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Note: This page contains sample records for the topic "waukesha packaged system" from the National Library of EnergyBeta (NLEBeta).
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We encourage you to perform a real-time search of NLEBeta
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1

Distributed Generation Study/615 kW Waukesha Packaged System | Open Energy  

Open Energy Info (EERE)

kW Waukesha Packaged System kW Waukesha Packaged System < Distributed Generation Study Jump to: navigation, search Study Location Des Plaines, Illinois Site Description Testing Laboratory Study Type Laboratory Test Technology Internal Combustion Engine Prime Mover Waukesha VGF 36GLD Heat Recovery Systems Sondex PHE-Type SL140-TM-EE-190, Sondex PHE-Type SL140-TM-EE-150, Cain UTR1-810A17.5SSP Fuel Natural Gas System Installer GTI System Enclosure Outdoor System Application Combined Heat and Power Number of Prime Movers 1 Stand-alone Capability None Power Rating 615 kW0.615 MW 615,000 W 615,000,000 mW 6.15e-4 GW 6.15e-7 TW Nominal Voltage (V) 480 Heat Recovery Rating (BTU/hr) 2500000 Cooling Capacity (Refrig/Tons) 90 Origin of Controller 3rd Party Off-the-Shelf Component Integration Factory Integrated

2

Waukesha Electric Systems Smart Grid Demonstration Project | Open Energy  

Open Energy Info (EERE)

Electric Systems Smart Grid Demonstration Project Electric Systems Smart Grid Demonstration Project Jump to: navigation, search Project Lead Waukesha Electric Systems Country United States Headquarters Location Waukesha, Wisconsin Recovery Act Funding $10,744,409.00 Total Project Value $21,548,821.00 Coordinates 43.0116784°, -88.2314813° 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":[]}

3

Waukesha 145 | Open Energy Information  

Open Energy Info (EERE)

145 Jump to: navigation, search Manufacturer Waukesha Technology Type Internal Combustion Engine Engine Type Synchronous Generator Power Output 145 kW0.145 MW 145,000 W 145,000,000...

4

Waukesha VGF 36GLD | Open Energy Information  

Open Energy Info (EERE)

36GLD Jump to: navigation, search Manufacturer Waukesha Technology Type Internal Combustion Engine Engine Type Synchronous Generator Power Output 615 kW0.615 MW 615,000 W...

5

Waukesha VHP5108GL | Open Energy Information  

Open Energy Info (EERE)

VHP5108GL Jump to: navigation, search Manufacturer Waukesha Technology Type Internal Combustion Engine Engine Type Synchronous Generator Power Output 800 kW0.8 MW 800,000 W...

6

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

7

Waukesha, Wisconsin: Energy Resources | Open Energy Information  

Open Energy Info (EERE)

Waukesha, WI) Waukesha, WI) Jump to: navigation, search Equivalent URI DBpedia Coordinates 43.0116784°, -88.2314813° 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":43.0116784,"lon":-88.2314813,"alt":0,"address":"","icon":"","group":"","inlineLabel":"","visitedicon":""}]}

8

STATEMENT OF CONSIDERATIONS REQUEST BY DRESSER WAUKESHA FOR AN ADVANCE WAIVER OF  

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

DRESSER WAUKESHA FOR AN ADVANCE WAIVER OF DRESSER WAUKESHA FOR AN ADVANCE WAIVER OF PATENT RIGHTS TO INVENTIONS MADE UNDER DOE COOPERATIVE AGREEMENT DE-EE0004016; W(A)-10-065 ; CH-1587 Dresser Waukesha (Dresser), requests an advance waiver of domestic and foreign patent rights for all subject inventions made under the above cooperative agreement with the Department of Energy. The purpose of the cooperative agreement is to design, develop and build a'n ultra clean 1.1 MW high efficiency natural gas engine powered system to serve the Combined Heat and Power market. The waiver is to apply to Dresser's employee subject inventions only. The work under this cooperative agreement is expected to take place between October 1,2010 and September 30,2014. The total estimated cost of the cooperative

9

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

10

Waukesha VGF L36GSID | Open Energy Information  

Open Energy Info (EERE)

L36GSID Jump to: navigation, search Manufacturer Waukesha Technology Type Internal Combustion Engine Engine Type Synchronous Generator Power Output 560 kW0.56 MW 560,000 W...

11

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

12

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

13

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

14

System specification for the plutonium stabilization and packaging system  

Science Conference Proceedings (OSTI)

This document describes functional design requirements for the Plutonium Stabilization and Packaging System (Pu SPS), as required by DOE contract DE-AC03-96SF20948 through contract modification 9 for equipment in Building 707 at Rocky Flats Environmental Technology Site (RFETS).

NONE

1996-07-01T23:59:59.000Z

15

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

16

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

17

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

18

System design document for the plutonium stabilization and packaging system  

Science Conference Proceedings (OSTI)

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 for DOE standards for safe storage of these materials for 50 years. This document describes the highest level design information and user characteristics from an operational perspective. It provides guidance for developing procurement and installation specifications, interface requirements, and test plans.

NONE

1996-05-08T23:59:59.000Z

19

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

20

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

Note: This page contains sample records for the topic "waukesha packaged system" 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

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 |...

22

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

23

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

24

Ultra Clean 1.1MW High Efficiency Natural Gas Engine Powered System  

Science Conference Proceedings (OSTI)

Dresser, Inc. (GE Energy, Waukesha gas engines) will develop, test, demonstrate, and commercialize a 1.1 Megawatt (MW) natural gas fueled combined heat and power reciprocating engine powered package. This package will feature a total efficiency > 75% and ultra low CARB permitting emissions. Our modular design will cover the 1 6 MW size range, and this scalable technology can be used in both smaller and larger engine powered CHP packages. To further advance one of the key advantages of reciprocating engines, the engine, generator and CHP package will be optimized for low initial and operating costs. Dresser, Inc. will leverage the knowledge gained in the DOE - ARES program. Dresser, Inc. will work with commercial, regulatory, and government entities to help break down barriers to wider deployment of CHP. The outcome of this project will be a commercially successful 1.1 MW CHP package with high electrical and total efficiency that will significantly reduce emissions compared to the current central power plant paradigm. Principal objectives by phases for Budget Period 1 include: Phase 1 market study to determine optimum system performance, target first cost, lifecycle cost, and creation of a detailed product specification. Phase 2 Refinement of the Waukesha CHP system design concepts, identification of critical characteristics, initial evaluation of technical solutions, and risk mitigation plans. Background

Zurlo, James; Lueck, Steve

2011-08-31T23:59:59.000Z

25

Solar heating system final design package  

DOE Green Energy (OSTI)

Contemporary Systems has taken its Series V Solar Heating System and developed it to a degree acceptable by local codes and regulatory agencies. The system is composed of the Series V warm air collector, the LCU-110 logic control unit and the USU-A universal switching and transport unit. The collector was originally conceived and designed as an integrated roof/wall system and provides a dual function in the structure. The collector serves both as a solar energy conversion system and as a structural weather resistant skin. The collector can be fabricated in any length from 12 to 24 feet. This provides maximum flexibility in design and installation. The LCU-110 control unit provides totally automatic control over the operation of the system. It receives input data from sensor probes in collectors, storage and living space. The logic is designed so as to make maximum use of solar energy and minimize use of conventional energy. The USU-A transport and switching unit is a high-efficiency air-handling system equipped with gear motor valves that respond to outputs from the control system. The fan unit is designed for maximum durability and efficiency in operation, and has permanently lubricated ball bearings and excellent air-handling efficiency.

Not Available

1979-05-01T23:59:59.000Z

26

Packaging for a drug delivery microelectromechanical system  

E-Print Network (OSTI)

Local drug delivery is a fast expanding field, and has been a center of attention for researchers in medicine in the last decade. Its advantages over systemic drug delivery are clear in cancer therapy, with localized tumors. ...

Ho Duc, Hong Linh, 1978-

2005-01-01T23:59:59.000Z

27

Water Rights Analysis Package (WRAP) Modeling System Reference Manual  

E-Print Network (OSTI)

The Texas Water Resources Institute (TWRI), and many other agencies and organizations, have worked with Ralph Wurbs over the years to develop WRAP (the Water Rights Analysis Package). The WRAP model simulates management of the water resources of a river basin, or multiple-basin region, under a priority-based water allocation system. The model facilitates assessment of hydrologic and institutional water availability/reliability for existing and proposed requirements for water use and management. Basin-wide impacts of water resources development projects and management strategies may be evaluated. The software package is generalized for application to any river/reservoir/use system, with input files being developed for the particular river basin of concern. The model is documented by reference and users manuals that may be downloaded from this site along with the software. WRAP is incorporated in the Texas Commission on Environmental Quality (TCEQ) Water Availability Modeling (WAM) System.

Wurbs, R.

2012-10-01T23:59:59.000Z

28

Energy Management Systems Package for Small Commercial Buildings  

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

EnMS (energy management 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 | Building Technologies Office eere.energy.gov Purpose & Objectives Problem Statement: Small commercial buildings present two challenges for implementing energy efficiency strategies 1) high transaction cost relative to total savings 2) lack of personnel time or skill available for energy management

29

FRAMES Software System: Linking to the Statistical Package R  

SciTech Connect

This document provides requirements, design, data-file specifications, test plan, and Quality Assurance/Quality Control protocol for the linkage between the statistical package R and the Framework for Risk Analysis in Multimedia Environmental Systems (FRAMES) Versions 1.x and 2.0. The requirements identify the attributes of the system. The design describes how the system will be structured to meet those requirements. The specification presents the specific modifications to FRAMES to meet the requirements and design. The test plan confirms that the basic functionality listed in the requirements (black box testing) actually functions as designed, and QA/QC confirms that the software meets the clients needs.

Castleton, Karl J.; Whelan, Gene; Hoopes, Bonnie L.

2006-12-11T23:59:59.000Z

30

System design package for solar heating and cooling system installed at Akron, Ohio  

DOE Green Energy (OSTI)

This package contains information used to evaluate the design of Solaron's solar heating, cooling, and domestic hot water system. A conventional heat pump provides summer cooling and back-up heating (when solar energy is not available). Included in the package are such items as the design data brochure, system performance specification, system hazard analysis, spare parts list, and detailed design drawings. A Solaron solar system is installed in a single-family dwelling at Akron, Ohio, and at Duffield, Virginia.

Not Available

1979-04-01T23:59:59.000Z

31

Hanford high-level waste melter system evaluation data packages  

SciTech Connect

The Tank Waste Remediation System is selecting a reference melter system for the Hanford High-Level Waste vitrification plant. A melter evaluation was conducted in FY 1994 to narrow down the long list of potential melter technologies to a few for testing. A formal evaluation was performed by a Melter Selection Working Group (MSWG), which met in June and August 1994. At the June meeting, MSWG evaluated 15 technologies and selected six for more thorough evaluation at the Aug. meeting. All 6 were variations of joule-heated or induction-heated melters. Between the June and August meetings, Hanford site staff and consultants compiled data packages for each of the six melter technologies as well as variants of the baseline technologies. Information was solicited from melter candidate vendors to supplement existing information. This document contains the data packages compiled to provide background information to MSWG in support of the evaluation of the six technologies. (A separate evaluation was performed by Fluor Daniel, Inc. to identify balance of plant impacts if a given melter system was selected.)

Elliott, M.L.; Shafer, P.J.; Lamar, D.A.; Merrill, R.A.; Grunewald, W.; Roth, G.; Tobie, W.

1996-03-01T23:59:59.000Z

32

Remote Handling Equipment for a High-Level Waste Waste Package Closure System  

SciTech Connect

High-level waste will be placed in sealed waste packages inside a shielded closure cell. The Idaho National Laboratory (INL) has designed a system for closing the waste packages including all cell interior equipment and support systems. This paper discusses the material handling aspects of the equipment used and operations that will take place as part of the waste package closure operations. Prior to construction, the cell and support system will be assembled in a full-scale mockup at INL.

Kevin M. Croft; Scott M. Allen; Mark W. Borland

2006-04-01T23:59:59.000Z

33

Radioisotope thermoelectric generator transportation system safety analysis report for packaging. Volumes 1 and 2  

Science Conference Proceedings (OSTI)

This SARP describes the RTG Transportation System Package, a Type B(U) packaging system that is used to transport an RTG or similar payload. The payload, which is included in this SARP, is a generic, enveloping payload that specifically encompasses the General Purpose Heat Source (GPHS) RTG payload. The package consists of two independent containment systems mounted on a shock isolation transport skid and transported within an exclusive-use trailer.

Ferrell, P.C.

1996-04-18T23:59:59.000Z

34

Packaged air cleaning systems tame desert dust storms in Oman  

SciTech Connect

Vast storms created when cold, northwesterly air masses slam into hot, southwesterly monsoons, moving lethargically over the Sudan and Red Sea, generate swift downdrafts that strike the ground and deflect forward in a powerful, swirling air stream up to 500 km long. As the wind moves along the ground, it churns up particles ranging in size from 80 to 2000 micrometers. This churning also kicks up particles in the 0.1 to 80 micrometer range, and these may rise to heights of 500 m or more, the smaller of which remain suspended for hours. These conditions made it imperative to protect the blades and internal mechanisms of the gas turbines in use at Yibal, Sultanate of Oman. Each of the gas turbines is equipped with a packaged intake air cleaning system. Because no single air filter has been designed to handle effectively the extremely high concentrations of particulates encountered during storms, the AAF air filters are multistage filtration systems. These systems are discussed.

1980-12-01T23:59:59.000Z

35

Yucca Mountain Waste Package Closure System Robotic Welding and Inspection System  

Science Conference Proceedings (OSTI)

The Waste Package Closure System (WPCS), for the closure of radioactive waste in canisters for permanent storage of spent nuclear fuel (SNF) and high-level waste in the Yucca Mountain Repository was designed, fabricated, and successfully demonstrated at the Idaho National Laboratory (INL). This article focuses on the robotic hardware and tools necessary to remotely weld and inspect the closure lid welds. The system was operated remotely and designed for use in a radiation field, due to the SNF contained in the waste packages being closed.

C. I. Nichol; D. P. Pace; E. D. Larsen; T. R. McJunkin; D. E. Clark; M. L. Clark; K. L. Skinner; A. D. Watkins; H. B. Smartt

2011-10-01T23:59:59.000Z

36

System specification/system design document comment review: Plutonium Stabilization and Packaging System. Notes of conference  

SciTech Connect

A meeting was held between DOE personnel and the BNFL team to review the proposed resolutions to DOE comments on the initial issue of the system specification and system design document for the Plutonium Stabilization and Packaging System. The objectives of this project are to design, fabricate, install, and start up a glovebox system for the safe repackaging of plutonium oxide and metal, with a requirement of a 50-year storage period. The areas discussed at the meeting were: nitrogen in can; moisture instrumentation; glovebox atmosphere; can marking-bar coding; weld quality; NFPA-101 references; inner can swabbing; ultimate storage environment; throughput; convenience can screw-top design; furnace/trays; authorization basis; compactor safety; schedule for DOE review actions; fire protection; criticality safety; applicable standards; approach to MC and A; homogeneous oxide; resistance welder power; and tray overfill. Revised resolutions were drafted and are presented.

NONE

1996-07-01T23:59:59.000Z

37

System design package for SIMS prototype system 3, solar heating and domestic hot water  

DOE Green Energy (OSTI)

This report is a collation of documents and drawings that describe a prototype solar heating and hot water system using liquid flat plat collectors and a gas or electric furnace energy subsystem. The system was designed for installation into a single-family dwelling. The description, performance specification, subsystem drawings, verification plan/procedure, and hazard analysis of the system are packaged for evaluation of the system with information sufficient to assemble a similar system. The SIMS Prototype Heating and Hot Water System, Model Number 3 has been installed in a residence at Glendo State Park, Glendo, Wyoming.

Not Available

1978-11-01T23:59:59.000Z

38

Work plan for the fabrication of the radioisotope thermoelectric generator transportation system package mounting  

DOE Green Energy (OSTI)

The Radioisotope Thermoelectric Generator (RTG) has available a dedicated system for the transportation of RTG payloads. The RTG Transportation System (System 100) is comprised of four systems; the Package (System 120), the Semi-trailer (System 140), the Gas Management (System 160), and the Facility Transport (System 180). This document provides guidelines on the fabrication, technical requirements, and quality assurance of the Package Mounting (Subsystem 145), part of System 140. The description follows the Development Control Requirements of WHC-CM-6-1, EP 2.4, Rev. 3.

Satoh, J.A.

1994-11-09T23:59:59.000Z

39

Packaging design of the IBM system z10 enterprise class platform central electronic complex  

Science Conference Proceedings (OSTI)

The IBM System z10 Enterprise Class mainframe addresses the modern data center requirements for minimizing floor space while increasing computing power efficiency. These objectives placed challenges on the z10 packaging ...

J. G. Torok; F. E. Bosco; W. L. Brodsky; E. F. Furey; G. F. Goth; D. J. Kearney; J. J. Loparco; M. T. Peets; K. L. Pizzolato; D. W. Porter; G. Ruehle; W. H. White

2009-01-01T23:59:59.000Z

40

Property:Heat Recovery Systems | Open Energy Information  

Open Energy Info (EERE)

Systems Systems Jump to: navigation, search Property Name Heat Recovery Systems Property Type Page Description Distributed Data heat recovery systems Pages using the property "Heat Recovery Systems" Showing 25 pages using this property. (previous 25) (next 25) C Capstone C30 + Unifin + Capstone C60 + Unifin HX + D Distributed Generation Study/10 West 66th Street Corp + Built-in + Distributed Generation Study/615 kW Waukesha Packaged System + Sondex PHE-Type SL140-TM-EE-190 +, Sondex PHE-Type SL140-TM-EE-150 +, Cain UTR1-810A17.5SSP + Distributed Generation Study/Aisin Seiki G60 at Hooligans Bar and Grille + Built-in + Distributed Generation Study/Arrow Linen + Built-in + Distributed Generation Study/Dakota Station (Minnegasco) + Unifin + Distributed Generation Study/Elgin Community College + Beaird Maxim Model TRP-12 +

Note: This page contains sample records for the topic "waukesha packaged system" 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

Unitary solar heating/cooling system package development. Progress report, June 1, 1977--January 31, 1978  

DOE Green Energy (OSTI)

During this period, a 3 ton residential system hardware package has been developed and is operating in an Arkla owned solar house in Evansville. The Arkla tower-cooled WF36 chiller has been substituted for the evaporatively cooled chiller under development in the package. The residential software and manufacturing programs are underway. Only preliminary thinking has been done on the commercial 25 ton program which will soon be getting major attention.

Merrick, R.H.

1978-01-01T23:59:59.000Z

42

Property:Distributed Generation System Application | Open Energy  

Open Energy Info (EERE)

System Application System Application Jump to: navigation, search This is a property of type Page. Pages using the property "Distributed Generation System Application" Showing 22 pages using this property. D Distributed Generation Study/10 West 66th Street Corp + Combined Heat and Power + Distributed Generation Study/615 kW Waukesha Packaged System + Combined Heat and Power + Distributed Generation Study/Aisin Seiki G60 at Hooligans Bar and Grille + Combined Heat and Power + Distributed Generation Study/Arrow Linen + Combined Heat and Power + Distributed Generation Study/Dakota Station (Minnegasco) + Combined Heat and Power + Distributed Generation Study/Elgin Community College + Combined Heat and Power + Distributed Generation Study/Emerling Farm + Combined Heat and Power +

43

Property:Distributed Generation System Enclosure | Open Energy Information  

Open Energy Info (EERE)

System Enclosure System Enclosure Jump to: navigation, search This is a property of type String. The allowed values for this property are: Indoor Outdoor Dedicated Shelter Pages using the property "Distributed Generation System Enclosure" Showing 22 pages using this property. D Distributed Generation Study/10 West 66th Street Corp + Indoor + Distributed Generation Study/615 kW Waukesha Packaged System + Outdoor + Distributed Generation Study/Aisin Seiki G60 at Hooligans Bar and Grille + Outdoor + Distributed Generation Study/Arrow Linen + Outdoor + Distributed Generation Study/Dakota Station (Minnegasco) + Outdoor + Distributed Generation Study/Elgin Community College + Indoor + Distributed Generation Study/Emerling Farm + Dedicated Shelter + Distributed Generation Study/Floyd Bennett + Outdoor +

44

System design package for SIMS Prototype System 4, solar heating and domestic hot water  

DOE Green Energy (OSTI)

This report is a collation of documents and drawings that describe a prototype solar heating and hot water system using air type solar energy collection techniques. The system consists of a modular designed prepackaged solar unit containing solar collctors, a rock storage container, blowers, dampers, ducting, air-to-water heat exchanger, DHW preheat tank, piping and system controls. The system was designed to be installed adjacent to a small single family dwelling. The description, performance specification, subsystem drawings, verification plan/procedure, and hazard analysis of the system are packaged for evaluation of the system with inforation sufficient to assemble a similar system. The prepackage solar unit has been installed at the Mississippi Power and Light Company, Training Facilities, Clinton, Mississippi.

Not Available

1978-11-01T23:59:59.000Z

45

Design and installation package for solar hot water system  

DOE Green Energy (OSTI)

This report contains the design and installation procedure for the Solar Engineering and Manufacturing Company's solar hot water system. Included are the system performance specifications, system design drawings, hazard analysis and other information necessary to evaluate the design and instal the system.

Not Available

1978-12-01T23:59:59.000Z

46

Documentation pckage for the RFID temperature monitoring system (Of Model 9977 packages at NTS).  

Science Conference Proceedings (OSTI)

The technical basis for extending the Model 9977 shipping package periodic maintenance beyond the one-year interval to a maximum of five years is based on the performance of the O-ring seals and the environmental conditions. The DOE Packaging Certification Program (PCP) has tasked Argonne National Laboratory to develop a Radio-Frequency Identification (RFID) temperature monitoring system for use by the facility personnel at DAF/NTS. The RFID temperature monitoring system, depicted in the figure below, consists of the Mk-1 RFId tags, a reader, and a control computer mounted on a mobile platform that can operate as a stand-alone system, or it can be connected to the local IT network. As part of the Conditions of Approval of the CoC, the user must complete the prescribed training to become qualified and be certified for operation of the RFID temperature monitoring system. The training course will be administered by Argonne National Laboratory on behalf of the Headquarters Certifying Official. This is a complete documentation package for the RFID temperature monitoring system of the Model 9977 packagings at NTS. The documentation package will be used for training and certification. The table of contents are: Acceptance Testing Procedure of MK-1 RFID Tags for DOE/EM Nuclear Materials Management Applications; Acceptance Testing Result of MK-1 RFID Tags for DOE/EM Nuclear Materials Management Applications; Performance Test of the Single Bolt Seal Sensor for the Model 9977 Packaging; Calibration of Built-in Thermistors in RFID Tags for Nevada Test Site; Results of Calibration of Built-in Thermistors in RFID Tags; Results of Thermal Calibration of Second Batch of MK-I RFID Tags; Procedure for Installing and Removing MK-1 RFID Tag on Model 9977 Drum; User Guide for RFID Reader and Software for Temperature Monitoring of Model 9977 Drums at NTS; Software Quality Assurance Plan (SQAP) for the ARG-US System; Quality Category for the RFID Temperature Monitoring System; The Documentation Package for the RFID Temperature Monitoring System; Software Test Plan and Results for ARG-US OnSite; Configuration Management Plan (CMP) for the ARG-US System; Requirements Management Plan for the ARG-US System; and Design Management Plan for ARG-US.

Chen, K.; Tsai, H.; Decision and Information Sciences

2009-02-20T23:59:59.000Z

47

Radioisotope Thermoelectric Generator Transporation System licensed hardware second certification test series and package shock mount system test  

Science Conference Proceedings (OSTI)

This paper presents a summary of two separate drop test a e performed in support of the Radioisotope Thermoelectric Generator (RTG) Transportation System (RTGTS). The first portion of this paper presents the second series of drop testing required to demonstrate that the RTG package design meets the requirements of Title 10, Code of Federal Regulations, ``Part 71`` (10 CFR 71). Results of the first test series, performed in July 1994, demonstrated that some design changes were necessary. The package design was modified to improve test performance and the design changes were incorporated into the Safety Analysis Report for Packaging (SARP). The second full-size certification test article (CTA-2) incorporated the modified design and was tested at the US Department of Energy`s (DOE) Hanford Site near Richland, Washington. With the successful completion of the test series, and pending DOE Office of Facility Safety Analysis approval of the SARP, a certificate of compliance will be issued for the RTG package allowing its use. The second portion of this paper presents the design and testing of the RTG Package Mount System. The RTG package mount was designed to protect the RTG from excessive vibration during transport, provide shock protection during on/off loading, and provide a mechanism for moving the RTG package with a forklift. Military Standard (MIL-STD) 810E, Transit Drop Procedure (DOE 1989), was used to verify that the shock limiting system limited accelerations in excess of 15 G`s at frequencies below 150 Hz. Results of the package mount drop tests indicate that an impact force of 15 G`s was not exceeded in any test from a free drop height of 457 mm (18 in.).

Ferrell, P.C.; Moody, D.A.

1995-10-01T23:59:59.000Z

48

Impact of a New Radiation Package, McRad, in the ECMWF Integrated Forecasting System  

Science Conference Proceedings (OSTI)

A new radiation package, McRad, has become operational with cycle 32R2 of the Integrated Forecasting System (IFS) of the European Centre for Medium-Range Weather Forecasts (ECMWF). McRad includes an improved description of the land surface ...

J-J. Morcrette; H. W. Barker; J. N. S. Cole; M. J. Iacono; R. Pincus

2008-12-01T23:59:59.000Z

49

Vendor Assessment for the Waste Package Closure System (Yucca Mtn. Project)  

Science Conference Proceedings (OSTI)

The Idaho National Engineering and Environmental Laboratory (INEEL) has been tasked with developing, designing, constructing, and operating a full-scale prototype of the work package closure system. As a precursor to developing the conceptual design, all commercially available equipment was assessed to identify any existing technology gaps. This report presents the results of that assessment for all major equipment.

Colleen Shelton-Davis

2003-09-01T23:59:59.000Z

50

Vendor Assessment for the Waste Package Closure System (Yucca Mountain Project)  

Science Conference Proceedings (OSTI)

The Idaho National Engineering and Environmental Laboratory (INEEL) has been tasked with developing, designing, constructing, and operating a full-scale prototype of the work package closure system. As a precursor to developing the conceptual design, all commercially available equipment was assessed to identify any existing technology gaps. This report presents the results of that assessment for all major equipment.

Shelton-Davis, C.V.

2003-09-26T23:59:59.000Z

51

FUEL SUPPLY SYSTEM ANALYSIS FOR ESF PACKAGE 1E  

SciTech Connect

The primary objective of this analysis is to capture new inputs relative to the design of the Fuel Supply System (FSS) at the Yucca Mountain Site Characterization Project (YMP) Exploratory Studies Facility (ESF). The new inputs are analyzed and changes to the Fuel Supply System are made as necessary.

D.F. Vanica

1995-06-14T23:59:59.000Z

52

Preliminary design package for prototype solar heating system  

DOE Green Energy (OSTI)

A summary is given of the preliminary analysis and design activity on solar heating systems. The analysis was made without site specific ata other than weather; therefore, the results indicate performance expected under these special conditions. Major items in this report include systeem candidates, design approaches, trade studies and other special data required to evaluate the preliminary analysis and design. The program calls for the development and delivery of eight prototype solar heating and coolin systems for installation and operational test. Two-heating and six heating and cooling units will be delivered for Single Family Residences (SFR), Multi-Family Residences (MFR) and commercial applications.

Not Available

1978-12-01T23:59:59.000Z

53

Preliminary design package for prototype solar heating and cooling systems  

DOE Green Energy (OSTI)

A summary is presented of the preliminary analysis and design activity on solar heating and cooling systems. The analysis was made without site specific data other than weather; therefore, the results indicate performance expected under these special conditions. Major items in this report include a market analysis, design approaches, trade studies and other special data required to evaluate the preliminary analysis and design. The program calls for the development and delivery of eight prototype solar heating and cooling systems for installation and operational test. Two heating and six heating and cooling units will be delivered for Single Family Residences (SFR), Multiple-Family Residences (MFR), and commerical applications.

Not Available

1978-12-01T23:59:59.000Z

54

Welding Robot and Remote Handling System for the Yucca Mountain Waste Package Closure System  

SciTech Connect

In preparation for the license application and construction of a repository for housing the nation's spent nuclear fuel and high-level waste in Yucca Mountain, the Idaho National Laboratory (INL) has been charged with preparing a mock-up of a full-scale prototype system for sealing the waste packages (WP). Three critical pieces of the closure room include two PaR Systems TR4350 Telerobotic Manipulators and a PaR Systems XR100 Remote Handling System (RHS). The TR4350 Manipulators are 6-axis programmable robots that will be used to weld the WP lids and purge port cap as well as conduct nondestructive examinations. The XR100 Remote Handling System is a 4-axis programmable robot that will be used to transport the WP lids and process tools to the WP for operations and remove equipment for maintenance. The welding and RHS robots will be controlled using separate PaR 5/21 CIMROC Controllers capable of complex motion control tasks. A tele-operated PaR 4350 Manipulator will also be provided with the XR100 Remote Handling System. It will be used for maintenance and associated activities within the closure room. (authors)

Barker, M.E.; Holt, T.E.; LaValle, D.R. [PaR Systems, Inc., Shoreview, MN (United States); Pace, D.P.; Croft, K.M.; Shelton-Davis, C.V. [Battelle Energy Alliance, LLC/Idaho National Laboratory, Idaho Falls, ID (United States)

2008-07-01T23:59:59.000Z

55

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:

56

Data processing unit and power system for the LANL REM instrument package. Final report  

SciTech Connect

The NEPSTP spacecraft needs highly reliable instrumentation to measure the nuclear reactor health and performance. These reactor measurements are essential for initial on-orbit phase operations and documentation of performance over time. Los Alamos National Laboratory (LANL), under the guidance of W. C. Feldman, principal investigator, has designed the Radiation Environment Monitoring (REM) package to meet these needs. The instrumentation package contains two neutron detectors, one gamma-ray detector, a data processing unit, and an instrument power system. The REM package is an integration of quick turn-around, state of the practice technology for detectors, data processors, and power systems. A significant portion of REM consists of subsystems with flight history. Southwest Research Institute (SwRI) has been tasked by LANL to design support electronics, including the Data Processing Unit (DPU) and Power System for REM. The goal for this project is to use technologies from current programs to speed up and simplify the design process. To meet these design goals, the authors use an open architecture VME bus for the DPU and derivatives of CASSINI power supplies for the instrument power system. To simplify integration and test activities, they incorporate a proven software development strategy and tool kits from outside vendors. The objective of this report is to illustrate easily incorporated system level designs for the DPU, power system and ground support electronics (GSE) in support of the important NEPSTP program.

Lockhart, W. [Southwest Research Inst., San Antonio, TX (United States). Instrumentation and Space Research Div.

1994-03-01T23:59:59.000Z

57

Disposal Systems Evaluations and Tool Development - Engineered Barrier System Evaluation (Work Package LL1015080425)  

SciTech Connect

The Disposal Systems Evaluation Framework (DSEF) will use a logical process for developing one or more disposal system concepts (also referred to as repository system in this report) for any given waste form and geologic setting combination. In the Features, Events, and Processes (FEPs) group of work packages, there are seven categories of waste forms and eight categories of geologic setting being studied. The DSEF will also establish a Used Fuel Disposition Campaign (UFDC) knowledge management system to organize high-level information, data, and assumptions, thereby facilitating consistency in high-level system simulation and economic analyses. This system likely will be housed with the INL-based documentation system. Attention is given to lessons oearned from the systems used at the Waste Isolation Pilot Plant (WIPP) and the Yucca Mountain Project (YMP). Where reference material from other programs (e.g., international) is used or cited, the knowledge-management system imports the reference material directly or refer to it in bibliography form. Alternative data sets (e.g., from other programs) will also be utilized to evaluate their influence on DSEF analyses for given waste form and disposal-system combinations. The knowledge-management system can also be used to maintain the results of DSEF realizations, enabling the comparison and ranking of various waste-form/disposal-system-environment/disposal-system-design options. Finally, the UFDC knowledge-management system will be able to provide a compendium of 'templates' that can be utilized, in a labor-efficient fashion, to build parallel DSEF analyses (e.g., 'one offs'). The DSEF will not be a stand-alone, push-the-button and wait for the results, item of software. it will use osftware (probably EXCEL, initially), to guide the team members through a logical process of evaluating combinations of waste-form, disposal-syste-environment, and disposal-system design. In later stages, it will utilize software developed in the field of knowledge engineering and knowledge-management systems (Umeki et al. 2009). At certain points in the logical process, the DSEF software will point the evaluate to other software tools to do analyses needed to move the process forward. In the development of the DSEF, they will be mindful to make it no more complex than necessary to evaluate the system being considered. The DSEF will organize and document the work such that multiple realizations for different combinations can be compared and contrasted.

Blink, J A; Buscheck, T A; Halsey, W G; Wolery, T

2010-03-19T23:59:59.000Z

58

Using Single-Camera 3-D Imaging to Guide Material Handling Robots in a Nuclear Waste Package Closure System  

SciTech Connect

Nuclear reactors for generating energy and conducting research have been in operation for more than 50 years, and spent nuclear fuel and associated high-level waste have accumulated in temporary storage. Preparing this spent fuel and nuclear waste for safe and permanent storage in a geological repository involves developing a robotic packaging systema system that can accommodate waste packages of various sizes and high levels of nuclear radiation. During repository operation, commercial and government-owned spent nuclear fuel and high-level waste will be loaded into casks and shipped to the repository, where these materials will be transferred from the casks into a waste package, sealed, and placed into an underground facility. The waste packages range from 12 to 20 feet in height and four and a half to seven feet in diameter. Closure operations include sealing the waste package and all its associated functions, such as welding lids onto the container, filling the inner container with an inert gas, performing nondestructive examinations on welds, and conducting stress mitigation. The Idaho National Laboratory is designing and constructing a prototype Waste Package Closure System (WPCS). Control of the automated material handling is an important part of the overall design. Waste package lids, welding equipment, and other tools must be moved in and around the closure cell during the closure process. These objects are typically moved from tool racks to a specific position on the waste package to perform a specific function. Periodically, these objects are moved from a tool rack or the waste package to the adjacent glovebox for repair or maintenance. Locating and attaching to these objects with the remote handling system, a gantry robot, in a loosely fixtured environment is necessary for the operation of the closure cell. Reliably directing the remote handling system to pick and place the closure cell equipment within the cell is the major challenge.

Rodney M. Shurtliff

2005-09-01T23:59:59.000Z

59

A Method for On-Going Commissioning of VRV Package Systems Using a Simulation Model  

E-Print Network (OSTI)

Variable refrigerant volume (VRV) systems, which have several indoor units and a single outdoor unit, have become very popular HVAC systems in Japan. However, some systems may be operated under inefficient conditions and consume excessive energy, since verification of system performance is not conducted. Although the performance of systems should be evaluated by some indices such as coefficient of performance (COP), calculating such a value is difficult, because the heat load handled by machines is not known. A simulation model based on a refrigeration cycle was proposed to evaluate system performance. Basic conditions for evaporation and condensation were defined from conditions provided in Japanese Industrial Standards (JIS). Flow rate of refrigerant was calculated from heat load under full occupancy and enthalpy difference of the evaporator. If power consumption exceeds the calculated value, malfunctions or inadequate conditions are considered to occur. The method presented here can be used for on-going commissioning of VRV package systems.

Yamaha, M.; Sekiyama, K.; Misaki, S.

2006-01-01T23:59:59.000Z

60

Status of integrated performance assessment of the waste packages and engineered barrier system  

SciTech Connect

Performance assessment of the engineered barrier system for a nuclear waste repository combines information from relevant disciplines and predicts the net long-term performance of the EBS in unites of regulatory goals for performance. The performance assessment models are specific to the proposed Yucca Mountain, Nevada site. Early assessments are used for project planning and feedback. The EBS scenarios activity develops the scenarios and the consequent event sequences. Initial model development for single waste packages indicates that the radionuclide release rate performance is sensitive to the water flux, element solubilities, and/or the mode of water contact with the waste. The latter in turn depends on local scale hydrology and the modes of corrosion for the container material. For the release rate summed over waste packages, variations among waste packages and their near-field environments are anticipated. These variations place demands on data acquisition and modeling, as well as modulate the impact of localized changes of conditions. Sampling in uncertainty assessment is a subsequent step in examining the reliability of predictions made in the performance assessments. Advances made in sampling methods are referenced. 14 refs., 6 figs.

O`Connell, W.J.

1990-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "waukesha packaged system" 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

Uranium hexafluoride packaging tiedown systems overview at Portsmouth Gaseous Diffusion Plant, Piketon, Ohio. Revision 1  

SciTech Connect

The Portsmouth Gaseous Diffusion Plant (PORTS) in Piketon, Ohio, is operated by Martin Marietta Energy Systems, Inc., through the US Department of Energy-Oak Ridge Operations Office (DOE-ORO) for the US Department of Energy-Headquarters, Office of Nuclear Energy. The PORTS conducts those operations that are necessary for the production, packaging, and shipment of uranium hexafluoride (UF{sub 6}). Uranium hexafluoride enriched uranium than 1.0 wt percent {sup 235}U shall be packaged in accordance with the US Department of Transportation (DOT) regulations of Title 49 CFR Parts 173 (Reference 1) and 178 (Reference 2), or in US Nuclear Regulatory Commission (NRC) or US Department of Energy (DOE) certified package designs. Concerns have been expressed regarding the various tiedown methods and condition of the trailers being used by some shippers/carriers for international transport of the UF{sub 6} cylinders/overpacks. Because of the concerns about international shipments, the US Department of Energy-Headquarters (DOE-HQ) Office of Nuclear Energy, through DOE-HQ Transportation Management Division, requested Westinghouse Hanford Company (Westinghouse Hanford) to review UF{sub 6} packaging tiedown and shipping practices used by PORTS, and where possible and appropriate, provide recommendations for enhancing these practices. Consequently, a team of two individuals from Westinghouse Hanford visited PORTS on March 5 and 6, 1990, for the purpose of conducting this review. The paper provides a brief discussion of the review activities and a summary of the resulting findings and recommendations. A detailed reporting of the is documented in Reference 4.

Becker, D.L.; Green, D.J.; Lindquist, M.R.

1993-07-01T23:59:59.000Z

62

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: ...

63

Engineered barrier system and waste package design concepts for a potential geologic repository at Yucca Mountain  

Science Conference Proceedings (OSTI)

We are using an iterative process to develop preliminary concept descriptions for the Engineered Barrier System and waste-package components for the potential geologic repository at Yucca Mountain. The process allows multiple design concepts to be developed subject to major constraints, requirements, and assumptions. Involved in the highly interactive and interdependent steps of the process are technical specialists in engineering, metallic and nonmetallic materials, chemistry, geomechanics, hydrology, and geochemistry. We have developed preliminary design concepts that satisfy both technical and nontechnical (e.g., programmatic or policy) requirements.

Short, D.W.; Ruffner, D.J.; Jardine, L.J.

1991-10-01T23:59:59.000Z

64

Packaged residential active-solar space-conditioning system. Appendix E. System performance monitoring. Final subcontract report  

Science Conference Proceedings (OSTI)

This report documents the testing of four solar space heating systems that had cost and performance characteristics equalling or exceeding competing conventional heating systems. Design concepts for these systems were solicited from the solar industry and field tested by Vitro Corporation. The designers of the four prototype systems were: Calmac Manufacturing Corporation, Contemporary Systems, Inc., Honeywell Inc., and Trident Energy Systems. Vitro Corporation reports the results of field test performance for the four packaged space heating systems. Their review presents the primary performance factors for all systems, comparing them to the best National Solar Data Network (NSDN) space heating systems. Performance factors evaluated and reported on were: collection subsystem efficiency, collector array operational efficiency, percentage of incident solar delivered to loads, collector coefficients of performance, system coefficients of performance, percent collected solar to load, and solar energy to loads/ft/sup 2/ collector/day. The data indicate that these packaged space heating systems compare well with the most recent National Solar Data Network systems.

Not Available

1986-05-01T23:59:59.000Z

65

An Inverter Packaging Scheme for an Integrated Segmented Traction Drive System  

Science Conference Proceedings (OSTI)

The standard voltage source inverter (VSI), widely used in electric vehicle/hybrid electric vehicle (EV/HEV) traction drives, requires a bulky dc bus capacitor to absorb the large switching ripple currents and prevent them from shortening the battery s life. The dc bus capacitor presents a significant barrier to meeting inverter cost, volume, and weight requirements for mass production of affordable EVs/HEVs. The large ripple currents become even more problematic for the film capacitors (the capacitor technology of choice for EVs/HEVs) in high temperature environments as their ripple current handling capability decreases rapidly with rising temperatures. It is shown in previous work that segmenting the VSI based traction drive system can significantly decrease the ripple currents and thus the size of the dc bus capacitor. This paper presents an integrated packaging scheme to reduce the system cost of a segmented traction drive.

Su, Gui-Jia [ORNL; Tang, Lixin [ORNL; Ayers, Curtis William [ORNL; Wiles, Randy H [ORNL

2013-01-01T23:59:59.000Z

66

Proposal for the award of a contract for dismantling, removal and packaging of the existing Heating, Ventilation and Air-Conditioning (HVAC) systems in the PS tunnel  

E-Print Network (OSTI)

Proposal for the award of a contract for dismantling, removal and packaging of the existing Heating, Ventilation and Air-Conditioning (HVAC) systems in the PS tunnel

2012-01-01T23:59:59.000Z

67

Building America Top Innovations Hall of Fame Profile … 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

68

North Portal Fuel Storage System Fire Hazard Analysis-ESF Surface Design Package ID  

SciTech Connect

The purpose of the fire hazard analysis is to comprehensively assess the risk from fire within the individual fire areas. This document will only assess the fire hazard analysis within the Exploratory Studies Facility (ESF) Design Package ID, which includes the fuel storage system area of the North Portal facility, and evaluate whether the following objectives are met: 1.1.1--This analysis, performed in accordance with the requirements of this document, will satisfy the requirements for a fire hazard analysis in accordance with U.S. Department of Energy (DOE) Order 5480.7A. 1.1.2--Ensure that property damage from fire and related perils does not exceed an acceptable level. 1.1.3--Provide input to the ESF Basis For Design (BFD) Document. 1.1.4 Provide input to the facility Safety Analysis Report (SAR) (Paragraph 3.8).

N.M. Ruonavaara

1995-01-18T23:59:59.000Z

69

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

70

Application of RFID on equipment parts readiness management system of semiconductor packaging plant  

Science Conference Proceedings (OSTI)

Management of equipment parts readiness for process setup adjustment to meet variable order requirements in a semiconductor packaging plant is crucial to the health of production lines and downtime avoidance. In order to improve the current equipment ...

Wei-Ling Wang; Chiao-Tzu Huang; Shu-Jen Wang; Chia-Pao Chang; Hui-Wen Liao

2013-01-01T23:59:59.000Z

71

System design package for SIMS Prototype System 2, solar hot water  

DOE Green Energy (OSTI)

This report is a collection of documents and drawings that describe a solar hot water system. The necessary information to evaluate the design and with information sufficient to assemble a similar system is presented. The International Business Machines Corporation developed prototype system 2 solar hot water for use in a single family dwelling. The system has been installed in Building Number 20, which is a single family residence on the grounds of the Veterans Administration Hospital at Togus, Maine. It consists of the following subsystems: collector, storage, energy transport, and control. It is a design with wide-spread application potential with only slight adjustments necessary in system size.

Not Available

1977-12-01T23:59:59.000Z

72

Tabulation of thermodynamic data for chemical reactions involving 58 elements common to radioactive waste package systems  

DOE Green Energy (OSTI)

The rate of release and migration of radionuclides from a nuclear waste repository to the biosphere is dependent on chemical interactions between groundwater, the geologic host rock, and the radioactive waste package. For the purpose of this report, the waste package includes the wasteform, canister, overpack, and repository backfill. Chemical processes of interest include sorption (ion exchange), dissolution, complexation, and precipitation. Thermochemical data for complexation and precipitation calculations for 58 elements common to the radioactive waste package are presented. Standard free energies of formation of free ions, complexes, and solids are listed. Common logarithms of equilibrium constants (log K's) for speciation and precipitation reactions are listed. Unless noted otherwise, all data are for 298.15/sup 0/K and one atmosphere.

Benson, L.V.; Teague, L.S.

1980-08-01T23:59:59.000Z

73

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: ...

74

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: ...

75

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

76

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

77

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

78

Installation package for a domestic solar heating and hot water system  

DOE Green Energy (OSTI)

Fern Engineering Company, Inc. has developed two prototype solar heating and hot water systems. The systems have been installed at Tunkhannock, Pennsylvania, and Lansing, Michigan. The system consists of the following subsystems: solar collector, storage, control, transport, and auxiliary energy. General guidelines which may be utilized in development of detailed installation plans and specifications are presented. In addition, instruction on operation, maintenance, and repair of a solar heating and hot water system is provided.

Not Available

1978-08-01T23:59:59.000Z

79

Tank vapor sampling and analysis data package for tank 241-C-106 waste retrieval sluicing system process test phase III  

Science Conference Proceedings (OSTI)

This data package presents sampling data and analytical results from the March 28, 1999, vapor sampling of Hanford Site single-shell tank 241-C-106 during active sluicing. Samples were obtained from the 296-C-006 ventilation system stack and ambient air at several locations. Characterization Project Operations (CPO) was responsible for the collection of all SUMMATM canister samples. The Special Analytical Support (SAS) vapor team was responsible for the collection of all triple sorbent trap (TST), sorbent tube train (STT), polyurethane foam (PUF), and particulate filter samples collected at the 296-C-006 stack. The SAS vapor team used the non-electrical vapor sampling (NEVS) system to collect samples of the air, gases, and vapors from the 296-C-006 stack. The SAS vapor team collected and analyzed these samples for Lockheed Martin Hanford Corporation (LMHC) and Tank Waste Remediation System (TWRS) in accordance with the sampling and analytical requirements specified in the Waste Retrieval Sluicing System Vapor Sampling and Analysis Plan (SAP) for Evaluation of Organic Emissions, Process Test Phase III, HNF-4212, Rev. 0-A, (LMHC, 1999). All samples were stored in a secured Radioactive Materials Area (RMA) until the samples were radiologically released and received by SAS for analysis. The Waste Sampling and Characterization Facility (WSCF) performed the radiological analyses. The samples were received on April 5, 1999.

LOCKREM, L.L.

1999-08-13T23:59:59.000Z

80

Solar energy heating system design package for a single-family residence at New Castle, Pennsylvania  

DOE Green Energy (OSTI)

The design of a solar heating and hot water system for the New Castle Redevelopment Authority's single-family dwelling located at New Castle, Pennsylvania is described. Documentation submitted by the contractor for Government review of plans, specifications, cost trade studies and verification status for approval to commit the system to fabrication is presented. Also included are system integration drawings, major subsystems drawings, and architect's specifications and plans.

Not Available

1977-08-01T23:59:59.000Z

Note: This page contains sample records for the topic "waukesha packaged system" 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

cMsg: a publish/subscribe package for real-time and online control systems  

Science Conference Proceedings (OSTI)

cMsg is a messaging system designed for use in realtime data acquisition and online controls systems, and includes support for C/C++ and Java clients. It is highly customizable and extensible, and includes a full-featured asynchronous publish/subscribe ...

Elliott Wolin; D. Abbott; V. Gurjyan; E. Jastrzembski; D. Lawrence; C. Timmer

2005-06-01T23:59:59.000Z

82

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

83

System installation package for the new Hampshire Vocational Technical College, Manchester, N. H  

DOE Green Energy (OSTI)

Contemporary Systems, Incorporated of Jaffrey, New Hampshire, under NASA/MSFC Contract NAS8-32243 has taken its Series V Solar Heating System and developed it to a degree acceptable by local codes and regulatory agencies. The system is composed of the Series V warm air collector, the LCU-110 logic control unit and the USU-A universal switching and transport unit. The collector was originally conceived and designed as an integrated roof/wall system and provides a dual function in the structure. This document describes the above system which has been installed in the residential solar laboratory located at the New Hampshire Vocational Technical College in Manchester, N.H. In addition, it provides general guidelines which may be utilized in development of detailed installation plans and specifications, as well as instructions on operation and maintenance.

Not Available

1979-05-01T23:59:59.000Z

84

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

85

Preliminary design package for residential heating/cooling system--Rankine air conditioner redesign  

DOE Green Energy (OSTI)

This report contains a summary of the preliminary redesign and development of a marketable single-family heating and cooling system. The objectives discussed are the interim design and schedule status of the Residential (3-ton) redesign, problem areas and solutions, and the definition of plans for future design and development activities. The proposed system for a single-family residential heating and cooling system is a single-loop, solar-assisted, hydronic-to-warm-air heating subsystem with solar-assisted domestic water heating and a Rankine-driven expansion air-conditioning subsystem.

Not Available

1978-12-01T23:59:59.000Z

86

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: ...

87

Wang OIS glossary package for reformatting documents telecommunicated to the OIS system  

SciTech Connect

Documents that are composed on a computer and then transmitted by telecommunications into a Wang Office Information System (OIS) word processing system need to be reformatted and cleaned up before they can be used properly as word processing documents suitable for further revisions or additions. This report describes a group of glossary entries created for the Wang OIS which simplifies the job of cleaning up telecommunicated documents. This glossary is a semi-automated process designed to eliminate most of the tedious work needed to be performed in removing extra spaces and returns, adjusting formats, moving material, repagination, using tabs or indents, and similar problems. The report briefly discusses the problems, describes the glossary approach to solving them, and gives instructions for actually using the glossary entries.

Markow, S.R.

1983-12-09T23:59:59.000Z

88

APOLLO LUNAR SURFACE EXPERIMENTS PACKAGE SYSTEMS HANDBOOK ALSEP 5 -ARRAY E  

E-Print Network (OSTI)

PCN-1 DC-1 10/6/72 4-14 TAB 4-V VOLTAGE DISTRIBUTION AND BUS LOAD ANALYSIS PCN-1 DC-1 10/6/72 4-15 TAB the first publication of Section 11, the Lunar Seismic Profiling Experiment (S203), and updating previously-1 DC-1 10/6/72 3-6 SECTION 4 ELECTRICAL POWER SUBSYSTEM PAR 4.1 SYSTEM DESCRIPTION PCN-1 DC-1 10

Rathbun, Julie A.

89

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 ...

90

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

91

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

92

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

93

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

94

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

95

? Thermal Packaging  

E-Print Network (OSTI)

? Final devices will be lab bench and field tested for reliability. Recent Results ? Fuel delivery system fabricated ? 500um thick NiFe structures plated ? 900um Rotor/Housing fabrication process improved Next Six Months ? Fuel / air mixture manifold

Dorian Liepmann Ph. D; David C. Walther; Prof Al Pisano

2003-01-01T23:59:59.000Z

96

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

97

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: ...

98

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

99

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

100

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

Note: This page contains sample records for the topic "waukesha packaged system" 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

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

102

Waukesha, Wisconsin: Energy Resources | Open Energy Information  

Open Energy Info (EERE)

116784°, -88.2314813° 116784°, -88.2314813° 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":43.0116784,"lon":-88.2314813,"alt":0,"address":"","icon":"","group":"","inlineLabel":"","visitedicon":""}]}

103

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

104

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

105

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

106

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

107

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

108

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

109

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

110

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

111

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

112

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...

113

Assessment of the impacts of spent fuel disassembly alternatives on the Nuclear Waste Isolation System. [Preparing and packaging spent fuel assemblies for geologic disposal  

SciTech Connect

The objective of this report was to evaluate four possible alternative methods of preparing and packaging spent fuel assemblies for geologic disposal against the Reference Process of unmodified spent fuel. The four alternative processes were: (1) End fitting removal, (2) Fission gas venting and resealing, (3) Fuel bundle disassembly and close packing of fuel pins, and (4) Fuel shearing and immobilization. Systems analysis was used to develop a basis of comparison of the alternatives. Conceptual processes and facility layouts were devised for each of the alternatives, based on technology deemed feasible for the purpose. Assessments were made of 15 principal attributes from the technical, operational, safety/risk, and economic considerations related to each of the alternatives, including both the surface packaging and underground repository operations. Specific attributes of the alternative processes were evaluated by assigning a number for each that expressed its merit relative to the corresponding attribute of the Reference Process. Each alternative process was then ranked by summing the numbers for attributes in each of the four assessment areas and collectively. Fuel bundle disassembly and close packing of fuel pins was ranked the preferred method of disposal of spent fuel. 63 references, 46 figures, 46 tables.

Not Available

1984-07-01T23:59:59.000Z

114

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

115

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

116

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

117

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

118

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

119

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

120

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

Note: This page contains sample records for the topic "waukesha packaged system" 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

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

122

A smooth transition from serial to parallel processing in the industrial petroleum system modeling package PetroMod  

Science Conference Proceedings (OSTI)

Petroleum system modeling is a crucial technology to numerically simulate the generation, migration, accumulation, and loss of oil and gas through geologic time. The OpenMP programming paradigm is used to achieve modest parallelism on a shared-memory ... Keywords: Monte Carlo, OpenMP, Parallel computing, Petroleum system modeling, Shared-memory parallelization

H. Martin Bcker; Armin I. Kauerauf; Arno Rasch

2008-11-01T23:59:59.000Z

123

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

124

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

125

Solar heating system design package for a single-family residence at William O'Brien State Park, Minnesota  

DOE Green Energy (OSTI)

Honeywell, Inc. has undertaken the design, fabrication, installation, and monitoring of a prototype solar heating and hot water system for the Minnesota Department of Natural Resources' single-family dwelling located at O'Brien State Park, 30 miles east of Minneapolis, Minnesota. Documentation submitted by Honeywell for government review of plans, specifications, cost trade studies and verification status in order to provide the contractor with approval to commit the system to fabrication are included.

Not Available

1977-07-01T23:59:59.000Z

126

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

127

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

128

Remaining Sites Verification Package for the 1607-F3 Sanitary Sewer System, Waste Site Reclassification Form 2006-047  

Science Conference Proceedings (OSTI)

The 1607-F3 waste site is the former location of the sanitary sewer system that supported the 182-F Pump Station, the 183-F Water Treatment Plant, and the 151-F Substation. The sanitary sewer system included a septic tank, drain field, and associated pipeline, all in use between 1944 and 1965. In accordance with this evaluation, the verification sampling results support a reclassification of this site to Interim Closed Out. The results of verification sampling demonstrated that residual contaminant concentrations do not preclude any future uses and allow for unrestricted use of shallow zone soils. The results also showed that residual contaminant concentrations are protective of groundwater and the Columbia River.

L. M. Dittmer

2007-04-26T23:59:59.000Z

129

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

130

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

131

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

132

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

133

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

134

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

135

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

136

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

137

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

138

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

139

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

140

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

Note: This page contains sample records for the topic "waukesha packaged system" 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

Thin-film multichip module packages for high-end IBM servers  

Science Conference Proceedings (OSTI)

A new generation of multilevel thin-film packages has been developed for IBM high-end S/390 and AS/400 systems. Thin-film structures in these packages are nonplanar and can be fabricated by either pattern electroplating ...

E. D. Perfecto; A. P. Giri; R. R. Shields; H. P. Longworth; J. R. Pennacchia; M. P. Jeanneret

1998-09-01T23:59:59.000Z

142

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

143

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

144

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

145

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

146

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

147

Description of the Canadian Particulate-Fill WastePackage (WP) System for Spent-Nuclear Fuel (SNF) and its Applicability to Ligh-Water Reactor SNF WPS with Depleted Uranium-Dioxide Fill  

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

3502 3502 Chemical Technology Division DESCRIPTION OF THE CANADIAN PARTICULATE-FILL WASTE-PACKAGE (WP) SYSTEM FOR SPENT-NUCLEAR FUEL(SNF) AND ITS APPLICABILITY TO LIGHT- WATER REACTOR SNF WPS WITH DEPLETED URANIUM-DIOXIDE FILL Charles W. Forsberg Oak Ridge National Laboratory * P.O. Box 2008 Oak Ridge, Tennessee 37831-6180 Tel: (423) 574-6783 Fax: (423) 574-9512 Email: forsbergcw@ornl.gov October 20, 1997 _________________________ Managed by Lockheed Martin Energy Research Corp. under contract DE-AC05-96OR22464 for the * U.S. Department of Energy. iii CONTENTS LIST OF FIGURES . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . v LIST OF TABLES . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . vii ACRONYMS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

148

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

149

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

150

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

151

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....

152

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

153

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

154

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

155

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.

156

Rooftop package unit diagnostician  

DOE Patents (OSTI)

A diagnostic system for an HVAC system includes a number of sensors used to measure the operation of the HVAC system. Sensor readings are measured by timing the delay between when a strobe signal is sent to a sensor and when an interrupt signal from the sensor is received. A device driver used to measure the sensor readings stores the sensor readings in pseudo-character device files, which are universally accessible by different subsystems of the diagnostic system. Based on the readings from these sensors, this diagnostic system is able to determine the operational status of the HVAC system and if an economizer in the HVAC system is operating properly.

Chassin, David P [Pasco, WA; Pratt, Robert G [Kennewick, WA; Reid, Larry Dean [Benton City, WA

2004-08-17T23:59:59.000Z

157

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

158

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

159

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

160

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

Note: This page contains sample records for the topic "waukesha packaged system" 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

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

162

Solar control design package  

DOE Green Energy (OSTI)

Information used in the evaluation of design of Solar Control's solar heating and cooling system controller and the Solarstat is presented. System performance specifications, design data brochures, and detailed design drawings are presented.

Not Available

1978-08-01T23:59:59.000Z

163

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

164

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

165

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

166

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

167

Waukesha County, Wisconsin: Energy Resources | Open Energy Information  

Open Energy Info (EERE)

County, Wisconsin: Energy Resources County, Wisconsin: Energy Resources Jump to: navigation, search Equivalent URI DBpedia Coordinates 43.0072599°, -88.3239309° 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":43.0072599,"lon":-88.3239309,"alt":0,"address":"","icon":"","group":"","inlineLabel":"","visitedicon":""}]}

168

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

169

SHIELD certification package  

Science Conference Proceedings (OSTI)

Certification as applied to existing computer codes includes the verification and validation process, placing the code in configuration control, establishing user qualification standards and training requirements. All software intended for use in critical calculations must be certified. This report is intended to fulfill the requirements for the certification of the SHIELD, SHLDED, GEDIT, GENPRT, FIPROD, FPCALC, and PROCES modules of the SHIELD system built February, 1992, by W.S. Parks. These modules are used for burnup, cooling, separate, and edit calculations.

Boman, C.

1992-02-01T23:59:59.000Z

170

Microelectronics plastic molded packaging  

Science Conference Proceedings (OSTI)

The use of commercial off-the-shelf (COTS) microelectronics for nuclear weapon applications will soon be reality rather than hearsay. The use of COTS for new technologies for uniquely military applications is being driven by the so-called Perry Initiative that requires the U.S. Department of Defense (DoD) to accept and utilize commercial standards for procurement of military systems. Based on this philosophy, coupled with several practical considerations, new weapons systems as well as future upgrades will contain plastic encapsulated microelectronics. However, a conservative Department of Energy (DOE) approach requires lifetime predictive models. Thus, the focus of the current project is on accelerated testing to advance current aging models as well as on the development of the methodology to be used during WR qualification of plastic encapsulated microelectronics. An additional focal point involves achieving awareness of commercial capabilities, materials, and processes. One of the major outcomes of the project has been the definition of proper techniques for handling and evaluation of modern surface mount parts which might be used in future systems. This program is also raising the familiarity level of plastic within the weapons complex, allowing subsystem design rules accommodating COTS to evolve. A two year program plan is presented along with test results and commercial interactions during this first year.

Johnson, D.R. [Ktech Corp., Albuquerque, NM (United States); Palmer, D.W.; Peterson, D.W. [Sandia National Lab., Albuquerque, NM (United States)] [and others

1997-02-01T23:59:59.000Z

171

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

172

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

173

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

174

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

175

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

176

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 &...

177

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

178

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

179

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

180

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

Note: This page contains sample records for the topic "waukesha packaged system" 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

Identification of unique reciprocal and non reciprocal cross packaging relationships between HIV-1, HIV-2 and SIV reveals an efficient SIV/HIV-2 lentiviral vector system with highly favourable features for in vivo testing and clinical usage  

E-Print Network (OSTI)

, transduction of neural stem cells with lentiviral and adeno associated viral vectors express- ing therapeutic genes that will affect differentiation and Gag-Pol packaging constructsFigure 1 Gag-Pol packaging constructs. gag Poly ApolLTR vpx vprvif rev tat ?Env... (1153bp) ?? ? ? gag Poly A polCMV rev tat ?Env ?? HIV-1 Gag-Pol ?8.9 (2nd Generation) gag LTRpolLTR vpx vprvif rev tat nef ?Env (550bp) ?? ? ? RRE RRE RRE SIV Gag-Pol (SgpDelta2) Gag-Pol packaging constructs HIV-2 Gag-PolPage 2 of 14 (page number...

Strappe, Padraig M; Hampton, David W; Brown, Douglas; Gonzales, Begona-cachon; Caldwell, Maeve; Fawcett, James W; Lever, Andrew M L

2005-09-16T23:59:59.000Z

182

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

183

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

184

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

185

Remaining Sites Verification Package for the 100-F-31, 144-F Sanitary Sewer System, Waste Site Reclassification Form 2006-033  

SciTech Connect

The 100-F-31 waste site is a former septic system that supported the inhalation laboratories, also referred to as the 144-F Particle Exposure Laboratory (132-F-2 waste site), which housed animals exposed to particulate material. The 100-F-31 waste site has been remediated to achieve the remedial action objectives specified in the Remaining Sites ROD. The results of verification sampling show that residual contaminant concentrations do not preclude any future uses and allow for unrestricted use of shallow zone soils. The results also demonstrate that residual contaminant concentrations are protective of groundwater and the Columbia River.

L. M. Dittmer

2006-08-24T23:59:59.000Z

186

Quality Assurance requirements - Safety Analysis Reports for Packaging. An effective approach in developing QA requirements  

SciTech Connect

Application of QA requirements for packaging and transportation of radioactive materials should not be solely based on safety-related considerations. The operability of items, components, and systems must be considered as equally important. The nuclear industry has begun to recognize operability considerations along with safety concerns. This has resulted in a new approach in establishing QA requirements for packaging.

Fabian, R.R.

1986-01-01T23:59:59.000Z

187

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

188

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

189

Mixed waste chemical compatibility: A testing program for plastic packaging 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 in the United States 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 by the US Department of Transportation (DOT, 49 CFR 173) and the US Nuclear Regulatory Commission (NRC, 10 CFR 71). The design requirements for both hazardous [49 CFR 173.24 (e)(1)] and radioactive [49 CFR 173.412 (g)] materials packaging specify packaging compatibility, i.e., that the materials of the packaging @d any contents be chemically compatible with each other. Furthermore, Type A [49 CFR 173.412 (g)] and Type B (10 CFR 71.43) 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 attempts to assure any regulatory body that the issue of packaging material compatibility towards hazardous and radioactive materials has been addressed. This program has been described in considerable detail in an internal SNL document, the Chemical Compatibility Test Plan & Procedure Report (Nigrey 1993).

Nigrey, P.J.

1995-12-01T23:59:59.000Z

190

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

191

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

192

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

193

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

194

The Disappearing Package - Materials Technology @ TMS  

Science Conference Proceedings (OSTI)

Feb 25, 2013 ... The largest percentage of thisabout 76 million tonsis attributable to consumer packaging. For More Information: Visit The Disappearing...

195

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

196

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

197

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,...

198

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.

199

Property:Distributed Generation Prime Mover | Open Energy Information  

Open Energy Info (EERE)

Property Property Edit with form History Facebook icon Twitter icon » Property:Distributed Generation Prime Mover Jump to: navigation, search Property Name Distributed Generation Prime Mover Property Type Page Description Make and model of power sources. Pages using the property "Distributed Generation Prime Mover" Showing 22 pages using this property. D Distributed Generation Study/10 West 66th Street Corp + Ingersoll Rand I-R PowerWorks 70 + Distributed Generation Study/615 kW Waukesha Packaged System + Waukesha VGF 36GLD + Distributed Generation Study/Aisin Seiki G60 at Hooligans Bar and Grille + Aisin Seiki G60 + Distributed Generation Study/Arrow Linen + Coast Intelligen 150-IC with ECS + Distributed Generation Study/Dakota Station (Minnegasco) + Capstone C30 +

200

T-529: Apple Mac OS PackageKit Distribution Script Remote Code Execution  

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

29: Apple Mac OS PackageKit Distribution Script Remote Code 29: Apple Mac OS PackageKit Distribution Script Remote Code Execution Vulnerability T-529: Apple Mac OS PackageKit Distribution Script Remote Code Execution Vulnerability January 6, 2011 - 2:53pm Addthis PROBLEM: Apple Mac OS PackageKit Distribution Script Remote Code Execution Vulnerability PLATFORM: Apple Mac OS X Server 10.6 - 10.6.5, Apple Mac OS X 10.6 - 10.6.5 Vulnerable Platforms Details ABSTRACT: A format string issue exists in PackageKit's handling of distribution scripts. A man-in-the-middle attacker may be able to cause an unexpected application termination or arbitrary code execution when Software Update checks for new updates. This issue is addressed through improved validation of distribution scripts. This issue does not affect systems prior to Mac OS

Note: This page contains sample records for the topic "waukesha packaged system" from the National Library of EnergyBeta (NLEBeta).
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they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
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201

Conduction cooling for an LSI package: a one-dimensional approach  

Science Conference Proceedings (OSTI)

The introduction of LSI packaging has significantly increased the number of circuits per silicon chip, and at the same time has greatly increased their heat flux density. In comparison to earlier MST (monolithic systems technology) products, the heat ...

R. C. Chu; U. P. Hwang; R. E. Simons

1982-01-01T23:59:59.000Z

202

Technical Review Report for the Safety Analysis Report for Packaging Model 9977 S-SARP-G-00001 Revision 2  

SciTech Connect

This Technical Review Report (TRR) summarizes the review findings for the Safety Analysis Report for Packaging (SARP) for the Model 9977 B(M)F-96 shipping container. The content analyzed for this submittal is Content Envelope C.1, Heat Sources, in assemblies of Radioisotope Thermoelectric Generators or food-pack cans. The SARP under review, i.e., S-SARP-G-00001, Revision 2 (August 2007), was originally referred to as the General Purpose Fissile Material Package. The review presented in this TRR was performed using the methods outlined in Revision 3 of the Department of Energy's (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 9977 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. The Model 9977 Package design includes a single, 6-inch diameter, stainless steel pressure vessel containment system (i.e., the 6CV) that was designed and fabricated in accordance with Section III, Subsection NB, of the American Society of Mechanical Engineers Boiler & Pressure Vessel Code. The earlier package designs, i.e., the Model 9965, 9966, 9967 and 9968 Packages, were originally designed and certified in the 1980s. In the 1990s, updated package designs that incorporated design features consistent with new safety requirements, based on International Atomic Energy Agency guidelines, were proposed. The updated package designs were the Model 9972, 9973, 9974 and 9975 Packages, respectively. The Model 9975 Package was certified by the Packaging Certification Program, under the Office of Safety Management and Operations. Differences between the Model 9975 Package and the Model 9977 Package include: (1) The lead shield present in the Model 9975 Package is absent in the Model 9977 Package; (2) The Model 9975 Package has eight allowable contents, while the Model 9977 Package has a single allowable content. (3) The 6CV of the Model 9977 Package is similar in design to the outer Containment Vessel of the Model 9975 Package that also incorporates a 5-inch Containment Vessel as the inner Containment Vessel. (4) The Model 9975 Package uses a Celotex{reg_sign}-based impact limiter while the Model 9977 Package uses Last-A-Foam{reg_sign}, a polyurethane foam, for the impact limiter. (5) The Model 9975 Package has two Containment Vessels, while the Model 9977 Package has a single Containment Vessel.

DiSabatino, A; Hafner, R; West, M

2007-10-04T23:59:59.000Z

203

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:

204

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...

205

Page not found | Department of Energy  

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

04-google-chrome-updated-version-adobe-flash-player Article Secretary Chu Discovers Transformers in Wisconsin Secretary Chu visits Waukesha Electric Systems to see how tax credit...

206

Page not found | Department of Energy  

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

psh-11-0008-matter-personnel-security-hearing Article Secretary Chu Discovers Transformers in Wisconsin Secretary Chu visits Waukesha Electric Systems to see how tax credit...

207

Page not found | Department of Energy  

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

Chu visits Waukesha Electric Systems to see how tax credit benefits will lead to new jobs and advanced electricity transformers. http:energy.govarticles...

208

NETL F 451.1-1/1 Categorical Exclusion (CX) Designation Form  

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

Inc. EE DE-EE0004016 ITP 2010 Christopher Harp 912010-9312014 Waukesha, WI Combined Heat and Power Systems Technology Development & Demonstration The objective of this...

209

Mold Heating and Cooling Pump Package Operator Interface Controls Upgrade  

SciTech Connect

The modernization of the Mold Heating and Cooling Pump Package Operator Interface (MHC PP OI) consisted of upgrading the antiquated single board computer with a proprietary operating system to off-the-shelf hardware and off-the-shelf software with customizable software options. The pump package is the machine interface between a central heating and cooling system that pumps heat transfer fluid through an injection or compression mold base on a local plastic molding machine. The operator interface provides the intelligent means of controlling this pumping process. Strict temperature control of a mold allows the production of high quality parts with tight tolerances and low residual stresses. The products fabricated are used on multiple programs.

Josh A. Salmond

2009-08-07T23:59:59.000Z

210

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

211

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 ...

212

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...

213

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

214

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

215

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

216

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

217

Thermal analysis of Yucca Mountain commercial high-level waste packages  

Science Conference Proceedings (OSTI)

The thermal performance of commercial high-level waste packages was evaluated on a preliminary basis for the candidate Yucca Mountain repository site. The purpose of this study is to provide an estimate for waste package component temperatures as a function of isolation time in tuff. Several recommendations are made concerning the additional information and modeling needed to evaluate the thermal performance of the Yucca Mountain repository system.

Altenhofen, M.K. [Altenhofen (M.K.), Richland, WA (United States); Eslinger, P.W. [Pacific Northwest Lab., Richland, WA (United States)

1992-10-01T23:59:59.000Z

218

Developing Energy Efficiency Packages for ENERGY STAR New Homes  

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

Developing Energy Efficiency Packages for ENERGY STAR New Homes Developing Energy Efficiency Packages for ENERGY STAR New Homes Speaker(s): Rich Brown Date: July 23, 1998 - 12:00pm Location: 90-3148 The Environmental Protection Agency's ENERGY STAR Homes program promotes the construction of new homes that consume at least 30% less energy than homes meeting the 1993 Model Energy Code. Thus far, builders participating in the program have needed an individual Home Energy Rating System (HERS) rating for each house certified under the program. Tract-home builders have been reluctant to participate in the program, however, because of the time and cost of HERS ratings, as well as the uncertainty about precisely what measures their homes will need to meet the ENERGY STAR guidelines. To make it easier for large production builders

219

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

220

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.

Note: This page contains sample records for the topic "waukesha packaged system" 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

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

222

Validation of the guidelines for portable meteorological instrument packages. Task IV. Development of an insolation handbook and instrumentation package  

DOE Green Energy (OSTI)

The purpose of this report is to show how the objective of developing guidelines for a solar energy related portable meteorology instrument package, under the auspices of the International Energy Agency (IEA), was carried out and preliminarily demonstrated and validated. A project to develop guidelines for such packages was initiated at IEA's Solar Heating and Cooling of Buildings Program Expert's Meeting held in Norrkoping, Sweden in February 1976. An international comparison of resultant devices was conducted on behalf of the IEA at a conference held in Hamburg, Federal Republic of Germany, in 1978. Results of the 1978 Hamburg comparison of two devices and the Swiss Mobile Solar Radiation System, using German meteorological standards, are discussed. The consensus of the IEA Task Group is that the objective of the subtask has been accomplished.

None

1980-10-01T23:59:59.000Z

223

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

224

Automated Transportation Management System (ATMS) | Department...  

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

Waste Management Packaging and Transportation Automated Transportation Management System (ATMS) Automated Transportation Management System (ATMS) The Department of Energy's...

225

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

226

Initial Package Design Concepts Integrated Product Team (IPT) Summary Report  

Science Conference Proceedings (OSTI)

Initially, the question of transporting TRU waste to WIPP was raised as part of the EM Integration activities. The issue was re-examined as part of the system-wide view to re-engineer the TRU waste program. Consequently, the National Transportation Program and the National TRU Waste Program, in a cooperative effort, made a commitment to EM-20 to examine the feasibility of using rail to transport TRU waste material to WIPP. In December of 1999 Mr. Philip Altomare assembled a team of subject matter experts (SME) to define initial concepts for a Type B package capable of shipping TRU waste by rail (see Attachment 1 for a list of team members). This same team of experts also provided input to a preliminary study to determine if shipping TRU waste by rail could offer cost savings or other significant advantages over the current mode of operation using TRUPACT-II packages loaded on truck. As part of the analysis, the team also identified barriers to implementing rail shipments to WIPP and outlined a path forward. This report documents the findings of the study and its initial set of recommendations. As the study progressed, it was expanded to include new packages for truck as well as rail in recognition of the benefits of shipping large boxes and contaminated equipment.

Moss, J.; Luke, Dale Elden

2000-03-01T23:59:59.000Z

227

Active Desiccant Dehumidification Module Integration with Rooftop Packaged HVAC  

Science Conference Proceedings (OSTI)

This report summarizes a research and development program that produced a stand-alone active desiccant module (ADM) that can be easily integrated with new or existing packaged cooling equipment. The program also produced a fully integrated hybrid system, combining the active desiccant section with a conventional direct expansion air-conditioning unit, that resulted in a compact, low-cost, energy-efficient end product. Based upon the results of this investigation, both systems were determined to be highly viable products for commercialization. Major challenges--including wheel development, compact packaging, regeneration burner development, control optimization, and low-cost design--were all successfully addressed by the final prototypes produced and tested as part of this program. Extensive laboratory testing was completed in the SEMCO laboratory for each of the two ADM system approaches. This testing confirmed the performance of the ADM systems to be attractive compared with that of alternate approaches currently used to precondition outdoor air, where a return air path is not readily available for passive desiccant recovery or where first cost is the primary design criterion. Photographs, schematics, and performance maps are provided for the ADM systems that were developed; and many of the control advantages are discussed. Based upon the positive results of this research and development program, field tests are under way for fully instrumented pilot installations of ADM systems in both a hotel/motel and a restaurant.

Fischer, J

2002-04-17T23:59:59.000Z

228

Avoiding low frequency noise in packaged HVAC equipment  

Science Conference Proceedings (OSTI)

The purpose of this article is to help those involved in the design and commissioning of packaged HVAC systems to understand the root causes of low frequency noise problems and how to avoid many of them at the design stage. In the 1980's, two things happened to dramatically change the types of noise problems encountered in typical new construction. The first was the introduction of new energy regulations that favored variable air volume (VAV) distribution systems over constant volume air distribution systems. A by-product of VAV design is that mid- and high frequency sound pressure levels produced by current air terminal devices and diffusers in many applications are significantly lower than in the past. The second factor was a trend away from the use of built-up central station fan equipment in favor of packaged, floor-by-floor air handlers or rooftop units. As a result, today's HVAC system noise problems are not confined to just the roar and hiss of the past, but now include intense low frequency rumble and time modulation. Indeed, most current noise problems in modern buildings occur in the frequency range well below 250 Hz. A large fraction of these are a result of the dominant sound pressure levels in the 12 to 40 Hz region. These factors, combined with a substantial increase in the level of low frequency sound from the rest of the system, can produce a non-neutral, time modulated, rumbly sounding background noise that many people find objectionable.

Ebbing, C.E. (Carrier Corp., Syracuse, NY (United States). Commercial Unitary Division); Blazier, W.E.Jr. (Warren Blazier Associates, San Francisco, CA (United States))

1993-06-01T23:59:59.000Z

229

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.

230

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

231

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

232

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

233

9978 AND 9975 TYPE B PACKAGING INTERNAL DATA COLLECTION FEASIBILITY TESTING  

SciTech Connect

The objective of this report is to document the findings from a series of proof-of-concept tests performed by Savannah River National Laboratory (SRNL) R and D Engineering, for the DOE Packaging Certification Program to determine if a viable radio link could be established from within the stainless steel confines of several drum-style DOE certified Type B radioactive materials packagings. Two in-hand, off-the-shelf radio systems were tested. The first system was a Wi-Fi Librestream Onsight{trademark} camera with a Fortress ES820 Access Point and the second was the On-Ramp Wireless Ultra-Link Processing{trademark} (ULP) radio system. These radio systems were tested within the Model 9975 and 9978 Type B packagings at the SRNL. This report documents the test methods and results. A path forward will also be recommended.

Fogle, R.

2012-05-07T23:59:59.000Z

234

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

235

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

236

Grid Data Mirroring Package (GDMP)  

Science Conference Proceedings (OSTI)

The GDMP client-server software system is a generic file replication tool that replicates files securely and efficiently from one site to another in a Data Grid environment using Globus Grid tools. In addition, it manages replica catalogue entries for ...

Heinz Stockinger; Asad Samar; Shahzad Muzaffar; Flavia Donno

2002-04-01T23:59:59.000Z

237

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

238

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 projects 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

239

Design package for instrumentation of the Decade 80 House in Tucson, Arizonia  

DOE Green Energy (OSTI)

This design package covers instrumentation and system design material submitted to the George C. Marshall Space Flight Center for the Decade 80 solar house, located in Tucson, Arizona, for the purpose of gathering data to determine the solar heating and cooling system performance.

Not Available

1978-07-01T23:59:59.000Z

240

OFFICE OF HEALH, SAFETY AND SECURITY INFORMATION COLLECTION PACKAGE  

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

HEALH, SAFETY AND SECURITY HEALH, SAFETY AND SECURITY INFORMATION COLLECTION PACKAGE OMB 1910-0300: ES&H Reporting Systems Description of Collections April 10, 2012 The information obtained from DOE contractors by this information collection is used by Department management at the appropriate levels to manage the work pertaining to environment, safety and health throughout DOE and will include automated reporting of information into the following systems: Computerized Accident/Incident Reporting System (CAIRS) - The CAIRS is a database used to collect and analyze DOE and DOE contractor reports of injuries, illnesses, and other accidents that occur during DOE operations as described in DOE O 231.1B, Environment, Safety and Health Reporting. This system contains information from reporting contractors and

Note: This page contains sample records for the topic "waukesha packaged system" 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

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

242

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

243

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 ...........................................................................................................................................

244

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

245

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

246

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-

247

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

248

Evaluation Framework and Analyses for Thermal Energy Storage Integrated with Packaged Air Conditioning  

SciTech Connect

Few third-party guidance documents or tools are available for evaluating thermal energy storage (TES) integrated with packaged air conditioning (AC), as this type of TES is relatively new compared to TES integrated with chillers or hot water systems. To address this gap, researchers at the National Renewable Energy Laboratory conducted a project to improve the ability of potential technology adopters to evaluate TES technologies. Major project outcomes included: development of an evaluation framework to describe key metrics, methodologies, and issues to consider when assessing the performance of TES systems integrated with packaged AC; application of multiple concepts from the evaluation framework to analyze performance data from four demonstration sites; and production of a new simulation capability that enables modeling of TES integrated with packaged AC in EnergyPlus. This report includes the evaluation framework and analysis results from the project.

Kung, F.; Deru, M.; Bonnema, E.

2013-10-01T23:59:59.000Z

249

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

250

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

251

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

252

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

253

High Availability Instrumentation Packaging Standards for the ILC and Detectors  

Science Conference Proceedings (OSTI)

ILC designers are exploring new packaging standards for Accelerator Controls and Instrumentation, particularly high-speed serial interconnect systems for intelligent instruments versus the existing parallel backplanes of VME, VXI and CAMAC. The High Availability Advanced Telecom Computing Architecture (ATCA) system is a new industrial open standard designed to withstand single-point hardware or software failures. The standard crate, controller, applications module and sub-modules are being investigated. All modules and sub-modules are hot-swappable. A single crate is designed for a data throughput in communications applications of 2 Tb/s and an Availability of 0.99999, which translates into a downtime of five minutes per year. The ILC is planning to develop HA architectures for controls, beam instrumentation and detector systems.

Downing, R.W.; Larsen, R.S.; /SLAC

2006-11-30T23:59:59.000Z

254

Property:Component Integration | Open Energy Information  

Open Energy Info (EERE)

Component Integration Component Integration Jump to: navigation, search This is a property of type String. The allowed values for this property are: Customer Assembled Factory Integrated Pages using the property "Component Integration" Showing 22 pages using this property. D Distributed Generation Study/10 West 66th Street Corp + Customer Assembled + Distributed Generation Study/615 kW Waukesha Packaged System + Factory Integrated + Distributed Generation Study/Aisin Seiki G60 at Hooligans Bar and Grille + Customer Assembled + Distributed Generation Study/Arrow Linen + Customer Assembled + Distributed Generation Study/Dakota Station (Minnegasco) + Customer Assembled + Distributed Generation Study/Elgin Community College + Customer Assembled + Distributed Generation Study/Emerling Farm + Factory Integrated +

255

Degree project in Communication Systems  

E-Print Network (OSTI)

to the customer. Additionally, the packaging keeps the product safe from the environment and also protects S I D D I Q I Smart Card Packaging Process Control System KTH Information and Communication Technology #12;Smart Card Packaging Process Control System Saad Ahmed Siddiqi August 1, 2012 Masters Thesis

Maguire Jr., Gerald Q.

256

Assessment of microelectronics packaging for high temperature, high reliability applications  

DOE Green Energy (OSTI)

This report details characterization and development activities in electronic packaging for high temperature applications. This project was conducted through a Department of Energy sponsored Cooperative Research and Development Agreement between Sandia National Laboratories and General Motors. Even though the target application of this collaborative effort is an automotive electronic throttle control system which would be located in the engine compartment, results of this work are directly applicable to Sandia`s national security mission. The component count associated with the throttle control dictates the use of high density packaging not offered by conventional surface mount. An enabling packaging technology was selected and thermal models defined which characterized the thermal and mechanical response of the throttle control module. These models were used to optimize thick film multichip module design, characterize the thermal signatures of the electronic components inside the module, and to determine the temperature field and resulting thermal stresses under conditions that may be encountered during the operational life of the throttle control module. Because the need to use unpackaged devices limits the level of testing that can be performed either at the wafer level or as individual dice, an approach to assure a high level of reliability of the unpackaged components was formulated. Component assembly and interconnect technologies were also evaluated and characterized for high temperature applications. Electrical, mechanical and chemical characterizations of enabling die and component attach technologies were performed. Additionally, studies were conducted to assess the performance and reliability of gold and aluminum wire bonding to thick film conductor inks. Kinetic models were developed and validated to estimate wire bond reliability.

Uribe, F.

1997-04-01T23:59:59.000Z

257

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

258

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,

259

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

260

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

Note: This page contains sample records for the topic "waukesha packaged system" 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

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

262

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,

263

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

264

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

265

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:

266

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

267

Packaging and transportation-related occurrence reports - January-March 1994  

SciTech Connect

The Oak Ridge National Lab. (ORNL) Packaging and Transportation Safety Program (PATS), which is sponsored by the US Department of Energy (DOE) Office of Environment, Safety and Health Transportation and Packaging Safety Division, EH-332, has been charged with the responsibility of retrieving reports and information pertaining to transportation or packaging incidents or accidents from the Occurrence Reporting and Processing System (ORPS). These selected reports are being analyzed for trends, impact on EH-332 policies and concerns, and lessons learned concerning transportation and packaging safety. This task is designed not only to keep EH-332 aware of what is occurring on DOE sites and potential transportation and packaging problems that may need attention, but also it is intended to allow future dissemination of lessons learned to the Operations Offices and subsequently to management and operating contractors. This report, which covers the first quarter of 1994, includes the weekly tabular reports OR-91-1 through OR-94-13, which were submitted to EH-332 for its information and use. Thirteen reports containing 43 selected occurrences were transmitted during this quarter.

Welch, M.J.; Dickerson, L.S.; Jennings, S.D.

1994-06-01T23:59:59.000Z

268

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

269

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

270

Safety evaluation for packaging (onsite) nitrogen trailers propane tanks  

SciTech Connect

The purpose of the Safety Evaluation for Packaging (SEP) is the evaluation and authorization of the onsite transport of propane tanks that are mounted on the Lockheed Martin Hanford Corporation Characterization Project`s nitrogen trailers. This SEP authorizes onsite transport of the nitrogen trailers, including the propane tanks, until May 31, 1998. The three nitrogen trailers (HO-64-4966, HO-64-4968, and HO-64-5170) are rated for 1,361 kg (30,000 lb) and are equipped with tandem axles and pintel hitches. Permanently mounted on each trailer is a 5,678 L (1,500 gal) cryogenic dewar that is filled with nitrogen, and a propane fired water bath vaporizer system, and a 454 L (1 20 gal) propane tank. The nitrogen trailer system is operated only when it is disconnected from the tow vehicle and is leveled and stabilized. When the trailers are transported, the propane tanks are isolated via closed supply valves.

Ferrell, P.C.

1998-01-28T23:59:59.000Z

271

Packaging- and transportation-related occurrence reports, January--March 1995  

Science Conference Proceedings (OSTI)

Reports on transportation/packaging incidents, from the Occurrence Reporting and Processing System, are being analyzed for trends, impact on DOE EH-32 policies and concerns, and lessons learned concerning transportation and packaging safety. Besides keeping EH-32 aware of current incidents and potential problems that may need attention on DOE sites, this task allows future dissemination of lessons learned to the Operations Offices and to management and operating contractors. This report covers the weekly tabular reports OR-95-01 through OR-95-13, which contained a total of 50 occurrence reports.

Dickerson, L.S.; Welch, M.J.; Armstrong, C.J.

1995-04-01T23:59:59.000Z

272

Notice of construction for proposed backup package boiler  

Science Conference Proceedings (OSTI)

The Hanford Site steam plant consists of coal-fired boilers located at the 200 East and the 200 West Areas. These boilers have provided steam to heat and cool facilities in the 200 Areas since the early 1940`s. As part of Project L-017, ``Steam System Rehabilitation, Phase II``, the 200 West Area coal-fired boilers will be permanently shut down. The shut down will only occur after a proposed package backup boiler (50,000 pounds per hour (lb/hr) steam, firing No. 2 oil) is installed at the 200 West Area. The proposed backup boiler will provide back-up services when the 200 East Area steam line, which provides steam to the 200 West Area, is down for maintenance or, when the demand for steam exceeds the supply available from the 200 East Plant. This application is a request for approval to construct and operate the package backup boiler. This request is being made pursuant to Washington Administration Code (WAC) Chapter 173-400, ``General Regulations for Air Pollution Sources``, and Chapter 173-460, ``Controls for New Sources of Toxic Air Pollutants``.

Not Available

1993-10-01T23:59:59.000Z

273

Safety evaluation for packaging 222-S laboratory cargo tank for onetime type B material shipment  

Science Conference Proceedings (OSTI)

The purpose of this Safety Evaluation for Packaging (SEP) is to evaluate and document the safety of the onetime shipment of bulk radioactive liquids in the 222-S Laboratory cargo tank (222-S cargo tank). The 222-S cargo tank is a US Department of Transportation (DOT) MC-312 specification (DOT 1989) cargo tank, vehicle registration number HO-64-04275, approved for low specific activity (LSA) shipments in accordance with the DOT Title 49, Code of Federal Regulations (CFR). In accordance with the US Department of Energy, Richland Operations Office (RL) Order 5480.1A, Chapter III (RL 1988), an equivalent degree of safety shall be provided for onsite shipments as would be afforded by the DOT shipping regulations for a radioactive material package. This document demonstrates that this packaging system meets the onsite transportation safety criteria for a onetime shipment of Type B contents.

Nguyen, P.M.

1994-08-19T23:59:59.000Z

274

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

275

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

276

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

277

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

278

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

279

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

280

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

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


281

Depleted uranium as a backfill for nuclear fuel waste package  

DOE Patents (OSTI)

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

Forsberg, C.W.

1998-11-03T23:59:59.000Z

282

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

283

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

284

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

285

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

286

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

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

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

289

10 Solar powerplants. gas turbines packaged for offshore gas platform  

SciTech Connect

Weatherby Engineering Co. neared completion recently of 8 modules mounting a total of 9 gas turbine engines, all destined for an offshore gas injection platform. The platform capacity is 80 MMcfd. The inlet pressure on the platform is 45 psig and the discharge pressure is 3,410 psig. The system constitutes a complete gas dehydration and compressor station and the modules house the gas turbines which drive the centrifugal and reciprocating compressors for gas injection service, and 2 gas turbine-powered generating units to supply electric power for the platform complex. The gas turbines and compressors are installed in sound attenuated enclosures. These complete power packages are built up by Solar and supplied to Weatherby for the project. The complete module is described.

Alberte, T.

1976-05-01T23:59:59.000Z

290

Evaluation of Packaging Film Mechanical Integrity Using a Standardized Scratch Test  

E-Print Network (OSTI)

Polymeric packaging films see widespread use in the food packaging industry, and their mechanical integrity is paramount to maintaining product appearance, freshness, and overall food safety. Current testing methods, such as tensile or puncture tests, do not necessarily correlate well with field damages that are observed to be scratch-like. The standardized linearly increasing load scratch test is investigated as a new means of evaluating the mechanical integrity of packaging films. Mechanical clamp and vacuum fixtures were considered for securing the films to a set of backing materials and tested under various testing rates and film orientation conditions. Film performance was evaluated according to their puncture load. Based on the above study, the vacuum fixture offers the most consistent and meaningful results by providing a more intimate contact between film and backing and minimizing uncontrolled buckling of the film during testing. Additional testing was also carried out on a commercial film to confirm similarity between damage observed in the scratched films and that from the field. The scratch test gives good correlation between field performance and scratch test results on a set of commercial films. The usefulness of the scratch test methodology for packaging film mechanical integrity evaluation is discussed. Scratch-induced damages on multi-layer commercial packaging films are investigated using cross- and longitudinal-sectioning. Scratch test results show clear distinction between the two tested systems on both the inside and outside surfaces. Microscopy was performed to investigate the feasibility of utilizing this methodology as a tool for packaging film structure evaluation by determining the effect each layer has on the resistance of scratch damages. It is shown that the film showing superior scratch test results also shows significantly better stress distribution through its layers during the scratch test, as well as better layer adhesion during severe deformation. The scratch test shows good ability to provide more in-depth film mechanical integrity testing by allowing for layer-by-layer analysis of damages and layer adhesion after testing.

Hare, Brian

2011-08-01T23:59:59.000Z

291

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

292

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...

293

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

294

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

295

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...

296

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...

297

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.

298

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...

299

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

300

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 "waukesha packaged system" 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

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...

302

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...

303

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

304

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...

305

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...

306

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...

307

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

308

Plastic packaging and burn-in effects on ionizing dose response in CMOS microcircuits  

Science Conference Proceedings (OSTI)

Results are reported from an investigation of the effects of packaging and burn-in on the post-irradiation performance of National Semiconductor 54AC02 Quad 2-input NOR gates. The test population was drawn from a single wafer fabricated in the National process qualified under Mil-Prf-38535 to an ionizing radiation hardness of 100 krads(Si). The test sample was divided between plastic and ceramic packages. Additionally, half of the plastic samples and half of the two ceramic samples received a 168 hour/125 C burn-in. Two irradiation schemes were used. The first followed Mil-Std-883 Method 1019.4 (dose rate = 50 rads(Si)/s). The second used a low dose rate (0.1 rads(Si)/s). AC, DC, transfer function and functional behavior were monitored throughout the tests. Significant differences among the package types and burn-in variations were noted with the plastic, burned-in components demonstrating enhanced degradation. They show the worst post-irradiation parameter values as well as very broad post-irradiation parameter distributions. Degradation is highly dependent upon dose rate and anneal conditions. Two different radiation induced leakage paths have been identified, and their characteristics have been correlated to variations in high dose rate and low dose rate circuit performance. Caution is recommended for system developers to ensure that radiation hardness characterization is performed for the same package/burn-in configuration to be used in the system.

Clark, S.D.; Bings, J.P. [Naval Surface Warfare Center, Crane, IN (United States). Crane Div.; Maher, M.C.; Williams, M.K.; Alexander, D.R.; Pease, R.L.

1995-12-01T23:59:59.000Z

309

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

310

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

311

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

312

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

313

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

314

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

315

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

316

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

317

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

318

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

319

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

320

Technical considerations for evaluating substantially complete containment of high-level waste within the waste package  

SciTech Connect

This report deals with technical information that is considered essential for demonstrating the ability of the high-level radioactive waste package to provide substantially complete containment'' of its contents (vitrified waste form or spent light-water reactor fuel) for a period of 300 to 1000 years in a geological repository environment. The discussion is centered around technical considerations of the repository environment, materials and fabrication processes for the waste package components, various degradation modes of the materials of construction of the waste packages, and inspection and monitoring of the waste package during the preclosure and retrievability period, which could begin up to 50 years after initiation of waste emplacement. The emphasis in this report is on metallic materials. However, brief references have been made to other materials such as ceramics, graphite, bonded ceramic-metal systems, and other types of composites. The content of this report was presented to an external peer review panel of nine members at a workshop held at the Center for Nuclear Waste Regulatory Analyses (CNWRA), Southwest Research Institute, San Antonio, Texas, April 2--4, 1990. The recommendations of the peer review panel have been incorporated in this report. There are two companion reports; the second report in the series provides state-of-the-art techniques for uncertainty evaluations. 97 refs., 1 fig.

Manaktala, H.K. (Southwest Research Inst., San Antonio, TX (USA). Center for Nuclear Waste Regulatory Analyses); Interrante, C.G. (Nuclear Regulatory Commission, Washington, DC (USA). Div. of High-Level Waste Management)

1990-12-01T23:59:59.000Z

Note: This page contains sample records for the topic "waukesha packaged system" 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

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

322

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

323

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

324

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

325

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

326

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

327

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

328

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

329

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

330

Instrumentation package for a shrouded SWERVE/EPW rocket sled test  

SciTech Connect

A shrouded SWERVE test vehicle was instrumented and tested at MACH 3. The instrumentation consisted of accelerometers, pressure transducers, and event markers arranged in a nine-channel configuration. Data from the instrumentation were transmitted from the vehicle through an FM/FM telemetry system. Two fire sets and their associated command and controls were also included in this package. The event was recorded on high-speed color film, and the trajectory data were recorded by a laser tracker.

Garavaglia, E.G.

1987-08-01T23:59:59.000Z

331

Guidelines for Trial Use of Leading Indicators of Human Performance: The Human Performance Assistance Package  

Science Conference Proceedings (OSTI)

This report documents ongoing research and the results of two projects, Leading Indicators of Human Performance and Corrective Action Selection System. These projects have created the following products available to EPRI-member utilities: this report and two software programs with user manuals, Proactive Assessment of Organizational and Workplace Factors (PAOWF) and Corrective Action Research and Evaluation (CARE). Together, these elements constitute the Human Performance Assistance Package (HPAP).

2000-09-26T23:59:59.000Z

332

Irradiated integrated circuits dose-attenuation mapping using optically stimulated phosphors for packaging dosimetry  

Science Conference Proceedings (OSTI)

The feasibility of a dose mapping system using Optically Stimulated Luminescent (OSL) Phosphors is demonstrated. The OSL technique is briefly reviewed as well as its interest for calculation codes calibration. The sensors and the reading apparatus are presented. An example of attenuation dose map obtained for a Dual In Line Plastic Package (DIL) is given and the results compared to calculations with the code EGS4 PRESTA. Results obtained by experiment and simulation are discussed as well as the potentialities of the method.

Dusseau, L.; Polge, G.; Albert, L.; Magnac, Y.; Fesquet, J.; Gasiot, J. [Univ. Montpellier II (France); Bessiere, J.C. [CORAD P.I.T. Pompignane, Montpellier (France)

1998-12-01T23:59:59.000Z

333

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

334

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

335

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

336

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

337

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

338

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

339

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

340

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

Note: This page contains sample records for the topic "waukesha packaged system" 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

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

342

Stress Corrosion Cracking of the Drip Shield, the Waste Package Outer Barrier, and the Stainless Steel Structural Material  

Science Conference Proceedings (OSTI)

Stress corrosion cracking is one of the most common corrosion-related causes for premature breach of metal structural components. Stress corrosion cracking is the initiation and propagation of cracks in structural components due to three factors that must be present simultaneously: metallurgical susceptibility, critical environment, and static (or sustained) tensile stresses. This report was prepared according to ''Technical Work Plan for: Regulatory Integration Modeling and Analysis of the Waste Form and Waste Package'' (BSC 2004 [DIRS 171583]). The purpose of this report is to provide an evaluation of the potential for stress corrosion cracking of the engineered barrier system components (i.e., the drip shield, waste package outer barrier, and waste package stainless steel inner structural cylinder) under exposure conditions consistent with the repository during the regulatory period of 10,000 years after permanent closure. For the drip shield and waste package outer barrier, the critical environment is conservatively taken as any aqueous environment contacting the metal surfaces. Appendix B of this report describes the development of the SCC-relevant seismic crack density model (SCDM). The consequence of a stress corrosion cracking breach of the drip shield, the waste package outer barrier, or the stainless steel inner structural cylinder material is the initiation and propagation of tight, sometimes branching, cracks that might be induced by the combination of an aggressive environment and various tensile stresses that can develop in the drip shields or the waste packages. The Stainless Steel Type 316 inner structural cylinder of the waste package is excluded from the stress corrosion cracking evaluation because the Total System Performance Assessment for License Application (TSPA-LA) does not take credit for the inner cylinder. This document provides a detailed description of the process-level models that can be applied to assess the performance of Alloy 22 (used for the waste package outer barrier) and Titanium Grade 7 (used for the drip shield) that are subjected to the effects of stress corrosion cracking. The use of laser peening or other residual stress mitigation techniques is considered as a means of mitigating stress corrosion cracking in the waste package final closure lid weld.

G. Gordon

2004-10-13T23:59:59.000Z

343

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)...

344

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.

345

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

346

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

347

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

348

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 ...

349

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 ...

350

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

351

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

352

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

353

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

354

DIFFERENCES AND SIMILARITIES IN ANDRA'S ASSESSMENT OF ACTIVITIES CARRIED OUT BY RADIOACTIVE WASTE GENERATORS AND AFFECTING THE QUALITY OF IL-LL SHORT-LIVED WASTE PACKAGES AND HL-IL LONG-LIVED WASTE PACKAGES  

Science Conference Proceedings (OSTI)

In both cases of packages for either low-level and intermediate-level short-lived (LL-IL/SL) or high-level and intermediate-level long-lived (HL-IL/LL) radioactive waste, Andra has defined a quality reference system, manages it, follows up its appropriate implementation in production plants and verifies its effectiveness in production. The purpose of such a reference system is to ensure, in the first case, that waste packages comply with the Centre de l'Aube's acceptance criteria and, in the second case, that the characteristics submitted by the waste generators to Andra as input data for the deep geological repository project reflect the actual production conditions. In that context, the three management steps of the quality reference system include differences due to the fact that HL-IL/SL packages have not been submitted yet to any technical acceptance criterion. Compliance with any such criterion should be the subject of a characterization report during the qualification phase and of a examination during the verification phase. The management of the quality reference system also involves similarities that facilitate the joint work carried out by Andra with the waste generators, especially in the facilities where both package types are produced.

Trentesaux, C.; Cairon, P.; Dumont, J.-N.; Felix, B.; Losada, F.

2003-02-27T23:59:59.000Z

355

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

356

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

357

A survey of packages for large linear systems  

E-Print Network (OSTI)

Technical Report SAND99-8231, Sandia National Laboratories,Technical Report SAND95- 1559, Sandia National Laboratories,a group of scientists from Sandia National Laboratories, Ray

Wu, Kesheng; Milne, Brent

2000-01-01T23:59:59.000Z

358

The Plutonium Stabilization andPackaging System at the Rocky...  

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

Technology Site (Rocky Flats) produced nuclear weapons components for the Department of Energy. In January 1992, the primary mission of the site changed from nuclear weapons...

359

Techniques and Facilities for Handling and Packaging Tritiated Liquid Wastes for Burial  

SciTech Connect

Methods and facilities have been developed for the collection, storage, measurement, assay, solidification, and packaging of tritiated liquid wastes (concentrations up to 5 Ci/ml) for disposal by land burial. Tritium losses to the environment from these operations are less than 1 ppm. All operations are performed in an inert gas-purged glovebox system vented to an effluent removal system which permits nearly complete removal of tritium from the exhaust gases prior to their dischardge to the environment. Waste oil and water from tritium processing areas are vacuum-transferred to glovebox storage tanks through double-walled lines. Accommodations are also available for emptying portable liquid waste containers and for removing tritiated water from molecular sieve beds with heat and vacuum. The tritium concentration of the collected liquids is measured by an in-line calorimeter. A low-volume metering pump is used to transfer liquids from holding tanks to heavy walled polyethylene drums filled with an absorbent or cement for solidification. Final packaging of the sealed polyethylene drums is in either an asphalt-filled combination 30- and 55- gallon metal drum package or a 30-gallon welded stainless steel container.

Rhinehammer, T. B.; Mershad, E. A.

1974-06-01T23:59:59.000Z

360

Evaluation and compilation of DOE waste package test data: Biannual report, August 1986-January 1987  

Science Conference Proceedings (OSTI)

This report summarizes results of the National Bureau of Standards (NBS) evaluations of Department of Energy (DOE) activities on waste packages designed for containment of radioactive high-level nuclear waste (HLW). The waste package is a proposed engineered barrier that is part of a permanent repository for HLW. Metal alloys are the principal barriers within the engineered system. Technical discussions are given for the corrosion of metals proposed for the canister, particularly carbon and stainless steels, and copper. In the section on tuff, the current level of understanding of several canister materials is questioned. Within the Basalt Waste Isolation Project (BWIP) section, discussions are given on problems concerning groundwater, materials for use in the metallic overpack, and diffusion through the packing. For the proposed salt site, questions are raised on the work on both ASTM A216 Steel and Ti-Code 12. NBS work related to the vitrification of HLW borosilicate glass at the West Valley Demonstration Project (WVDP) and the Defense Waste Processing Facility (DWPF) is covered. NBS reviews of selected DOE technical reports and a summary of current waste-package activities of the Materials Characterization Center (MCC) is presented. Using a database management system, a computerized database for storage and retrieval of reviews and evaluations of HLW data has been developed and is described. 17 refs., 2 figs., 2 tabs.

Interrante, C.; Escalante, E.; Fraker, A.; Harrison, S.; Shull, R.; Linzer, M.; Ricker, R.; Ruspi, J.

1987-10-01T23:59:59.000Z

Note: This page contains sample records for the topic "waukesha packaged system" 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

Demands placed on waste package performance testing and modeling by some general results on reliability analysis  

Science Conference Proceedings (OSTI)

Waste packages for a US nuclear waste repository are required to provide reasonable assurance of maintaining substantially complete containment of radionuclides for 300 to 1000 years after closure. The waiting time to failure for complex failure processes affecting engineered or manufactured systems is often found to be an exponentially-distributed random variable. Assuming that this simple distribution can be used to describe the behavior of a hypothetical single barrier waste package, calculations presented in this paper show that the mean time to failure (the only parameter needed to completely specify an exponential distribution) would have to be more than 10{sub 7} years in order to provide reasonable assurance of meeting this requirement. With two independent barriers, each would need to have a mean time to failure of only 10{sup 5} years to provide the same reliability. Other examples illustrate how multiple barriers can provide a strategy for not only achieving but demonstrating regulatory compliance.

Chesnut, D.A.

1991-09-01T23:59:59.000Z

362

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 instruments 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

363

Detecting corrosion in plastic encapsulated micro-electronics packages  

Science Conference Proceedings (OSTI)

In the past, most defense microelectronics components were packaged in ceramic, hermetic enclosures. PEMs are not hermetic because the plastic molding compounds are permeable to moisture. This lack of hermeticity creates an unknown liability, especially with respect to corrosion of the metallization features. This potential liability must be addressed to ensure long-term reliability of these systems is maintained under conditions of long-term dormant storage. However, the corrosion process is difficult to monitor because it occurs under the encapsulating plastic and is therefore not visible. The authors have developed techniques that allow them to study corrosion of Al bondpads and traces under relevant atmospheric corrosion conditions. The cornerstone of this capability is the ATC 2.6, a microelectronic test device designed at Sandia National Laboratories. Corrosion tests were performed by exposing test chips to aggressive environments. The electrical response of the ATC indicated an increase in bondpad resistance with exposure time. Note that the change in resistance is not uniform from one bondpad to another. This illustrates the stochastic nature of the corrosion process. The change in resistance correlated with visual observation of corrosion of the bondpads on the unencapsulated test chips.

Sorensen, N.R.; Braithwaite, J.W.; Peterson, D.W.; Sweet, J.N.

1998-08-01T23:59:59.000Z

364

OPERATING PROCEDURE FOR THE PORTABLE ACOUSTIC MONITORING PACKAGE (PAMP)  

Science Conference Proceedings (OSTI)

The Portable Acoustic Monitoring Package (PAMP) has been designed to record and monitor acoustic signals in high-pressure natural gas (NG) transmission lines. Of particular interest are the three acoustic signals associated with a pipeline fracture. The system is portable (less than 30 lbm) and can be used at all line pressures up to 1000 psig. The PAMP requires a shut-off valve equipped 1/2 inch NPT access port in the pipeline. It is fully functional over the typical pressure range found in the natural gas transmission pipelines in the West Virginia, Virginia, Pennsylvania, and Ohio areas. With the use of the PAMP, a full spectrum of acoustic signals can be recorded and defined in terms of acoustic energy in decibels. To detect natural gas pipeline infringements and leaks, the acoustic energy generated inside the line is monitored with a sensitive pressure-equalized microphone and a step function type {Delta}p transducer. The assembly is mounted on a 1000 psig pipe fitting-tree called the PAMP. The electronics required to record, store and analyze the data are described within this report in the format of an operating manual.

John L. Loth; Gary J. Morris; George M. Palmer; Richard Guiler; Patrick Browning

2004-08-29T23:59:59.000Z

365

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

366

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

367

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

368

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

369

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

370

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

371

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

372

Occurrence Classifications, Severity Weighting, and Normalization for the DOE Packaging and Transportation Safety Metrics Indicator Program  

SciTech Connect

The US Department of Energy (DOE) Occurrence Reporting and Processing System (ORPS) is an interactive computer system designed to support DOE-owned or -operated facilities in reporting and processing information concerning occurrences related to facility operations. The Oak Ridge National Laboratory has been charged by the DOE National Transportation Program Albuquerque (NTPA) with the responsibility of retrieving reports and information pertaining to packaging and transportation (P and T) incidents from the centralized ORPS database. These selected reports are analyzed for trends, impact on P and T operations and safety concerns, and ''lessons learned'' in P and T safety.

Dickerson, L.S.; Pope, R.B.; Michelhaugh, R.D.; Harrison, I.G.; Hermann, B.; Lester, P.B.

1999-06-01T23:59:59.000Z

373

Elucidating the role of interfacial materials properties in microfluidic packages.  

SciTech Connect

The purpose of this work was to discover a method to investigate the properties of interfaces as described by a numerical physical model. The model used was adopted from literature and applied to a commercially available multiphysics software package. By doing this the internal properties of simple structures could be elucidated and then readily applied to more complex structures such as valves and pumps in laminate microfluidic structures. A numerical finite element multi-scale model of a cohesive interface comprised of heterogeneous material properties was used to elucidate irreversible damage from applied strain energy. An unknown internal state variable was applied to characterize the damage process. Using a constrained blister test, this unknown internal state variable could be determined for an adherend/adhesive/adherend body. This is particularly interesting for laminate systems with microfluidic and microstructures contained within the body. A laminate structure was designed and fabricated that could accommodate a variety of binary systems joined using nearly any technique such as adhesive, welding (solvent, laser, ultrasonic, RF, etc.), or thermal. The adhesive method was the most successful and easy to implement but also one of the more difficult to understand, especially over long periods of time. Welding methods are meant to achieve a bond that is similar to bulk properties and so are easier to predict. However, methods of welding often produce defects in the bonds.. Examples of the test structures used to elucidate the internal properties of the model were shown and demonstrated. The real life examples used this research to improve upon current designs and aided in creating complex structures for sensor and other applications.

Edwards, Thayne L.

2013-01-01T23:59:59.000Z

374

TOPICAL REPORT ON ACTINIDE-ONLY BURNUP CREDIT FOR PWR SPENT NUCLEAR FUEL PACKAGES  

Science Conference Proceedings (OSTI)

A methodology for performing and applying nuclear criticality safety calculations, for PWR spent nuclear fuel (SNF) packages with actinide-only burnup credit, is described. The changes in the U-234, U-235, U-236, U-238, Pu-238, Pu-239, Pu-240, Pu-241, Pu-242, and Am-241 concentration with burnup are used in burnup credit criticality analyses. No credit for fission product neutron absorbers is taken. The methodology consists of five major steps. (1) Validate a computer code system to calculate isotopic concentrations of SNF created during burnup in the reactor core and subsequent decay. A set of chemical assay benchmarks is presented for this purpose as well as a method for assessing the calculational bias and uncertainty, and conservative correction factors for each isotope. (2) Validate a computer code system to predict the subcritical multiplication factor, k{sub eff}, of a spent nuclear fuel package. Fifty-seven UO{sub 2}, UO{sub 2}/Gd{sub 2}O{sub 3}, and UO{sub 2}/PuO{sub 2} critical experiments have been selected to cover anticipated conditions of SNF. The method uses an upper safety limit on k{sub eff} (which can be a function of the trending parameters) such that the biased k{sub eff}, when increased for the uncertainty is less than 0.95. (3) Establish bounding conditions for the isotopic concentration and criticality calculations. Three bounding axial profiles have been established to assure the ''end effect'' is accounted for conservatively. (4) Use the validated codes and bounding conditions to generate package loading criteria (burnup credit loading curves). Burnup credit loading curves show the minimum burnup required for a given initial enrichment. The utility burnup record is compared to this requirement after the utility accounts for the uncertainty in its record. Separate curves may be generated for each assembly design, various minimum cooling times and burnable absorber histories. (5) Verify that SNF assemblies meet the package loading criteria and confirm proper assembly selection prior to loading. A measurement of the average assembly burnup is required and that measurement must be within 10% of the utility burnup record for the assembly to be accepted. The measurement device must be accurate to within 10%. Each step is described in detail for use with any computer code system and is then demonstrated with the SCALE 4.2 computer code package using 27BURNUPLIB cross sections.

DOE

1997-04-01T23:59:59.000Z

375

Waste Package Materials Performance Peer Review | Department...  

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

Report on Dual-Purpose Canister Disposal Alternatives (FY13) A Review of Stress Corrosion CrackingFatigue Modeling for Light Water Reactor Cooling System Components Working...

376

Review of waste package verification tests. Semiannual report, April 1985-September 1985  

Science Conference Proceedings (OSTI)

Several studies were completed this period to evaluate experimental and analytical methodologies being used in the DOE waste package program. The first involves a determination of the relevance of the test conditions being used by DOE to characterize waste package component behavior in a salt repository system. Another study focuses on the testing conditions and procedures used to measure radionuclide solubility and colloid formation in repository groundwaters. An attempt was also made to evaluate the adequacy of selected waste package performance codes. However, the latter work was limited by an inability to obtain several codes from DOE. Nevertheless, it was possible to comment briefly on the structures and intents of the codes based on publications in the open literature. The final study involved an experimental program to determine the likelihood of stress-corrosion cracking of austenitic stainless steels and Incoloy 825 in simulated tuff repository environments. Tests for six-month exposure periods in water and air-steam conditions are described. 52 figs., 48 tabs.

Soo, P. (ed.)

1986-01-01T23:59:59.000Z

377

FEPs Screening of Processes and Issues in Drip Shield and Waste Package Degradation  

Science Conference Proceedings (OSTI)

The purpose of this report is to evaluate and document the inclusion or exclusion of features, events and processes (FEPs) with respect to drip shield and waste package modeling used to support the Total System Performance Assessment for License Application (TSPA-LA). Thirty-three FEPs associated with the waste package and drip shield performance have been identified (DTN: MO0407SEPFEPLA.000 [DIRS 170760]). A screening decision, either ''included'' or ''excluded,'' has been assigned to each FEP, with the technical bases for screening decisions, as required by the Nuclear Regulatory Commission (NRC) in 10 CFR 63.114 (d, e, and f) [DIRS 156605]. The FEPs analyses in this report address issues related to the degradation and potential failure of the drip shield and waste package over the post closure regulatory period of 10,000 years after permanent closure. For included FEPs, this report summarizes the disposition of the FEP in TSPA-LA. For excluded FEPs, this report provides the technical bases for the screening arguments for exclusion from TSPA-LA. The analyses are for the TSPA-LA base-case design (BSC 2004 [DIRS 168489]), where a drip shield is placed over the waste package without backfill over the drip shield (BSC 2004 [DIRS 168489]). Each FEP includes one or more specific issues, collectively described by a FEP name and description. The FEP description encompasses a single feature, event, or process, or a few closely related or coupled processes, provided the entire FEP can be addressed by a single specific screening argument or TSPA-LA disposition. The FEPs were assigned to associated Project reports, so the screening decisions reside with the relevant subject-matter experts.

K. Mon

2004-10-11T23:59:59.000Z

378

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

379

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

380

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

Note: This page contains sample records for the topic "waukesha packaged system" 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

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

382

Using Experience to Train the Next Generation of Workers | Department of  

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

Using Experience to Train the Next Generation of Workers Using Experience to Train the Next Generation of Workers Using Experience to Train the Next Generation of Workers July 5, 2011 - 1:46pm Addthis Bob Wilds working at a winding machine. | Photo Courtesy of Waukesha Electric Systems Bob Wilds working at a winding machine. | Photo Courtesy of Waukesha Electric Systems Lindsey Geisler Lindsey Geisler Public Affairs Specialist, Office of Public Affairs Bob Wilds has worked at Waukesha Electric Systems for the last 12 years as a coil winder. Waukesha Electric Systems makes transformers -- an essential part of the electric grid, transferring electrical current from one circuit to another. The coils that Bob works with are one of the most important components that make transformers work. The component involves winding insulated copper wire, but workers involved in transformer

383

Secretary Chu Discovers Transformers in Wisconsin | Department of Energy  

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

Discovers Transformers in Wisconsin Discovers Transformers in Wisconsin Secretary Chu Discovers Transformers in Wisconsin June 30, 2011 - 1:01pm Addthis Employees of the Waukesha Electric Systems give Secretary Chu a tour of the transformer manufacturing plant. | Courtesy of Waukesha Electric Systems Employees of the Waukesha Electric Systems give Secretary Chu a tour of the transformer manufacturing plant. | Courtesy of Waukesha Electric Systems Lindsey Geisler Lindsey Geisler Public Affairs Specialist, Office of Public Affairs While Americans head to the box office this weekend to check out the latest "Transformers" movie on the big screen, the Energy Department's Secretary Chu checked out a different kind of transformer being manufactured in Wisconsin. They may not be as charismatic as Optimus Prime or Bumblebee, but the

384

Packaging the Blue Gene/L supercomputer  

Science Conference Proceedings (OSTI)

As 1999 ended, IBM announced its intention to construct a one-petaflop supercomputer. The construction of this system was based on a cellular architecture--the use of relatively small but powerful building blocks used together in sufficient quantities ...

P. Coteus; H. R. Bickford; T. M. Cipolla; P. G. Crumley; A. Gara; S. A. Hall; G. V. Kopcsay; A. P. Lanzetta; L. S. Mok; R. Rand; R. Swetz; T. Takken; P. La Rocca; C. Marroquin; P. R. Germann; M. J. Jeanson

2005-03-01T23:59:59.000Z

385

One Packaging Technique of Exposed MEMS Sensors  

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

Compact SiC-based Power Converter System * Develop a high-efficiency compact power inverter based on SiC- based semiconductor technology - High efficiency, small size, and light...

386

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

387

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

388

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

389

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

390

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

391

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

392

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

393

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

394

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

395

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

396

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

397

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

398

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

399

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

400

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

Note: This page contains sample records for the topic "waukesha packaged system" 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

One Packaging Technique of Exposed MEMS Sensors  

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

High High A High - - efficiency Compact SiC efficiency Compact SiC - - based Power based Power Converter System Converter System Timothy Lin Timothy Lin Aegis Technology Inc. Aegis Technology Inc. 3300 A Westminster Ave., Santa Ana, CA 92703 3300 A Westminster Ave., Santa Ana, CA 92703 DOE STTR Phase II (DE DOE STTR Phase II (DE - - FG02 FG02 - - 05ER86234) 05ER86234) Research Institute: Research Institute: The University of Tennessee, Knoxville The University of Tennessee, Knoxville DoE Peer Review 2008, September 29 DoE Peer Review 2008, September 29 - - 30,Washington, D.C. 30,Washington, D.C. Funded by the Energy Storage Systems Program of the U.S. Department Of Energy (DOE/ESS) through the Small Business Technology Transfer (STTR) program and managed by Sandia National Laboratories (SNL). Sandia is a multi-program laboratory operated by Sandia Corporation, a Lockheed Martin Company, for the

402

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

403

Low-power, miniature {sup 171}Yb ion clock using an ultra-small vacuum package  

SciTech Connect

We report a demonstration of a very small microwave atomic clock using the 12.6 GHz hyperfine transition of the trapped {sup 171}Yb ions inside a miniature, completely sealed-off 3 cm{sup 3} ion-trap vacuum package. In the ion clock system, all of the components are highly miniaturized with low power consumption except the 369 nm optical pumping laser still under development for miniaturization. The entire clock, including the control electronics, consumes <300 mW. The fractional frequency instability of the miniature Yb{sup +} clock reaches the 10{sup -14} range after a few days of integration.

Jau, Y.-Y.; Schwindt, P. D. D. [Sandia National Laboratories, Albuquerque, New Mexico 87185 (United States); Partner, H. [Sandia National Laboratories, Albuquerque, New Mexico 87185 (United States); Center for Quantum Information and Control (CQuIC), Department of Physics and Astronomy, University of New Mexico, Albuquerque, New Mexico 87131 (United States); Prestage, J. D.; Kellogg, J. R.; Yu, N. [Jet Propulsion Laboratory, California Institute of Technology, Pasadena, California 91109 (United States)

2012-12-17T23:59:59.000Z

404

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.

405

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

406

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

407

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

408

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

409

Remark on Algorithm 702the 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.46111. 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

410

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

411

Test procedure forms for sludge retrieval and packaging  

SciTech Connect

This document provides test procedure forms for sludge retrieval and packaging tests in the 305 Cold Test Facility. The completed and approved forms provide all descriptions, criteria and analysis to safely perform sludge equipment tests in the 305 Cold Test Facility.

Feigenbutz, L.V.

1994-09-27T23:59:59.000Z

412

EXTERNAL CRITICALITY CALCULATION FOR DOE SNF CODISPOSAL WASTE PACKAGES  

SciTech Connect

The purpose of this document is to evaluate the potential for criticality for the fissile material that could accumulate in the near-field (invert) and in the far-field (host rock) beneath the U.S. Department of Energy (DOE) spent nuclear fuel (SNF) codisposal waste packages (WPs) as they degrade in the proposed monitored geologic repository at Yucca Mountain. The scope of this calculation is limited to the following DOE SNF types: Shippingport Pressurized Water Reactor (PWR), Enrico Fermi, Fast Flux Test Facility (FFTF), Fort St. Vrain, Melt and Dilute, Shippingport Light Water Breeder Reactor (LWBR), N-Reactor, and Training, Research, Isotope, General Atomics reactor (TRIGA). The results of this calculation are intended to be used for estimating the probability of criticality in the near-field and in the far-field. There are no limitations on use of the results of this calculation. The calculation is associated with the waste package design and was developed in accordance with the technical work plan, ''Technical Work Plan for: Department of Energy Spent Nuclear Fuel and Plutonium Disposition Work Packages'' (Bechtel SAIC Company, LLC [BSC], 2002a). This calculation is subject to the Quality Assurance Requirements and Description (QARD) per the activity evaluation under work package number P6212310Ml in the technical work plan TWP-MGR-MD-0000 10 REV 01 (BSC 2002a).

H. Radulescu

2002-10-18T23:59:59.000Z

413

Design package for concentrating solar collector panels  

DOE Green Energy (OSTI)

Information used to evaluate the design of the Northrup concentrating collector is presented. Included are the system performance specifications, the applications manual, and the detailed design drawings of the collector. The Northrup concentrating solar collector is a water/glycol/working fluid type, dipped galvanized steel housing, transparent acrylic Fresnel lens cover, copper absorber tube, fiber glass insulation and weighs 98 pounds. The gross collector area is about 29.4/sup 2/ per collector. A collector assembly includes four collector units within a tracking mount array.

Not Available

1978-08-01T23:59:59.000Z

414

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

415

Complex-wide representation of material packaged in 3013 containers  

SciTech Connect

The DOE sites packaging plutonium oxide materials packaged according to Department of Energy 3013 Standard (DOE-STD-3013) are responsible for ensuring that the materials are represented by one or more samples in the Materials Identification and Surveillance (MIS) program. The sites categorized most of the materials into process groups, and the remaining materials were characterized, based on the prompt gamma analysis results. The sites issued documents to identify the relationships between the materials packaged in 3013 containers and representative materials in the MIS program. These Represented documents were then reviewed and concurred with by the MIS Working Group. However, these documents were developed uniquely at each site and were issued before completion of sample characterization, small-scale experiments, and prompt gamma analysis, which provided more detailed information about the chemical impurities and the behavior of the material in storage. Therefore, based on the most recent data, relationships between the materials packaged in 3013 containers and representative materials in the MIS program been revised. With the prompt gamma analysis completed for Hanford, Rocky Flats, and Savannah River Site 3013 containers, MIS items have been assigned to the 3013 containers for which representation is based on the prompt gamma analysis results. With the revised relationships and the prompt gamma analysis results, a Master Represented table has been compiled to document the linkages between each 3013 container packaged to date and its representative MIS items. This table provides an important link between the Integrated Surveillance Program database, which contains information about each 3013 container to the MIS items database, which contains the characterization, prompt gamma data, and storage behavior data from shelf-life experiments for the representative MIS items.

Narlesky, Joshua E.; Peppers, Larry G.; Friday, Gary P.

2009-06-01T23:59:59.000Z

416

One Packaging Technique of Exposed MEMS Sensors  

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

High-efficiency Compact SiC-based Power High-efficiency Compact SiC-based Power Converter System Research Institute: The University of Tennessee, Knoxville Technical Supervisor: Stanley Atcitty, Sandia National Laboratories Timothy Lin Aegis Technology Inc. 3300 A Westminster Ave., Santa Ana, CA 92703 DoE Peer Review 2006, November 2-3,Washington, D.C. STTR (DE-FG02-05ER86234), Energy Storage Program, Department of Energy Part 1. Aegis Technology Development and fabrication in: a) thermal management & high-temperature power electronics; b) composites (e.g. nanocomposite) President Company located at a modern industry park in Santa Ana, CA, 10 miles away from University of California, Irvine * A high-technology company with design, development and manufacturing capabilities * Operation since 2002 currently with 4 Ph.D/M.S Scientists/engineers and 10 employee

417

Method of fabricating a microelectronic device package with an integral window  

DOE Patents (OSTI)

A method of fabricating a microelectronic device package with an integral window for providing optical access through an aperture in the package. The package is made of a multilayered insulating material, e.g., a low-temperature cofired ceramic (LTCC) or high-temperature cofired ceramic (HTCC). The window is inserted in-between personalized layers of ceramic green tape during stackup and registration. Then, during baking and firing, the integral window is simultaneously bonded to the sintered ceramic layers of the densified package. Next, the microelectronic device is flip-chip bonded to cofired thick-film metallized traces on the package, where the light-sensitive side is optically accessible through the window. Finally, a cover lid is attached to the opposite side of the package. The result is a compact, low-profile package, flip-chip bonded, hermetically-sealed package having an integral window.

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

2003-01-01T23:59:59.000Z

418

Thermal And Mechanical Analysis of High-power Light-emitting Diodes with Ceramic Packages  

E-Print Network (OSTI)

In this paper we present the thermal and mechanical analysis of high-power light-emitting diodes (LEDs) with ceramic packages. Transient thermal measurements and thermo-mechanical simulation were performed to study the thermal and mechanical characteristics of ceramic packages. Thermal resistance from the junction to the ambient was decreased from 76.1 oC/W to 45.3 oC/W by replacing plastic mould to ceramic mould for LED packages. Higher level of thermo-mechanical stresses in the chip were found for LEDs with ceramic packages despite of less mismatching coefficients of thermal expansion comparing with plastic packages. The results suggest that the thermal performance of LEDs can be improved by using ceramic packages, but the mounting process of the high power LEDs with ceramic packages is critically important and should be in charge of delaminating interface layers in the packages.

J. Hu; L. Yang; M. -W. Shin

2008-01-07T23:59:59.000Z

419

2011-2012 and 2013-2014 Additions and Revisions Package  

Science Conference Proceedings (OSTI)

2011-2012 Additions and Revisions + 2013 2014 Additions and Revisions package 2011-2012 and 2013-2014 Additions and Revisions Package Methods - Analyses Books Methods - Analyses Books The 2013 2014 Additions and Revisions are now av

420

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

Note: This page contains sample records for the topic "waukesha packaged system" 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

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

422

Technical Review Report for the Model 9977 Safety Analysis Report for Packaging Addendum 1 Justification for DNDO Contents  

Science Conference Proceedings (OSTI)

The Model 9977 Package is currently certified for Content Envelope C.1, {sup 238}Pu Heat Sources, either in Radioisotope Thermoelectric Generator (RTG), or in Food-Pack Can configurations, under Certificate of Compliance (CoC) Certificate Number 9977 and Package Identification Number USA/9977/B(M)F-96 (DOE). Addendum 1, Justification for DNDO Contents,--the Submittal--supplements Revision 2 of the Safety Analysis Report for Packaging for the Model 9977 Package. The Submittal adds five new contents to the Model 9977 Package, Content Envelopes, AC.1 through AC.5. The Content Envelopes are neptunium metal, the beryllium-reflected plutonium ball (BeRP Ball), plutonium/uranium metal, plutonium/uranium metal with enhanced wt% {sup 240}Pu (to 50 wt%), and uranium metal. The last three Content Envelopes are stabilized to DOE-STD-3013. These Content Envelopes will be shipped to the Device Assembly Facility (DAF) at the Nevada Test Site (NTS), where they will reside, and, hence, to off-site locations in support of the Department of Homeland Security (DHS) Domestic Nuclear Detection Office (DNDO). The new certificate will apply to a limited number of Model 9977 Packages. At the same time, the Submittal requests an extension of the periodic maintenance requirements from one (1) year to up to five (5) years using Radio-Frequency Identification (RFID) temperature-monitoring systems to measure the ambient storage temperature in order to ensure that the temperature of the Viton{reg_sign} O-rings for the 6-inch Containment Vessel (6CV) remain less than 200 F. The RFIDs have been developed by Argonne National Laboratory. An on-going surveillance program at the K-Area Materials Storage (KAMS) facility at the Savannah River Site, and an on-going examination of Viton{reg_sign} O-rings from mock Primary Containment Vessels (PCVs) at Savannah River National Laboratory (SRNL) provide the technical justification for the extension of the periodic maintenance interval. Where extended periodic maintenance is desired, the decay heat rate for the Model 9977 Package is limited to 15 watts.

West, M H

2008-12-17T23:59:59.000Z

423

Performance oriented packaging report for fuse, blasting, time, M700. Final report  

Science Conference Proceedings (OSTI)

This POP report is for the Fuse, Blasting, Time, M700 which is packaged 4000 feet/ Mil-B-2427 wood box. This report describes the results of testing conducted on a similar packaging which is used as an analogy for this item....Performance oriented packaging, POP, Fuse, Blasting, Time, M700, Mil-B-2427 Wood box.

Sniezek, F.M.

1992-11-02T23:59:59.000Z

424

The Need for a Full-Chip and Package Thermal Model for Thermally Optimized IC Designs  

E-Print Network (OSTI)

ceramic ball-grid array (CBGA) pack- age consisting of the chip (die), thermal interface material, heat to the heat spreader. The fact that detailed package information is needed to build an accurate com- pact spreader, heat sink and other layers of packaging components is shown in Fig. 1. Through this package, heat

Skadron, Kevin

425

Nuclear materials stabilization and packaging end-of-year status report, April 1--September 30, 1996  

SciTech Connect

This report documents progress on the Los Alamos Nuclear Materials Stabilization and Packaging projects for the third and fourth quarters of fiscal year 1996. It covers development and production activities for the Plutonium Packaging project, the Plutonium Recovery and Stabilization project, and the Uranium Recovery and Stabilization project. In addition, it reports on quality assurance activities for the Plutonium Packaging project.

Rink, N.A.; Aguino, V.T. [comps.

1997-02-01T23:59:59.000Z

426

CUSHOP: A SIMULATED SHOPPING ENVIRONMENT FOSTERING CONSUMER-CENTRIC PACKAGING DESIGN &  

E-Print Network (OSTI)

Consumer product packaging provides product damage protection, extends prod- uct shelf life . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 68 #12;v List of Figures Figure Page 1.1 Holistic package design should include structural, logistics. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 1.2 Graphic Communications and Packaging Science students using state-of-the-art structural

Duchowski, Andrew T.

427

Analysing the Java Package/Access Concepts in Isabelle/HOL  

E-Print Network (OSTI)

, but this internal structure only plays a role in the lookup process for a package. For accessibility concerns modifiers are described as enumeration: datatype acc-modi = Private | Package | Protected | Public an ordering on the access mod- ifiers, from most restrictive to most liberal: Private Package Protected

428

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

429

Environment on the Surfaces of the Drip Shield and Waste Package Outer Barrier  

Science Conference Proceedings (OSTI)

This report provides supporting analysis of the conditions at which an aqueous solution can exist on the drip shield or waste package surfaces, including theoretical underpinning for the evolution of concentrated brines that could form by deliquescence or evaporation, and evaluation of the effects of acid-gas generation on brine composition. This analysis does not directly feed the total system performance assessment for the license application (TSPA-LA), but supports modeling and abstraction of the in-drift chemical environment (BSC 2004 [DIRS 169863]; BSC 2004 [DIRS 169860]). It also provides analyses that may support screening of features, events, and processes, and input for response to regulatory inquiries. This report emphasizes conditions of low relative humidity (RH) that, depending on temperature and chemical conditions, may be dry or may be associated with an aqueous phase containing concentrated electrolytes. Concentrated solutions at low RH may evolve by evaporative concentration of water that seeps into emplacement drifts, or by deliquescence of dust on the waste package or drip shield surfaces. The minimum RH for occurrence of aqueous conditions is calculated for various chemical systems based on current understanding of site geochemistry and equilibrium thermodynamics. The analysis makes use of known characteristics of Yucca Mountain waters and dust from existing tunnels, laboratory data, and relevant information from the technical literature and handbooks.

T. Wolery

2005-02-22T23:59:59.000Z

430

Development and feasibility of a waste package coupled reactive transport model (AREST-CT)  

Science Conference Proceedings (OSTI)

Most models that analyze the waste package and engineered barrier system (near-field) of an underground geologic repository assume constant boundary conditions at the waste form surface and constant chemical properties of the groundwater. These models are useful for preliminary modeling, iterative modeling to estimate uncertainties, and as a source for a total systems analysis. However, the chemical behavior of the system is a very important factor in the containment and release of radionuclides, and one needs to understand the underlying processes involved. Therefore, the authors are developing a model to couple the calculation of the chemical properties with the reactive transport which can be used to assess the near-field. This report describes the models being implemented and presents some simple analyses demonstrating the feasibility of the chemical and coupled transport models.

Engel, D.W.; McGrail, B.P.; Fort, J.A.; Roberts, J.S.

1994-05-01T23:59:59.000Z

431

Waste-paper recyling in the packaging industry. January 1982-August 1989 (a Bibliography from Packaging Science and Technology Abstracts data base). Report for January 1982-August 1989  

Science Conference Proceedings (OSTI)

This 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 142 citations fully indexed and including a title list.)

Not Available

1990-03-01T23:59:59.000Z

432

EVALUATION OF THE FINAL REPORT: WASTE PACKAGE MATERIALS PERFORMANCE PEER  

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

EVALUATION OF THE FINAL REPORT: WASTE EVALUATION OF THE FINAL REPORT: WASTE PACKAGE MATERIALS PERFORMANCE PEER REVIEW PANEL B00000000-01717-5700-00005 REV 00 August 2002 This document is not an official copy and is for informational purposes only. QA: QA B00000000-01717-5700-00005 REV 00 August 2002 Evaluation of the Final Report: Waste Package Materials Performance Peer Review Panel Prepared by: Jack N. Bailey, Jack D. Cloud, Thomas E. Rodgers, and Tammy S.E. Summers Prepared for: U.S. Department of Energy Yucca Mountain Site Characterization Office P.O. Box 364629 North Las Vegas, Nevada 89036-8629 Prepared by: Bechtel SAIC Company, LLC 1180 Town Center Drive Las Vegas, Nevada 89144 Under Contract Number DE-AC28-01RW12101 Disclaimer Signature Page Change History Acknowledgments

433

Criteria for Packaging and Storing Uranium-233-Bearing Materials  

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

3028-2000 3028-2000 July 2000 DOE STANDARD CRITERIA FOR PACKAGING AND STORING URANIUM-233-BEARING MATERIALS U.S. Department of Energy AREA SAFT Washington, D.C. 20585 DISTRIBUTION STATEMENT A. Approved for public release; distribution is unlimited. TS This document has been reproduced from the best available copy. Available to DOE and DOE contractors from ES&H Technical Information Services, U.S. Department of Energy, (800) 473-4375, fax: (301) 903-9823. Available to the public from the U.S. Department of Commerce, Technology Administration, National Technical Information Service, Springfield, VA 22161; (703) 605-6000. DOE-STD-3028-2000 iii ABSTRACT This Standard provides guidance for the packaging and long-term (50 years) storage of stabilized, separated uranium-233(

434

Cermet Waste Packages Using Depleted Uranium Dioxide and Steel  

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

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

435

Stabilization, Packaging, and Storage of Plutonium-Bearing Materials  

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

DOE-STD-3013-2000 September 2000 Superseding DOE-STD-3013-99 November 1999 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 This document has been reproduced from the best available copy. Available to DOE and DOE contractors from ES&H Technical Information Services, U.S. Department of Energy, (800) 473-4375, fax: (301) 903-9823. Available to the public from the U.S. Department of Commerce, Technology Administration, National Technical Information Service, Springfield, VA 22161; (703) 605-6000. DOE-STD-3013-2000 iii ABSTRACT This Standard provides guidance for the stabilization, packaging and safe storage of plutonium-

436

Treatment, packaging, and storage of bundle scrap hardware  

SciTech Connect

A study was performed to identify and evaluate the various technical options for treatment, packaging and storing the bundle scrap hardware that results from rod consolidation. The three general scenarios addressed were keeping the treated scrap in the pool, moving it to on-site dry storage, or immediate disposal. The study concluded that practical alternatives existed for all three cases. Use of novel scrap packaging techniques achieved an overall net consolidation ratio of two. The most economical concept was found to be using advanced technology in the pool storage scenario with dry storage schemes a close second. The project also provides information on scrap characterization and provides tools to assist in classifying the scrap hardware.

Fuierer, A. (Rochester Gas and Electric Corp., NY (United States)); Dabolt, R. (Chem-Nuclear Systems, Inc., Columbia, SC (United States))

1991-09-01T23:59:59.000Z

437

Flammability Analysis For Actinide Oxides Packaged In 9975 Shipping Containers  

SciTech Connect

Packaging options are evaluated for compliance with safety requirements for shipment of mixed actinide oxides packaged in a 9975 Primary Containment Vessel (PCV). Radiolytic gas generation rates, PCV internal gas pressures, and shipping windows (times to reach unacceptable gas compositions or pressures after closure of the PCV) are calculated for shipment of a 9975 PCV containing a plastic bottle filled with plutonium and uranium oxides with a selected isotopic composition. G-values for radiolytic hydrogen generation from adsorbed moisture are estimated from the results of gas generation tests for plutonium oxide and uranium oxide doped with curium-244. The radiolytic generation of hydrogen from the plastic bottle is calculated using a geometric model for alpha particle deposition in the bottle wall. The temperature of the PCV during shipment is estimated from the results of finite element heat transfer analyses.

2013-03-21T23:59:59.000Z

438

RECERTIFICATION OF THE MODEL 9977 RADIOACTIVE MATERIAL PACKAGING  

SciTech Connect

The Model 9977 Packaging was initially issued a Certificate of Compliance (CoC) by the Department of Energys Office of Environmental Management (DOE-EM) for the transportation of radioactive material (RAM) in the Fall of 2007. This first CoC was for a single radioactive material and two packing configurations. In the five years since that time, seven Addendums have been written to the Safety Analysis Report for Packaging (SARP) and five Letter Amendments have been written that have authorized either new RAM contents or packing configurations, or both. This paper will discuss the process of updating the 9977 SARP to include all the contents and configurations, including the addition of a new content, and its submittal for recertification.

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

2013-06-05T23:59:59.000Z

439

Interactive Visualization Package for 4D Lattice Field Theories  

E-Print Network (OSTI)

Recent interest in exploring local vacuum structure of QCD through the properties of the eigenmodes of the lattice Dirac operators rises again the challenge to visualize four-dimensional objects and structures which appear in lattice field theories. In spite of complex and powerful commercial visualization software packages on the market, there are reasons to develop Interactive Visualization Package (IVP). We believe that an apprehension of the complex structures is possible only through the interactive approach, with the user being able to manipulate data representations and slices through the lattice in real-time. Further insight should also be gained by an interactive parallel examination of different physical quantities, e.g. eigenmode density with topological charge or action densities. Finally, thanks to constantly falling hardware prices, IVP makes it possible to use almost any Linux PC as a visualization tool for research in lattice field theory.

Ivan Hip

2007-10-03T23:59:59.000Z

440

Strategy for experimental validation of waste package performance assessment  

SciTech Connect

A strategy for the experimental validation of waste package performance assessment has been developed as part of a program supported by the Repository Technology Program. The strategy was developed by reviewing the results of laboratory analog experiments, in-situ tests, repository simulation tests, and material interaction tests. As a result of the review, a listing of dependent and independent variables that influence the ingress of water into the near-field environment, the reaction between water and the waste form, and the transport of radionuclides from the near-field environment was developed. The variables necessary to incorporate into an experimental validation strategy were chosen by identifying those which had the greatest effect of each of the three major events, i.e., groundwater ingress, waste package reactions, and radionuclide transport. The methodology to perform validation experiments was examined by utilizing an existing laboratory analog approach developed for unsaturated testing of glass waste forms. 185 refs., 9 figs., 2 tabs.

Bates, J.K.; Abrajano, T.A. Jr.; Wronkiewicz, D.J.; Gerding, T.J.; Seils, C.A.

1990-07-01T23:59:59.000Z

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


441

The radioactive materials packaging handbook: Design, operations, and maintenance  

Science Conference Proceedings (OSTI)

As part of its required activities in 1994, the US Department of Energy (DOE) made over 500,000 shipments. Of these shipments, approximately 4% were hazardous, and of these, slightly over 1% (over 6,400 shipments) were radioactive. Because of DOE`s cleanup activities, the total quantities and percentages of radioactive material (RAM) that must be moved from one site to another is expected to increase in the coming years, and these materials are likely to be different than those shipped in the past. Irradiated fuel will certainly be part of the mix as will RAM samples and waste. However, in many cases these materials will be of different shape and size and require a transport packaging having different shielding, thermal, and criticality avoidance characteristics than are currently available. This Handbook provides guidance on the design, testing, certification, and operation of packages for these materials.

Shappert, L.B.; Bowman, S.M. [Oak Ridge National Lab., TN (United States); Arnold, E.D. [Lockheed Martin Energy Systems, Oak Ridge, TN (United States)] [and others

1998-08-01T23:59:59.000Z

442

FAQS Job Task Analyses - NNSA Package Certification Engineer FAQS  

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

NNSA Package Certification Engineer Functional Area NNSA Package Certification Engineer Functional Area Qualification Standard DOE-STD-1026-2009 Step 1 Identify and evaluate tasks - Develop a comprehensive list of tasks that define the job. o A great starting point is the list of Duties and Responsibilities from the FAQS. o Give careful thought to additional tasks that could be considered. o Don't worry about deleting tasks at this point - that is a part of the process further down. - List the tasks (and their sources, e.g., Duties and Responsibilities #1) in the chart below. - Discuss each task as a group and come to a consensus pertaining to Importance and Frequency of the task (i.e., each team member can consent to the assigned value, even if they don't exactly agree with it).

443

Assessment of Small Reciprocating Engine Manufacturers and Generator Set Packagers  

Science Conference Proceedings (OSTI)

This report presents an overview of reciprocating engine manufacturers and packagers of generators less that 300 kW in North America, Western Europe and Japan. This includes diesel (or compression ignition) engines as well as spark ignited engines fueled by gasoline, natural gas, liquid petroleum gas, and other similar fuels. Chapter 1 provides an overview of the market for smaller reciprocating engines, including a discussion of market channels and production levels. Chapter 2 primarily lists reciprocat...

2000-12-08T23:59:59.000Z

444

Retractable pin dual in-line package test clip  

DOE Patents (OSTI)

This invention is a Dual In-Line Package (DIP) test clip for use when troubleshooting circuits containing DIP integrated circuits. This test clip is a significant improvement over existing DIP test clips in that it has retractable pins which will permit troubleshooting without risk of accidentally shorting adjacent pins together when moving probes to different pins on energized circuits or when the probe is accidentally bumped while taking measurements.

Bandzuch, Gregory S. (Washington, PA); Kosslow, William J. (Jefferson Boro, PA)

1996-01-01T23:59:59.000Z

445

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