This document updates the Version Description Document with the changes incorporated in the Revision 11.0 software installation on the Tank Monitor and Control System (TMACS).
INCOMING DOCUMENT CONTROL FORM DOCUMENT DESCRIPTION ORGANIZATIO )ATE COMPLETED: ACTION NUMBER: I ! I I DOCUMENT CONTROL DATE INITIALS DATA BASE: ACTION LOG: FILED: To : Doug Tonkay, OTS Decen From: MIchele Landis, dRW Subject: Draft report ~ Result= of the Radiologic; Former Ore Storage Site, Palmerton, Pennsylvania Attached is one copy of the draft report. PIE provide your comments to me by January 16, 1990. tlichele Landis ,9, 1989 "ey at the review and Results of the Radiological SJrvey
Revenue Requirements Modeling System (RRMS) documentation. Volume I. Methodology description and user's guide. Appendix A: model abstract; Appendix B: technical appendix; Appendix C: sample input and output. [Compustat
The Revenue Requirements Modeling System (RRMS) is a utility specific financial modeling system used by the Energy Information Administration (EIA) to evaluate the impact on electric utilities of changes in the regulatory, economic, and tax environments. Included in the RRMS is a power plant life-cycle revenue requirements model designed to assess the comparative economic advantage of alternative generating plant. This report is Volume I of a 2-volume set and provides a methodology description and user's guide, a model abstract and technical appendix, and sample input and output for the models. Volume II provides an operator's manual and a program maintenance guide.
The purpose of this facility description document (FDD) is to establish requirements and associated bases that drive the design of the Canister Handling Facility (CHF), which will allow the design effort to proceed to license application. This FDD will be revised at strategic points as the design matures. This FDD identifies the requirements and describes the facility design, as it currently exists, with emphasis on attributes of the design provided to meet the requirements. This FDD is an engineering tool for design control; accordingly, the primary audience and users are design engineers. This FDD is part of an iterative design process. It leads the design process with regard to the flowdown of upper tier requirements onto the facility. Knowledge of these requirements is essential in performing the design process. The FDD follows the design with regard to the description of the facility. The description provided in this FDD reflects the current results of the design process.
The purpose of this system description document (SDD) is to establish requirements that drive the design of the spent nuclear fuel (SNF) aging system and associated bases, which will allow the design effort to proceed. This SDD will be revised at strategic points as the design matures. This SDD identifies the requirements and describes the system design, as it currently exists, with emphasis on attributes of the design provided to meet the requirements. This SDD is an engineering tool for design control; accordingly, the primary audience and users are design engineers. This SDD is part of an iterative design process. It leads the design process with regard to the flow down of upper tier requirements onto the system. Knowledge of these requirements is essential in performing the design process. The SDD follows the design with regard to the description of the system. The description provided in the SDD reflects the current results of the design process. Throughout this SDD, the term aging cask applies to vertical site-specific casks and to horizontal aging modules. The term overpack is a vertical site-specific cask that contains a dual-purpose canister (DPC) or a disposable canister. Functional and operational requirements applicable to this system were obtained from ''Project Functional and Operational Requirements'' (F&OR) (Curry 2004 [DIRS 170557]). Other requirements that support the design process were taken from documents such as ''Project Design Criteria Document'' (PDC) (BSC 2004 [DES 171599]), ''Site Fire Hazards Analyses'' (BSC 2005 [DIRS 172174]), and ''Nuclear Safety Design Bases for License Application'' (BSC 2005 [DIRS 171512]). The documents address requirements in the ''Project Requirements Document'' (PRD) (Canori and Leitner 2003 [DIRS 166275]). This SDD includes several appendices. Appendix A is a Glossary; Appendix B is a list of key system charts, diagrams, drawings, lists and additional supporting information; and Appendix C is a list of
The purpose of this revision of the System Design Description (SDD) is to establish requirements that drive the design of the electrical support system and their bases to allow the design effort to proceed to License Application. This SDD is a living document that will be revised at strategic points as the design matures over time. This SDD identifies the requirements and describes the system design as they exist at this time, with emphasis on those attributes of the design provided to meet the requirements. This SDD has been developed to be an engineering tool for design control. Accordingly, the primary audience/users are design engineers. This type of SDD both ''leads'' and ''trails'' the design process. It leads the design process with regard to the flow down of upper tier requirements onto the system. Knowledge of these requirements is essential in performing the design process. The SDD trails the design with regard to the description of the system. The description provided in the SDD is a reflection of the results of the design process to date. Functional and operational requirements applicable to electrical support systems are obtained from the ''Project Functional and Operational Requirements'' (F&OR) (Siddoway 2003). Other requirements to support the design process have been taken from higher-level requirements documents such as the ''Project Design Criteria Document'' (PDC) (Doraswamy 2004), and fire hazards analyses. The above-mentioned low-level documents address ''Project Requirements Document'' (PRD) (Canon and Leitner 2003) requirements. This SDD contains several appendices that include supporting information. Appendix B lists key system charts, diagrams, drawings, and lists, and Appendix C includes a list of system procedures.
The purpose of this system description document (SDD) is to establish requirements that drive the design of the surface industrial heating, ventilation, and air-conditioning (HVAC) system and its bases to allow the design effort to proceed to license application. This SDD will be revised at strategic points as the design matures. This SDD identifies the requirements and describes the system design, as it currently exists, with emphasis on attributes of the design provided to meet the requirements. This SDD is an engineering tool for design control; accordingly, the primary audience and users are design engineers. This SDD is part of an iterative design process. It leads the design process with regard to the flowdown of upper tier requirements onto the system. Knowledge of these requirements is essential to performing the design process. The SDD follows the design with regard to the description of the system. The description that provided in this SDD reflects the current results of the design process.
Buck, R M; Lent, E M
This COG Software Architecture Design Description Document describes the organization and functionality of the COG Multiparticle Monte Carlo Transport Code for radiation shielding and criticality calculations, at a level of detail suitable for guiding a new code developer in the maintenance and enhancement of COG. The intended audience also includes managers and scientists and engineers who wish to have a general knowledge of how the code works. This Document is not intended for end-users. This document covers the software implemented in the standard COG Version 10, as released through RSICC and IAEA. Software resources provided by other institutions will not be covered. This document presents the routines grouped by modules and in the order of the three processing phases. Some routines are used in multiple phases. The routine description is presented once - the first time the routine is referenced. Since this is presented at the level of detail for guiding a new code developer, only the routines invoked by another routine that are significant for the processing phase that is being detailed are presented. An index to all routines detailed is included. Tables for the primary data structures are also presented.
This document updates the Version Description Document with the changes incorporated in the Revision 12.0 software installation on the Tank Monitor and Control System (TMACS).
Abstract: We present a unique approach to the design and synthesis of "giant molecules" ... Herein, "nano-atoms" refer to shape-persistent molecular nanoparticles (MNPs) with ...
This report contains document control information and abstracts for the National Renewable Energy Laboratory (NREL) subcontracted photovoltaic program publications. It also lists source information on additional publications that describe US Department of Energy (DOE) PV research activities. It is not totally exhaustive, so it lists NREL contacts for requesting further information on the DOE and NREL PV programs. This report covers the period from August 1, 1991, through July 31, 1992. The purpose of continuing this type of publication is to help people keep abreast of specific PV interests, while maintaining a balance on the costs to the PV program. The information in this report is organized under PV technology areas: Amorphous silicon research; polycrystalline thin films (including copper indium diselenide, cadmium telluride, and thin-film silicon); crystalline materials and advanced concepts (including silicon, gallium arsenide, and other group III-V materials); and PV manufacturing technology development (which may include manufacturing information for various types of PV materials).
4 Federal Register / Vol. 68, No. 79 / Thursday, April 24, 2003 / Notices j. Deadline for filing comments and/ or motions: May 19, 2003. All documents (original and eight copies) should be filed with: Magalie R. Salas, Secretary, Federal Energy Regulatory Commission, 888 First Street, NE., Washington, DC 20426. Please include the project number (P- 10855-005) on any comments or motions filed. k. Description of Request: Upper Peninsula Power Company (UPPCO) proposes to add additional acreage to
Oak Ridge Operations P.O. Box 2001 Oak Ridge, Tennessee 37831- May 2 2, 20 0 7 Dr. Ronald D. Townsend, Director Oak Ridge Institute for Science and Education Mai! Stop 22 Post Office Box I 17 Oak Ridge, Tennessee 37831-0117 Dear Dr. Townsend: CONTRACT NO. DEAC05-06OR23100, OAK RIDGE INSTITUTE FOR SCIENCE AND EDUCATION (ORISE) 10 CFR 851 WORKER SAFETY AND HEALTH PROGRAM (WSHP) DESCRIPTION DOCUMENT The ORISE WSHP submitted to us on February 26, 2007, was evaluated to provide reasonable assurance
This document is a compilation of the published, unclassified abstracts produced by mechanical engineers at Lawrence Livermore National Laboratory (LLNL) during the calendar year 1990. Many abstracts summarize work completed and published in report form. These are UCRL-JC series documents, which include the full text of articles to be published in journals and of papers to be presented at meetings, and UCID reports, which are informal documents. Not all UCIDs contain abstracts: short summaries were generated when abstracts were not included. Technical Abstracts also provides descriptions of those documents assigned to the UCRL-MI (miscellaneous) category. These are generally viewgraphs or photographs presented at meetings. An author index is provided at the back of this volume for cross referencing.
171 Federal Register / Vol. 75, No. 108 / Monday, June 7, 2010 / Notices an accessible format (e.g., braille, large print, audiotape, or computer diskette) on request to the contact person listed under FOR FURTHER INFORMATION CONTACT. Electronic Access to This Document You can view this document, as well as all other documents of this Department published in the Federal Register, in text or Adobe Portable Document Format (PDF) on the Internet at the following site: http://www.ed.gov/
Summation version Stakeholder Summation version DOE Documents Environmental Management SSAB 15 Year Anniversary Paper (presented at the Waste Management Symposium, March 4, 2009)...
Therefore, a more detailed announcement was made in the April 14, 1999, Federal Register which included a description of the proposed HCP and the EIS and included a web site ...
published in the Federal Register, in text or Adobe Portable Document Format (PDF) on the Internet at the following site: http:www.ed.gov newsfedregister. To use PDF you must...
The Code of Federal Regulations is sold by the Superintendent of Documents. Prices of new books are listed in the first FEDERAL REGISTER issue of each week. Rules and Regulations ...
... is available on the Internet through the NEPA Web site at http:www.gc.energy.govnepa. ... internet Web site at http:www.ferc.gov under the link to Documents and Filings. ...
of the Draft EIS was also published in four local and regional newspapers (in English and Spanish) and over 200 copies of the document were distributed to federal, state...
... Beth Burandt, Document Manager, Office of River Protection, U.S. Department of Energy, Post Office Box 450, Mail Stop H6-60, Richland, WA 99352, Electronic mail: TC&WMEIS@saic.com. ...
The Spent Nuclear Fuel (SNF) Project document control and records management program, as defined within this document, is based on a broad spectrum of regulatory requirements, Department of Energy (DOE) and Project Hanford and SNF Project-specific direction and guidance. The SNF Project Execution Plan, HNF-3552, requires the control of documents and management of records under the auspices of configuration control, conduct of operations, training, quality assurance, work control, records management, data management, engineering and design control, operational readiness review, and project management and turnover. Implementation of the controls, systems, and processes necessary to ensure compliance with applicable requirements is facilitated through plans, directives, and procedures within the Project Hanford Management System (PHMS) and the SNF Project internal technical and administrative procedures systems. The documents cited within this document are those which directly establish or define the SNF Project document control and records management program. There are many peripheral documents that establish requirements and provide direction pertinent to managing specific types of documents that, for the sake of brevity and clarity, are not cited within this document.
60017 Federal Register / Vol. 76, No. 188 / Wednesday, September 28, 2011 / Notices 1 Enforcement of Statutes, Orders, Rules, and Regulations, 132 FERC ¶ 61,216 (2010). Persons who wish to comment only on the environmental review of this project should submit an original and two copies of their comments to the Secretary of the Commission. Environmental commentors will be placed on the Commission's environmental mailing list, will receive copies of the environmental documents, and will be
Description Expert operators from both military and civilian bomb squads and other public safety organizations use advanced skills to maneuver Hazardous Duty Robots in challenging, ...
of Energy Docket_N._EO-05-01signedby_Secretary_Bodman-_dated_92806.PDF Docket_N._EO-05-01signedby_Secretary_Bodman-_dated_92806.PDF (104.04 KB) More Documents & Publications Department of Energy Order No. 202-07-1 Senator Dingell Letter to Secretary Bodman Support for City of Alexandria's Comments on the District of Columbia Public Service Commission, Docket No. EO-05-01
Dockets Open for Public Comment Dockets Open for Public Comment Below is a list of the dockets that are currently
This document describes the currently active and proposed infrastructure projects listed in Appendix B of the Idaho National Laboratory 2013-2022 Ten Year Site Plan (DOE/ID-11449). It was produced in accordance with Contract Data Requirements List I.06. The projects delineated in this document support infrastructure needs at INL's Research and Education Campus, Materials and Fuels Complex, Advanced Test Reactor Complex and the greater site-wide area. The projects provide critical infrastructure needed to meet current and future INL opereational and research needs. Execution of these projects will restore, rebuild, and revitalize INL's physical infrastructure; enhance program execution, and make a significant contribution toward reducing complex-wide deferred maintenance.
Womack, J.C.; Cramond, R.; Paedon, R.J.
This document is a revision to WHC-SD-SNF-SD-002, and is issued to support the individual projects that make up the Spent Nuclear Fuel Project in the lower-tier functions, requirements, interfaces, and technical baseline items. It presents results of engineering analyses since Sept. 1994. The mission of the SNFP on the Hanford site is to provide safety, economic, environmentally sound management of Hanford SNF in a manner that stages it to final disposition. This particularly involves K Basin fuel, although other SNF is involved also.
Document Details Document Number Date of Document Document Title/Description [Links below to each document] D195066340 Not listed. N/A REVISIONS IN STRATIGRAPHIC NOMENCLATURE OF COLUMBIA RIVER BASALT GROUP D196000240 Not listed. N/A EPA DENIAL OF LINER LEACHATE COLLECTION SYSTEM REQUIREMENTS D196005916 Not listed. N/A LATE CENOZOIC STRATIGRAPHY AND TECTONIC EVOLUTION WITHIN SUBSIDING BASIN SOUTH CENTRAL WASHINGTON D196025993 RHO-BWI-ST-14 N/A SUPRABASALT SEDIMENTS OF COLD CREEK SYNCLINE AREA
Abstract Template Please use this abstract template (docx) Abstract Submission Do not submit classified information to the form. First Name* Middle Name (optional) Last Name* ...
Documentation Policies, Plans, Descriptions Data Documentation Home Data Sharing and Distribution Policy Data Management and Documentation Plan Data Product Registration and ...
Prepare Your Abstract The abstract should provide a brief overview of your entire research. The abstract briefly states the research problem or purpose of the research (Introduction), how the problem was studied (Methods), what was discovered (Results), and how the results might be interpreted (Discussions and Conclusions). Acronyms may be used in an abstract, however they should be spelled out the first time they are used. Abstracts should be concise and descriptive. Symposium Abstract Format
Error and fault abstractions Mattan Erez UT Austin *Who should care about faults and errors? *Ideally, only system cares about masked faults? - Assuming application bugs are not...
19, 2007 for poster submission only). Abstract should be text only and written in good English. No figures, images, equations and special characters are allowed. The limit on the...
& DEVELOPMENT: PROGRAM ABSTRACTS Energy Efficiency and Renewable Energy Office of Transportation Technologies Office of Advanced Automotive Technologies Catalyst Layer Bipolar Plate Electrode Backing Layers INTEGRATED SYSTEMS Polymer Electrolyte Membrane Fuel Cells Fuel Cell Stack PEM STACK & STACK COMPONENTS Fuel Cell Stack System Air Management System Fuel Processor System For Transportation June 1999 ENERGY EFFICIENCY AND RENEWABLE ENERGY OFFICE OF TRANSPORTATION TECHNOLOGIES OFFICE
... Associated Changes of UV-B Solar Radiation for Subarctric ... Clouds and Earth's Radiant Energy System Terra Observations ... Shadowband Radiometer Datasets Improving GCM Aerosol ...
Freer, M. and McFarquhar, G. Algorithms for Processing Cloud Microphysical Data Acquired by Atmospheric Radiation Measurement Program Unmanned Aerospace Vehicle Applications to ...
... Approximation Model Intercomparison Project (McMIP)* Barnard, J. Dust Properties ... Beljaars, A. Validation of Global Weather Forecast and Climate Models over the North Slope ...
DocumentationData Management and Documentation Plan Policies, Plans, Descriptions Data Documentation Home Data Sharing and Distribution Policy Data Management and Documentation ...
The Assembly Transfer System (ATS) receives, cools, and opens rail and truck transportation casks from the Carrier/Cask Handling System (CCHS). The system unloads transportation casks consisting of bare Spent Nuclear Fuel (SNF) assemblies, single element canisters, and Dual Purpose Canisters (DPCs). For casks containing DPCs, the system opens the DPCs and unloads the SNF. The system stages the assemblies, transfer assemblies to and from fuel-blending inventory pools, loads them into Disposal Containers (DCs), temporarily seals and inerts the DC, decontaminates the DC and transfers it to the Disposal Container Handling System. The system also prepares empty casks and DPCs for off-site shipment. Two identical Assembly Transfer System lines are provided in the Waste Handling Building (WHB). Each line operates independently to handle the waste transfer throughput and to support maintenance operations. Each system line primarily consists of wet and dry handling areas. The wet handling area includes a cask transport system, cask and DPC preparation system, and a wet assembly handling system. The basket transport system forms the transition between the wet and dry handling areas. The dry handling area includes the dry assembly handling system, assembly drying system, DC preparation system, and DC transport system. Both the wet and dry handling areas are controlled by the control and tracking system. The system operating sequence begins with moving transportation casks to the cask preparation area. The cask preparation operations consist of cask cavity gas sampling, cask venting, cask cool-down, outer lid removal, and inner shield plug lifting fixture attachment. Casks containing bare SNF (no DPC) are filled with water and placed in the cask unloading pool. The inner shield plugs are removed underwater. For casks containing a DPC, the cask lid(s) is removed, and the DPC is penetrated, sampled, vented, and cooled. A DPC lifting fixture is attached and the cask is placed into the cask unloading pool. In the cask unloading pool the DPC is removed from the cask and placed in an overpack and the DPC lid is severed and removed. Assemblies are removed from either an open cask or DPC and loaded into assembly baskets positioned in the basket staging rack in the assembly unloading pool. A method called ''blending'' is utilized to load DCs with a heat output of less than 11.8 kW. This involves combining hotter and cooler assemblies from different baskets. Blending requires storing some of the hotter fuel assemblies in fuel-blending inventory pools until cooler assemblies are available. The assembly baskets are then transferred from the basket staging rack to the assembly handling cell and loaded into the assembly drying vessels. After drying, the assemblies are removed from the assembly drying vessels and loaded into a DC positioned below the DC load port. After installation of a DC inner lid and temporary sealing device, the DC is transferred to the DC decontamination cell where the top area of the DC, the DC lifting collar, and the DC inner lid and temporary sealing device are decontaminated, and the DC is evacuated and backfilled with inert gas to prevent prolonged clad exposure to air. The DC is then transferred to the Disposal Container Handling System for lid welding. In another cask preparation and decontamination area, lids are replaced on the empty transportation casks and DPC overpacks, the casks and DPC overpacks are decontaminated, inspected, and transferred to the Carrier/Cask Handling System for shipment off-site. All system equipment is designed to facilitate manual or remote operation, decontamination, and maintenance. The system interfaces with the Carrier/Cask Handling System for incoming and outgoing transportation casks and DPCs. The system also interfaces with the Disposal Container Handling System, which prepares the DC for loading and subsequently seals the loaded DC. The system support interfaces are the Waste Handling Building System and other internal WHB support systems.
The Canister Transfer System receives transportation casks containing large and small disposable canisters, unloads the canisters from the casks, stores the canisters as required, loads them into disposal containers (DCs), and prepares the empty casks for re-shipment. Cask unloading begins with cask inspection, sampling, and lid bolt removal operations. The cask lids are removed and the canisters are unloaded. Small canisters are loaded directly into a DC, or are stored until enough canisters are available to fill a DC. Large canisters are loaded directly into a DC. Transportation casks and related components are decontaminated as required, and empty casks are prepared for re-shipment. One independent, remotely operated canister transfer line is provided in the Waste Handling Building System. The canister transfer line consists of a Cask Transport System, Cask Preparation System, Canister Handling System, Disposal Container Transport System, an off-normal canister handling cell with a transfer tunnel connecting the two cells, and Control and Tracking System. The Canister Transfer System operating sequence begins with moving transportation casks to the cask preparation area with the Cask Transport System. The Cask Preparation System prepares the cask for unloading and consists of cask preparation manipulator, cask inspection and sampling equipment, and decontamination equipment. The Canister Handling System unloads the canister(s) and places them into a DC. Handling equipment consists of a bridge crane hoist, DC loading manipulator, lifting fixtures, and small canister staging racks. Once the cask has been unloaded, the Cask Preparation System decontaminates the cask exterior and returns it to the Carrier/Cask Handling System via the Cask Transport System. After the DC is fully loaded, the Disposal Container Transport System moves the DC to the Disposal Container Handling System for welding. To handle off-normal canisters, a separate off-normal canister handling cell is located adjacent to the canister transfer cell and is interconnected to the transfer cell by means of the off-normal canister transfer tunnel. All canister transfer operations are controlled by the Control and Tracking System. The system interfaces with the Carrier/Cask Handling System for incoming and outgoing transportation casks. The system also interfaces with the Disposal Container Handling System, which prepares the DC for loading and subsequently seals the loaded DC. The system support interfaces are the Waste Handling Building System and other internal Waste Handling Building (WHB) support systems.
The Subsurface Facility System encompasses the location, arrangement, size, and spacing of the underground openings. This subsurface system includes accesses, alcoves, and drifts. This system provides access to the underground, provides for the emplacement of waste packages, provides openings to allow safe and secure work conditions, and interfaces with the natural barrier. This system includes what is now the Exploratory Studies Facility. The Subsurface Facility System physical location and general arrangement help support the long-term waste isolation objectives of the repository. The Subsurface Facility System locates the repository openings away from main traces of major faults, away from exposure to erosion, above the probable maximum flood elevation, and above the water table. The general arrangement, size, and spacing of the emplacement drifts support disposal of the entire inventory of waste packages based on the emplacement strategy. The Subsurface Facility System provides access ramps to safely facilitate development and emplacement operations. The Subsurface Facility System supports the development and emplacement operations by providing subsurface space for such systems as ventilation, utilities, safety, monitoring, and transportation.
Abstractions: The first step towards a programmable WAN Inder Monga TIP 2013 January 15 th , 2013 Lawrence Berkeley National Laboratory U.S. Department of Energy | Office of Science Ongoing Science Revolution Data-intensive Science * Era of Big-Data' Exascale, HPC and Future Data Centers * Optics to the end 12/18/12 2 Inder Monga, OTS Demo Lawrence Berkeley National Laboratory U.S. Department of Energy | Office of Science Data Integration Bringing together big-data' from various sources Dataset
Induced fission in real-time Professor Aurel Bolgac Department of Physics, University of Washington, Seattle, Washington Abstract: Nuclear fission appears to be one of the most difficult problems in quantum many-body physics and is approaching shortly the venerable age of 80 years and it still defies efforts to arrive at a microscopic description. A quantum theory of superconductivity was developed in contrast in less than 50 years. Major progress in developing an extension of the Density
Documentation External Data Center Order Data Description of External Data Streams Data Viewers and Plots (selected data sets) XDC Documentation XDC Documentation BNL's ARM Related General Report The monthly reports on work done for the ARM Project. Description of External Data Streams Documentation of External Data-Streams includes sources, measurements, area, time-ranges, contacts, etc. External Projects Contacts Includes information on external projects covering ARM ACRF sites. Instructions
Microscopic Description of Induced Nuclear Fission Citation Details In-Document Search Title: Microscopic Description of Induced Nuclear Fission You are accessing a document ...
Poster Abstract Guidelines Poster Abstract Guidelines Poster Abstract Guidelines.pdf (343.35 KB) More Documents & Publications Call For Abstracts (Student Research Forum) 2016 U.S. Department of Energy Race to Zero Student Design Competition Guide Microsoft Word - rDE-FOA-0000080.rtf
Description Jump to: navigation, search OpenEI Reference LibraryAdd to library Web Site: BIA Description Abstract Description of Bureau of Indian Affairs. Author Bureau of Indian...
Rutkowski, R.W.; Henline, D.M.
Energy Research Abstracts (ERA) provides abstracting and indexing coverage of all scientific and technical reports and patent applications originated by the US Department of Energy, its laboratories, energy centers, and contractors, as well as theses and conference papers and proceedings issued by these organizations in report form. Audiovisual materials, computer media (magnetic tapes, diskettes, etc.), and engineering drawings are included in this definition. ERA also covers other energy information prepared in report form by federal and state government organizations, foreign governments, and domestic and foreign universities and research organizations, provided that the full text of the document has been received by OSTI. Foreign report information is obtained through the International Energy Agency's fourteen nation Energy Technology Data Exchange, the International Atomic Energy Agency's International Nuclear Information System, or nation-to-nation agreements. The purpose of this publication is to announce documents produced or obtained by DOE that are not so readily available as journal articles, books, or patents. ERA does not cover nonreport literature. The scope of ERA encompasses DOE's research, development, demonstration, and technology programs resulting from its broad charter for energy sources, supplies, safety, environmental impacts, and regulation.
Services » Environmental Justice » Call for Abstracts Call for Abstracts 2013 National Environmental Justice Conference and Training Program Call for Abstracts Please join us for the 2013 National Environmental Justice Conference and Training Program, April 3 - 5, 2013, co-located at the Howard University School of Law and the Marriott at Metro Center. Call for Abstracts (137.64 KB) More Documents & Publications CALL FOR ABSTRACTS for the 2014 National Environmental Justice Conference and
This document provides a description of the Tank Monitor and Control System (TMACS). It is intended as an introduction for those persons unfamiliar with the system as well as a reference document for the users, maintenance personnel, and system designers. In addition to describing the system, the document outlines the associated drawing documentation, provides maintenance and spare parts information, and discusses other TMACS documents that provide additional detail
abstracts highlighting research activities conducted over the past year at SSRL for oral and poster presentations at the Users' Meeting. Please use the abstract submission form...
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FTP Document Upload Website Abstract The Drinking Water and Groundwater Protection Division's (DWGPD) File Transfer Protocol (FTP) document upload website. The DWGPD is a division...
Clifford, David J.
This document contains the system specifications derived to satisfy the system requirements found in the IDC System Requirements Document for the IDC Reengineering Phase 2 project. Revisions Version Date Author/Team Revision Description Authorized by V1.0 12/2014 IDC Reengineering Project Team Initial delivery M. Harris
Detailed Course Module Description Detailed Course Module Description This document lists the course modules for building science courses offered at Cornell's Collaborator...
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The Office of Document Reviews, within the Office of Health, Safety and Security information and document declassification efforts promote the release of information needed by an informed citizenry...
Call For Abstracts (Student Research Forum) Call For Abstracts (Student Research Forum) Call For Abstracts (Student Research Forum).pdf (439.22 KB) More Documents & Publications Poster Abstract Guidelines 2015 National Environmental Justice Conference and Training Program Concludes in Washington, DC Program Update: 4th Quarter 2011
BALANCED SCORECARD PERFORMANCE MEASUREMENT AND PERFORMANCE MANAGEMENT PROGRAM FOR FEDERAL PROCUREMENT AND MANAGEMENT AND OPERATING CONTRACTOR PURCHASING SYSTEMS Revised: June 2016 ii PREFACE Over the past decade, the Department of Energy (DOE) has reengineered its programs for oversight of Federal and contractor procurement/purchasing systems, replacing Headquarters- based, process-oriented review programs with ones which rely on local assessment of performance against Departmental expectations.
... the Department of Energy Acquisition Regulation (DEAR) still requires compliance with ... DEAR Department of Energy Acquisition Regulation FASA Federal Acquisition Streamlining ...
E. F. Loros
The Disposal Container Handling System receives and prepares new disposal containers (DCs) and transfers them to the Assembly Transfer System (ATS) or Canister Transfer System (CTS) for loading. The system receives the loaded DCs from ATS or CTS and welds the lids. When the welds are accepted the DCs are termed waste packages (WPs). The system may stage the WP for later transfer or transfer the WP directly to the Waste Emplacement/Retrieval System. The system can also transfer DCs/WPs to/from the Waste Package Remediation System. The Disposal Container Handling System begins with new DC preparation, which includes installing collars, tilting the DC upright, and outfitting the container for the specific fuel it is to receive. DCs and their lids are staged in the receipt area for transfer to the needed location. When called for, a DC is put on a cart and sent through an airlock into a hot cell. From this point on, all processes are done remotely. The DC transfer operation moves the DC to the ATS or CTS for loading and then receives the DC for welding. The DC welding operation receives loaded DCs directly from the waste handling lines or from interim lag storage for welding of the lids. The welding operation includes mounting the DC on a turntable, removing lid seals, and installing and welding the inner and outer lids. After the weld process and non-destructive examination are successfully completed, the WP is either staged or transferred to a tilting station. At the tilting station, the WP is tilted horizontally onto a cart and the collars removed. The cart is taken through an air lock where the WP is lifted, surveyed, decontaminated if required, and then moved into the Waste Emplacement/Retrieval System. DCs that do not meet the welding non-destructive examination criteria are transferred to the Waste Package Remediation System for weld preparation or removal of the lids. The Disposal Container Handling System is contained within the Waste Handling Building System. This includes the primary hot cell bounded by the receiving area and WP transport exit air locks; and isolation doors at ATS, CTS, and Waste Package Remediation. The hot cell includes areas for welding, various staging, tilting, and WP transporter loading. There are associated operating galleries and equipment maintenance areas outside the hot cell. These areas operate concurrently to accommodate the DC/WP throughput rates and support system maintenance. The new DC preparation area is located in an unshielded structure. The handling equipment includes DC/WP bridge cranes, tilting stations, and horizontal transfer carts. The welding area includes DC/WP welders and staging stations. Welding operations are supported by remotely operated equipment including a bridge crane and hoists, welder jib cranes, welding turntables, and manipulators. WP transfer includes a transfer/decontamination and transporter load area. The transfer operations are supported by a remotely operated horizontal lifting system, decontamination system, decontamination and inspection manipulator, and a WP horizontal transfer cart. All handling operations are supported by a suite of fixtures including collars, yokes, lift beams, and lid attachments. Remote equipment is designed to facilitate decontamination and maintenance. Interchangeable components are provided where appropriate. Set-aside areas are included, as required, for fixtures and tooling to support off-normal and recovery operations. Semi-automatic, manual, and backup control methods support normal, maintenance, and recovery operations. The system interfaces with the ATS and CTS to provide empty and receive loaded DCs. The Waste Emplacement/Retrieval System interfaces are for loading/unloading WPs on/from the transporter. The system also interfaces with the Waste Package Remediation System for DC/WP repair. The system is housed, shielded, supported, and has ventilation boundaries by the Waste Handling Building (WHB). The system is ventilated by the WHB Ventilation System, which in conjunction with ventilation boundaries ensure that ai
The Waste Package Remediation System remediates waste packages (WPs) and disposal containers (DCs) in one of two ways: preparation of rejected DC closure welds for repair or opening of the DC/WP. DCs are brought to the Waste Package Remediation System for preparation of rejected closure welds if testing of the closure weld by the Disposal Container Handling System indicates an unacceptable, but repairable, welding flaw. DC preparation of rejected closure welds will require removal of the weld in such a way that the Disposal Container Handling System may resume and complete the closure welding process. DCs/WPs are brought to the Waste Package Remediation System for opening if the Disposal Container Handling System testing of the DC closure weld indicates an unrepairable welding flaw, or if a WP is recovered from the subsurface repository because suspected damage to the WP or failure of the WP has occurred. DC/WP opening will require cutting of the DC/WP such that a temporary seal may be installed and the waste inside the DC/WP removed by another system. The system operates in a Waste Package Remediation System hot cell located in the Waste Handling Building that has direct access to the Disposal Container Handling System. One DC/WP at a time can be handled in the hot cell. The DC/WP arrives on a transfer cart, is positioned within the cell for system operations, and exits the cell without being removed from the cart. The system includes a wide variety of remotely operated components including a manipulator with hoist and/or jib crane, viewing systems, machine tools for opening WPs, and equipment used to perform pressure and gas composition sampling. Remotely operated equipment is designed to facilitate DC/WP decontamination and hot cell equipment maintenance, and interchangeable components are provided where appropriate. The Waste Package Remediation System interfaces with the Disposal Container Handling System for the receipt and transport of WPs and DCs. The Waste Handling Building System houses the system, and provides the facility, safety, and auxiliary systems required to support operations. The system receives power from the Waste Handling Building Electrical System. The system also interfaces with the various DC systems.
The INL Wind Farm project proposes to install a 20 MW to 40 MW wind farm on government property, consisting of approximately ten to twenty full-sized (80-meter hub height) towers with 2 MW turbines, and access roads. This includes identifying the optimal turbine locations, building access roads, and pouring the tower foundations in preparation for turbine installation. The project successfully identified a location on INL lands with commercially viable wind resources (i.e., greater than 11 mph sustained winds) for a 20 to 40 MW wind farm. Additionally, the proposed Wind Farm was evaluated against other General Plant Projects, General Purpose Capital Equipment projects, and Line Item Construction Projects at the INL to show the relative importance of the proposed Wind Farm project.
The Waste Emplacement/Retrieval System transports Waste Packages (WPs) from the Waste Handling Building (WHB) to the subsurface area of emplacement, and emplaces the WPs once there. The Waste Emplacement/Retrieval System also, if necessary, removes some or all of the WPs from the underground and transports them to the surface. Lastly, the system is designed to remediate abnormal events involving the portions of the system supporting emplacement or retrieval. During emplacement operations, the system operates on the surface between the WHB and North Portal, and in the subsurface in the North Ramp, access mains, and emplacement drifts. During retrieval or abnormal conditions, the operations areas may also extend to a surface retrieval storage site and South Portal on the surface, and the South Ramp in the subsurface. A typical transport and emplacement operation involves the following sequence of events. A WP is loaded into a WP transporter at the WHB, and coupled to a pair of transport locomotives. The locomotives transport the WP from the WHB, down the North Ramp, and to the entrance of an emplacement drift. Once docked at the entrance of the emplacement drift, the WP is moved outside of the WP transporter, and engaged by a WP emplacement gantry. The WP emplacement gantry lifts the WP, and transports it to its emplacement location, where the WP is then lowered to its final resting position. The WP emplacement gantry remains in the drift while the WP transporter is returned to the WHB by the locomotives. When the transporter reaches the WHB, the sequence of operations is repeated. Retrieval of all the WPs, or a large group of WPs, under normal conditions is achieved by reversing the emplacement operations. Retrieval of a small set of WPs, under normal or abnormal conditions, is known as recovery. Recovery performed under abnormal conditions will involve a suite of specialized equipment designed to perform a variety of tasks to enable the recovery process. Recovery after abnormal events may require clearing of equipment, rock, and ground support to facilitate recovery operations. Stabilization of existing ground support and installation of new ground support may also be needed. Recovery of WP(s) after an event that has contaminated drifts and/or WPs will require limiting the spread of contamination. Specialized equipment will also be necessary for system restoration (e.g., after a derailment, component failure). The Waste Emplacement/Retrieval System interfaces with the Subsurface Facility System and Ground Control System for the size and layout of the underground openings. The system interfaces with the Subsurface Ventilation System for the emplacement drift operating environment and the size of the drift isolation doors. The system interfaces with all WP types for the size, weight, and other important parameters affecting emplacement, recovery, and retrieval. The system interfaces with the Subsurface Emplacement Transportation System for the rail system upon which it operates and the distribution of power through the rail system. The system interfaces with the Monitored Geologic Repository (MGR) Operations Monitoring and Control System for the transmission of data to and from the system equipment, and for remote control of system equipment. The system interfaces with the Ground Control System for any repairs that are made. The system interfaces with the Emplacement Drift System for the WP emplacement mode and hardware. The system interfaces with the Disposal Container Handling System and the Waste Handling Building System for the receipt (during emplacement) and delivery (during retrieval/recovery) of WPs.
The Waste Emplacement/Retrieval System transports Waste Packages (WPs) from the Waste Handling Building (WHB) to the subsurface area of emplacement, and emplaces the WPs once there. The system also, if necessary, removes some or all of the WPs from the underground and transports them to the surface. Lastly, the system is designed to remediate abnormal events involving the portions of the system supporting emplacement or retrieval. During emplacement operations, the system operates on the surface between the WHB and North Portal, and in the subsurface in the North Ramp, access mains, and emplacement drifts. During retrieval or abnormal conditions, the operations areas may also extend to a surface retrieval storage site and South Portal on the surface, and the South Ramp in the subsurface. A typical transport and emplacement operation involves the following sequence of events. A WP is loaded into a WP transporter at the WHB, and coupled to a pair of transport locomotives. The locomotives transport the WP from the WHB, down the North Ramp, and to the entrance of an emplacement drift. Once docked at the entrance of the emplacment drift, the WP is moved outside of the WP transporter, and engaged by a WP emplacement gantry. The gantry lifts the WP, and transports it to its emplacement location, where the WP is then lowered to its final resting position. The gantry remains in the drift while the WP transporter is returned to the WHB by the locomotives. When the transporter reaches the WHB, the sequence of operations is repeated. Retrieval of all the WPs, or a large group of WPs, under normal conditions is achieved by reversing the emplacement operations. Retrieval of a small set of WPs, under normal or abnormal conditions, is known as recovery. Recovery performed under abnormal conditions will involve a suite of specialized equipment designed to perform a variety of tasks to enable the recovery process. Recovery after abnormal events may require clearing of equipment, rock, and ground support to facilitate recovery operations. Stabilization of existing ground support and installation of new ground support may also be needed. Recovery of WPs after an event that has contaminated drifts and/or WPs will require limiting the spread of contamination. Specialized equipment will also be necessary for system restoration. The system interfaces with the Subsurface Facility System and Ground Control System for the size and layout of the underground openings. The system interfaces with the Subsurface Ventilation System for the emplacement drift operating environment and the size of the drift isolation doors. The system interfaces with all WP types for the size, weight, and other important parameters affecting emplacement, recovery, and retrieval. The system interfaces with the Subsurface Emplacement Transportation System for the rail system upon which it operates and the distribution of power throuch the rail system. The system interfaces with the Monitored Geologic Repository (MGR) Operations Monitoring and Control System for the transmission of data to and from the system equipment, and for remote control of system equipment. The system interfaces with the Ground Control System for any repairs that are made. The system interfaces with the Emplacement Drift System for the WP emplacement mode and hardware. The system interfaces with the Disposal Container Handling System and the Waste Handling Building System for the receipt (during emplacement) and delivery (during retrieval/recovery) of WPs.
... to ensure the: (1) Acquisition of quality products and services at fair and reasonable prices; (2) Use of capable and reliable subcontractors who either (i) Have track records ...
The Site Electrical Power System receives and distributes utility power to all North Portal site users. The major North Portal users are the Protected Area including the subsurface facility and Balance of Plant areas. The system is remotely monitored and controlled from the Surface Operations Monitoring and Control System. The system monitors power quality and provides the capability to transfer between Off-Site Utility and standby power (including dedicated safeguards and security power). Standby power is only distributed to selected loads for personnel safety and essential operations. Security power is only distributed to essential security operations. The standby safeguards and security power is independent from all other site power. The system also provides surface lighting, grounding grid, and lightning protection for the North Portal. The system distributes power during construction, operation, caretaker, and closure phases of the repository. The system consists of substation equipment (disconnect switches, breakers, transformers and grounding equipment) and power distribution cabling from substation to the north portal switch gear building. Additionally, the system includes subsurface facility substation (located on surface), switch-gear, standby diesel generators, underground duct banks, power cables and conduits, switch-gear building and associated distribution equipment for power distribution. Each area substation distributes power to the electrical loads and includes the site grounding, site lighting and lightning protection equipment. The site electrical power system distributes power of sufficient quantity and quality to meet users demands. The Site Electrical Power System interfaces with the North Portal surface systems requiring electrical power. The system interfaces with the Subsurface Electrical Distribution System which will supply power to the underground facilities from the North Portal. Power required for the South Portal and development side activities of the subsurface facility will be provided at the South Portal by the Subsurface Electrical Distribution System. The Site Electrical Power System interfaces with the Off-Site Utility System for the receipt of power. The System interfaces with the Surface Operations Monitoring and Control System for monitoring and control. The System interfaces with MGR Site Layout System for the physical location of equipment and power distribution.
major contractors, have an enabling or a constraining role, but will rarely be the primary objective for business systems. Success for such organizations should be measured by...
abstracts highlighting research activities conducted over the past year at SSRL for oral or poster presentation at the meeting. Posters will be displayed throughout the meeting...
Abstract Submission Process Focusing on methods and computational tools used to help sequence, assemble, and finish genomes, including new sequencing technologies. Contact Shannon...
This volume provides abstracts of presentations made at the Sixteenth Meeting of The Bioelectromagnetics Society held June 12-17, 1994 in Copenhagen, Denmark.
Theory Matches Experiment and More Citation Details In-Document Search Title: Kinetics of the Hydrogen Atom Abstraction Reactions from 1-Butanol by Hydroxyl Radical: Theory ...
advanced logistical systems and focused bioenergy harvesting technologies that supply crop ... More Documents & Publications ABSTRACT: Bioenergy Harvesting Technologies to Supply Crop ...
RELEASE FORM C (1) Document Number: RPP-RPT-431 74 (2) Revision Number: (3) Effective Date: 9/30/2009 (4) Document Type: El Digital Image El Hard copy (a) Number of pages (including the DRF) or 107 E PDF E] Video number of digital images (5) Release Type 0 New El Cancel El Page Change El complete Revision (6) Document Title: 2009 Auto-TOR for Tank 241 -T-204 (7) Change/Release Initial Issuance Description: (8) Change Initial Issuance Justification: (9) Associated (a) Structure Location: (c)
Testbed Description Network R&D Overview Experimental Network Testbeds 100G SDN Testbed Testbed Description Testbed Results Proposal Process Terms and Conditions Dark Fiber Testbed...
This volume contains 571 abstracts of contributed papers to be presented during the Twelfth US National Congress of Applied Mechanics. Abstracts are arranged in the order in which they fall in the program -- the main sessions are listed chronologically in the Table of Contents. The Author Index is in alphabetical order and lists each paper number (matching the schedule in the Final Program) with its corresponding page number in the book.
the PI controller gains in the generic WECC photovoltaic power plant have on the system modes. Key Words - Generic photovoltaic model, photovoltaic power plant (PVPP), root locus. ...
since 2009 5 U.S.C. § 552 10 CFR 1004 Other Documents Transuranic Waste Defense Determination Approval Form
Large file size alert This symbol means the document may be a large file size. Environmental Monitoring Documents about environmental monitoring at WIPP, including annual site environmental reports Environmental Protection Agency Certification Documents about WIPP's EPA certification Federal Regulations Standards and compliance criteria for WIPP Hazardous Waste Facility Permit Documents related to the state of New Mexico's oversight of WIPP under the authority of the Resource Conservation and
Submit Ober Abstracts All project abstracts should be submitted via email to: Please include the project title and principal investigator's name along with the abstract submission. ...
Thrya primarily defines a set of abstract C++ class interfaces needed for the development of abstract numerical atgorithms (ANAs) such as iterative linear solvers, transient solvers all the way up to optimization. At the foundation of these interfaces are abstract C++ classes for vectors, vector spaces, linear operators and multi-vectors. Also included in the Thyra package is C++ code for creating concrete vector, vector space, linear operator, and multi-vector subclasses as well as other utilitiesmore » to aid in the development of ANAs. Currently, very general and efficient concrete subclass implementations exist for serial and SPMD in-core vectors and multi-vectors. Code also currently exists for testing objects and providing composite objects such as product vectors.« less
NEPA OtherDocuments Property Type Page Description Additional supporting documents (e.g. biological assessment, cultural, completion reports, etc.) that don't fit any other...
Parallelization of the TRANSIMS Microsimulator - design, development, and performance Michael Hope Transportation Research and Analysis Computing Center Argonne National Laboratory List of Authors ================ Michael Hope Transportation Research and Analysis Computing Center Argonne National Laboratory 277 International Drive West Chicago, IL 60185 Abstract ========= The original TRANSIMS Microsimulator was designed as a purely parallel program. As desktop machine performance grew by leaps
The primary purpose of this model report is to develop abstractions for the response of engineered barrier system (EBS) components to seismic hazards at a geologic repository at Yucca Mountain, Nevada, and to define the methodology for using these abstractions in a seismic scenario class for the Total System Performance Assessment - License Application (TSPA-LA). A secondary purpose of this model report is to provide information for criticality studies related to seismic hazards. The seismic hazards addressed herein are vibratory ground motion, fault displacement, and rockfall due to ground motion. The EBS components are the drip shield, the waste package, and the fuel cladding. The requirements for development of the abstractions and the associated algorithms for the seismic scenario class are defined in ''Technical Work Plan For: Regulatory Integration Modeling of Drift Degradation, Waste Package and Drip Shield Vibratory Motion and Seismic Consequences'' (BSC 2004 [DIRS 171520]). The development of these abstractions will provide a more complete representation of flow into and transport from the EBS under disruptive events. The results from this development will also address portions of integrated subissue ENG2, Mechanical Disruption of Engineered Barriers, including the acceptance criteria for this subissue defined in Section 188.8.131.52.2.3 of the ''Yucca Mountain Review Plan, Final Report'' (NRC 2003 [DIRS 163274]).
Narrows Dam - Power Section Intake Trash Racks Location: Steel trash racks located at the ... documenting the condition of the rusted trash racks and adjacent corroded steel guides. ...
Documents Website Jump to: navigation, search OpenEI Reference LibraryAdd to library Web Site: BLM Geothermal Guidance Documents Website Abstract This website contains a list...
Associated Documents Jump to: navigation, search OpenEI Reference LibraryAdd to library Web Site: CDWR Well Permitting Forms and Associated Documents Abstract This webpage...
Waste Partnership (NWP) Quality Assurance Program Description (QAPD) Nuclear Waste Partnership (NWP) Quality Assurance Program Description (QAPD) The documents included in this ...
Conference: Microscopic Description of Nuclear Fission: Fission Barrier Heights of Even-Even Actinides Citation Details In-Document Search Title: Microscopic Description of Nuclear ...
Description of Induced Nuclear Fission with Skyrme Energy Functionals: II. Finite Temperature Effects Citation Details In-Document Search Title: Description of Induced Nuclear ...
Microsoft Word - 564MBiomassProject Descriptions FINAL 120409 Microsoft Word - 564MBiomassProject Descriptions FINAL 120409 (100.66 KB) More Documents & Publications ...
CleanEnergyProjectsonTribalLandsProjectDescriptions072011.pdf More Documents & Publications CleanEnergyProjectsonTribalLandsProjectDescriptions072011.pdf...
visualizations - TransVis capabilities and usage Michael Hope Transportation Research and Analysis Computing Center Argonne National Laboratory List of Authors ================ Michael Hope Transportation Research and Analysis Computing Center Argonne National Laboratory 277 International Drive West Chicago, IL 60185 Abstract ========= TRANSIMS is an extremely powerful software package in terms of both the breadth and depth of its analysis. However, there has been relatively little development
Simulation of building evacuation exit rates for TRANSIMS Reinaldo Moraga Department of Industrial and Systems Engineering Northern Illinois University 590 Garden Road DeKalb, IL 60115-2854 (815) 753-1442 List of Authors ================ Reinaldo Moraga Department of Industrial and Systems Engineering Northern Illinois University Abstract ========= This presentation deals with the topic of building evacuation modeling for TRANSIMS large scale simulation models in major metropolitan cities. The
capture by any means necessary Dr. Shea Mosby Nuclear Astrophysics and Structure, Los Alamos National Laboratory, Los Alamos, NM Abstract: Knowledge of nuclear reactions in general, and neutron capture cross sections in particular, are necessary to understand both heavy element nucleosynthesis and applications in nuclear energy and defense. While many nuclei of interest lie on or near the valley of stability and can be studied directly, many more are beyond the reach of any direct measurement.
Exotic Nuclei and Astrophysics" Professor Yuri Penionzhkevich Flerov, Lab. of Nucl. Reactions. JINR, Dubna, Russian Federation Abstract: This talk is an attempt to present some problems on the evolution of the Universe: the nucleosynthesis and cosmochronology from the standpoint of physics of particles and nuclei, in particular with the use of the latest results, obtained by means of radioactive nuclear beams. The comparison is made between the processes taking place in the Universe and the
Fission Chips" - Unusual Flavors (Dynamic nuclear instabilities in fission-like reactions) Professor W. Udo Schroeder Departments of Chemistry and Physics, University of Rochester, Rochester, NY 14627, USA Abstract Fission of cold nuclei is essentially a binary, adiabatic process, with only a mi- nute probability for the emission of associated light charged clusters. In contrast, nuclear systems in fast heavy-ion reactions respond to significant mechanical and thermal stresses by exhibiting
ABSTRACTS FOR PAPERS PUBLISHED April 1, 2000 - March 31, 2001 Isoscalar Giant Resonances and Nuclear Matter Compressibility D. H. Youngblood Nucl. Phys. A687, 1 (2001) Compression mode giant resonances have been measured in many nuclei from 12 C to 208 Pb with inelastic scattering of 240 MeV ∀ particles at small angles. Isoscalar monopole (GMR) distributions have been extracted for 17 nuclei and isoscalar dipole (ISDGR) distributions extracted for 11 nuclei. The isoscalar E1 strength
8 (2) Revision Number: 0 (3) Effective Date: 9/28/2009 (4) Document Type:  Digital Image El Hard copy (a) Number of pages (including the DRF) or 74 0PDF E] Video number of digital images (5) Release Type E New El cancel l Page Change El complete Revision (6) Document Title: 2009 Auto-TCR for Tank 241-13-204 (7) Change/Release Initial Issuance Description: (8) Change Initial Issuance Justification: (9) Associated (a) Structure Location: (c) Building Number: Structure, System, and Component N/A
31 97 (2) Revision Number: 0 -- (3) Effective Date: 9/30/2009 (4) Document Type: E] Digital Image l Hard copy (a) Number of pages (including the DRF) or 84 0 POE E Video number of digital images (5) Release Type Z New 1:1 Cancel liiPage Change Elcomplete Revision (6) Document Title: 2009 Auto-TOR for Tank 241 -TY-1 05 (7) Change/Release Initial Issuance Description: (8) Change Initial Issuance Justification: (9) Associated (a) Structure Location: (c) Building Number: Structure, System, and
This document contains the Software Design Description for Phase II of the SACS project, and Impact Level 3Q system
Omega Laser Facility Documentation 3000 LFORM 6950 Incident Review and Reporting 6610 LLE Radiological Controls Manual 9800 Introduction of Computers Into the OMEGA Facility Operations Procedure Document Release Process (M-TM-P-028) Product Data Management (PDM) (look up and administer numbered documents) LLE Clean Room Procedures and Protocol Blank WAP Template OMEGA Laser System Volume I - System Description (S-AA-M-12) Volume II - System Operation Procedures (S-AA-M-13) Volume III - Subsystem
The purpose of this report is to develop and analyze the engineered barrier system (EBS) radionuclide transport abstraction model, consistent with Level I and Level II model validation, as identified in Technical Work Plan for: Near-Field Environment and Transport: Engineered Barrier System: Radionuclide Transport Abstraction Model Report Integration (BSC 2005 [DIRS 173617]). The EBS radionuclide transport abstraction (or EBS RT Abstraction) is the conceptual model used in the total system performance assessment (TSPA) to determine the rate of radionuclide releases from the EBS to the unsaturated zone (UZ). The EBS RT Abstraction conceptual model consists of two main components: a flow model and a transport model. Both models are developed mathematically from first principles in order to show explicitly what assumptions, simplifications, and approximations are incorporated into the models used in the TSPA. The flow model defines the pathways for water flow in the EBS and specifies how the flow rate is computed in each pathway. Input to this model includes the seepage flux into a drift. The seepage flux is potentially split by the drip shield, with some (or all) of the flux being diverted by the drip shield and some passing through breaches in the drip shield that might result from corrosion or seismic damage. The flux through drip shield breaches is potentially split by the waste package, with some (or all) of the flux being diverted by the waste package and some passing through waste package breaches that might result from corrosion or seismic damage. Neither the drip shield nor the waste package survives an igneous intrusion, so the flux splitting submodel is not used in the igneous scenario class. The flow model is validated in an independent model validation technical review. The drip shield and waste package flux splitting algorithms are developed and validated using experimental data. The transport model considers advective transport and diffusive transport
Cyclotron Colloquium on Friday, April 18, 2014, at 11:00 am in Room 300 Refreshments will be served at 10:45 am Title: The neutron star in Cassiopeia A and what it is telling us? Professor Madappa Prakash Ohio University Athens, Ohio, USA Abstract: The neutron star in Cassiopeia A (Cas A) is now 333 years old and is the youngest known star from which thermal emission for over a decade has been observed. Initial reports from the analysis of archival data indicated Cas A's surface temperature to
response to ASCR Program Announcement LAB 15-1295 SENSE: SDN for End-to-end Networked Science at the Exascale Lead PI: Inder Monga, Lawrence Berkeley National Lab, email@example.com, 510-499-8065 Team: ANL - Linda Winkler, Kate Keahey, Caltech - Harvey Newman, Ramiro Voicu, FNAL - Phil DeMar, LBNL/ESnet - Chin Guok, John MacAuley, LBNL/NERSC - Jason Hick, UMD/MAX - Tom Lehman, Xi Yang, Alberto Jimenez Abstract: Traditionally, WAN and campus networks and services have evolved independently from each
Cyclotron Colloquium on Friday, August 17th, 2016, at 3:45 pm in Room 228 Refreshments will be served at 3:30 pm Dr. Justin Mabiala Cyclotron Institute Abstract: Pre-equilibrium emission and its possible relation to alpha-clustering in nuclei Cluster structure effects in nuclei have been investigated looking to the preequilibrium particles emitted in the 16O+65Cu and 19F+62Ni reactions at the same beam velocity of 16 AMeV which lead to the same 81Rb* compound nucleus. Despite the slight
For questions on the Environmental Assessment for Conducting Astrophysics and Other Basic Science Experiments at the WIPP Site, email Harold.Johnson@ or call (505) 234-7349. Environmental Assessment for Conducting Astrophysics and Other Basic Science Experiments at the WIPP Site Final - January, 2001 This document has been provided to you in PDF format. Please install Adobe Acrobat Reader before accessing these documents. Cover Sheet, Table of Contents, List of Tables, List of Figures, and
The purpose of this report is to develop and analyze the engineered barrier system (EBS) radionuclide transport abstraction model, consistent with Level I and Level II model validation, as identified in ''Technical Work Plan for: Near-Field Environment and Transport: Engineered Barrier System: Radionuclide Transport Abstraction Model Report Integration'' (BSC 2005 [DIRS 173617]). The EBS radionuclide transport abstraction (or EBS RT Abstraction) is the conceptual model used in the total system performance assessment for the license application (TSPA-LA) to determine the rate of radionuclide releases from the EBS to the unsaturated zone (UZ). The EBS RT Abstraction conceptual model consists of two main components: a flow model and a transport model. Both models are developed mathematically from first principles in order to show explicitly what assumptions, simplifications, and approximations are incorporated into the models used in the TSPA-LA. The flow model defines the pathways for water flow in the EBS and specifies how the flow rate is computed in each pathway. Input to this model includes the seepage flux into a drift. The seepage flux is potentially split by the drip shield, with some (or all) of the flux being diverted by the drip shield and some passing through breaches in the drip shield that might result from corrosion or seismic damage. The flux through drip shield breaches is potentially split by the waste package, with some (or all) of the flux being diverted by the waste package and some passing through waste package breaches that might result from corrosion or seismic damage. Neither the drip shield nor the waste package survives an igneous intrusion, so the flux splitting submodel is not used in the igneous scenario class. The flow model is validated in an independent model validation technical review. The drip shield and waste package flux splitting algorithms are developed and validated using experimental data. The transport model considers
Welcome to the Biological and Environmental Research Abstracts Database The U.S. ... This database contains abstracts of research projects supported by the program. Work was ...
Journal Article: Investigation and Analytical Description of Acoustic Production by Magneto-Acoustic Mixing Technology Citation Details In-Document Search This content will become...
Program Description Inspiring girls to recognize their potential and pursue opportunities in science, technology, engineering and mathematics. Through Expanding Your Horizon (EYH) ...
Bence, P. J.
This Management Control System (MCS) description describes the processes used to manage the cost and schedule of work performed by Westinghouse Hanford Company (Westinghouse Hanford) for the US Department of Energy, Richland Operations Office (DOE-RL), Richland, Washington. Westinghouse Hanford will maintain and use formal cost and schedule management control systems, as presented in this document, in performing work for the DOE-RL. This MCS description is a controlled document and will be modified or updated as required. This document must be approved by the DOE-RL; thereafter, any significant change will require DOE-RL concurrence. Westinghouse Hanford is the DOE-RL operations and engineering contractor at the Hanford Site. Activities associated with this contract (DE-AC06-87RL10930) include operating existing plant facilities, managing defined projects and programs, and planning future enhancements. This document is designed to comply with Section I-13 of the contract by providing a description of Westinghouse Hanford's cost and schedule control systems used in managing the above activities. 5 refs., 22 figs., 1 tab.
5 Document Information Document # FOIA-2009-0054 7 Revision Title FREEDOM OF INFORMATION ACT REQUEST (FOI 2009-0054) Date 09/02/2009 Originator RIEHLE DC Originator Co. [LOE-RL Recipient JARVIS R Recipient Co. HEART OF __________AMERICA NW References Keywords OCE, FOIA, SENSITIVE, PRIVATE CITIZEN Projects Other Inf ormation___________________________ WHC-SD-W025-AP-001, Rev. 2 1 1.0 INTRODUCTION 2 3 4 This response action plan (RAP) has been prepared for the Low-Level 5 Burial Grounds, Trenches
SECTION 5 of 5 Document Information Document # FOIA2011-01376 Revision Title FREEDOM OF INFORMATION ACT REQUEST (FOI 2011-01 376) [SEC. 5 OF 5] Date 07/26/2011 Originator RIEHLE DC Originator Co. DOE-RL Recipient O'BRIEN L Recipient Co. HOA References 4, WRPI -SV-1 706, 0031161, WRPI -SV-1 603, 2404-WB, 2404-WC, 5, SW-040-043, W-040-0439 6, EM-RL- PHMC-SOLIDWASTE-2008-0007, EM-RL-PHMC- SOLI DWASTE-2010-0003, WRAP-RP-1 1-03 Keywords OCE, FOIA, SENSITIVE Projects Other Information Attachment V
Services » Document Library Document Library August 31, 2016 Consent-Based Siting Summary of Public Input Meeting Consent-Based Siting Summary of Public Input Meeting August 16, 2016 NEAC CHARGE LETTERS August 8, 2016 Consent-Based Siting Meeting with the Town of Wiscasset, Maine (June 3, 2016) Consent-Based Siting Meeting with the Town of Wiscasset, Maine (June 3, 2016) July 19, 2016 Excess Uranium Management On July 19, 2016, the Department issued a Request for Information on the effects of
DOCUMENT RELEASE FORM G5 (1) Document Number: RPP-RPT-431 69 (2) Revision Number: 0 (3) Effective Date: 9/30/2009 (4) Document Type: E] Digital Image l Hard copy (a) Number of pages (including the IDRF) or 125 E PDF ElVideo number of digital images (5) Release Type Z New 0 Cancel El Page Change l complete Revision (6) Document Title: 2009 Auto-TCR for Tank 241 -T-1 11 (7) Change/Release Initial Issuance Description: (8) Change Initial Issuance Justification: (9) Associated (a) Structure
ABSTRACT A Monte Carlo simulation can be used to model freeze-out from high energy collisions. Existing Monte Carlo freeze-out algorithms usually do not account consistently for all conservation laws, such as the conservation of momentum or the conservation of energy. This poster will document the author's work during his REU program, to develop a Monte Carlo simulation modeling the freeze-out from high energy nuclear collisions imposing momentum conservation. We briefly explain the sampling
Applications Greg McFarquhar ISDAC Breakout Session ARM Science Team Meeting 10-13 March 2008, Norfolk, Virginia. ISDAC Applications * Described in Appendix of flight overview document - Description of needed profiles - Description of probes needed to make measurements to meet applications - Applications listed separately for clouds and aerosols Cloud water closure * Science Motivation: Compare measured bulk cloud water with that calculated by integrating measured size distribution-important
Testbed Description Network R&D Software-Defined Networking (SDN) Experimental Network Testbeds 100G SDN Testbed Testbed Description Proposal Process Terms and Conditions Dark Fiber Testbed Test Circuit Service Testbed Results Current Testbed Research Previous Testbed Research Performance (perfSONAR) Software & Tools Development Data for Researchers Partnerships Publications Workshops Contact Us Technical Assistance: 1 800-33-ESnet (Inside US) 1 800-333-7638 (Inside US) 1 510-486-7600
3 - March 31, 2004 (links to abstracts or full version of paper provided if available) Isoscalar Multipole Strength in 110 Cd and 116 Cd Y.-W. Lui, D.H. Youngblood, Y. Tokimoto, H.L. Clark, and B. John Phys. Rev. C 69 , 034611 (2004) Isoscalar E0-E3 Strength in 116 Sn, 144 Sm, 154 Sm, and 208 Pb D.H. Youngblood, Y.-W. Lui, H.L. Clark, B. John, Y. Tokimoto and X. Chen Phys. Rev. C 69 , 034315 (2004) Isoscalar Giant Dipole Resonance for Several Nuclei with A ≥ 90 Y.-W. Lui, X. Chen, H.L. Clark,
Note for: Cynthia Quarterman Keith Harper From: Carol Borgstrom Subject: NEPA Documentation Date: December 3, 2008 Attached, per your request, are two lists: (1) DOE environmental assessments (EAs) issued since 12/1/2006 and (2) DOE environmental impact statements (EISs) issued since 12/1/2006. Also, per your request, is a copy of a general NEPA briefing provided to the Acting Deputy Secretary in May 2008. Please let me know if you have any further questions (carol.borgstrom @hq.doe.gov;
f Enron Documents 1994 U.S. DEPARTMENT OF ENERGY 13S. 12 CORRESPONDENCE CONTROL FORM 1) OFFICE OF THE EXECUTIVE SECRETARIAT 8CTIVITY ADD DO NOT DETACH FROM ORIGINAL CORRESPONDENCE 0/03/Y4 10: O0 5OURCECODE PM PUBLIC MAIL :?EC INT: CONTROL NO: ES94-012853 ,ATE CORR: 04/25/94 DATE RECD: 05/02/94 DATE CNTRL: 05/03/94 DATE DUE: NONE :TTER: X MEMO: TWX: _ OTHER: TO: SECY: X DEP SEC: _ UN SEC: OTHER: )M:LAY,KENNETH L \ TX O REMARKS: RELATES TO ES94-009882. i ENRON CORP. J: PUBLIC INFORMATION NATIONAL
6 ,. OFC OU.S. DEPARTMENT OF ENERGY OFFICE OF THE EXECUTIVE SECRETARIAT CORRESPONDENCE CONTROL TICKET IMPORTANT ES NUMBER:- ES96-000274 EXTERNAL kTE OF DOC: 12/28/95 REC'D: 01/04/96 CONTROLLED: 01/04/96 DUE: 01/26/96 FROM: I HAVE A DREAM NOTE REA: SUBJECT INFORMS SECRETARY THAT ENRON SUMMARY: GORP HAS MADE A CONTRIBUTION TO "I HAVE A DREAM - HOUSTON" IN THE SECRETARY HONOR SOURCE: PUBLIC MAIL DOCUMENT TYPE: LETTER ADDRESSED TO: SECRETARY FOR SIGNATURE OF: SECRETARY ACTION TO: OFFICE OF
ADMIN RCD _ COMM REF _ RESPONSE TRACKING INFORMAnON I lOWED BY: (ORG) I TARGET DATE I I I CLOSING CCN COMPL. DATE I I CLOSING REF I I lOWED BY: (ORG) I I I I I TARGET DATE I CLOSING CCN COMPL DATE CLOSING REF TECHNICAL SERVICES DIVISION (TSD) BACKFIT (Documents dated prior to 1 November 1988) FUSRAP COMMUNICATIONS DISTRIBUTION DOEIORO TECHNICAL SERVICES DIVISION (CE-53) BECHTEL NATIONAl.. INC. - JOB 14501 AI$Wl E.e... COMM DATE b~5i=-'/T-'-I'''' ADDR CODE I I I I CLOSES CCN WBS 1/~ .. :2 O~
Ehron Documents 1993 S-F-1325.12 CORRESPONDENCE CONTROL FORM (11-90) OFFICE OF THE EXECLTIVE SECRETARIAT ACTIVITY ADD DO NOT DETACH FROM ORIGINAL CORRESPONDENCE 01/19/93 10:17 SOURCE CODE pM PUBLIC MAIL SPEC INT: _ CONTROL N( S93-000578 DATE CORR: 01/13/93 DATERECD: 01/19/93 DATECNTRL: 01/19/93 -DATE DUE: LETTER: MEMO: TWX: _OTHER: MOTION TO:SECY: X DEPSEC: UN SEC: OTHER: ROM:FLOWERS,G PATRICK TX O REMARKS: ENRON CORP. UB J : LEGAL -=--_- LITIGATION FOR USE fY ACT N OFFICE ONLY MOTION FOR LEAVE
This document describes the joint U.S. Department of Energy (DOE) Office of Legacy Management (LM) and the Legacy Management Support (LMS) Contractor Team Environmental Management System (EMS).
govPublicationsConference Documents Publications Journal Articles Conference Documents Program Documents Technical Reports Publications Database Public Information Materials Image...
ABBREVIATION DESCRIPTION AAVP ARM Aerial Vehicles Program ACP Atmospheric Chemistry Program ACP - CE ACP - Capital Equipment AmeriFlux AmeriFlux ARM Atmospheric Radiation ...
The Mechanical Engineering Department publishes listings of technical abstracts twice a year to inform readers of the broad range of technical activities in the Department, and to promote an exchange of ideas. Details of the work covered by an abstract may be obtained by contacting the author(s). Overall information about current activities of each of the Department's seven divisions precedes the technical abstracts.
quark gluon plasma Dr. Michael Strickland Gettysburg College Abstract: In this talk I will review our theoretical understanding of the dynamics of a non- equilibrium quark ...
Physics is needed" Professor Ulrich Mosel Univ Giessen, Inst Theoret Phys, Giessen, Germany Abstract: Long baseline experiments with neutrinos require a precise knowledge of the ...
Cluster formation in nuclear systems Professor Gerd Roepke Institute of Physics, Rostock University, Germany Abstract To describe cluster formation in nuclear matter at ...
Dennis McNabb Lawrence Livermore National Laboratory Abstract: LLNL is an applied science laboratory that innovates technology to enable new ideas and concepts for government ...
This document provides a description of the baseline system conceptualized for remediating the tank waste stored within the Hanford Site. Remediation of the tank waste will be performed by the Tank Waste Remediation System (TWRS). This baseline system description (BSD) document has been prepared to describe the current planning basis for the TWRS for accomplishing the tank waste remediation functions. The BSD document is not intended to prescribe firm program management strategies for implementing the TWRS. The scope of the TWRS Program includes managing existing facilities, developing technology for new systems; building, testing and operating new facilities; and maintaining the system. The TWRS Program will manage the system used for receiving, safely storing, maintaining, treating, and disposing onsite, or packaging for offsite disposal, all tank waste. The scope of the TWRS Program encompasses existing facilities such as waste storage tanks, evaporators, pipelines, and low-level radioactive waste treatment and disposal facilities. It includes support facilities that comprise the total TWRS infrastructure, including upgrades to existing facilities or equipment and the addition of new facilities.
water was integral to the Site's Cold War nuclear production mission as it was used ... The study provides historic contexts for the site's Cold War history and a context for ...
Simulations showed actinide inventories stabilizing to steady levels while fresh actinide fuel from feedstocks of Spent Nuclear Fuel or uranium-238 or thorium-232 continued to be ...
Ridge, TN 37831-6131-6210 3Imaging & Nanoscale Characterization Group, Center for ... Microscopy and Fluorescence Techniques. Nanoscale 2009, 1, 40-49. 13 Petibois, C. Imaging ...
A prototypical disease example is the brain cancer glioblastoma multiforme (GBM). At the molecular level, it is rare for any two GBM patients to appear as if they have the same ...
... to ensure successful operation of the test unit, had sufficient funds been available. ... principles for soot content detection, 3) test operation scheme, and 4) specifics ...
... Atlanta, GA, American Society of Heating, Refrigerating, and Air Conditioning Engineers, Inc. Beko, G., G. Clausen and C. J. Weschler (2008). "Sensory pollution from bag filters, ...
will discuss recent experiments on the structural, chemical, and electronic properties of graphene and hBN, including high resolution electron microscopy where real-time dynamics...
Acknowledgements xv 1 Introduction ...... 1 1.1 Physics motivation ... Introduction 1.1 Physics motivation High momentum transfer phenomena are known to be a ...
... Witterseh T. 2001. Environmental perception, SBS symptoms and performance of office work under combined exposure to temperature, noise and air pollution. PhD Thesis. International ...
... passed through Nafion tubing coiled inside a container containing silica gel desiccant. ... and the reductions in outdoor ozone production with cooler temperatures, the study was ...
BROWNE, MICHAEL CHARLES. Preparation for Deployment of the Neutral Current Detectors (NCDs) for the Sudbury Neutrino Observatory (SNO). (Under the direction of John F. Wilkerson and Christopher R. Gould.) The Sudbury Neutrino Observatory (SNO) is the latest generation of solar neutrino experiments designed to investigate the Solar Neutrino Problem (SNP). Through detection of all flavors of neutrinos, SNO will be capable of testing the neutrino oscillation hypothesis as a solution to the SNP.
Phase Fabrication Problems 5.4 Staggered Overlap Joint Design 6. D-spar Static & Modal Testing 79 6.1 Static Test Set-up 6.2 Static Test Results 6.3 Comparison Between Estimated...
SAND2007-2331 Unlimited Release Printed April 2007 Autothermal Reforming of Natural Gas to Synthesis Gas Reference: KBR Paper 2031 Steven F. Rice and David P. Mann Prepared by ...
... standards barriers to progressive "value added" support for the utility grid or for economic benefits of intelligent distributed PV grid-tied systems. The IEEE Std1547 does ...
... at all currently operational coal and natural gas fired power plants in the U.S. ... Water Treatment and Use for Power Plant Cooling Peter H. Kobos, Sandia ...
Program Description SAGE, the Summer of Applied Geophysical Experience, is a unique educational program designed to introduce students in geophysics and related fields to "hands on" geophysical exploration and research. The program emphasizes both teaching of field methods and research related to basic science and a variety of applied problems. SAGE is hosted by the National Security Education Center and the Earth and Environmental Sciences Division of the Los Alamos National
will be served at 3:30 pm New Result from RIKEN RIBF Dr. H. Sakai RIKEN, Wako. Japan Abstract: Very recent experimental results from RI Beam Factory(RIBF) of RIKEN will be...
Monday, May 22nd, at 1:30 pm "Dilepton production at SPS and RHIC energies" Dr. Olena Linnyk Frankfurt Institute for Advanced Study (FIAS), Frankfurt, Germany Abstract: Analysis of ...
Pibero Djawotho Texas A&M University Abstract: For polarized protons colliding at RHIC energies, the production of jets and hadrons is dominated by gg and qg scattering, making the ...
Handbook Abstract Outlines required NEPA documents for FWS NEPA process. Author Fish and Wildlife Service Published Fish and Wildlife Service, 1996 DOI Not Provided Check...
Guiding Documents and Links Guiding Documents and Links Federal Executive Order 13653, Preparing the United States for the Impacts of Climate Change Executive Order 13693, Planning for Federal Sustainability in the Next Decade DOE DOE Orders DOE Order 430.1B - Real Property and Asset Management DOE Order 436.1 - Departmental Sustainability DOE Policy 450.4A - Integrated Safety Management Policy 2014 DOE Strategic Sustainability Performance Plan LM Documents EMS Description LM Environmental
Document Document Extracted Pages Document (52.04 KB) More Documents & Publications ADR Policy Federal Register Microsoft Word - ADR Revised Policy82508Reformatted.doc 2009 ECR FINAL REPORT 2010
This volume and its appendixes supplement the Advisory Committee`s final report by reporting how we went about looking for information concerning human radiation experiments and intentional releases, a description of what we found and where we found it, and a finding aid for the information that we collected. This volume begins with an overview of federal records, including general descriptions of the types of records that have been useful and how the federal government handles these records. This is followed by an agency-by-agency account of the discovery process and descriptions of the records reviewed, together with instructions on how to obtain further information from those agencies. There is also a description of other sources of information that have been important, including institutional records, print resources, and nonprint media and interviews. The third part contains brief accounts of ACHRE`s two major contemporary survey projects (these are described in greater detail in the final report and another supplemental volume) and other research activities. The final section describes how the ACHRE information-nation collections were managed and the records that ACHRE created in the course of its work; this constitutes a general finding aid for the materials deposited with the National Archives. The appendices provide brief references to federal records reviewed, descriptions of the accessions that comprise the ACHRE Research Document Collection, and descriptions of the documents selected for individual treatment. Also included are an account of the documentation available for ACHRE meetings, brief abstracts of the almost 4,000 experiments individually described by ACHRE staff, a full bibliography of secondary sources used, and other information.
8 Science Team MeetingPoster Abstract 2008
7 Science Team MeetingPoster Abstract 2007
Citation Details In-Document Search Title: Description of induced nuclear fission with Skyrme energy functionals: Static potential energy surfaces and fission fragment properties ...
Section I - FUNDING OPPORTUNITY DESCRIPTION More Documents & Publications U. S. Department of Energy - Headquarters Advanced Research Projects Agency Advanced Research Projects...
Fragment Properties Citation Details In-Document Search Title: Description of Induced Nuclear Fission with Skyrme Energy Functionals: I. Static Potential Energy Surfaces and...
Pricing Information (IDIQ Attachment J-5) Descriptions of ESPC Task Order Schedules and Placement of Pricing Information (IDIQ Attachment J-5) Document provides task order ...
PDF icon Tribal Energy Program Feb 2012 Awards Project Descriptions0.pdf More Documents & Publications Community-Scale Project Development and Finance Workshop Agenda and ...
"Title","Speaker","Publication Date","OSTI Identifier","Report Number(s)","DOE Contract Number","Other Number(s)","Resource Type","Specific Type","Coverage","Research Org.","Sponsoring Org.","Subject","Related Subject","Description/Abstract","Publisher","Country of Publication","Language","Format","Availability","Rights","System Entry Date"
Title","Speaker","Publication Date","OSTI Identifier","Report Number(s)","DOE Contract Number","Other Number(s)","Resource Type","Specific Type","Coverage","Research Org.","Sponsoring Org.","Subject","Related Subject","Description/Abstract","Publisher","Country of
... world's leading centers for research, teaching, enterprise and innovation in ... by title, author, abstract, year, language (all, English, Swedish), document type. ...
Document provides task order schedule descriptions and information on the placement of pricing for energy savings performance contracts (ESPCs).
This document focuses on the scientific and technical information (STT) reports, articles, and presentations generated at the site by various authors and organizations of Westinghouse Savannah River Company and its subcontractors. Abstracts of these STI products are contained within this document. The abstracts have been compiled as they originally appeared in the source reports. No changes to the content have been made except as necessary to correct errors of spelling, to reduce abstract length, or to ensure that the information is unclassified. The abstracts are organized according to information categories ( UC'' categories) established by the Department of Energy's Office of Scientific and Technical Information (OSTI). When reports fall into more than one category, their abstract is included as an entry in the most applicable section of this document. UC-700 General, Miscellaneous, and Progress Reports, UC-701 Chemistry, UC-702 Environmental Sciences, UC-703 Geosciences, UC-704 Materials, UC-705 Mathematics and Computer Sciences, UC-706 Engineering, Equipment, and Instruments, UC-707 Health and Safety, UC-708 Biological Sciences, UC-711 Chemical Separation Processes for Plutonium and Uranium, UC-712 Inertial Confinement Fusion, UC-713 Radioisotope and Radiation Applications, UC-714 Criticality Studies, UC-715 Technology - Feed Materials, UC-721 Defense Waste Management, UC-722 Transportation of Nuclear Materials, UC-731 Nuclear Materials Production, UC-732 Special Isotope Separation (Plutonium), UC-733 Nuclear Raw Materials, UC-741 Chemical High Explosives, UC-742 Applications of Explosions, UC-743 Nuclear Propulsion Systems, UC-744 Aerospace Nuclear Safety, and Index 91.
This document focuses on the scientific and technical information (STT) reports, articles, and presentations generated at the site by various authors and organizations of Westinghouse Savannah River Company and its subcontractors. Abstracts of these STI products are contained within this document. The abstracts have been compiled as they originally appeared in the source reports. No changes to the content have been made except as necessary to correct errors of spelling, to reduce abstract length, or to ensure that the information is unclassified. The abstracts are organized according to information categories (``UC`` categories) established by the Department of Energy`s Office of Scientific and Technical Information (OSTI). When reports fall into more than one category, their abstract is included as an entry in the most applicable section of this document. UC-700 General, Miscellaneous, and Progress Reports, UC-701 Chemistry, UC-702 Environmental Sciences, UC-703 Geosciences, UC-704 Materials, UC-705 Mathematics and Computer Sciences, UC-706 Engineering, Equipment, and Instruments, UC-707 Health and Safety, UC-708 Biological Sciences, UC-711 Chemical Separation Processes for Plutonium and Uranium, UC-712 Inertial Confinement Fusion, UC-713 Radioisotope and Radiation Applications, UC-714 Criticality Studies, UC-715 Technology - Feed Materials, UC-721 Defense Waste Management, UC-722 Transportation of Nuclear Materials, UC-731 Nuclear Materials Production, UC-732 Special Isotope Separation (Plutonium), UC-733 Nuclear Raw Materials, UC-741 Chemical High Explosives, UC-742 Applications of Explosions, UC-743 Nuclear Propulsion Systems, UC-744 Aerospace Nuclear Safety, and Index 91.
The purpose of this document is to provide a system design description (SDD) and design basis for the Plutonium Finishing Plant (PFP) Thermal Stabilization project. The chief objective of the SDD is to document the Structures, Systems, and Components (SSCs) that establish and maintain the facility Safety Envelope necessary for normal safe operation of the facility; as identified in the FSAR, the OSRs, and Safety Assessment Documents (SADs). This safety equipment documentation should satisfy guidelines for the SDD given in WHC-SD-CP-TI-18 1, Criteria for Identification and Control of Equipment Necessary for Preservation of the Safety Envelope and Safe Operation of PFP. The basis for operational, alarm response, maintenance, and surveillance procedures are also identified and justified in this document. This document and its appendices address the following elements of the PFP Thermal Stabilization project: Functional and design requirements; Design description; Safety Envelope Analysis; Safety Equipment Class; and Operational, maintenance and surveillance procedures.
Note: Documents that do not have document numbers are not included in this listing. Large file size alert This symbol means the document may be a large file size. All documents by number Common document prefixes DOE/CAO DOE/TRU DOE/CBFO DOE/WIPP DOE/EA NM DOE/EIS Other DOE/CAO Back to top DOE/CAO 95-1095, Oct. 1995 Remote Handled Transuranic Waste Study This study was conducted to satisfy the requirements defined by the WIPP Land Withdrawal Act and considered by DOE to be a prudent exercise in
May 15, 2012, at 3:45 pm Room MIST 102 at the Mitchell Institute Refreshment will be served at 3:30 pm New instruments and recent results in the study of transfer reactions at the HRIBF Dr. Dan Bardayan Oak Ridge National Laboratory Abstract: Single-nucleon transfer reactions on heavy neutron-rich nuclei are critical to providing an empirical foundation for the determination of the incredibly large neutron fluxes in extreme environments such as exploding stars, internal confinement fusion
NSI Colloquium on Monday, August 27 at 3:45 pm in Hawking Auditorium--Mitchel Institute Refreshments will be served at 3:30 pm FORENSIC RADIOCHEMISTRY Dr. Ken Moody Chemical Sciences Division, Lawrence Livermore National Laboratory Abstract: Signatures inherent in a sample containing radionuclides give clues about the origin of the material. This information can be quite important when dealing with smuggled nuclear materials interdicted by law enforcement personnel, or potential debris samples
June 1st at 3:30 PM " Experimental evidence of repeatability in high-spin data and phenomenological interpretation Part one: Differential distributions" Dr. Ninel Nica Cyclotron Institute, Texas A&M University Abstract: We present the experimental evidence of a general correlation property of high-spin physics that we named Repeatability, consisting in highly hierarchized ordering relationships in two-dimensional gamma-ray coincidence data. However despite its generality
12, 2010 at 3:45 pm "RF Carpet Development at the NSCL" Gregory K. Pang** Departments of Astronomy and Physics Univ. of Illinois, Urbana, IL NSCL, Michigan State University, E. Lansing, MI ABSTRACT: The slowing down and thermalizing of nuclear reaction products from projectile fragmentation processes is essential for allowing the study of rare isotopes in low-energy precision experiments. Current methods of stopping fast beams rely on gas filled linear chambers equipped with electrodes
April 6 at 3:45 PM Designer Nuclei: New possibilities with the Facility for Rare Isotope Beams Professor Brad Sherrill Abstract: A quest of experimental nuclear science is to synthesize atoms made of all possible combinations of neutrons, protons and electrons. In part, based on our current capabilities for creating new isotopes, our understanding of atomic nuclei has changed dramatically. Many of the so called basic properties of atomic nuclei turn out to not be as universal as we thought.
"Critical-like behavior in a lattice gas model" Professor Andrzej Wieloch M. Smoluchowski Inst. of Physics, Jagiellonian Univ., Krakow, Poland Abstract: The ALADIN multifragmentation data for reaction Au+Au at several hundreds A.MEV show features characteristic of critical behavior, which are very well reproduced by a bond percolation model. This suggests, in the context of the lattice gas model, that fragments are formed at nearly normal nuclear densities and temperatures
Theory Seminar Friday, January 21st, at 4:00 pm Triangular flow and dihadron azimuthal correlations in heavy ion collisions Dr. Jun Xu Abstract The dihadron azimuthal correlations triggered by energetic particles in heavy ion collisions at RHIC are studied in a multiphase transport (AMPT) model. A double- peak structure at the away side of triggered particles is obtained after subtracting background correlations due to the elliptic flow as observed in experiments. Both the near-side peak and the
Decommissioning Documents PDF icon Decommissioning Documents More Documents & Publications Decommissioning Benchmarking Study Final Report Decommissioning Handbook ...
The ''Yucca Mountain Site Description'' summarizes, in a single document, the current state of knowledge and understanding of the natural system at Yucca Mountain. It describes the geology; geochemistry; past, present, and projected future climate; regional hydrologic system; and flow and transport within the unsaturated and saturated zones at the site. In addition, it discusses factors affecting radionuclide transport, the effect of thermal loading on the natural system, and tectonic hazards. The ''Yucca Mountain Site Description'' is broad in nature. It summarizes investigations carried out as part of the Yucca Mountain Project since 1988, but it also includes work done at the site in earlier years, as well as studies performed by others. The document has been prepared under the Office of Civilian Radioactive Waste Management quality assurance program for the Yucca Mountain Project. Yucca Mountain is located in Nye County in southern Nevada. The site lies in the north-central part of the Basin and Range physiographic province, within the northernmost subprovince commonly referred to as the Great Basin. The basin and range physiography reflects the extensional tectonic regime that has affected the region during the middle and late Cenozoic Era. Yucca Mountain was initially selected for characterization, in part, because of its thick unsaturated zone, its arid to semiarid climate, and the existence of a rock type that would support excavation of stable openings. In 1987, the United States Congress directed that Yucca Mountain be the only site characterized to evaluate its suitability for development of a geologic repository for high-level radioactive waste and spent nuclear fuel.
J. D. Bigbee
The Waste Handling Building Fire Protection System provides the capability to detect, control, and extinguish fires and/or mitigate explosions throughout the Waste Handling Building (WHB). Fire protection includes appropriate water-based and non-water-based suppression, as appropriate, and includes the distribution and delivery systems for the fire suppression agents. The Waste Handling Building Fire Protection System includes fire or explosion detection panel(s) controlling various detectors, system actuation, annunciators, equipment controls, and signal outputs. The system interfaces with the Waste Handling Building System for mounting of fire protection equipment and components, location of fire suppression equipment, suppression agent runoff, and locating fire rated barriers. The system interfaces with the Waste Handling Building System for adequate drainage and removal capabilities of liquid runoff resulting from fire protection discharges. The system interfaces with the Waste Handling Building Electrical Distribution System for power to operate, and with the Site Fire Protection System for fire protection water supply to automatic sprinklers, standpipes, and hose stations. The system interfaces with the Site Fire Protection System for fire signal transmission outside the WHB as needed to respond to a fire emergency, and with the Waste Handling Building Ventilation System to detect smoke and fire in specific areas, to protect building high-efficiency particulate air (HEPA) filters, and to control portions of the Waste Handling Building Ventilation System for smoke management and manual override capability. The system interfaces with the Monitored Geologic Repository (MGR) Operations Monitoring and Control System for annunciation, and condition status.
The Monitored Geologic Repository Operations Monitoring and Control System provides supervisory control, monitoring, and selected remote control of primary and secondary repository operations. Primary repository operations consist of both surface and subsurface activities relating to high-level waste receipt, preparation, and emplacement. Secondary repository operations consist of support operations for waste handling and treatment, utilities, subsurface construction, and other selected ancillary activities. Remote control of the subsurface emplacement operations, as well as, repository performance confirmation operations are the direct responsibility of the system. In addition, the system monitors parameters such as radiological data, air quality data, fire detection status, meteorological conditions, unauthorized access, and abnormal operating conditions, to ensure a safe workplace for personnel. Parameters are displayed in a real-time manner to human operators regarding surface and subsurface conditions. The system performs supervisory monitoring and control for both important to safety and non-safety systems. The system provides repository operational information, alarm capability, and human operator response messages during emergency response situations. The system also includes logic control to place equipment, systems, and utilities in a safe operational mode or complete shutdown during emergency response situations. The system initiates alarms and provides operational data to enable appropriate actions at the local level in support of emergency response, radiological protection response, evacuation, and underground rescue. The system provides data communications, data processing, managerial reports, data storage, and data analysis. This system's primary surface and subsurface operator consoles, for both supervisory and remote control activities, will be located in a Central Control Center (CCC) inside one of the surface facility buildings. The system consists of instrument and control equipment and components necessary to provide human operators with sufficient information to monitor and control the operation of the repository in an efficient and safe manner. The system consists of operator consoles and workstations, multiple video display terminals, communications and interfacing equipment, and instrument and control software with customized configuration to meet the needs of the Monitored Geologic Repository (MGR). Process and logic controllers and the associated input/output units of each system interfaced with this system will be configured into Remote Terminal Units (RTU) and located close to the systems to be monitored and controlled. The RTUs are configured to remain operational should communication with CCC operations be lost. The system provides closed circuit television to selectively view systems, operations, and equipment areas and to aid in the operation of mechanical systems. Control and monitoring of site utility systems will be located in the CCC. Site utilities include heating, ventilation, and air conditioning equipment; plant compressed air; plant water; firewater; electrical systems; and inert gases, such as nitrogen, if required. This system interfaces with surface and subsurface systems that either generate output data or require remote control input. The system interfaces with the Site Communications System for bulk storage of operational data, on-site and off-site communication, and a plant-wide public announcement system. The system interfaces with the Safeguards and Security System to provide operational status and emergency alarm indications. The system interfaces with the Site Operation System to provide site wide acquisition of data for analysis and reports, historical information for trends, utility information for plant operation, and to receive operating plans and procedures.
N. E. Pettit
The Naval Spent Nuclear Fuel Disposal Container System supports the confinement and isolation of waste within the Engineered Barrier System of the Monitored Geologic Repository (MGR). Disposal containers/waste packages are loaded and sealed in the surface waste handling facilities, transferred underground through the access drifts using a rail mounted transporter, and emplaced in emplacement drifts. The Naval Spent Nuclear Fuel Disposal Container System provides long term confinement of the naval spent nuclear fuel (SNF) placed within the disposal containers, and withstands the loading, transfer, emplacement, and retrieval operations. The Naval Spent Nuclear Fuel Disposal Container System provides containment of waste for a designated period of time and limits radionuclide release thereafter. The waste package maintains the waste in a designated configuration, withstands maximum credible handling and rockfall loads, limits the waste form temperature after emplacement, resists corrosion in the expected handling and repository environments, and provides containment of waste in the event of an accident. Each naval SNF disposal container will hold a single naval SNF canister. There will be approximately 300 naval SNF canisters, composed of long and short canisters. The disposal container will include outer and inner cylinder walls and lids. An exterior label will provide a means by which to identify a disposal container and its contents. Different materials will be selected for the waste package inner and outer cylinders. The two metal cylinders, in combination with the Emplacement Drift System, drip shield, and the natural barrier will support the design philosophy of defense-in-depth. The use of materials with different properties prevents a single mode failure from breaching the waste package. The inner cylinder and inner cylinder lids will be constructed of stainless steel while the outer cylinder and outer cylinder lids will be made of high-nickel alloy.
The Pool Water Treatment and Cooling System is located in the Waste Handling Building (WHB), and is comprised of various process subsystems designed to support waste handling operations. This system maintains the pool water temperature within an acceptable range, maintains water quality standards that support remote underwater operations and prevent corrosion, detects leakage from the pool liner, provides the capability to remove debris from the pool, controls the pool water level, and helps limit radiological exposure to personnel. The pool structure and liner, pool lighting, and the fuel staging racks in the pool are not within the scope of the Pool Water Treatment and Cooling System. Pool water temperature control is accomplished by circulating the pool water through heat exchangers. Adequate circulation and mixing of the pool water is provided to prevent localized thermal hotspots in the pool. Treatment of the pool water is accomplished by a water treatment system that circulates the pool water through filters, and ion exchange units. These water treatment units remove radioactive and non-radioactive particulate and dissolved solids from the water, thereby providing the water clarity needed to conduct waste handling operations. The system also controls pool water chemistry to prevent advanced corrosion of the pool liner, pool components, and fuel assemblies. Removal of radioactivity from the pool water contributes to the project ALARA (as low as is reasonably achievable) goals. A leak detection system is provided to detect and alarm leaks through the pool liner. The pool level control system monitors the water level to ensure that the minimum water level required for adequate radiological shielding is maintained. Through interface with a demineralized water system, adequate makeup is provided to compensate for loss of water inventory through evaporation and waste handling operations. Interface with the Site Radiological Monitoring System provides continuous radiological monitoring of the pool water. The Pool Water Treatment and Cooling System interfaces with the Waste Handling Building System, Site-Generated Radiological Waste Handling System, Site Radiological Monitoring System, Waste Handling Building Electrical System, Site Water System, and the Monitored Geologic Repository Operations Monitoring and Control System.
N. E. Pettit
The Uncanistered Spent Nuclear Fuel (SNF) Disposal Container System supports the confinement and isolation of waste within the Engineered Barrier System of the Monitored Geologic Repository (MGR). Disposal containers are loaded with intact uncanistered assemblies and/or individually canistered SNF assemblies and sealed in the surface waste handling facilities, transferred to the underground through the access drifts, and emplaced in emplacement drifts. The Uncanistered SNF Disposal Container provides long-term confinement of the commercial SNF placed inside, and withstands the loading, transfer, emplacement, and retrieval loads and environments. The Uncanistered SNF Disposal Container System provides containment of waste for a designated period of time, and limits radionuclide release. The disposal container maintains the waste in a designated configuration, withstands maximum handling and rockfall loads, limits the individual SNF assembly temperatures after emplacement, limits the introduction of moderator into the disposal container during the criticality control period, resists corrosion in the expected handling and repository environments, and provides containment of waste in the event of an accident.
The Uncanistered Spent Nuclear Fuel (SNF) Disposal Container System supports the confinement and isolation of waste within the Engineered Barrier System of the Monitored Geologic Repository (MGR). Disposal containers are loaded with intact uncanistered assemblies and/or individually canistered SNF assemblies and sealed in the surface waste handling facilities, transferred to the underground through the access drifts, and emplaced in the emplacement drifts. The Uncanistered SNF Disposal Container provides long-term confinement of the commercial SNF placed inside, and withstands the loading, transfer, emplacement, and retrieval loads and environments. The Uncanistered SNF Disposal Container System provides containment of waste for a designated period of time, and limits radionuclide release. The disposal container maintains the waste in a designated configuration, withstands maximum handling and rockfall loads, limits the individual SNF assembly temperatures after emplacement, limits the introduction of moderator into the disposal container during the criticality control period, resists corrosion in the expected handling and repository environments, and provides containment of waste in the event of an accident. Multiple boiling water reactor (BWR) and pressurized water reactor (PWR) disposal container designs are needed to accommodate the expected range of spent fuel assemblies and provide long-term confinement of the commercial SNF. The disposal container will include outer and inner cylinder walls, outer cylinder lids (two on the top, one on the bottom), inner cylinder lids (one on the top, one on the bottom), and an internal metallic basket structure. Exterior labels will provide a means by which to identify the disposal container and its contents. The two metal cylinders, in combination with the cladding, Emplacement Drift System, drip shield, and natural barrier, will support the design philosophy of defense-in-depth. The use of materials with different properties prevents a single mode failure from breaching the waste package. The inner cylinder and inner cylinder lids will be constructed of stainless steel and the outer cylinder and outer cylinder lid will be made of high-nickel alloy. The basket will assist criticality control, provide structural support, and improve heat transfer. The Uncanistered SNF Disposal Container System interfaces with the emplacement drift environment and internal waste by transferring heat from the SNF to the external environment and by protecting the SFN assemblies and their contents from damage/degradation by the external environment. The system also interfaces with the SFN by limiting access of moderator and oxidizing agents of the SFN. The waste package interfaces with the Emplacement Drift System's emplacement drift pallets upon which the wasted packages are placed. The disposal container interfaces with the Assembly Transfer System, Waste Emplacement/Retrieval System, Disposal Container Handling System, and Waste Package Remediation System during loading, handling, transfer, emplacement and retrieval of the disposal container/waste package.
regarding Hanford's previous mission of plutonium production. Posting every document dating back to 1943 on this website would be unrealistic. However, certain documents are...
23 at 10:30 AM "Decay Spectroscopy at FAIR Using the Advanced Implantation Detector Array (AIDA)" Dr. Thomas Davinson The University of Edinburgh, UK Abstract: The objective of the Advanced Implantation Detector Array (AIDA) project is to develop, commission and exploit a state of the art silicon detector array for decay spectroscopy experiments at the SuperFRS, FAIR. Multi-GeV exotic ions will be implanted into the silicon detector array and AIDA will perform spectroscopy quality
29th, 4:00 PM Bulk spectral function sum rule in QCD-like theories with a holographic dual Dr. Paul M. Hohler University of Illinois at Chicago Abstract: In this talk, the sum rule for the spectral function of the stress-energy tensor in the bulk (uniform dilatation) channel is derived for a general class of strongly coupled field theories. This class includes theories holographically dual to a theory of gravity coupled to a single scalar field, representing the operator of the scale anomaly. In
April 24, 2012, at 2:00 pm Refreshment will be served at 1:45 pm Beta-decay Studies for Nova Nucleosynthesis Dr. Antti Saastamoinen University of Jyväskylä / TAMU Abstract Classical novae occur in interacting binary systems, where hydrogen-rich material accretes on a white dwarf from its low-mass main-sequence companion. Eventually, the accretion of the hydrogen-rich matter leads to a thermonuclear runaway (TNR). Understanding the dynamics of the nova outbursts and the nucleosynthesis fueling
November 9th, at 3:45 pm 2p-2p decay in 8 C and other 2p decay cases in light nuclei Professor L. G. Sobotka Departments of Chemistry and Physics Washington University, St. Louis Abstract Recent technical advances have allowed for high-order correlation experiments to be done. We have primarily focused on experiments in which the final channel is composed of only alphas and protons. Three cases we have studied are: 6 Be, 10 C and 8 C via 3, 4, and 5-particle correlation experiments respectively.
March 9, at 3:45 pm "Neutron Stars as Astrophysical Laboratories for Nuclear and Particle Physics" Professor Fridolin Weber Department of Physics, San Diego State University Abstract: Neutron stars are among the most enigmatic objects that exist in the Universe. They are as massive as our Sun but are trillions of times smaller in volume. The matter in the cores of neutron stars is therefore compressed to densities that are several times greater than the densities of atomic nuclei. This
Friday July 27, 2012, at 2:00 pm Room MIST 102 at the Mitchell Institute Refreshment will be served at 1:45 pm High spin resonances in hadron reactions Dr. Yongseok Department of Physics, Kyungpook National University, Korea Abstract: (I) To understand the reaction mechanisms of the baryon/meson production processes, it is necessary to consider high spin baryon fields since many resonances in the mass of 2 GeV carry spin higher than 3/2. In this talk, we will discuss how to introduce high spin
Document Document Extracted Pages Document (64.65 KB) More Documents & Publications EIS-0396: Advance Notice of Intent o Prepare an Environmental Impact Statement EIS-0396: Notice of Intent to Prepare a Programmatic Environmental Impact Statement Meeting Minutes: February 20-21, 2007
Kaper, H. G.; Tipei, S.
In this article we have outlined a formal framework for an abstract approach to music and music composition. The model is formulated in terms of objects that have attributes, obey relationships, and are subject to certain well-defined operations. The motivation for this approach uses traditional terms and concepts of music theory, but the approach itself is formal and uses the language of mathematics. The universal object is an audio wave; partials, sounds, and compositions are special objects, which are placed in a hierarchical order based on time scales. The objects have both static and dynamic attributes. When we realize a composition, we assign values to each of its attributes: a (scalar) value to a static attribute, an envelope and a size to a dynamic attribute. A composition is then a trajectory in the space of aural events, and the complex audio wave is its formal representation. Sounds are fibers in the space of aural events, from which the composer weaves the trajectory of a composition. Each sound object in turn is made up of partials, which are the elementary building blocks of any music composition. The partials evolve on the fastest time scale in the hierarchy of partials, sounds, and compositions. The ideas outlined in this article are being implemented in a digital instrument for additive sound synthesis and in software for music composition. A demonstration of some preliminary results has been submitted by the authors for presentation at the conference.
STEP Intern Job Description, from the Tool Kit Framework: Small Town University Energy Program (STEP).
Use the links below to download documents from the GTT Transmission Workshop, held November 1-2, 2012.
Documents Home Stationary Power Safety, Security & Resilience of Energy Infrastructure Grid Modernization Cyber Security for Electric Infrastructure National Supervisory Control...
Technical Documentation Hardware Component Database: Mechanical Electrical Drawing shor tcuts BPM Development SSRL | SLAC | Stanford University | SSRL Computing | SLAC Computing...
Certain documents and publications created or issued by the Office of Classification are available from this page.
RCRA Documents Menu Permit Modifications Available for Public Comment Final Documents Draft Documents None currently available RCRA-Related Documents EEG Preliminary Comments on the Fundamental Bases of the Characterization Requirements for Disposal of Transuranic Waste at the Waste Isolation Pilot Plant and Findings and Recommendations of the Transuranic Waste Characterization Task Force Final Report EEG Response to NAS WIPP Committee Questions for May 19, 2003 Meeting Quality Assurance Program
The following lists documents that provide the statutory and legislative framework for the Title XVII loan guarantee program.
Only critical information was scanned. Entire document is available upon request - Click here to email a request....
Pekour, Mikhail S.; Berg, Larry K.
This report provides a detailed description of the Rapidly Deployable Chemical Defense System (RDCDS) Meteorological Component. The Meteorological Component includes four surface meteorological stations, miniSODAR, laptop computers, and communications equipment. This report describes the equipment that is used, explains the operation of the network, and gives instructions for setting up the Component and replacing defective parts. A detailed description of operation and use of the individual sensors, including the data loggers is not covered in the current document, and the interested reader should refer to the manufacturer’s documentation.
The Office of Document Reviews ensures that all documents prepared at DOE Headquarters are properly marked to identify the level and category of protected information they contain (if any) and to ensure that all documents the Department prepares or is required to review under applicable statutes for public release contain no information requiring protection under law, regulations and Executive orders.
Burns, John F.
This document contains a description of the system architecture for the IDC Re-Engineering Phase 2 project. This is a draft version that primarily provides background information for understanding delivered Use Case Realizations.
DFTool performs the following: ? A tool to conduct, capture, document, and manage a systematic review and flowdown of contractual requirements/documents to the site, facility, and project-level implementing documents. ? Ability to alert/email document owners to impending changes/updates and impacts to upper-level linked documents. ? Custom ability to generate reports and/or include custom functionalities based on other needs or consideration for site use. ? Ability to be accessed by all personnel (particularly document owners). ? Shows both document flow-up and flow-down. ? Provides visibility where links/flowdown does not currently exist or is incorrect so it can be changed/updated (no visibility currently exists). ? Ability to capture requirements and ultimately link to an existing/proven requirements-based commitment tracking system which can be used (electively) at the facility/organizational-level
DFTool performs the following: A tool to conduct, capture, document, and manage a systematic review and flowdown of contractual requirements/documents to the site, facility, and project-level implementing documents. Ability to alert/email document owners to impending changes/updates and impacts to upper-level linked documents. Custom ability to generate reports and/or include custom functionalities based on other needs or consideration for site use. Ability to be accessed by all personnel (particularly document owners). more » Shows both document flow-up and flow-down. Provides visibility where links/flowdown does not currently exist or is incorrect so it can be changed/updated (no visibility currently exists). Ability to capture requirements and ultimately link to an existing/proven requirements-based commitment tracking system which can be used (electively) at the facility/organizational-level« less
Separate abstracts were prepared for the 16 papers presented in this annual report of the Energy and Environment Division. (KRM)
navigation, search OpenEI Reference LibraryAdd to library Web Site: Bureau of Land Management - Techniques for Documenting a No Action Alternative in an EA Abstract This page...
No job description found Current Research Opportunities Water Quality Standards and Feasibility Studies National Permit Discharge Elimination System Permitting Physiologically...
0 Enron Documents 2000 Enron Documents for 2000, enron2000.pdf PDF icon Enron Documents 2000 More Documents & Publications Enron Documents 1996 FOIA - Enron Documents Documents ...
8 Enron Documents 1998 Enron Documents 1998 PDF icon Enron Documents 1998 More Documents & Publications FOIA - Enron Documents Enron Documents 1993 Enron Documents 1996
3 Enron Documents 1993 Enron Documents 1993. enron1993.pdf PDF icon Enron Documents 1993 More Documents & Publications FOIA - Enron Documents Enron Documents 1998 Enron Documents ...
6 Enron Documents 1996 Enron Documents 1996 PDF icon Enron Documents 1996 More Documents & Publications Enron Documents 2000 FOIA - Enron Documents Enron Documents 2001
Library NETL Document Library You can search for documents by selecting the appropriate link with in the content section or use the Search feature below Coal Document Library In response to concerns of climate change, the United States is contemplating a complete and rapid transformation of the way it both produces and consumes energy to significantly reduce its carbon emissions. The integrated Coal Program focuses on retaining the benefits of continuing to use coal to produce electric power.
Bylaws and Other Documents Postdoc Association Bylaws Bylaws and information about rules of order, meeting conduct, and motions. Contact Postdoc Program Office Email How to go about properly conducting business at a General Assembly Meeting Refer to the postdoc bylaws and other documents, below, for information on how to go about properly conducting business at a LAPA General Assembly (GA) Meeting. The first two documents will be available on the tables at the GA meetings for reference: Bylaws
Community » Community impact documents Community impact documents Fact sheets, program summaries, and other documents provide insight into the Laboratory's community efforts and impact in Northern New Mexico. Contacts Kathy Keith Community Partnerships Office (505) 665-4400 Email Making a difference in Northern New Mexico Fact sheets by county Los Alamos (pdf) Rio Arriba (pdf) San Miguel and Mora (pdf) Santa Fe (pdf) Taos (pdf) General Community Commitment Plan (pdf) | Archive Community Leaders
present the following documents when they register at the ALS User Services Office: Passport: Passport must show issue and expiration date, passport number, and photo. I-94...
The Energy Efficiency and Conservation Block Grant (EECBG) Program released guidance documents that explain how the recipients of EECBG funds need to report and manage those funds.
This standard establishes uniform Office of Environmental Management (EM) guidance on hazard baseline documents that identify and control radiological and non-radiological hazards for all EM facilities.
Archived Publications and Documents Print ALS 20-Year Roadmap, 2003 Presentations made to the BESAC subcommittee on the 20-Year BES Facilities Roadmap, with references and relevant...
Permit for Storm Water Documents Individual Permit NPDES No. NM0030759 (pdf) Storm Water Plans Site Discharge Pollution Prevention Plan (SDPPP) Volume 1 - Los AlamosPueblo...
EFRC management reference document Energy Frontier Research Centers Acknowledgments of Support (v.1, October 2009) Office of Basic Energy Sciences Office of Science US Department ...
Projects funded by the American Recovery and Reinvestment Act of 2009 (Recovery Act) were required to follow the Buy American Provision. Below are Buy American guidance documents.
Documents Memorandum from Secretary Moniz on the Freedom of Information Act (PDF) Agency Improvement Plan (PDF) FOIA Backlog Reduction Goals for Fiscal Years 2008, 2009, and 2010 ...
This document gives an overview and description of the Tank Waste Remediation System (TWRS) Information Locator Database (ILD)system design. The TWRS ILD system is an inventory of information used in the TWRS Systems Engineering process to represent the TWRS Technical Baseline. The inventory is maintained in the form of a relational database developed in Paradox 4.5.
Policy & Guidance Documents Project Management Policy & Guidance Documents << Return to Directives & Documents | Proceed to Publications & Documents >> Document Type Function
This document contains description of the technologies selected for inclusions in the Integrated Nonthermal Treatment Systems (INTS) Study. The purpose of these descriptions is to provide a more complete description of the INTS technologies. It supplements the summary descriptions of candidate nonthermal technologies that were considered for the INTS.
Problem Description * Why adding FT to MPI is difficult? * Challenges & areas of concern Lessons Learned * Where do we go from here? * Summary Approaches * Current solutions to...
ALEGRA: User Input and Physics Descriptions Version 4.2 Citation Details In-Document Search Title: ALEGRA: User Input and Physics Descriptions Version 4.2 ALEGRA is an arbitrary ...
ALEGRA: User Input and Physics Descriptions Version 4.2 Citation Details In-Document Search Title: ALEGRA: User Input and Physics Descriptions Version 4.2 You are accessing a ...
description of nuclear three-cluster systems Citation Details In-Document Search Title: Advances in the ab initio description of nuclear three-cluster systems Authors: Redondo, C R ...
This document describes facilities at the Hanford Site which are currently storing spent nuclear fuels. The descriptions provide a basis for the no-action alternatives of ongoing and planned National Environmental Protection Act reviews.
Documents Home Stationary Power Energy Conversion Efficiency Water Power Reference Model Project (RMP) Reference Model Documents Reference Model DocumentsTara Camacho-Lopez2015-05-...
Colbaugh, Richard; Glass, Kristin.; Willard, Gerald
This paper presents a new methodology for analyzing complex networks in which the network of interest is first abstracted to a much simpler (but equivalent) representation, the required analysis is performed using the abstraction, and analytic conclusions are then mapped back to the original network and interpreted there. We begin by identifying a broad and important class of complex networks which admit abstractions that are simultaneously dramatically simplifying and property preserving - we call these aggressive abstractions -- and which can therefore be analyzed using the proposed approach. We then introduce and develop two forms of aggressive abstraction: 1.) finite state abstraction, in which dynamical networks with uncountable state spaces are modeled using finite state systems, and 2.) onedimensional abstraction, whereby high dimensional network dynamics are captured in a meaningful way using a single scalar variable. In each case, the property preserving nature of the abstraction process is rigorously established and efficient algorithms are presented for computing the abstraction. The considerable potential of the proposed approach to complex networks analysis is illustrated through case studies involving vulnerability analysis of technological networks and predictive analysis for social processes.
Professor Gerd Roepke University of Rostock, Germany Abstract: Correlations are significant for the properties of nuclear systems at low densities and moderate temperatures. ...
9 Science Team MeetingPoster Abstract 2009 Proceedings Proceedings Sorted by Title Proceedings Sorted by Author Proceedings Sorted by Category
All documents by title A B C D E F G H I J K L M N O P Q R S T U V W X Y Z 40 CFR Part 191 Environmental radiation protection standards for management and disposal of spent nuclear fuel, high-level and transuranic radioactive wastes. 40 CFR Part 194 Criteria for the certification and re-certification of theWaste Isolation Pilot Plant's compliance with the 40 CFR Part 191 disposal regulations. A Back to top Accelerating Cleanup: Paths to Closure The Department of Energy Carlsbad Field Office's
This document has been compiled and issued to provide an illustrated engineering summary description of the FFTF. The document is limited to a description of the plant and its functions, and does not cover the extensive associated programs that have been carried out in the fields of design, design analysis, safety analysis, fuels development, equipment development and testing, quality assurance, equipment fabrication, plant construction, acceptance testing, operations planning and training, and the like.
The Plant Control System (PCS) is a heterogeneous computer system composed of numerous sub-systems. The PCS represents every major computer system that is used to support operation of the Waste Receiving and Processing (WRAP) facility. This document, the System Design Description (PCS SDD), includes several chapters and appendices. Each chapter is devoted to a separate PCS sub-system. Typically, each chapter includes an overview description of the system, a list of associated documents related to operation of that system, and a detailed description of relevant system features. Each appendice provides configuration information for selected PCS sub-systems. The appendices are designed as separate sections to assist in maintaining this document due to frequent changes in system configurations. This document is intended to serve as the primary reference for configuration of PCS computer systems. The use of this document is further described in the WRAP System Configuration Management Plan, WMH-350, Section 4.1.
09 D I S C L A I M E R This document was designed for the internal use of the United States Department of Energy. This document will be occasionally updated and, therefore, this copy may not reflect the most current version. This document was prepared as account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency thereof, nor any of their employees, makes any warranty, express or implied, or assumes any legal liability or
This document lists the course modules for building science courses offered at Cornell's Collaborator Sustainable Buildingi Practice course.
Becker, C.D.; Gray, R.H.
This abstracted bibliography provides a reference to the diverse environmental activities conducted on the Hanford Site from 1980 through 1988. It includes 500 reports and articles that were prepared largely by onsite contractors and the Department of Energy. Documents contained here were separated into eight subject areas: air and atmosphere, aquatic ecology, effluents and wastes, geology and hydrology, Hanford Site, radioactivity, terrestrial ecology, and socioeconomics. These areas form the basis of a key word index, which is intended to help the reader locate subjects of interest. An author index is also included.
Several hundred distinct types of DOE-owned spent nuclear fuel (DSNF) may potentially be disposed in the Yucca Mountain repository. These fuel types represent many more types than can be viably individually examined for their effect on the Total System Performance Assessment for the License Application (TSPA-LA). Additionally, for most of these fuel types, there is no known direct experimental test data for the degradation and dissolution of the waste form in repository groundwaters. The approach used in the TSPA-LA model is, therefore, to assess available information on each of 11 groups of DSNF, and to identify a model that can be used in the TSPA-LA model without differentiating between individual codisposal waste packages containing different DSNF types. The purpose of this report is to examine the available data and information concerning the dissolution kinetics of DSNF matrices for the purpose of abstracting a degradation model suitable for use in describing degradation of the DSNF inventory in the Total System Performance Assessment for the License Application. The data and information and associated degradation models were examined for the following types of DSNF: Group 1--Naval spent nuclear fuel; Group 2--Plutonium/uranium alloy (Fermi 1 SNF); Group 3--Plutonium/uranium carbide (Fast Flux Test Facility-Test Fuel Assembly SNF); Group 4--Mixed oxide and plutonium oxide (Fast Flux Test Facility-Demonstration Fuel Assembly/Fast Flux Test Facility-Test Demonstration Fuel Assembly SNF); Group 5--Thorium/uranium carbide (Fort St. Vrain SNF); Group 6--Thorium/uranium oxide (Shippingport light water breeder reactor SNF); Group 7--Uranium metal (N Reactor SNF); Group 8--Uranium oxide (Three Mile Island-2 core debris); Group 9--Aluminum-based SNF (Foreign Research Reactor SNF); Group 10--Miscellaneous Fuel; and Group 11--Uranium-zirconium hydride (Training Research Isotopes-General Atomics SNF). The analyses contained in this document provide an ''upper-limit'' (i
55 Revision 0 Hanford Standardized HAZWOPER Training Program Description Prepared for the U.S. Department of Energy Assistant Secretary for Environmental Management Approved for Public Release; Further Dissemination Unlimited Hanford Standardized HAZWOPER Training Program Description, DOE-0355 Page 2 of 12 Senior Management Team Approval Hanford Standardized HAZWOPER Training Program Description, DOE-0355 Page 3 of 12 Hanford Training Manager Approval Hanford Standardized HAZWOPER Training