All mass spectral tuning requirements were met for all standards and samples. Internal standard criteria were met for field blank R5306. Perylene-d12 was out on the low side. This sample was reanalyzed and all internal standard criteria were met. The R5302rerr was reported instead of R5302re (the original run of the re-extract) because R5302re failed its internal standard criteria. RSBLK03rr was reported instead of RSBLK03 (the original run of the method blank) because RSBLK03 failed its internal standard criteria. Internal standard criteria for all other samples in this package were met.

Vogel, R.E.

1994-08-31T23:59:59.000Z

357

Device for packaging a lithium battery  

Science Conference Proceedings (OSTI)

Battery packing construction is described for packaging at least one lithium battery, the lithium battery including a solid polymer electrolyte in electrical contact with an anode of lithium or a lithium alloy and a cathode containing at least one metallic salt, the device comprising a first metallic foil having a first continuous band of plastic film bonded thereto by means of a thermoset adhesive along entire peripheral edges of the first metallic foil, a second metallic foil having a second continuous band of plastic film bonded thereto by means of a thermoset adhesive along entire peripheral edges of the second metallic foil, the first and second metallic foils disposed over one another with the first and second plastic films arranged adjacent one another in facing relationship, the lithium battery being sandwiched between the first and the second metallic foils in space inside the first and the second continuous bands of plastic film with the anode in contact with one metallic foil and the cathode in contact with the other metallic foil, the first and second continuous bands of plastic film being imperviously heat-sealed together to prevent any outside substance to contact the battery.

Duval, M.; Giguere, Y.

1993-07-13T23:59:59.000Z

358

A New CNT-Oriented Shell Theory  

E-Print Network (OSTI)

A theory of linearly elastic orthotropic shells is presented, with potential application to the continuous modeling of Carbon NanoTubes. Two relevant features are: the selected type of orthotropic response, which should be suitable to capture differences in chirality; the possibility of accounting for thickness changes due to changes in inter-wall separation to be expected in multi-wall CNTs. A simpler version of the theory is also proposed, in which orthotropy is preserved but thickness changes are excluded, intended for possible application to single-wall CNTs. Another feature of both versions of the present theory is boundary-value problems of torsion, axial traction, uniform inner pressure, and rim flexure, can be solved explicitly in closed form. Various directions of ongoing further research are indicated.

Antonino Favata; Paolo Podio-Guidugli

2011-04-05T23:59:59.000Z

359

Energy conditions, traversable wormholes and dust shells  

E-Print Network (OSTI)

Firstly, we review the pointwise and averaged energy conditions, the quantum inequality and the notion of the ``volume integral quantifier'', which provides a measure of the ``total amount'' of energy condition violating matter. Secondly, we present a specific metric of a spherically symmetric traversable wormhole in the presence of a generic cosmological constant, verifying that the null and the averaged null energy conditions are violated, as was to be expected. Thirdly, a pressureless dust shell is constructed around the interior wormhole spacetime by matching the latter geometry to a unique vacuum exterior solution. In order to further minimize the usage of exotic matter, we then find regions where the surface energy density is positive, thereby satisfying all of the energy conditions at the junction surface. An equation governing the behavior of the radial pressure across the junction surface is also deduced. Lastly, taking advantage of the construction, specific dimensions of the wormhole, namely, the t...

Lobo, F S N

2004-01-01T23:59:59.000Z

360

Double-shell tank waste pretreatment  

SciTech Connect

Double-shell tanks contain most of the transuranic/high-level chemical processing waste generated at the Hanford Site in recent years. A small mass fraction of this waste is responsible for its characterization as transuranic/high-level waste. Pretreatment will partition the waste into a small fraction containing most of the transuranic/high-level components and a large fraction that is a low-level waste. The operations for achieving this objective include dissolution of water-soluble salts, dissolution of precipitated metal oxides in acid, clarification of the resulting dissolver liquors, transuranium element removal by solvent extraction and cesium removal by ion exchange. The primary benefit of pretreatment is a reduction in the overall cost of waste disposal.

Orme, R.M.; Appel, J.N.

1990-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "reduce shell package" 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

Double Shell Tank (DST) Utilities Specification  

SciTech Connect

This specification establishes the performance requirements and provides the references to the requisite codes and standards to he applied during the design of the Double-Shell Tank (DST) Utilities Subsystems that support the first phase of waste feed delivery (WFD). The DST Utilities Subsystems provide electrical power, raw/potable water, and service/instrument air to the equipment and structures used to transfer low-activity waste (LAW) and high-level waste (HLW) to designated DST staging tanks. The DST Utilities Subsystems also support the equipment and structures used to deliver blended LAW and HLW feed from these staging tanks to the River Protection Project (RPP) Privatization Contractor facility where the waste will be immobilized. This specification is intended to be the basis for new projects/installations. This specification is not intended to retroactively affect previously established project design criteria without specific direction by the program.

SUSIENE, W.T.

2000-04-27T23:59:59.000Z

362

U-157: Ruby Mail Gem Directory Traversal and Shell Command Injection...  

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

57: Ruby Mail Gem Directory Traversal and Shell Command Injection Vulnerabilities U-157: Ruby Mail Gem Directory Traversal and Shell Command Injection Vulnerabilities April 27,...

363

OVERVIEW OF ENHANCED HANFORD SINGLE-SHELL TANK (SST) INTEGRITY PROJECT - 12128  

SciTech Connect

To improve the understanding of the single-shell tanks integrity, Washington River Protection Solutions, LLC, the USDOE Hanford Site tank contractor, developed an enhanced Single-Shell Tank (SST) Integrity Project in 2009. An expert panel on SST integrity, consisting of various subject matters experts in industry and academia, was created to provide recommendations supporting the development of the project. This panel developed 33 recommendations in four main areas of interest: structural integrity, liner degradation, leak integrity and prevention, and mitigation of contamination migration, Seventeen of these recommendations were used to develop the basis for the M-45-10-1 Change Package for the Hanford Federal Agreement and Compliance Order, which is also known as the Tri-Party Agreement. The change package identified two phases of work for SST integrity. The initial phase has been focused on efforts to envelope the integrity of the tanks. The initial phase was divided into two primary areas of investigation: structural integrity and leak integrity. If necessary based on the outcome from the initial work, a second phase would be focused on further definition of the integrity of the concrete and liners. Combined these two phases are designed to support the formal integrity assessment of the Hanford SSTs in 2018 by Independent Qualified Registered Engineer. The work to further define the DOE's understanding of the structural integrity SSTs involves preparing a modern Analysis of Record using a finite element analysis program. Structural analyses of the SSTs have been conducted since 1957, but these analyses used analog calculation, less rigorous models, or focused on individual structures. As such, an integrated understanding of all of the SSTs has not been developed to modern expectations. In support of this effort, other milestones will address the visual inspection of the tank concrete and the collection of concrete core samples from the tanks for analysis of current mechanics properties. The work on the liner leak integrity has examined the leaks from 23 tanks with liner failures. Individual leak assessments are being developed for each tank to identify the leak cause and location. Also a common cause study is being performed to take the data from individual tanks to look for trends in the failure. Supporting this work is an assessment of the leak rate from tanks at both Hanford and the Savannah River Site and a new method to locate leak sites in tank liner using ionic conductivity. A separate activity is being conducted to examine the propensity for corrosion in select single shell tanks with aggressive waste layers. The work for these two main efforts will provide the basis for the phase two planning. If the margins identified aren't sufficient to ensure the integrity through the life of the mission, phase two would focus on activities to further enhance the understanding of tank integrity. Also coincident with any phase-two work would be the integrity analysis for the tanks, which would be complete in 2018. With delays in the completion of waste treatment facilities at Hanford, greater reliance on safe, continued storage of waste in the single shell tanks is increased in importance. The goal of integrity assessment would provide basis to continue SST activities till the end of the treatment mission.

VENETZ TJ; BOOMER KD; WASHENFELDER DJ; JOHNSON JB

2012-01-25T23:59:59.000Z

364

Preparation of activated carbons from macadamia nut shell and coconut shell by air activation  

Science Conference Proceedings (OSTI)

A novel, three-step process for the production of high-quality activated carbons from macadamia nut shell and coconut shell charcoals is described. In this process the charcoal is (1) heated to a high temperature (carbonized), (2) oxidized in air following a stepwise heating program from low (ca. 450 K) to high (ca. 660 K) temperatures (oxygenated), and (3) heated again in an inert environment to a high temperature (activated). By use of this procedure, activated carbons with surface areas greater than 1,000 m{sub 2}/g are manufactured with an overall yield of 15% (based on the dry shell feed). Removal of carbon mass by the development of mesopores and macropores is largely responsible for increases in the surface area of the carbons above 600 m{sub 2}/g. Thus, the surface area per gram of activated carbon can be represented by an inverse function of the yield for burnoffs between 15 and 60%. These findings are supported by mass-transfer calculations and pore-size distribution measurements. A kinetic model for gasification of carbon by oxygen, which provides for an Eley-Rideal type reaction of a surface oxide with oxygen in air, fits the measured gasification rates reasonably well over the temperature range of 550--660 K.

Tam, M.S.; Antal, M.J. Jr.

1999-11-01T23:59:59.000Z

365

Directory of Certificates of Compliance for radioactive materials packages: Report of NRC approved packages. Volume 1, Revision 18  

SciTech Connect

The purpose of this directory is to make available a convenient source of information on packagings which have been approved by the US Nuclear Regulatory Commission. To assist in identifying packaging, an index by Model Number and corresponding Certificate of Compliance Number is included at the front of Volumes 1 and 2. An alphabetical listing by user name is included in the back of Volume 3 of approved QA programs. The reports include a listing of all users of each package design and approved QA programs prior to the publication date.

NONE

1995-10-01T23:59:59.000Z

366

High Level Waste Feed Certification in Hanford Double Shell Tanks  

SciTech Connect

The ability to effectively mix, sample, certify, and deliver consistent batches of High Level Waste (HLW) feed from the Hanford Double Shell Tanks (DST) to the Waste Treatment and Immobilization Plant (WTP) presents a significant mission risk with potential to impact mission length and the quantity of HLW glass produced. DOE’s River Protection Project (RPP) mission modeling and WTP facility modeling assume that individual 3785 cubic meter (1 million gallon) HLW feed tanks are homogenously mixed, representatively sampled, and consistently delivered to the WTP. It has been demonstrated that homogenous mixing of HLW sludge in Hanford DSTs is not likely achievable with the baseline design thereby causing representative sampling and consistent feed delivery to be more difficult. Inconsistent feed to the WTP could cause additional batch to batch operational adjustments that reduces operating efficiency and has the potential to increase the overall mission length. The Hanford mixing and sampling demonstration program will identify DST mixing performance capability, will evaluate representative sampling techniques, and will estimate feed batch consistency. An evaluation of demonstration program results will identify potential mission improvement considerations that will help ensure successful mission completion. This paper will discuss the history, progress, and future activities that will define and mitigate the mission risk.

Thien, Micheal G.; Wells, Beric E.; Adamson, Duane J.

2010-03-01T23:59:59.000Z

367

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)...

368

Office of Packaging and Transportation Fiscal Year 2012 Annual Report |  

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

Packaging and Transportation Fiscal Year 2012 Annual Packaging and Transportation Fiscal Year 2012 Annual Report Office of Packaging and Transportation Fiscal Year 2012 Annual Report The Office of Environmental Management (EM) was established to mitigate the risks and hazards posed by the legacy of nuclear weapons production and research. The most ambitious and far ranging of these missions is dealing with the environmental legacy of the Cold War. Many problems posed by its operations are unique, and include the transportation of unprecedented amounts of contaminated waste, water, and soil, and a vast number of contaminated structures during remediation of the contaminated sites. Since Fiscal Year (FY) 2004, EM has completed over 150,000 shipments of radioactive material and waste. The mission of the Department of Energy (DOE) Office of Packaging and

369

LAC Regional Platform Workshop Participant Package | Open Energy  

Open Energy Info (EERE)

Participant Package Participant Package Jump to: navigation, search LEDSGP Logo.png Advancing climate-resilient low emission development around the world Home About Tools Expert Assistance Events Publications Join Us LAC Workshop Announcement Agenda Participant Package Accommodations Location & Transportation Insurance & Visas Participants Presentations Outcomes Report Links Contact Us General Information (Español) Participant Package.pdf Powered by OpenEI ledsgp.org is built on the same platform as the popular Wikipedia site. Like Wikipedia, it is a "wiki" or website developed collaboratively by a community of users. Thanks to our unique relationship with OpenEI.org, you can add or edit most content on ledsgp.org. For more information about this unique collaboration, contact us. View or edit this page on OpenEI.org.

370

Wien Automatic System Planning (WASP) Package | Open Energy Information  

Open Energy Info (EERE)

Wien Automatic System Planning (WASP) Package Wien Automatic System Planning (WASP) Package Jump to: navigation, search Tool Summary LAUNCH TOOL Name: Wien Automatic System Planning (WASP) Package Agency/Company /Organization: International Atomic Energy Agency Sector: Energy Focus Area: Renewable Energy, Energy Efficiency Topics: Pathways analysis Resource Type: Software/modeling tools Website: www-pub.iaea.org/MTCD/publications/PDF/CMS-16.pdf Cost: Free References: WASP[1] "The WASP-IV code permits finding the optimal expansion plan for a power generating system over a period of up to thirty years, within constraints given by the planner." References ↑ "WASP" Retrieved from "http://en.openei.org/w/index.php?title=Wien_Automatic_System_Planning_(WASP)_Package&oldid=403685

371

Data Domain to Model Domain Conversion Package | Argonne National  

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

Data Domain to Model Domain Conversion Package Data Domain to Model Domain Conversion Package Data Domain to Model Domain Conversion Package The Data Domain to Model Domain Conversion Package project will develop methods and implement a novel approach for generating data ensembles by using the latest available statistical modeling tools and knowledge of relevant physical and chemical process to develop climatologically aware methods for processing ACRF and other spatially sparse data sets. Data collected at the Atmospheric Radiation Measurement Program Climate Research Facility (ACRF) sites are employed mainly in column radiation models, to validate the models and develop new parameterizations. Currently, no single methodology can be used with data collected at the spatial scale of the ACRF sites or from specific AmeriFlux locations, to

372

Heart Rate Variability Analysis Using Threshold of Wavelet Package Coefficients  

E-Print Network (OSTI)

In this paper, a new efficient feature extraction method based on the adaptive threshold of wavelet package coefficients is presented. This paper especially deals with the assessment of autonomic nervous system using the background variation of the signal Heart Rate Variability HRV extracted from the wavelet package coefficients. The application of a wavelet package transform allows us to obtain a time-frequency representation of the signal, which provides better insight in the frequency distribution of the signal with time. A 6 level decomposition of HRV was achieved with db4 as mother wavelet, and the above two bands LF and HF were combined in 12 specialized frequencies sub-bands obtained in wavelet package transform. Features extracted from these coefficients can efficiently represent the characteristics of the original signal. ANOVA statistical test is used for the evaluation of proposed algorithm.

Kheder, G; Massoued, M Ben; Samet, M

2009-01-01T23:59:59.000Z

373

Multilayered Microelectronic Device Package With An Integral Window  

DOE Patents (OSTI)

A microelectronic package with an integral window mounted in a recessed lip for housing a microelectronic device. The device can be a semiconductor chip, a CCD chip, a CMOS chip, a VCSEL chip, a laser diode, a MEMS device, or a IMEMS device. The package can be formed of a low temperature co-fired ceramic (LTCC) or high temperature cofired ceramic (HTCC) multilayered material, with the integral window being simultaneously joined (e.g. co-fired) to the package body during LTCC or HTCC processing. The microelectronic device can be flip-chip bonded and oriented so that a light-sensitive side is optically accessible through the window. The result is a compact, low profile package, having an integral window mounted in a recessed lip, that can be hermetically sealed.

Peterson, Kenneth A. (Albuquerque, NM); Watson, Robert D. (Tijeras, NM)

2004-10-26T23:59:59.000Z

374

Sealed symmetric multilayered microelectronic device package with integral windows  

DOE Patents (OSTI)

A sealed symmetric multilayered package with integral windows for housing one or more microelectronic devices. The devices can be a semiconductor chip, a CCD chip, a CMOS chip, a VCSEL chip, a laser diode, a MEMS device, or a IMEMS device. The multilayered package can be formed of a low-temperature cofired ceramic (LTCC) or high-temperature cofired ceramic (HTCC) multilayer processes with the windows being simultaneously joined (e.g. cofired) to the package body during LTCC or HTCC processing. The microelectronic devices can be flip-chip bonded and oriented so that the light-sensitive sides are optically accessible through the windows. The result is a compact, low-profile, sealed symmetric package, having integral windows that can be hermetically-sealed.

Peterson, Kenneth A. (Albuquerque, NM); Watson, Robert D. (Tijeras, NM)

2002-01-01T23:59:59.000Z

375

POWER MODULE PACKAGING WITH DOUBLE SIDED PLANAR INTERCONNECTION ...  

A double sided cooled power module package having a single phase leg topology includes two IGBT and two diode semiconductor dies. Each IGBT die is spaced apart from a ...

376

Building Tcl/Tk 8.2 + misc packages  

Science Conference Proceedings (OSTI)

... Building Tcl/Tk 8.2.3 + BLT, BWidget, Tix and dp packages for LINUX. This page contains ... tcl. 2. Build and Install Tcl/Tk. Note there ...

377

Operational guidance for using DOT-6M/2R packaging  

SciTech Connect

The purpose of this paper is to describe a new US Department of Energy (DOE), Transportation Management Division task to create a US Department of Transportation (DOT) Specification 6M/2R packaging configuration user`s guide. The need for a user`s guide was identified because the DOT-6M/2R packaging configuration is widely used by DOE site contractors, and DOE receives many questions about the approved packaging configurations. Currently, two DOE organizations have the authority to approve new DOT-6M/2R configurations. For Defense Programs, the Transportation and Packaging Safety Division (EH-332) administers the program. For Environmental Restoration and Waste Management, the Transportation Management Division (EM-261) administers the program.

Kelly, D.L.; Hummer, J.H.

1994-03-01T23:59:59.000Z

378

Energy Management Systems Package for Small Commercial Buildings  

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

EnMS (energy management systems) Package for Small Commercial Buildings Jessica Granderson Lawrence Berkeley National Laboratory JGranderson@lbl.gov 510.486.6792 April 4, 2013 2 |...

379

Design package for programmable controller and hydronic subsystem  

DOE Green Energy (OSTI)

This report contains information used in the evaluation of design of Sunkeeper Control's electronic controllers and hydronic packages. Some of the information includes system performance specification, design data brochure, drawings, and qualification and acceptance test procedures.

Not Available

1979-03-01T23:59:59.000Z

380

LONG TERM AGING AND SURVEILLANCE OF 9975 PACKAGE COMPONENTS  

Science Conference Proceedings (OSTI)

The mission of the 9975 package, originally designed only for transportation of radioactive materials, has been broadened to include storage at the Savannah River Site. Two components of this package, namely the containment vessel O-rings and fiberboard overpack, require continued integrity assessment under the storage conditions. The performance of the components over time is being evaluated using accelerated-aging studies. Compression stress relaxation (CSR) and leak testing are being used to measure the performance of O-rings. The performance of the fiberboard is being evaluated using compression strength, thermal conductivity, specific heat capacity and other physical properties. Models developed from the data collected provide an initial prediction of service life for the two components, and support the conclusion that normal service conditions will not degrade the performance of the package beyond specified functional requirements for the first assessment interval. Increased confidence in this conclusion is derived from field surveillance data and destructive evaluation of packages removed from storage.

Hoffman, E.; Skidmore, E.; Daugherty, W.; Dunn, K.

2009-11-10T23:59:59.000Z

Note: This page contains sample records for the topic "reduce shell package" 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

CORROSION OF LEAD SHIELDING IN NUCLEAR MATERIALS PACKAGES  

SciTech Connect

Inspection of United States-Department of Energy (US-DOE) model 9975 nuclear materials shipping package revealed corrosion of the lead shielding that was induced by off-gas constituents from organic components in the package. Experiments were performed to determine the corrosion rate of lead when exposed to off-gas or degradation products of these organic materials. The results showed that the room temperature vulcanizing (RTV) sealant was the most corrosive organic species used in the construction of the packaging, followed by polyvinyl acetate (PVAc) glue. Fiberboard material, also used in the construction of the packaging induced corrosion to a much lesser extent than the PVAc glue and RTV sealant, and only in the presence of condensed water. The results indicated faster corrosion at temperatures higher than ambient and with condensed water. In light of these corrosion mechanisms, the lead shielding was sheathed in a stainless steel liner to mitigate against corrosion.

Subramanian, K; Kerry Dunn, K; Joseph Murphy, J

2008-07-18T23:59:59.000Z

382

Adaptable Sensor Packaging for High Temperature Fossil Fuel Energy System  

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

Adaptable Sensor Packaging for High Adaptable Sensor Packaging for High Temperature Fossil Fuel Energy Systems Background The Advanced Research Sensors and Controls Program is leading the effort to develop sensing and control technologies and methods to achieve automated and optimized intelligent power systems. The program is led by the U.S. Department of Energy (DOE) Office of Fossil Energy National Energy Technology Laboratory (NETL) and is implemented through research and development agreements with other

383

Safety analysis report for packaging (onsite) sample pig transport system  

Science Conference Proceedings (OSTI)

This Safety Analysis Report for Packaging (SARP) provides a technical evaluation of the Sample Pig Transport System as compared to the requirements of the U.S. Department of Energy, Richland Operations Office (RL) Order 5480.1, Change 1, Chapter III. The evaluation concludes that the package is acceptable for the onsite transport of Type B, fissile excepted radioactive materials when used in accordance with this document.

MCCOY, J.C.

1999-03-16T23:59:59.000Z

384

Nuclear criticality safety evaluation of SRS 9971 shipping package  

SciTech Connect

This evaluation is requested to revise the criticality evaluation used to generate Chapter 6 (Criticality Evaluation) of the Safety Analysis Report for Packaging (SARP) for shipment Of UO{sub 3} product from the Uranium Solidification Facility (USF) in the SRS 9971 shipping package. The pertinent document requesting this evaluation is included as Attachment I. The results of the evaluation are given in Attachment II which is written as Chapter 6 of a NRC format SARP.

Vescovi, P.J.

1993-02-01T23:59:59.000Z

385

Nuclear Maintenance Applications Center: Maintenance Work Package Planning Guidance  

Science Conference Proceedings (OSTI)

The work management process is one of the core business processes outlined within the Nuclear Energy Institute (NEI) Standard Nuclear Performance Model for operation and maintenance of nuclear power plants. The preparation of work packages is a key element of this overall process. The purpose of this report is to provide guidance to power plant personnel regarding work package quality as a supplement to Institute of Nuclear Power Operations (INPO) AP-928, Work Management Process Description. The ...

2013-09-10T23:59:59.000Z

386

River Data Package for the 2004 Composite Analysis  

Science Conference Proceedings (OSTI)

Beginning in fiscal year 2003, the DOE Richland Operations Office initiated activities, including the development of data packages, to support the 2004 Composite Analysis. The river data package provides calculations of flow and transport in the Columbia River system. This document presents the data assembled to run the river module components for the section of the Columbia River from Vernita Bridge to the confluence with the Yakima River.

Rakowski, Cynthia L.; Guensch, Gregory R.; Patton, Gregory W.

2004-08-01T23:59:59.000Z

387

Final system instrumentation design package for decade 80 solar house  

DOE Green Energy (OSTI)

This system instrumentation design package reflects the final configuration of the Decade 80 solar house to monitor and collect system performance data. The system instrumentation acceptance review was held on June 14, 1977. This review demonstrated by actual operation that the system and the data acquisition subsystem operated satisfactorily and installation of instrumentation was in accordance with the design. This design package is made up of: site and system description, operating and control modes, and instrumentation program (including sensor schematic).

Not Available

1978-12-01T23:59:59.000Z

388

Spent fuel handling and packaging program. Management summary report  

SciTech Connect

Objective is to design, develop, and demonstrate a spent fuel package for geologic storage and disposal; to design, license, and construct the facilities to produce this package; and to develop and demonstrate technology for the dry, passive surface storage of spent fuel. Progress is reported on engineering and system studies, technical R and D studies, demonstrations, project support studies, spent fuel facility project, and program management.

1978-09-01T23:59:59.000Z

389

Precision Manufacturing of Inertial Confinement Fusion Double Shell Laser Targets for OMEGA  

SciTech Connect

Double shell targets have been built by Lawrence Livermore National Laboratory (LLNL) for inertial confinement fusion (ICF) experiments on the Omega laser at the University of Rochester and as a prelude to similar experiments on NIF. Of particular interest to ICF studies are high-precision double shell implosion targets for demonstrating thermonuclear ignition without the need for cryogenic preparation. Because the ignition tolerance to interface instabilities is rather low, the manufacturing requirements for smooth surface finishes and shell concentricity are particularly strict. This paper describes a deterministic approach to manufacturing and controlling error sources in each component. Included is the design philosophy of why certain manufacturing techniques were chosen to best reduce the errors within the target. The manufacturing plan developed for this effort created a deterministic process that, once proven, is repeatable. By taking this rigorous approach to controlling all error sources during the manufacture of each component and during assembly, we have achieved the overall 5 {micro}m dimensional requirement with sub-micron surface flaws. Strengths and weaknesses of the manufacturing process will be discussed.

Amendt, P A; Bono, M J; Hibbard, R L; Castro, C; Bennett, D W

2003-11-21T23:59:59.000Z

390

1/12-Scale scoping experiments to characterize double-shell tank slurry uniformity: Test plan  

SciTech Connect

Million gallon double-shell tanks (DSTs) at Hanford are used to store transuranic, high-level, and low-level wastes. These wastes generally consist of a large volume of salt-laden solution covering a smaller volume of settled sludge primarily containing metal hydroxides. These wastes will be retrieved and processed into immobile waste forms suitable for permanent disposal. The current retrieval concept is to use submerged dual-nozzle pumps to mobilize the settled solids by creating jets of fluid that are directed at the tank solids. The pumps oscillate, creating arcs of high-velocity fluid jets that sweep the floor of the tank. After the solids are mobilized, the pumps will continue to operate at a reduced flow rate sufficient to maintain the particles in a uniform suspension. The objectives of these 1/12-scale scoping experiments are to determine how Reynolds number, Froude number, and gravitational settling parameter affect the degree of uniformity achieved during jet mixer pump operation in the full-scale double-shell tanks; develop linear models to predict the degree of uniformity achieved by jet mixer pumps operating in the full-scale double-shell tanks; apply linear models to predict the degree of uniformity that will be achieved in tank 241-AZ-101 and determine whether contents of that tank will be uniform to within {+-} 10% of the mean concentration; and obtain experimental concentration and jet velocity data to compared with the TEMPEST computational and modeling predictions to guide further code development.

Bamberger, J.A.; Liljegren, L.M.

1994-10-01T23:59:59.000Z

391

Building America Top Innovations Hall of Fame Profile Â… Advanced Framing Systems and Packages  

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

studies involving studies involving thousands of homes have documented significant material, labor, and energy savings when production builders implement advanced framing techniques. Advanced framing can reduce the number of studs in the walls by up to one-third, reducing the cost of materials. and reducing the cost of labor in terms of the time it takes to handle, cut, install, drill, and attach to studs. Actual savings have exceeded $1,000 per home. Studies show the resulting improvement in thermal performance can yield 13% energy savings. BUILDING AMERICA TOP INNOVATIONS HALL OF FAME PROFILE INNOVATIONS CATEGORY: 1. Advanced Technologies and Practices 1.1 Building Science Solutions Advanced Framing Systems and Packages Building America has developed best practices for advanced framing

392

Parity Dependent Shell Model Level Densities for Nuclear Astrophysics  

E-Print Network (OSTI)

Recently, we developed a methodology [1-4] of calculating the spin and parity dependent shell model nuclear level density, which is a very useful ingredient in the Huaser-Feshbach theory for calculating reaction rates for nuclear astrophysics[5]. We developed new techniques based on nuclear statistical spectroscopy [6] to calculate the spin and parity projected moments of the nuclear shell model Hamiltonian, that can be further used to obtain an accurate description of the nuclear level density up to about 15 MeV excitation energy. These techniques were fully tested for the sd-shell nuclei and some light f p-shell nuclei, by comparing with the level density obtained from exact shell model diagonalization. Here we present for the first time comparisons with the exact shell model diagonalization for nuclei heavier than 56 Ni, in a model space spanned by the f 5/2, p 3/2, p 1/2 and g 9/2 orbits. The ratio of nuclear level densities of opposite parities is also discussed. This analysis was possible due to a new and very efficient nuclear shell model code [7] that can provide a large number of states of given spin and parity. PoS(NIC X)132

Mike Scott; Mihai Horoi; Mike Scott

2008-01-01T23:59:59.000Z

393

Local Casimir energies for a thin spherical shell  

SciTech Connect

The local Casimir energy density for a massless scalar field associated with step-function potentials in a 3+1 dimensional spherical geometry is considered. The potential is chosen to be zero except in a shell of thickness {delta}, where it has height h, with the constraint h{delta}=1. In the limit of zero thickness, an ideal {delta}-function shell is recovered. In this limit, the behavior of the energy density as the surface of the shell is approached is studied in both the strong and weak coupling regimes. The former case corresponds to the well-known Dirichlet shell limit. New results, which shed light on the nature of surface divergences and on the energy contained within the shell, are obtained in the weak coupling limit, and for a shell of finite thickness. In the case of zero thickness, the energy has a contribution not only from the local energy density, but from an energy term residing entirely on the surface. It is shown that the latter coincides with the integrated local energy density within the shell. We also study the dependence of local and global quantities on the conformal parameter. In particular new insight is provided on the reason for the divergence in the global Casimir energy in third order in the coupling.

Cavero-Pelaez, Ines; Milton, Kimball A.; Wagner, Jeffrey [Homer L. Dodge Department of Physics and Astronomy, University of Oklahoma, Norman, Oklahoma 73019-2061 (United States)

2006-04-15T23:59:59.000Z

394

Packaging design criteria modified fuel spacer burial box. Revision 1  

Science Conference Proceedings (OSTI)

Various Hanford facilities must transfer large radioactively contaminated items to burial/storage. Presently, there are eighteen Fuel Spacer Burial Boxes (FSBBs) available on the Hanford Site for transport of such items. Previously, the FSBBS were transported from a rail car to the burial trench via a drag-off operation. To allow for the lifting of the boxes into the burial trench, it will be necessary to improve the packagings lifting attachments and provide structural reinforcement. Additional safety improvements to the packaging system will be provided by the addition of a positive closure system and package ventilation. FSBBs that are modified in such a manner are referred to as Modified Fuel Spacer Burial Boxes (MFSBs). The criteria provided by this PDC will be used to demonstrate that the transfer of the MFSB will provide an equivalent degree of safety as would be provided by a package meeting offsite transportation requirements. This fulfills the onsite transportation safety requirements implemented in WHC-CM-2-14, Hazardous Material Packaging and Shipping. A Safety Analysis Report for Packaging (SARP) will be prepared to evaluate the safety of the transfer operation. Approval of the SARP is required to authorize transfer. Criteria are also established to ensure burial requirements are met.

Stevens, P.F.

1994-09-13T23:59:59.000Z

395

Directory of certificates of compliance for radioactive materials packages. Revision 16, Volume 3  

SciTech Connect

This directory provides information on packagings approved by the U.S. Nuclear Regulatory Commission.

NONE

1996-10-01T23:59:59.000Z

396

An optimum approach for fabrication of tapered hemispherical-end fiber for laser module packaging  

Science Conference Proceedings (OSTI)

Keywords: coupling efficientcy, laser module packaging, semiempirical model, tapered hemispherical-end fiber

H. M. Yang; D. C. Jou; M. H. Chen; S. H. Wu; W. H. Cheng

2001-03-01T23:59:59.000Z

397

Thermal Performance and Reliability of Bonded Interfaces for Power Electronics Packaging Applications (Presentation)  

SciTech Connect

This presentation discusses the thermal performance and reliability of bonded interfaces for power electronics packaging applications.

Devoto, D.

2013-07-01T23:59:59.000Z

398

DOE G 430.1-1 Chp 2, Cost Estimation Package  

Directives, Delegations, and Requirements

This chapter focuses on the components (or elements) of the cost estimation package and their documentation.

1997-03-28T23:59:59.000Z

399

Letter to the editor/Shell treats LPG  

SciTech Connect

In response to an article on the MALAPROP process Shell International Petroleum Mij. B.V. notes that Shell's Adip process has gained a solid position world-wide in economically treating very large amounts of LPG for the removal of hydrogen sulfide and carbonyl sulfide. Most Shell refineries are equipped with the Adip process, which cumulatively treates approx. 7000 tons/day of LPG. Middle East LPG facilities designed for the Arabian American Oil Co. treat 30,000 tons/day, and an additional 16,000 will come on stream in Jan. 1983. The removal of carbonyl sulfide to a few parts-per-million is easy.

1979-10-01T23:59:59.000Z

400

Doc.384, 'Lali drums/gongs and davui shell trumpets'  

E-Print Network (OSTI)

lali drums/gongs and davui shell trumpets Translation of title Description (to be used in archive entry) Lali drum/gong beats and davui triton-shell trumpets, recorded at Serua Island in July 1957. 12 min 42 seconds. 1) Lali ni soqo ni vaka turaga... Fijian Musical instruments and / or other objects used in performance Lali drums/gongs, davui shell trumpets Level of public access (fully closed, fully open) Fully open last updated on Monday, 4 April 2011 Notes and context (include reference...

Roth, George Kingsley

Note: This page contains sample records for the topic "reduce shell package" 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

Energy transfers in shell models for MHD turbulence  

E-Print Network (OSTI)

A systematic procedure to derive shell models for MHD turbulence is proposed. It takes into account the conservation of ideal quadratic invariants such as the total energy, the cross-helicity and the magnetic helicity as well as the conservation of the magnetic energy by the advection term in the induction equation. This approach also leads to simple expressions for the energy exchanges as well as to unambiguous definitions for the energy fluxes. When applied to the existing shell models with nonlinear interactions limited to the nearest neighbour shells, this procedure reproduces well known models but suggests a reinterpretation of the energy fluxes.

T. Lessinnes; M. K. Verma; D. Carati

2008-07-31T23:59:59.000Z

402

Photoionization of hydrogenlike ions surrounded by a charged spherical shell  

Science Conference Proceedings (OSTI)

Within the framework of a model of a hollow atom as a hydrogenlike multicharged ion located at the center of a spherical shell formed by highly excited electrons, the photoionization cross sections of the inner 1s level of the ion have been calculated. The results show that the existence of the outer electronic shell of the hollow atom results in oscillations in the energy dependence of the photoionization cross section. It has been demonstrated also that the photoionization cross section as a function of photon energy is extremely sensitive to the magnitude of the discontinuity of the electric field at the surface of the outer electronic shell.

Baltenkov, A. S. [Arifov Institute of Electronics, 100125, Tashkent (Uzbekistan); Manson, S. T. [Department of Physics and Astronomy, Georgia State University, Atlanta, Georgia 30303 (United States); Msezane, A. Z. [Center for Theoretical Studies of Physical Systems, Clark Atlanta University, Atlanta, Georgia 30314 (United States)

2007-10-15T23:59:59.000Z

403

Thin-shell wormholes from regular charged black holes  

E-Print Network (OSTI)

We investigate a new thin-shell wormhole constructed by surgically grafting two regular charged black holes arising from the action using nonlinear electrodynamics coupled to general relativity. The stress-energy components within the shell violate the null and weak energy conditions but obey the strong energy condition. We study the stability in two ways: (i) taking a specific equation of state at the throat and (ii) analyzing the stability to linearized spherically symmetric perturbations about a static equilibrium solution. Various other aspects of this thin-shell wormhole are also analyzed.

F. Rahaman; K A Rahman; Sk. A Rakib; Peter K. F. Kuhfittig

2009-09-06T23:59:59.000Z

404

Low-cost flexible packaging for high-power Li-Ion HEV batteries.  

DOE Green Energy (OSTI)

Batteries with various types of chemistries are typically sold in rigid hermetically sealed containers that, at the simplest level, must contain the electrolyte while keeping out the exterior atmosphere. However, such rigid containers can have limitations in packaging situations where the form of the battery is important, such as in hand-held electronics like personal digital assistants (PDAs), laptops, and cell phones. Other limitations exist as well. At least one of the electrode leads must be insulated from the metal can, which necessitates the inclusion of an insulated metal feed-through in the containment hardware. Another limitation may be in hardware and assembly cost, such as exists for the lithium-ion batteries that are being developed for use in electric vehicles (EVs) and hybrid electric vehicles (HEVs). The large size (typically 10-100 Ah) of these batteries usually results in electric beam or laser welding of the metal cap to the metal can. The non-aqueous electrolyte used in these batteries are usually based on flammable solvents and therefore require the incorporation of a safety rupture vent to relieve pressure in the event of overcharging or overheating. Both of these features add cost to the battery. Flexible packaging provides an alternative to the rigid container. A common example of this is the multi-layered laminates used in the food packaging industry, such as for vacuum-sealed coffee bags. However, flexible packaging for batteries does not come without concerns. One of the main concerns is the slow egress of the electrolyte solvent through the face of the inner laminate layer and at the sealant edge. Also, moisture and air could enter from the outside via the same method. These exchanges may be acceptable for brief periods of time, but for the long lifetimes required for batteries in electric/hybrid electric vehicles, batteries in remote locations, and those in satellites, these exchanges are unacceptable. Argonne National Laboratory (ANL), in collaboration with several industrial partners, is working on low-cost flexible packaging as an alternative to the packaging currently being used for lithium-ion batteries [1,2]. This program is funded by the FreedomCAR & Vehicle Technologies Office of the U.S. Department of Energy. (It was originally funded under the Partnership for a New Generation of Vehicles, or PNGV, Program, which had as one of its mandates to develop a power-assist hybrid electric vehicle with triple the fuel economy of a typical sedan.) The goal in this packaging effort is to reduce the cost associated with the packaging of each cell several-fold to less than $1 per cell ({approx} 50 cells are required per battery, 1 battery per vehicle), while maintaining the integrity of the cell contents for a 15-year lifetime. Even though the battery chemistry of main interest is the lithium-ion system, the methodology used to develop the most appropriate laminate structure will be very similar for other battery chemistries.

Jansen, A. N.; Amine, K.; Henriksen, G. L.

2004-06-18T23:59:59.000Z

405

Surveillance Guides - PTS 13.2 Packaging and Preparation for Shipment  

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

PACKAGING AND PREPARATION FOR SHIPMENT PACKAGING AND PREPARATION FOR SHIPMENT 1.0 Objective The objective of this surveillance is to evaluate the effectiveness of the contractor's programs for packaging radioactive and hazardous wastes for shipment. The Facility Representative examines packages ready for shipment, observes preparation of packages, and reviews documents that establish the acceptability of packages. The Facility Representative verifies compliance with DOE requirements including requirements established by the Department of Transportation and the U.S. Nuclear Regulatory Commission. 2.0 References 2.1 DOE 5480.3, Safety Requirements for the Packaging and Transportation of Hazardous Materials, Hazardous Substances, and Hazardous Wastes

406

Ab Initio No-Core Shell Model  

SciTech Connect

A long-standing goal of nuclear theory is to determine the properties of atomic nuclei based on the fundamental interactions among the protons and neutrons (i.e., nucleons). By adopting nucleon-nucleon (NN), three-nucleon (NNN) and higher-nucleon interactions determined from either meson-exchange theory or QCD, with couplings fixed by few-body systems, we preserve the predictive power of nuclear theory. This foundation enables tests of nature's fundamental symmetries and offers new vistas for the full range of complex nuclear phenomena. Basic questions that drive our quest for a microscopic predictive theory of nuclear phenomena include: (1) What controls nuclear saturation; (2) How the nuclear shell model emerges from the underlying theory; (3) What are the properties of nuclei with extreme neutron/proton ratios; (4) Can we predict useful cross sections that cannot be measured; (5) Can nuclei provide precision tests of the fundamental laws of nature; and (6) Under what conditions do we need QCD to describe nuclear structure, among others. Along with other ab initio nuclear theory groups, we have pursued these questions with meson-theoretical NN interactions, such as CD-Bonn and Argonne V18, that were tuned to provide high-quality descriptions of the NN scattering phase shifts and deuteron properties. We then add meson-theoretic NNN interactions such as the Tucson-Melbourne or Urbana IX interactions. More recently, we have adopted realistic NN and NNN interactions with ties to QCD. Chiral perturbation theory within effective field theory ({chi}EFT) provides us with a promising bridge between QCD and hadronic systems. In this approach one works consistently with systems of increasing nucleon number and makes use of the explicit and spontaneous breaking of chiral symmetry to expand the strong interaction in terms of a dimensionless constant, the ratio of a generic small momentum divided by the chiral symmetry breaking scale taken to be about 1 GeV/c. The resulting NN and NNN interactions, characterized by the order of the expansion retained (e.g. 'next-to-next-to leading order' is NNLO), provide a high-quality fit to the NN data and the A = 3 ground-state (g.s.) properties. The derivations of NN, NNN, etc. interactions within meson-exchange and {chi}EFT are well-established but are not subjects of this review. Our focus is solution of the non-relativistic quantum many-body Hamiltonian that includes these interactions using our no core shell model (NCSM) formalism. In the next section we will briefly outline the NCSM formalism and then present applications, results and extensions in later sections.

Barrett, B R; Navratil, P; Vary, J P

2011-04-11T23:59:59.000Z

407

Design and Criticality Considerations for 9977 and 9978 Shipping Packages  

Science Conference Proceedings (OSTI)

Savannah River National Laboratory (SRNL) has developed two new, Type B, state-of-the-art, general purpose, fissile material Shipping Packages, designated 9977 and 9978, as replacements for the U.S. DOT specification 6M container, phased out in September 30, 2008 due to non-compliance with current requirements 10CFR71 regulation. The packages accommodate plutonium, uranium and other special nuclear materials in bulk quantities and in many forms with capabilities exceeding those of the 6M. These packages provide a high degree of single containment and comply with 10CFR71, Department of Energy (DOE) Order 460.1B, DOE Order 460.2, and 10CFR20 (As Low As Reasonably Achievable (ALARA)). Allowed package contents were determined accounting for nuclear criticality, radiation shielding, and decay heat rate. The Criticality Safety Index (CSI) for the package is 1.0. The package utilizes passive cooling to maintain internal temperatures within limits. Radiation shielding analyses have established the contents for which the packages can be shipped under non-exclusive use in the Safe-Secure Trailer or under exclusive use. The packages are designed to ship radioactive contents in several configurations; Radioisotope Thermoelectric Generators (RTGs), nested food-pack cans, site specific containers, and DOE-STD-3013 containers. Each shipping package includes a 35-gallon stainless steel outer drum, insulation, a drum liner, and a single containment vessel (CV). The 9977 includes a 6-inch ID CV while the 9978 includes a 5-inch ID CV. One inch of Fiberfrax{reg_sign} insulation is wrapped around and attached to the sides and bottom of the liner. The volume between the Fiberfrax{reg_sign} and the drum wall is filled with polyurethane foam. Top and bottom aluminum Load Distribution Fixtures (LDFs) within the drum liner cavity, above and below the CV, center the CV in the liner, stiffen the package radially, and distribute loads away from the CV. The 6CV fits directly into the LDFs while honeycomb spacers position the 5CV in the LDFs.

Reed, R; Biswas, D; Abramczyk, G

2008-11-25T23:59:59.000Z

408

L-Shell Spectroscopy of Au as a Temperature Diagnostic Tool  

SciTech Connect

In order to develop plasma diagnostic for reduced-size hot hohlraums under laser irradiation, they have studied the L-shell emission from highly charged gold ions in the SuperEBIT electron beam ion trap. The resolving power necessary to identify emission features from individual charge states in a picket fence pattern has been estimated, and the observed radiation features have been compared with atomic structure calculations. They find that the strong 3d{sub 5/2} {yields} 2p{sub 3/2} emission features are particularly useful in determining the charge state distribution and average ion charge , which are strongly sensitive to the electron temperature.

Tr?bert, E; Hansen, S B; Beiersdorfer, P; Brown, G V; Widmann, K; Chung, H K

2008-03-27T23:59:59.000Z

409

Energy conditions, traversable wormholes and dust shells  

E-Print Network (OSTI)

Firstly, we review the pointwise and averaged energy conditions, the quantum inequality and the notion of the ``volume integral quantifier'', which provides a measure of the ``total amount'' of energy condition violating matter. Secondly, we present a specific metric of a spherically symmetric traversable wormhole in the presence of a generic cosmological constant, verifying that the null and the averaged null energy conditions are violated, as was to be expected. Thirdly, a pressureless dust shell is constructed around the interior wormhole spacetime by matching the latter geometry to a unique vacuum exterior solution. In order to further minimize the usage of exotic matter, we then find regions where the surface energy density is positive, thereby satisfying all of the energy conditions at the junction surface. An equation governing the behavior of the radial pressure across the junction surface is also deduced. Lastly, taking advantage of the construction, specific dimensions of the wormhole, namely, the throat radius and the junction interface radius, and estimates of the total traversal time and maximum velocity of an observer journeying through the wormhole, are also found by imposing the traversability conditions.

Francisco S. N. Lobo

2004-10-18T23:59:59.000Z

410

On heat capacity of nanoclusters with a shell structure  

Science Conference Proceedings (OSTI)

Pair correlation effects in nanoclusters with a shell structure are analyzed by the exact diagonalization method. The singularity in the behavior of the heat capacity of such clusters is analyzed using the many-particle spectrum of nanoclusters.

Baturin, V. S., E-mail: baturin@lpi.ru; Losyakov, V. V., E-mail: losyakov@lpi.ru [Russian Academy of Sciences, Lebedev Physical Institute (Russian Federation)

2011-02-15T23:59:59.000Z

411

String Gas Shells, their Dual Radiation and Hedgehog Signature Control  

E-Print Network (OSTI)

We search for spherically symmetric, stationary solutions with a string gas shell as a source. The requirement of a uniform newtonian potential, or constancy of the 00 component of the metric, implies the existence of a "dual" radiation, which we argue can be interpreted as representing the virtual quantum fluctuations that stabilize the shell. A string hedgehog can be introduced also into the solution. For zero or small hedgehog strength the string gas shell is of a regular nature, while the dual radiation is of a spacelike nature. For higher hedgehog strengths however the radiation "materializes" and becomes timelike while the string gas shell becomes space like. The significance of these solutions for the quantum theory is discussed.

E. I. Guendelman

2009-03-12T23:59:59.000Z

412

Casimir interactions of an object inside a spherical metal shell  

E-Print Network (OSTI)

We investigate the electromagnetic Casimir interactions of an object contained within an otherwise empty, perfectly conducting spherical shell. For a small object we present analytical calculations of the force, which is ...

Zaheer, Saad

413

Double Shell Tank (DST) Monitor and Control Subsystem Specification  

Science Conference Proceedings (OSTI)

This specification revises the performance requirements and provides references to the requisite codes and standards to be applied during design of the Double-Shell Tank (DST) Monitor and Control Subsystem that supports the first phase of Waste Feed Delivery.

BAFUS, R.R.

2000-11-03T23:59:59.000Z

414

Double Shell Tank (DST) Process Waste Sampling Subsystem Specification  

SciTech Connect

This specification establishes the performance requirements and provides references to the requisite codes and standards to be applied to the Double-Shell Tank (DST) Process Waste Sampling Subsystem which supports the first phase of Waste Feed Delivery.

RASMUSSEN, J.H.

2000-05-03T23:59:59.000Z

415

STATEMENT OF CONSIDERATIONS REQUEST BY SHELL SOLAR INDUSTRIES...  

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

CH-1345 As set out in the attached waiver petition and in subsequent discussions with DOE Patent Counsel, Shell Solar Industries LP (SSI) has requested an advance waiver of...

416

STATEMENT OF CONSIDERATIONS REQUEST BY SHELL SOLAR INDUSTRIES...  

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

As set out in the attached waiver petition and in subsequent discussions with DOE, Shell Solar Industries, LP (SSI) has requested an advance waiver of domestic and foreign patent...

417

Functional Analysis for Double Shell Tank (DST) Subsystems  

Science Conference Proceedings (OSTI)

This functional analysis identifies the hierarchy and describes the subsystem functions that support the Double-Shell Tank (DST) System described in HNF-SD-WM-TRD-007, System Specification for the Double-Shell Tank System. Because of the uncertainty associated with the need for upgrades of the existing catch tanks supporting the Waste Feed Delivery (WFD) mission, catch tank functions are not addressed in this document. The functions identified herein are applicable to the Phase 1 WFD mission only.

SMITH, D.F.

2000-08-22T23:59:59.000Z

418

The Covariant Electromagnetic Casimir Effect for Real Conducting Cylindrical Shells  

E-Print Network (OSTI)

Using covariant quantization of the electromagnetic field, the Casimir force per unit area experienced by a long conducting cylindrical shell, under both Dirichlet and Neumann boundary conditions, is calculated. The renormalization procedure is based on the plasma cut-off frequency for real conductors. The real case of a gold (silver) cylindrical shell is considered and the corresponding electromagnetic Casimir pressure is computed. It is discussed that the Dirichlet and Neumann problems should be considered separately without adding their corresponding results.

H. Razmi; N. Fadaei

2013-07-31T23:59:59.000Z

419

Mineral processing techniques for recycling investment casting shell  

Science Conference Proceedings (OSTI)

The Albany Research Center of the U.S. Department of Energy used materials characterization and minerals beneficiation methods to separate and beneficially modify spent investment-mold components to identify recycling opportunities and minimize environmentally sensitive wastes. The physical and chemical characteristics of the shell materials were determined and used to guide bench-scale research to separate reusable components by mineral-beneficiation techniques. Successfully concentrated shell materials were evaluated for possible use in new markets.

Dahlin, Cheryl L.; Nilsen, David N.; Dahlin, David C.; Hunt, Alton H.; Collins, W. Keith

2002-01-01T23:59:59.000Z

420

FABRICATION OF GAS-FILLED TUNGSTEN-COATED GLASS SHELLS  

SciTech Connect

OAK-B135 Deuterium (D{sub 2}) filled glass shells coated with a high Z element are needed for high energy density (HED) experiments by researchers at Los Alamos National Laboratory. They report here on our initial attempt to produce such shells. Glass shells made using the drop tower technique were coated with gold, palladium or tungsten, or a mixture of two of these elements. It was found that gold and palladium coatings did not stick well to the glass and resulted in poor or delaminated films. Tungsten coatings resulted in films suitable for these targets. Bouncing of shells during coating resulted in uniform tungsten coatings, but the surface of such coatings were filled with small nodules. Proper agitation of shells using a tapping technique resulted in smooth films with minimal particulate contamination. For coating rates of {approx} 0.15 {micro}m/hr coatings with {approx} 2 nm RMS surface finish could be deposited. The surface roughness of coatings at higher rates, 0.7 {micro}m/hr, was considerably worse ({approx} 100 nm RMS). The columnar structure of the coatings allowed permeation filling of the tungsten coated glass shells with deuterium at 300 C.

NIKROO,A; BAUGH,W; STEINMAN,D.A

2003-06-01T23:59:59.000Z

Note: This page contains sample records for the topic "reduce shell package" 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

Materials of Criticality Safety Concern in Waste Packages  

Science Conference Proceedings (OSTI)

10 CFR 71.55 requires in part that the fissile material package remain subcritical when considering 'the most reactive credible configuration consistent with the chemical and physical form of the material'. As waste drums and packages may contain unlimited types of materials, determination of the appropriately bounding moderator and reflector materials to ensure compliance with 71.55 requires a comprehensive analysis. Such an analysis was performed to determine the materials or elements that produce the most reactive configuration with regards to both moderation and reflection of a Pu-239 system. The study was originally performed for the TRUPACT-II shipping package and thus the historical fissile mass limit for the package, 325 g Pu-239, was used [1]. Reactivity calculations were performed with the SCALE package to numerically assess the moderation or reflection merits of the materials [2]. Additional details and results are given in SAIC-1322-001 [3]. The development of payload controls utilizing process knowledge to determine the classification of special moderator and/or reflector materials and the associated fissile mass limit is also addressed. (authors)

Larson, S.L. [Science Applications International Corporation, 301 Laboratory Road, Oak Ridge, TN 37830 (United States); Day, B.A. [Washington TRU Solutions LLC, 4021 National Parks Highway, Carlsbad, NM 88220 (United States)

2006-07-01T23:59:59.000Z

422

Test concept for waste package environment tests at Yucca Mountain  

SciTech Connect

The Nevada Nuclear Waste Storage Investigations Project is characterizing a tuffaceous rock unit at Yucca Mountain, Nevada to evaluate its suitability for a repository for high level radioactive waste. The candidate repository horizon is a welded, devitrified tuff bed located at a depth of about 300 m in the unsaturated zone, over 100 m above the water table. As part of the project, Lawrence Livermore National Laboratory is responsible for designing the waste packages and for assessing their expected performance in the repository environment. The primary region of interest to package design and performance assessment is the portion of the rock mass within a few meters of waste emplacement holes. Hydrologic mechanisms active in this unsaturated near-field environment, along with thermal and mechanical phenomena that influence the hydrology, need to be understood well enough to confirm the basis of the waste package designs and performance assessment. Large scale in situ tests (called waste package environment tests) are being planned in order to develop this understanding and to provide data sets for performance assessment model validation (Yow, 1985). Exploratory shafts and limited underground facilities for in-situ testing will be constructed at Yucca Mountain during site characterization. Multiple waste package environment tests are being planned for these facilities to represent horizontal and vertical waste emplacement configurations in the repository target horizon. These approximately half-scale tests are being designed to investigate rock mass hydrologic conditions during a cycle of thermal loading.

Yow, J.L. Jr.

1987-06-01T23:59:59.000Z

423

Integrated head package cable carrier for a nuclear power plant  

DOE Patents (OSTI)

A cabling arrangement is provided for a nuclear reactor located within a containment. Structure inside the containment is characterized by a wall having a near side surrounding the reactor vessel defining a cavity, an operating deck outside the cavity, a sub-space below the deck and on a far side of the wall spaced from the near side, and an operating area above the deck. The arrangement includes a movable frame supporting a plurality of cables extending through the frame, each connectable at a first end to a head package on the reactor vessel and each having a second end located in the sub-space. The frame is movable, with the cables, between a first position during normal operation of the reactor when the cables are connected to the head package, located outside the sub-space proximate the head package, and a second position during refueling when the cables are disconnected from the head package, located in the sub-space. In a preferred embodiment, the frame straddles the top of the wall in a substantially horizontal orientation in the first position, pivots about an end distal from the head package to a substantially vertically oriented intermediate position, and is guided, while remaining about vertically oriented, along a track in the sub-space to the second position.

Meuschke, Robert E. (Monroeville, PA); Trombola, Daniel M. (Murrysville, PA)

1995-01-01T23:59:59.000Z

424

Harsh-Environment Packaging for Downhole Gas and Oil Exploration  

Science Conference Proceedings (OSTI)

This research into new packaging materials and methods for elevated temperatures and harsh environment electronics focused on gaining a basic understanding of current state-of-the-art in electronics packaging used in industry today, formulating the thermal-mechanical models of the material interactions and developing test structures to confirm these models. Discussions were initiated with the major General Electric (GE) businesses that currently sell into markets requiring high temperature electronics and packaging. They related the major modes of failure they encounter routinely and the hurdles needed to be overcome in order to improve the temperature specifications of these products. We consulted with our GE business partners about the reliability specifications and investigated specifications and guidelines that from IPC and the SAE body that is currently developing guidelines for electronics package reliability. Following this, a risk analysis was conducted for the program to identify the critical risks which need to be mitigated in order to demonstrate a flex-based packaging approach under these conditions. This process identified metal/polyimide adhesion, via reliability for flex substrates and high temperature interconnect as important technical areas for reliability improvement.

Shubhra Bansal; Junghyun Cho; Kevin Durocher; Chris Kapusta; Aaron Knobloch; David Shaddock; Harry Schoeller; Hua Xia

2007-08-31T23:59:59.000Z

425

Cranked Nilsson-Strutinsky vs the spherical shell model: A comparative study of pf-shell nuclei  

Science Conference Proceedings (OSTI)

A comparative study is performed of a deformed mean field theory, represented by the cranked Nilsson-Strutinsky (CNS) model and the spherical shell model. Energy spectra, occupation numbers, B(E2) values, and spectroscopic quadrupole moments in the light pf-shell nuclei are calculated in the two models and compared. The result is also compared to available experimental data which are generally well described by the shell model. Although the Nilsson-Strutinsky calculation does not include pairing, both the subshell occupation numbers and quadrupole properties are found to be rather similar in the two models. It is also shown that 'unpaired' shell model calculations produce energies similar to those from the CNS. The role of the pairing energy in the description of backbending and signature splitting in odd-mass nuclei is also discussed.

Juodagalvis, Andrius [Institute of Theoretical Physics and Astronomy, A. Gostauto St. 12, LT-01108 Vilnius (Lithuania); Ragnarsson, Ingemar; Angstromberg, Sven [Mathematical Physics, Lund Institute of Technology, P.O. Box 118, S-22100 Lund (Sweden)

2006-04-15T23:59:59.000Z

426

CHP Integrated with Burners for Packaged Boilers  

SciTech Connect

The objective of this project was to engineer, design, fabricate, and field demonstrate a Boiler Burner Energy System Technology (BBEST) that integrates a low-cost, clean burning, gas-fired simple-cycle (unrecuperated) 100 kWe (net) microturbine (SCMT) with a new ultra low-NOx gas-fired burner (ULNB) into one compact Combined Heat and Power (CHP) product that can be retrofit on new and existing industrial and commercial boilers in place of conventional burners. The Scope of Work for this project was segmented into two principal phases: (Phase I) Hardware development, assembly and pre-test and (Phase II) Field installation and demonstration testing. Phase I was divided into five technical tasks (Task 2 to 6). These tasks covered the engineering, design, fabrication, testing and optimization of each key component of the CHP system principally, ULNB, SCMT, assembly BBEST CHP package, and integrated controls. Phase I work culminated with the laboratory testing of the completed BBEST assembly prior to shipment for field installation and demonstration. Phase II consisted of two remaining technical tasks (Task 7 and 8), which focused on the installation, startup, and field verification tests at a pre-selected industrial plant to document performance and attainment of all project objectives. Technical direction and administration was under the management of CMCE, Inc. Altex Technologies Corporation lead the design, assembly and testing of the system. Field demonstration was supported by Leva Energy, the commercialization firm founded by executives at CMCE and Altex. Leva Energy has applied for patent protection on the BBEST process under the trade name of Power Burner and holds the license for the burner currently used in the product. The commercial term Power Burner is used throughout this report to refer to the BBEST technology proposed for this project. The project was co-funded by the California Energy Commission and the Southern California Gas Company (SCG), a division of Sempra Energy. These match funds were provided via concurrent contracts and investments available via CMCE, Altex, and Leva Energy The project attained all its objectives and is considered a success. CMCE secured the support of GI&E from Italy to supply 100 kW Turbec T-100 microturbines for the project. One was purchased by the project’s subcontractor, Altex, and a second spare was purchased by CMCE under this project. The microturbines were then modified to convert from their original recuperated design to a simple cycle configuration. Replacement low-NOx silo combustors were designed and bench tested in order to achieve compliance with the California Air Resources Board (CARB) 2007 emission limits for NOx and CO when in CHP operation. The converted microturbine was then mated with a low NOx burner provided by Altex via an integration section that allowed flow control and heat recovery to minimize combustion blower requirements; manage burner turndown; and recover waste heat. A new fully integrated control system was designed and developed that allowed one-touch system operation in all three available modes of operation: (1) CHP with both microturbine and burner firing for boiler heat input greater than 2 MMBtu/hr; (2) burner head only (BHO) when the microturbine is under service; and (3) microturbine only when boiler heat input requirements fall below 2 MMBtu/hr. This capability resulted in a burner turndown performance of nearly 10/1, a key advantage for this technology over conventional low NOx burners. Key components were then assembled into a cabinet with additional support systems for generator cooling and fuel supply. System checkout and performance tests were performed in the laboratory. The assembled system and its support equipment were then shipped and installed at a host facility where final performance tests were conducted following efforts to secure fabrication, air, and operating permits. The installed power burner is now in commercial operation and has achieved all the performance goals.

Castaldini, Carlo; Darby, Eric

2013-09-30T23:59:59.000Z

427

Technical Review Report for the Model 9975-96 Package Safety Analysis Report for Packaging (S-SARP-G-00003, Revision 0, January 2008)  

SciTech Connect

This Technical Review Report (TRR) documents the review, performed by the Lawrence Livermore National Laboratory (LLNL) Staff, at the request of the U.S. Department of Energy (DOE), on the Safety Analysis Report for Packaging, Model 9975, Revision 0, dated January 2008 (S-SARP-G-00003, the SARP). The review includes an evaluation of the SARP, with respect to the requirements specified in 10 CFR 71, and in International Atomic Energy Agency (IAEA) Safety Standards Series No. TS-R-1. The Model 9975-96 Package is a 35-gallon drum package design that has evolved from a family of packages designed by DOE contractors at the Savannah River Site. Earlier package designs, i.e., the Model 9965, the Model 9966, the Model 9967, and the Model 9968 Packagings, were originally designed and certified in the early 1980s. In the 1990s, updated package designs that incorporated design features consistent with the then newer safety requirements were proposed. The updated package designs at the time were the Model 9972, the Model 9973, the Model 9974, and the Model 9975 Packagings, respectively. The Model 9975 Package was certified by the Packaging Certification Program, under the Office of Safety Management and Operations. The safety analysis of the Model 9975-85 Packaging is documented in the Safety Analysis Report for Packaging, Model 9975, B(M)F-85, Revision 0, dated December 2003. The Model 9975-85 Package is certified by DOE Certificate of Compliance (CoC) package identification number, USA/9975/B(M)F-85, for the transportation of Type B quantities of uranium metal/oxide, {sup 238}Pu heat sources, plutonium/uranium metals, plutonium/uranium oxides, plutonium composites, plutonium/tantalum composites, {sup 238}Pu oxide/beryllium metal.

West, M

2009-05-22T23:59:59.000Z

428

Bridging the Efficiency Gap: Commercial Packaged Rooftop Air Conditioners  

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

Bridging Bridging the Efficiency Gap: Commercial Packaged Rooftop Air Conditioners John Shugars, Consultant Philip Coleman, Lawrence BerkeleyNational Laboratory ChristopherPayne, Lawrence Berkeley National Laboratory Laura Van Wie McGrory, Lawrence Berkeley National Laboratory ABSTRACT The energy efficiency ofmany products has increased markedly over the past decade. A conspicuous exception to this trend is commercial packaged rooftop air conditioners, which have experiencedlittle to no efficiency improvement since 1992 when the Energy Policy Act of 1992 imposed federal minimum standards. Packaged rooftop units have been estimated to use on the order of76 billion kWh annually in the US, at a cost ofroughly $5.6 billion. Sales of these units are growing, and the majority of units sold have energy efficiency ratios (EERs) at orjust above the current national minimum efficiency

429

General Equilibrium Modeling Package (GEMPACK) | Open Energy Information  

Open Energy Info (EERE)

General Equilibrium Modeling Package (GEMPACK) General Equilibrium Modeling Package (GEMPACK) Jump to: navigation, search LEDSGP green logo.png FIND MORE DIA TOOLS This tool is part of the Development Impacts Assessment (DIA) Toolkit from the LEDS Global Partnership. Tool Summary LAUNCH TOOL Name: General Equilibrium Modeling Package (GEMPACK) Agency/Company /Organization: Centre of Policy Studies, Monash University Sector: Climate Topics: Analysis Tools Complexity/Ease of Use: Advanced Website: www.monash.edu.au/policy/gempack.htm Cost: Paid Related Tools Ex Ante Appraisal Carbon-Balance Tool (EX-ACT) MIT Emissions Prediction and Policy Analysis (EPPA) Model Energy Forecasting Framework and Emissions Consensus Tool (EFFECT) ... further results A system for computable general equilibrium economic modeling, produced and

430

Stailization, Packaging, and Storage of Plutonium-Bearing Materials  

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

DOE-STD-3013-2012 MARCH 2012 DOE STANDARD STABILIZATION, PACKAGING, AND STORAGE OF PLUTONIUM-BEARING MATERIALS U.S. Department of Energy AREA PACK Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. TS Available on the Department of Energy Technical Standards Program Web site at http://www.hss.energy.gov/NuclearSafety/ns/techstds/ DOE-STD-3013-2012 iii ABSTRACT This Standard provides guidance for the stabilization, packaging, and safe storage of plutonium- bearing metals and oxides containing at least 30 wt% plutonium plus uranium. It supersedes DOE-STD-3013-2004, "Stabilization, Packaging, and Storage of Plutonium-Bearing Materials," and is approved for use by all DOE organizations and their contractors. Metals are stabilized by

431

Directory of certificates of compliance for radioactive materials packages  

SciTech Connect

The purpose of this directory is to make available a convenient source of information on packagings approved by the U.S. Nuclear Regulatory Commission. To assist in identifying packaging, an index by Model Number and corresponding Certificate of Compliance Number is included at the front of Volumes 1 and 2. An alphabetical listing by user name is included in the back of Volume 3 for approved Quality Assurance programs. The reports include a listing of all users of each package design and approved Quality Assurance programs prior to the publication date of the directory. Comments to make future revisions of this directory more useful are invited and should be directed to the Spent Fuel Project Office, U.S. Nuclear Regulatory Commission.

NONE

1997-10-01T23:59:59.000Z

432

Expanded Content Envelope For The Model 9977 Packaging  

SciTech Connect

An Addendum was written to the Model 9977 Safety Analysis Report for Packaging adding a new content consisting of DOE-STD-3013 stabilized plutonium dioxide materials to the authorized Model 9977 contents. The new Plutonium Oxide Content (PuO{sub 2}) Envelope will support the Department of Energy shipment of materials between Los Alamos National Laboratory and Savannah River Site facilities. The new content extended the current content envelope boundaries for radioactive material mass and for decay heat load and required a revision to the 9977 Certificate of Compliance prior to shipment. The Addendum documented how the new contents/configurations do not compromise the safety basis presented in the 9977 SARP Revision 2. The changes from the certified package baseline and the changes to the package required to safely transport this material is discussed.

2013-07-30T23:59:59.000Z

433

MODEL 9975 SHIPPING PACKAGE FABRICATION PROBLEMS AND SOLUTIONS  

Science Conference Proceedings (OSTI)

The Model 9975 Shipping Package is the latest in a series (9965, 9968, etc.) of radioactive material shipping packages that have been the mainstay for shipping radioactive materials for several years. The double containment vessels are relatively simple designs using pipe and pipe cap in conjunction with the Chalfont closure to provide a leak-tight vessel. The fabrication appears simple in nature, but the history of fabrication tells us there are pitfalls in the different fabrication methods and sequences. This paper will review the problems that have arisen during fabrication and precautions that should be taken to meet specifications and tolerances. The problems and precautions can also be applied to the Models 9977 and 9978 Shipping Packages.

May, C; Allen Smith, A

2008-05-07T23:59:59.000Z

434

CRUSH TESTING OF 9977 GENERAL PURPOSE FISSILE PACKAGINGS  

SciTech Connect

The 9977 General Purpose Fissile Package (GPFP) was designed in response to the adoption of the crush test requirement in the US regulations for packages for radioactive materials (10 CFR 71). This presentation on crush testing of the 9977 GPFP Reviews origins of Crush Test Requirements and implementation of crush test requirements in 10 CFR 71. SANDIA testing performed to support the rule making is reviewed. The differences in practice, on the part of the US Department of Energy from those required by the NRC for commercial purposes, are explained. The design features incorporated into the 9977 GPFP to enable it to withstand the crush test and the crush tests performed on the 9977 are described. Lessons learned from crush testing of GPFP packagings are given.

Smith, A.

2010-07-28T23:59:59.000Z

435

Hypothetical accident conditions thermal analysis of the 5320 package  

Science Conference Proceedings (OSTI)

An axisymmetric model of the 5320 package was created to perform hypothetical accident conditions (HAC) thermal calculations. The analyses assume the 5320 package contains 359 grams of plutonium-238 (203 Watts) in the form of an oxide powder at a minimum density of 2.4 g/cc or at a maximum density of 11.2 g/cc. The solution from a non-solar 100 F ambient steady-state analysis was used as the initial conditions for the fire transient. A 30 minute 1,475 F fire transient followed by cooling via natural convection and thermal radiation to a 100 F non-solar environment was analyzed to determine peak component temperatures and vessel pressures. The 5320 package was considered to be horizontally suspended within the fire during the entire transient.

Hensel, S.J.; Gromada, R.J.

1995-12-31T23:59:59.000Z

436

Soft plastic bread packaging: lead content and reuse by families  

Science Conference Proceedings (OSTI)

The presence of lead in labels painted on soft plastic bread packaging was evaluated. Lead was detected on the outside of 17 of 18 soft plastic bread bags that were analyzed, with an average of 26 +/- 6 mg per bag with lead. Of 106 families questioned, 16 percent of respondents reported turning the bags inside out before reusing for food storage, thus putting food in contact with the lead paint. We estimate that a weak acid, such as vinegar, could readily leach 100 micrograms of lead from a painted plastic bag within 10 minutes. Further, lead and other metals painted on food packaging of any type becomes part of the municipal waste stream subject to incineration and to land-filling. The use of lead in packaging presents an unnecessary risk to public health.

Weisel, C.; Demak, M.; Marcus, S.; Goldstein, B.D. (Univ. of Medicine and Dentistry of New Jersey-Robert Wood Johnson Medical School, Piscataway (USA))

1991-06-01T23:59:59.000Z

437

Method for Determining Optimal Residential Energy Efficiency Retrofit Packages  

SciTech Connect

Businesses, government agencies, consumers, policy makers, and utilities currently have limited access to occupant-, building-, and location-specific recommendations for optimal energy retrofit packages, as defined by estimated costs and energy savings. This report describes an analysis method for determining optimal residential energy efficiency retrofit packages and, as an illustrative example, applies the analysis method to a 1960s-era home in eight U.S. cities covering a range of International Energy Conservation Code (IECC) climate regions. The method uses an optimization scheme that considers average energy use (determined from building energy simulations) and equivalent annual cost to recommend optimal retrofit packages specific to the building, occupants, and location. Energy savings and incremental costs are calculated relative to a minimum upgrade reference scenario, which accounts for efficiency upgrades that would occur in the absence of a retrofit because of equipment wear-out and replacement with current minimum standards.

Polly, B.; Gestwick, M.; Bianchi, M.; Anderson, R.; Horowitz, S.; Christensen, C.; Judkoff, R.

2011-04-01T23:59:59.000Z

438

9975 SHIPPING PACKAGE LIFE EXTENSION SURVEILLANCE PROGRAM RESULTS SUMMARY  

SciTech Connect

Results from the 9975 Surveillance Program at the Savannah River Site (SRS) are summarized for justification to extend the life of the 9975 packages currently stored in the K-Area Materials Storage (KAMS) facility from 10 years to 15 years. This justification is established with the stipulation that surveillance activities will continue throughout this extended time to ensure the continued integrity of the 9975 materials of construction and to further understand the currently identified degradation mechanisms. The current 10 year storage life was developed prior to storage. A subsequent report was later used to extend the qualification of the 9975 shipping packages for 2 years for shipping plus 10 years for storage. However the qualification for the storage period was provided by the monitoring requirements of the Storage and Surveillance Program. This report summarizes efforts to determine a new safe storage limit for the 9975 shipping package based on the surveillance data collected since 2005 when the surveillance program began. KAMS is a zero-release facility that depends upon containment by the 9975 to meet design basis storage requirements. Therefore, to confirm the continued integrity of the 9975 packages while stored in KAMS, a 9975 Storage and Surveillance Program was implemented alongside the DOE required Integrated Surveillance Program (ISP) for 3013 plutonium-bearing containers. The 9975 Storage and Surveillance Program performs field surveillance as well as accelerated aging tests to ensure any degradation due to aging, to the extent that could affect packaging performance, is detected in advance of such degradation occurring in the field. The Program has demonstrated that the 9975 package has a robust design that can perform under a variety of conditions. As such the primary emphasis of the on-going 9975 Surveillance Program is an aging study of the 9975 Viton(reg.sign) GLT containment vessel O-rings and the Celotex(reg.sign) fiberboard thermal insulation at bounding conditions of radiation and elevated temperatures. Other materials of construction, however, are also discussed.

Daugherty, W.; Dunn, K.; Hackney, B.; Hoffman, E.; Skidmore, E.

2011-01-06T23:59:59.000Z

439

ISSUES ASSOCIATED WITH SAFE PACKAGING AND TRANSPORT OF NANOPARTICLES  

SciTech Connect

Nanoparticles have long been recognized a hazardous substances by personnel working in the field. They are not, however, listed as a separate, distinct category of dangerous goods at present. As dangerous goods or hazardous substances, they require packaging and transportation practices which parallel the established practices for hazardous materials transport. Pending establishment of a distinct category for such materials by the Department of Transportation, existing consensus or industrial protocols must be followed. Action by DOT to establish appropriate packaging and transport requirements is recommended.

Gupta, N.; Smith, A.

2011-02-14T23:59:59.000Z

440

Coarse-graining using the VOTCA package  

Science Conference Proceedings (OSTI)

Coarsegraining is a systematic way of reducing the number of degrees of freedom representing a system of interest. Several coarsegraining techniques have so far been developed, such as iterative Boltzmann inversion, forcematching, and inverse Monte Carlo. However, there is no unified framework that implements these methods and allows their direct comparison. We present a versatile objectoriented toolkit for coarsegraining applications that implements these techniques and provides a flexible modular platform for the further development of coarsegraining techniques. All methods are illustrated and compared by coarsegraining the SPCE water model and liquid propane.

Junghans, Christoph [Los Alamos National Laboratory

2012-06-07T23:59:59.000Z

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441

Technical Review Report for the Model 9978-96 Package Safety Analysis Report for Packaging (S-SARP-G-00002, Revision 1, March 2009)  

Science Conference Proceedings (OSTI)

This Technical Review Report (TRR) documents the review, performed by Lawrence Livermore National Laboratory (LLNL) Staff, at the request of the Department of Energy (DOE), on the 'Safety Analysis Report for Packaging (SARP), Model 9978 B(M)F-96', Revision 1, March 2009 (S-SARP-G-00002). The Model 9978 Package complies with 10 CFR 71, and with 'Regulations for the Safe Transport of Radioactive Material-1996 Edition (As Amended, 2000)-Safety Requirements', International Atomic Energy Agency (IAEA) Safety Standards Series No. TS-R-1. The Model 9978 Packaging is designed, analyzed, fabricated, and tested in accordance with Section III of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME B&PVC). The review presented in this TRR was performed using the methods outlined in Revision 3 of the DOE's 'Packaging Review Guide (PRG) for Reviewing Safety Analysis Reports for Packages'. The format of the SARP follows that specified in Revision 2 of the Nuclear Regulatory Commission's Regulatory Guide 7.9, i.e., 'Standard Format and Content of Part 71 Applications for Approval of Packages for Radioactive Material'. Although the two documents are similar in their content, they are not identical. Formatting differences have been noted in this TRR, where appropriate. The Model 9978 Packaging is a single containment package, using a 5-inch containment vessel (5CV). It uses a nominal 35-gallon drum package design. In comparison, the Model 9977 Packaging uses a 6-inch containment vessel (6CV). The Model 9977 and Model 9978 Packagings were developed concurrently, and they were referred to as the General Purpose Fissile Material Package, Version 1 (GPFP). Both packagings use General Plastics FR-3716 polyurethane foam as insulation and as impact limiters. The 5CV is used as the Primary Containment Vessel (PCV) in the Model 9975-96 Packaging. The Model 9975-96 Packaging also has the 6CV as its Secondary Containment Vessel (SCV). In comparison, the Model 9975 Packagings use Celotex{trademark} for insulation and as impact limiters. To provide a historical perspective, it is noted that the Model 9975-96 Packaging is a 35-gallon drum package design that has evolved from a family of packages designed by DOE contractors at the Savannah River Site. Earlier package designs, i.e., the Model 9965, the Model 9966, the Model 9967, and the Model 9968 Packagings, were originally designed and certified in the early 1980s. In the 1990s, updated package designs that incorporated design features consistent with the then-newer safety requirements were proposed. The updated package designs at the time were the Model 9972, the Model 9973, the Model 9974, and the Model 9975 Packagings, respectively. The Model 9975 Package was certified by the Packaging Certification Program, under the Office of Safety Management and Operations. The Model 9978 Package has six Content Envelopes: C.1 ({sup 238}Pu Heat Sources), C.2 ( Pu/U Metals), C.3 (Pu/U Oxides, Reserved), C.4 (U Metal or Alloy), C.5 (U Compounds), and C.6 (Samples and Sources). Per 10 CFR 71.59 (Code of Federal Regulations), the value of N is 50 for the Model 9978 Package leading to a Criticality Safety Index (CSI) of 1.0. The Transport Index (TI), based on dose rate, is calculated to be a maximum of 4.1.

West, M

2009-03-06T23:59:59.000Z

442

Nanotexturing of surfaces to reduce melting point.  

DOE Green Energy (OSTI)

This investigation examined the use of nano-patterned structures on Silicon-on-Insulator (SOI) material to reduce the bulk material melting point (1414 C). It has been found that sharp-tipped and other similar structures have a propensity to move to the lower energy states of spherical structures and as a result exhibit lower melting points than the bulk material. Such a reduction of the melting point would offer a number of interesting opportunities for bonding in microsystems packaging applications. Nano patterning process capabilities were developed to create the required structures for the investigation. One of the technical challenges of the project was understanding and creating the specialized conditions required to observe the melting and reshaping phenomena. Through systematic experimentation and review of the literature these conditions were determined and used to conduct phase change experiments. Melting temperatures as low as 1030 C were observed.

Garcia, Ernest J.; Zubia, David (University of Texas at El Paso El Paso, TX); Mireles, Jose (Universidad Aut%C3%94onoma de Ciudad Ju%C3%94arez Ciudad Ju%C3%94arez, Mexico); Marquez, Noel (University of Texas at El Paso El Paso, TX); Quinones, Stella (University of Texas at El Paso El Paso, TX)

2011-11-01T23:59:59.000Z

443

Vadose Zone Hydrogeology Data Package for Hanford Assessments  

SciTech Connect

This data package documents the technical basis for selecting physical and geochemical parameters and input values that will be used in vadose zone modeling for Hanford assessments. This work was originally conducted as part of the Characterization of Systems Task of the Groundwater Remediation Project managed by Fluor Hanford, Inc., Richland, Washington, and revised as part of the Characterization of Systems Project managed by the Pacific Northwest National Laboratory (PNNL) for the U.S. Department of Energy, Richland Operations Office (DOE-RL). This data package describes the geologic framework, the physical, hydrologic, and contaminant transport properties of the geologic materials, and deep drainage (i.e., recharge) estimates, and builds on the general framework developed for the initial assessment conducted using the System Assessment Capability (SAC) (Bryce et al. 2002). The general approach for this work was to update and provide incremental improvements over the previous SAC data package completed in 2001. As with the previous SAC data package, much of the data and interpreted information were extracted from existing documents and databases. Every attempt was made to provide traceability to the original source(s) of the data or interpretations.

Last, George V.; Freeman, Eugene J.; Cantrell, Kirk J.; Fayer, Michael J.; Gee, Glendon W.; Nichols, William E.; Bjornstad, Bruce N.; Horton, Duane G.

2006-06-01T23:59:59.000Z

444

Installation package for Hyde Memorial Observatory, Lincoln, Nebraska  

DOE Green Energy (OSTI)

This report contains installation information for a solar heating system installed in Hyde Memorial Observatory at Lincoln, Nebraska. This package includes a system operation and maintenance manual, hardware brochures, schematics, system operating modes and drawings. The Solar Engineering and Equipment Company (SEECO) developed this prototype solar heating system, which consists of the following subsystems: solar collector, control, and storage.

Not Available

1978-12-01T23:59:59.000Z

445

Bridging the Efficiency Gap: Commercial Packaged Rooftop Air Conditioners  

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

Bridging the Efficiency Gap: Commercial Packaged Rooftop Air Conditioners Bridging the Efficiency Gap: Commercial Packaged Rooftop Air Conditioners Title Bridging the Efficiency Gap: Commercial Packaged Rooftop Air Conditioners Publication Type Conference Proceedings Year of Publication 2000 Authors Shugars, John, Philip Coleman, Christopher T. Payne, and Laura Van Wie McGrory Conference Name Proceedings from the 2000 ACEEE Summer Study on Energy Efficiency in Buildings Volume 10 Pagination 217-226 Date Published 01/2000 Abstract The energy efficiency ofmany products has increased markedly over the past decade. A conspicuous exception to this trend is commercialpackaged rooftop air conditioners, which have experiencedlittle to no efficiency improvement since 1992 when the Energy Policy Act of 1992 imposed federal minimum standards. Packaged rooftop units have been estimated to use on the order of76 billion kWh annually in the US, at a cost ofroughly $5.6 billion. Sales of these units are growing, and the majority of units sold have energy efficiency ratios (EERs) at orjust above the current national minimum efficiency standards. In this paper we document the static efficiencies ofcommercialpackaged air conditioners, explore the reasons behindthis efficiency gap, and assess opportunities for overcoming the barriers to efficiency improvements in these products.

446

Testing hadronic-interaction packages at cosmic-ray energies  

Science Conference Proceedings (OSTI)

A comparative analysis of the secondary particles output of the main hadronic interaction packages used in simulations of extensive air showers is presented. Special attention is given to the study of events with very energetic leading secondary particles, including diffractive interactions.

Canal, C. A. Garcia; Sciutto, S. J. [Departamento de Fisica, Universidad Nacional de La Plata, C.C. 67-1900 La Plata (Argentina); IFLP - CONICET, Universidad Nacional de La Plata, C.C. 67-1900 La Plata (Argentina); Tarutina, T. [Departamento de Fisica, Universidad Nacional de La Plata, C.C. 67-1900 La Plata (Argentina)

2009-03-01T23:59:59.000Z

447

Testing of the CANDU Spent Fuel Storage Basket Package  

SciTech Connect

The paper described the results of testing for a CANDU Spent Fuel Storage Basket Package Prototype intended to be used for transport and storage of the CANDU spent fuel bundles within NPP CANDU Cernavoda, Romania. The results obtained proved that the objectives of those tests were achieved

Vieru, G.

2002-02-28T23:59:59.000Z

448

Revised Industry Steam Generator Program Generic License Change Package  

E-Print Network (OSTI)

License Change Package for NRC review and endorsement. Industry events during the subsequent months have delayed the NRC review and presented an opportunity for the industry to improve the submittal. A summary of the major changes from the February submittal is provided in Enclosure 1. The resulting package (Enclosures 2 through 8), which supercedes the earlier version in its entirety, is enclosed for your endorsement. Although the events of the last ten months have resulted in some changes to the industry steam generator program guidance, the fundamental principles remain sound. Equally as important, the program has demonstrated its resiliency. The steam generator program guidance is designed to accommodate new knowledge and experience, and that is precisely what is occurring. The enclosed Generic License Change Package includes changes that reflect recent experience. In addition, the appropriate underlying technical documents are currently being revised or supplemental guidance is being developed as necessary to reflect new information. The industry and the NRC worked diligently to address the technical and licensing issues that ultimately resulted in the February 2000 version of the Steam Generator Program Generic License Change Package. Although these documents have been revised since the previous submittal, the differences do not represent a change in our position on the issues.

David J. Modeen; Mr. Samuel; J. Collins; U. S. Nuclear; Regulatory Commission; Xuo Mr; Samuel J. Collins

2000-01-01T23:59:59.000Z

449

Spent Fuel Transportation Package Performance Study - Experimental Design Challenges  

Science Conference Proceedings (OSTI)

Numerous studies of spent nuclear fuel transportation accident risks have been performed since the late seventies that considered shipping container design and performance. Based in part on these studies, NRC has concluded that the level of protection provided by spent nuclear fuel transportation package designs under accident conditions is adequate. [1] Furthermore, actual spent nuclear fuel transport experience showcase a safety record that is exceptional and unparalleled when compared to other hazardous materials transportation shipments. There has never been a known or suspected release of the radioactive contents from an NRC-certified spent nuclear fuel cask as a result of a transportation accident. In 1999 the United States Nuclear Regulatory Commission (NRC) initiated a study, the Package Performance Study, to demonstrate the performance of spent fuel and spent fuel packages during severe transportation accidents. NRC is not studying or testing its current regulations, a s the rigorous regulatory accident conditions specified in 10 CFR Part 71 are adequate to ensure safe packaging and use. As part of this study, NRC currently plans on using detailed modeling followed by experimental testing to increase public confidence in the safety of spent nuclear fuel shipments. One of the aspects of this confirmatory research study is the commitment to solicit and consider public comment during the scoping phase and experimental design planning phase of this research.

Snyder, A. M.; Murphy, A. J.; Sprung, J. L.; Ammerman, D. J.; Lopez, C.

2003-02-25T23:59:59.000Z

450

Remark on Algorithm 702—the updated truncated Newton minimization package  

Science Conference Proceedings (OSTI)

A truncated Newton minimization package, TNPACK, was described in ACM Transactions on Mathematical Software 14, 1 (Mar. 1992), pp.46–111. Modifications to enhance performance, especially for large-scale minimization of molecular ... Keywords: indefinite preconditioner, modified Cholesky factorization, molecular potential minimization, truncated Newton method

Dexuan Xie; Tamar Schlick

1999-03-01T23:59:59.000Z

451

Effects of simulant Hanford tank waste on plastic packaging components  

Science Conference Proceedings (OSTI)

In this paper, the authors describe a chemical compatibility testing program for packaging components which might be used to transport mixed wastes. They mention the results of the screening phase of this program and then present the results of the second phase of this experimental program. This effort involved the comprehensive testing of five plastic liner materials in the aqueous mixed waste simulant. The testing protocol involved exposing the respective materials to {approximately} 140, 290, 570, and 3,670 krads of gamma radiation followed by 7, 14, 28, 180 day exposures to the waste simulant at 18, 50, and 60 C. From the data analysis performed to date in this study, they have identified the fluorocarbon Kel-F{trademark} as having the greatest chemical compatibility after being exposed to gamma radiation followed by exposure to the Hanford Tank simulant mixed waste. The most striking observation from this study was the poor performance of Teflon under these conditions. The data obtained from this testing program will be available to packaging designers for the development of mixed waste packagings. The implications of the testing results on the selection of appropriate materials as packaging components are discussed.

Nigrey, P.J.; Dickens, T.G.

1996-07-01T23:59:59.000Z

452

Glass, Plastic and Semiconductors: Packaging Techniques for Miniature Optoelectric Components  

Science Conference Proceedings (OSTI)

At Lawrence Livermore National Laboratory, they have extensive experience with the design and development of miniature photonic systems which require novel packaging schemes. Over the years they have developed silicon micro-optical benches to serve as a stable platform for precision mounting of optical and electronic components. They have developed glass ball lenses that can be fabricated in-situ on the microbench substrate. They have modified commercially available molded plastic fiber ribbon connectors (MT) and added thin film multilayer semiconductor coatings to create potentially low-cost wavelength combiners and wavelength selective filters. They have fabricated both vertical-cavity and in-plane semiconductor lasers and amplifiers, and have packaged these and other components into several miniature photonics systems. For example, they have combined the silicon optical bench with standard electronic packaging techniques and the custom-made wavelength-selective filters to develop a four-wavelength wavelength-division-multiplexing transmitter module mounted in a standard 120-pin ceramic PGA package that couples light from several vertical-cavity-surface-emitting-laser arrays into one multimode fiber-ribbon array. The coupling loss can be as low as 2dB, and the transmitters can be operated at over 1.25 GHz. While these systems were not designed for biomedical or environmental applications, the concepts and techniques are general and widely applicable.

Pocha, M.D.; Garrett, H.E.; Patel, R.R.; Jones II, L.M.; Larson, M.C.; Emanuel, M.A.; Bond, S.W.; Deri, R.J.; Drayton, R.F.; Peterson, H.E.; Lowry, M.E.

1999-12-20T23:59:59.000Z