Management plan documentation standard and Data Item Descriptions (DID). Volume of the information system life-cycle and documentation standards, volume 2

Science.gov (United States)

Callender, E. David; Steinbacher, Jody

1989-01-01

This is the second of five volumes of the Information System Life-Cycle and Documentation Standards. This volume provides a well-organized, easily used standard for management plans used in acquiring, assuring, and developing information systems and software, hardware, and operational procedures components, and related processes.

The System 80+ Standard Plant design control document. Volume 19

International Nuclear Information System (INIS)

1997-01-01

This Design Control Document (DCD) is a repository of information comprising the System 80+trademark Standard Plant Design. The DCD also provides that design-related information to be incorporated by reference in the design certification rule for the System 80+ Standard Plant Design. Applicants for a combined license pursuant to 10 CFR 52 must ensure that the final Design Certification Rule and the associated Statements of Consideration are used when making all licensing decisions relevant to the System 80+ Standard Plant Design. The Design Control Document contains the DCD introduction, The Certified Design Material (CDM) [i.e., ''Tier 1''] and the Approved Design Material (ADM) [i.e., ''Tier 2''] for the System 80+ Standard Plant Design. The CDM includes the following sections: (1) Introductory material; (2) Certified Design Material for System 80+ systems and structures; (3) Certified Design Material for non-system-based aspects of the System 80+ Certified design; (4) Interface requirements; and (5) Site parameters. The ADM, to the extent applicable for the System 80+ Standard Plant Design, includes: (1) the information required for the final safety analysis report under 20 CFR 50.34; (2) other relevant information required by 10 CFR 52.47; and (3) emergency operations guidelines. This volume contains five technical specification bases that are part of Appendix 16 A of the ADM Design and Analysis. They are: TS B3.3 Instrumentation Bases; TS B3.4 RCS Bases; TS B3.5 ECCS Bases; TS B3.6 Containment Systems Bases; and TS B3.7 Plant Systems Bases

The System 80+ Standard Plant design control document. Volume 24

International Nuclear Information System (INIS)

1997-01-01

This Design Control Document (DCD) is a repository of information comprising the System 80+trademark Standard Plant Design. The DCD also provides that design-related information to be incorporated by reference in the design certification rule for the System 80+ Standard Plant Design. Applicants for a combined license pursuant to 10 CFR 52 must ensure that the final Design Certification Rule and the associated Statements of Consideration are used when making all licensing decisions relevant to the System 80+ Standard Plant Design. The Design Control Document contains the DCD introduction, The Certified Design Material (CDM) [i.e., ''Tier 1''] and the Approved Design Material (ADM) [i.e., ''Tier 2''] for the System 80+ Standard Plant Design. The CDM includes the following sections: (1) Introductory material; (2) Certified Design Material for System 80+ systems and structures; (3) Certified Design Material for non-system-based aspects of the System 80+ Certified design; (4) Interface requirements; and (5) Site parameters. The ADM, to the extent applicable for the System 80+ Standard Plant Design, includes: (1) the information required for the final safety analysis report under 20 CFR 50.34; (2) other relevant information required by 10 CFR 52.47; and (3) emergency operations guidelines. This volume contains sections 7--11 of the ADM Emergency Operations Guidelines. Topics covered are: excess steam demand recovery; loss of all feedwater; loss of offsite power; station blackout recovery; and functional recovery guideline. Appendix A Severe Accident Management Guidelines and Appendix B Lower Mode Operational Guidelines are also included

The System 80+ Standard Plant design control document. Volume 10

International Nuclear Information System (INIS)

1997-01-01

This Design Control Document (DCD) is a repository of information comprising the System 80+trademark Standard Plant Design. The DCD also provides that design-related information to be incorporated by reference in the design certification rule for the System 80+ Standard Plant Design. Applicants for a combined license pursuant to 10 CFR 52 must ensure that the final Design Certification Rule and the associated Statements of Consideration are used when making all licensing decisions relevant to the System 80+ Standard Plant Design. The Design Control Document contains the DCD introduction, The Certified Design Material (CDM) [i.e., ''Tier 1''] and the Approved Design Material (ADM) [i.e., ''Tier 2''] for the System 80+ Standard Plant Design. The CDM includes the following sections: (1) Introductory material; (2) Certified Design Material for System 80+ systems and structures; (3) Certified Design Material for non-system-based aspects of the System 80+ Certified design; (4) Interface requirements; and (5) Site parameters. The ADM, to the extent applicable for the System 80+ Standard Plant Design, includes: (1) the information required for the final safety analysis report under 20 CFR 50.34; (2) other relevant information required by 10 CFR 52.47; and (3) emergency operations guidelines. This volume contains Appendices 6A, 6B, and 6C for section 6 (Engineered Safety Features) of the ADM Design and Analysis. Also, parts 1--5 of section 7 (Instrumentation and Control) of the ADM Design and Analysis are covered. The following information is covered in these parts: introduction; reactor protection system; ESF actuation system; system required for safe shutdown; and safety-related display instrumentation

DART II documentation. Volume III. Appendices

Energy Technology Data Exchange (ETDEWEB)

1979-10-01

The DART II is a remote, interactive, microprocessor-based data acquistion system suitable for use with air monitors. This volume of DART II documentation contains the following appendixes: adjustment and calibration procedures; mother board signature list; schematic diagrams; device specification sheets; ROM program listing; 6800 microprocessor instruction list, octal listing; and cable lists. (RWR)

The System 80+ Standard Plant design control document. Volume 17

International Nuclear Information System (INIS)

1997-01-01

This Design Control Document (DCD) is a repository of information comprising the System 80+trademark Standard Plant Design. The DCD also provides that design-related information to be incorporated by reference in the design certification rule for the System 80+ Standard Plant Design. Applicants for a combined license pursuant to 10 CFR 52 must ensure that the final Design Certification Rule and the associated Statements of Consideration are used when making all licensing decisions relevant to the System 80+ Standard Plant Design. The Design Control Document contains the DCD introduction, The Certified Design Material (CDM) [i.e., ''Tier 1''] and the Approved Design Material (ADM) [i.e., ''Tier 2''] for the System 80+ Standard Plant Design. The CDM includes the following sections: (1) Introductory material; (2) Certified Design Material for System 80+ systems and structures; (3) Certified Design Material for non-system-based aspects of the System 80+ Certified design; (4) Interface requirements; and (5) Site parameters. The ADM, to the extent applicable for the System 80+ Standard Plant Design, includes: (1) the information required for the final safety analysis report under 20 CFR 50.34; (2) other relevant information required by 10 CFR 52.47; and (3) emergency operations guidelines. This volume contains parts 2-7 and appendix 15A for section 15 (Accident Analysis) of the ADM Design and Analysis. Topics covered in these parts are: decrease in heat removal; decrease in RCS flow rate; power distribution anomalies; increase in RCS inventory; decrease in RCS inventory; release of radioactive materials. The appendix covers radiological release models. Also contained here are five technical specifications for section 16 (Technical Specifications) of the ADM Design and Analysis. They are: TS 1.0 Use and Applications; TS 2.0 Safety Limits; TS 3.0 LCO Availability; TS 3.1 Reactivity Control; and TS 3.2 Power Distribution

Documentation for Grants Equal to Tax model: Volume 1, Technical description

International Nuclear Information System (INIS)

1986-01-01

A computerized model, the Grants Equal to Tax (GETT) model, was developed to assist in evaluating the amount of federal grant monies that would go to state and local jurisdictions under the provisions outlined in the Nuclear Waste Policy Act of 1982. The GETT model is capable of forecasting the amount of tax liability associated with all property owned and all activities undertaken by the US Department of Energy (DOE) in site characterization and repository development. The GETT program is a user-friendly, menu-driven model developed using dBASE III/trademark/, a relational data base management system. The data base for GETT consists primarily of eight separate dBASE III/trademark/ files corresponding to each of the eight taxes levied by state and local jurisdictions on business property and activity. Additional smaller files help to control model inputs and reporting options. Volume 1 of the GETT model documentation is a technical description of the program and its capabilities providing (1) descriptions of the data management system and its procedures; (2) formulas for calculating taxes (illustrated with flow charts); (3) descriptions of tax data base variables for the Deaf Smith County, Texas, Richton Dome, Mississippi, and Davis Canyon, Utah, salt sites; and (4) data inputs for the GETT model. 10 refs., 18 figs., 3 tabs

The System 80+ Standard Plant design control document. Volume 18

International Nuclear Information System (INIS)

1997-01-01

This Design Control Document (DCD) is a repository of information comprising the System 80+trademark Standard Plant Design. The DCD also provides that design-related information to be incorporated by reference in the design certification rule for the System 80+ Standard Plant Design. Applicants for a combined license pursuant to 10 CFR 52 must ensure that the final Design Certification Rule and the associated Statements of Consideration are used when making all licensing decisions relevant to the System 80+ Standard Plant Design. The Design Control Document contains the DCD introduction, The Certified Design Material (CDM) [i.e., ''Tier 1''] and the Approved Design Material (ADM) [i.e., ''Tier 2''] for the System 80+ Standard Plant Design. The CDM includes the following sections: (1) Introductory material; (2) Certified Design Material for System 80+ systems and structures; (3) Certified Design Material for non-system-based aspects of the System 80+ Certified design; (4) Interface requirements; and (5) Site parameters. The ADM, to the extent applicable for the System 80+ Standard Plant Design, includes: (1) the information required for the final safety analysis report under 20 CFR 50.34; (2) other relevant information required by 10 CFR 52.47; and (3) emergency operations guidelines. This volume contains the following technical specifications of section 16 (Technical Specifications) of the ADM Design and Analysis: TS 3.3 Instrumentation; TS 3.4 Reactor Coolant System; TS 3.5 Emergency Core Cooling System; TS 3.6 Containment Systems; TS 3.7 Plant Systems; TS 3.8 Electrical Power Systems; TS 3.9 Refueling Operations; TS 4.0 Design Features; TS 5.0 Administrative Controls. Appendix 16 A Tech Spec Bases is also included. It contains the following: TS B2.0 Safety Limits Bases; TS B3.0 LCO Applicability Bases; TS B3.1 Reactivity Control Bases; TS B3.2 Power Distribution Bases

Community Documentation Centre on Industrial Risk. Volume 3 (consolidated volume containing also content of vol. 1 and 2)

International Nuclear Information System (INIS)

1990-09-01

The Directorate-General for Environment, Nuclear Safety and Civil Protection of the Commission of the European Communities is responsible for the effective and harmonized implementation of the Directive 82/501/EEC on the major-accident hazards of certain industrial activities. To this end, the Commission, in collaboration with the Committee of Competent Authorities responsible for the implementation of this Directive in the twelve Member States, carries out a whole range of activities. One of the most essential areas for action identified was the need for a systematic diffusion of information concerning the practical implementation of the Directive in the Member States, including the technical rules and guidelines applied, the safety practices and the lessons learnt from major accidents. Therefore, the Commission decided to set up a Community Documentation Centre on Industrial Risks (CDCIR). This Documentation Centre is run by the European Commission, Joint Research Centre, Institute for Systems Engineering and Informatics (ISEI), at Ispra, Italy, among its support activities on the implementation of the Directive. The Documentation Centre will collect, classify and review technical rules, guidelines and documents concerning the requirements of the Directive, as well as the safety of industrial installations produced by governments, administrative, scientific or technical bodies, national or international organizations and industrial or professional associations. Documents on major accidents in the form of reports, videotapes will also be collected and reviewed. The Centre is accessible to interested visitors, documents which are not covered by copyright and are not restricted can be obtained from the Documentation Centre on request. Periodical volumes which will feature the inventory, including abstracts, of the collected material will be published and made available to all interested parties. The Centre will also publish documents devoted to compare existing

Management control and status reports documentation standard and Data Item Descriptions (DID). Volume of the information system life-cycle and documentation standards, volume 5

Science.gov (United States)

Callender, E. David; Steinbacher, Jody

1989-01-01

This is the fifth of five volumes on Information System Life-Cycle and Documentation Standards. This volume provides a well organized, easily used standard for management control and status reports used in monitoring and controlling the management, development, and assurance of informations systems and software, hardware, and operational procedures components, and related processes.

Waste management system requirements document

International Nuclear Information System (INIS)

1991-02-01

This volume defines the top level requirements for the Mined Geologic Disposal System (MGDS). It is designed to be used in conjunction with Volume 1 of the WMSR, General System Requirements. It provides a functional description expanding the requirements allocated to the MGDS in Volume 1 and elaborates on each requirement by providing associated performance criteria as appropriate. Volumes 1 and 4 of the WMSR provide a minimum set of requirements that must be satisfied by the final MGDS design. This document sets forth specific requirements that must be fulfilled. It is not the intent or purpose of this top level document to describe how each requirement is to be satisfied in the final MGDS design. Each subsequent level of the technical document hierarchy must provide further guidance and definition as to how each of these requirements is to be implemented in the design. It is expected that each subsequent level of requirements will be significantly more detailed. Section 2 of this volume provides a functional description of the MGDS. Each function is addressed in terms of requirements, and performance criteria. Section 3 provides a list of controlling documents. Each document cited in a requirement of Chapter 2 is included in this list and is incorporated into this document as a requirement on the final system. The WMSR addresses only federal requirements (i.e., laws, regulations and DOE orders). State and local requirements are not addressed. However, it will be specifically noted at the potentially affected WMSR requirements that there could be additional or more stringent regulations imposed by a state or local requirements or administering agency over the cited federal requirements

Evaluation of potential severe accidents during low power and shutdown operations at Grand Gulf, Unit 1: Summary of results. Volume 1

International Nuclear Information System (INIS)

Whitehead, D.W.; Staple, B.D.; Daniel, S.L.

1995-07-01

During 1989 the Nuclear Regulatory Commission (NRC) initiated an extensive program to examine the potential risks during low power and shutdown operations. Two plants, Surry and Grand Gulf, were selected as the plants to be studied by Brookhaven National Laboratory (Surry) and Sandia National Laboratories (Grand Gulf). This report documents the work performed during the analysis of the Grand Gulf plant. A phased approach was used for the overall study. In Phase 1, the objectives were to identify potential vulnerable plant configurations, to characterize (on a high, medium, or low basis) the potential core damage accident scenario frequencies and risks, and to provide a foundation for a detailed Phase 2 analysis. It was in Phase 1 that the concept of plant operational states (POSs) was developed to allow the analysts to better represent the plant as it transitions from power operation to nonpower operation than was possible with the traditional technical specification divisions of modes of operation. This phase consisted of a coarse screening analysis performed for all POSs, including seismic and internal fire and flood for some POSs. In Phase 2, POS 5 (approximately cold shutdown as defined by Grand Gulf Technical Specifications) during a refueling outage was selected as the plant configuration to be analyzed based on the results of the Phase 1 study. The scope of the Level 1 study includes plant damage state analysis and uncertainty analysis and is documented in a multi-volume NUREG/CR report (i.e., NUREG/CR-6143). The internal events analysis is documented in Volume 2. Internal fire and internal flood analyses are documented in Volumes 3 and 4, respectively. A separate study on seismic analysis, documented in Volume 5, was performed for the NRC by Future Resources Associates, Inc. The Level 2/3 study of the traditional internal events is documented in Volume 6, and a summary of the results for all analyses is documented in Volume 1

Evaluation of potential severe accidents during low power and shutdown operations at Grand Gulf, Unit 1: Summary of results. Volume 1

Energy Technology Data Exchange (ETDEWEB)

Whitehead, D.W. [ed.; Staple, B.D.; Daniel, S.L. [and others

1995-07-01

During 1989 the Nuclear Regulatory Commission (NRC) initiated an extensive program to examine the potential risks during low power and shutdown operations. Two plants, Surry and Grand Gulf, were selected as the plants to be studied by Brookhaven National Laboratory (Surry) and Sandia National Laboratories (Grand Gulf). This report documents the work performed during the analysis of the Grand Gulf plant. A phased approach was used for the overall study. In Phase 1, the objectives were to identify potential vulnerable plant configurations, to characterize (on a high, medium, or low basis) the potential core damage accident scenario frequencies and risks, and to provide a foundation for a detailed Phase 2 analysis. It was in Phase 1 that the concept of plant operational states (POSs) was developed to allow the analysts to better represent the plant as it transitions from power operation to nonpower operation than was possible with the traditional technical specification divisions of modes of operation. This phase consisted of a coarse screening analysis performed for all POSs, including seismic and internal fire and flood for some POSs. In Phase 2, POS 5 (approximately cold shutdown as defined by Grand Gulf Technical Specifications) during a refueling outage was selected as the plant configuration to be analyzed based on the results of the Phase 1 study. The scope of the Level 1 study includes plant damage state analysis and uncertainty analysis and is documented in a multi-volume NUREG/CR report (i.e., NUREG/CR-6143). The internal events analysis is documented in Volume 2. Internal fire and internal flood analyses are documented in Volumes 3 and 4, respectively. A separate study on seismic analysis, documented in Volume 5, was performed for the NRC by Future Resources Associates, Inc. The Level 2/3 study of the traditional internal events is documented in Volume 6, and a summary of the results for all analyses is documented in Volume 1.

1991 SOLAR WORLD CONGRESS - VOLUME 1, PART I

Science.gov (United States)

The four-volume proceedings document the 1991 Solar World Congress (the biennial congress of the International Solar Energy Society) in Denver, CO, August 19-23, 1991. Volume 1 is dedicated to solar electricity, biofuels, and renewable resources. Volume 2 contains papers on activ...

Title list of documents made publicly available. Volume 17, No. 1

International Nuclear Information System (INIS)

1995-03-01

This document is a monthly publication containing descriptions of information received and generated by the US Nuclear Regulatory Commission (NRC). This information includes (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials, and (2) nondocketed material received and generated by NRC pertinent to its role as a regulatory agency. The following indexes are included: Personal author, corporate source, report number, and cross reference of enclosures to principal documents

Title list of documents made publicly available. Volume 17, No. 1

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-03-01

This document is a monthly publication containing descriptions of information received and generated by the US Nuclear Regulatory Commission (NRC). This information includes (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials, and (2) nondocketed material received and generated by NRC pertinent to its role as a regulatory agency. The following indexes are included: Personal author, corporate source, report number, and cross reference of enclosures to principal documents.

Guidance and Control Software Project Data - Volume 4: Configuration Management and Quality Assurance Documents

Science.gov (United States)

Hayhurst, Kelly J. (Editor)

2008-01-01

The Guidance and Control Software (GCS) project was the last in a series of software reliability studies conducted at Langley Research Center between 1977 and 1994. The technical results of the GCS project were recorded after the experiment was completed. Some of the support documentation produced as part of the experiment, however, is serving an unexpected role far beyond its original project context. Some of the software used as part of the GCS project was developed to conform to the RTCA/DO-178B software standard, "Software Considerations in Airborne Systems and Equipment Certification," used in the civil aviation industry. That standard requires extensive documentation throughout the software development life cycle, including plans, software requirements, design and source code, verification cases and results, and configuration management and quality control data. The project documentation that includes this information is open for public scrutiny without the legal or safety implications associated with comparable data from an avionics manufacturer. This public availability has afforded an opportunity to use the GCS project documents for DO-178B training. This report provides a brief overview of the GCS project, describes the 4-volume set of documents and the role they are playing in training, and includes configuration management and quality assurance documents from the GCS project. Volume 4 contains six appendices: A. Software Accomplishment Summary for the Guidance and Control Software Project; B. Software Configuration Index for the Guidance and Control Software Project; C. Configuration Management Records for the Guidance and Control Software Project; D. Software Quality Assurance Records for the Guidance and Control Software Project; E. Problem Report for the Pluto Implementation of the Guidance and Control Software Project; and F. Support Documentation Change Reports for the Guidance and Control Software Project.

Guidance and Control Software Project Data - Volume 2: Development Documents

Science.gov (United States)

Hayhurst, Kelly J. (Editor)

2008-01-01

The Guidance and Control Software (GCS) project was the last in a series of software reliability studies conducted at Langley Research Center between 1977 and 1994. The technical results of the GCS project were recorded after the experiment was completed. Some of the support documentation produced as part of the experiment, however, is serving an unexpected role far beyond its original project context. Some of the software used as part of the GCS project was developed to conform to the RTCA/DO-178B software standard, "Software Considerations in Airborne Systems and Equipment Certification," used in the civil aviation industry. That standard requires extensive documentation throughout the software development life cycle, including plans, software requirements, design and source code, verification cases and results, and configuration management and quality control data. The project documentation that includes this information is open for public scrutiny without the legal or safety implications associated with comparable data from an avionics manufacturer. This public availability has afforded an opportunity to use the GCS project documents for DO-178B training. This report provides a brief overview of the GCS project, describes the 4-volume set of documents and the role they are playing in training, and includes the development documents from the GCS project. Volume 2 contains three appendices: A. Guidance and Control Software Development Specification; B. Design Description for the Pluto Implementation of the Guidance and Control Software; and C. Source Code for the Pluto Implementation of the Guidance and Control Software

Guidance and Control Software Project Data - Volume 3: Verification Documents

Science.gov (United States)

Hayhurst, Kelly J. (Editor)

2008-01-01

The Guidance and Control Software (GCS) project was the last in a series of software reliability studies conducted at Langley Research Center between 1977 and 1994. The technical results of the GCS project were recorded after the experiment was completed. Some of the support documentation produced as part of the experiment, however, is serving an unexpected role far beyond its original project context. Some of the software used as part of the GCS project was developed to conform to the RTCA/DO-178B software standard, "Software Considerations in Airborne Systems and Equipment Certification," used in the civil aviation industry. That standard requires extensive documentation throughout the software development life cycle, including plans, software requirements, design and source code, verification cases and results, and configuration management and quality control data. The project documentation that includes this information is open for public scrutiny without the legal or safety implications associated with comparable data from an avionics manufacturer. This public availability has afforded an opportunity to use the GCS project documents for DO-178B training. This report provides a brief overview of the GCS project, describes the 4-volume set of documents and the role they are playing in training, and includes the verification documents from the GCS project. Volume 3 contains four appendices: A. Software Verification Cases and Procedures for the Guidance and Control Software Project; B. Software Verification Results for the Pluto Implementation of the Guidance and Control Software; C. Review Records for the Pluto Implementation of the Guidance and Control Software; and D. Test Results Logs for the Pluto Implementation of the Guidance and Control Software.

Forecasted electric power demands for the Baltimore Gas and Electric Company. Volume 1 and Volume 2. Documentation manual

International Nuclear Information System (INIS)

Estomin, S.L.; Beach, J.E.; Goldsmith, J.V.

1991-05-01

The two-volume report presents the results of an econometric forecast of peak load and electric power demand for the Baltimore Gas and Electric Company (BG ampersand E) through the year 2009. Separate energy sales models were estimated for residential sales in Baltimore City, residential sales in the BG ampersand E service area excluding Baltimore City, commercial sales, industrial sales, streetlighting sales, and Company use plus losses. Econometric equations were also estimated for electric space heating and air conditioning saturation in Baltimore City and in the remainder of the BG ampersand E service territory. In addition to the energy sales models and the electric space conditioning saturation models, econometric models of summer and winter peak demand on the BG ampersand E system were estimated

Uranium milling: Draft generic environmental impact statement: Volume 2, Appendices

International Nuclear Information System (INIS)

1979-04-01

This volume contains appendices supporting the discussions in Volume 1. In some cases, the appendices expound upon arguments developed in the main document; in other cases, supplementary material considered to be relevant but not presented in Volume 1 is included. A third category encompasses reprinting of pertinent documents felt to be necessary for a comprehensive presentation of the current situation, e.g., Public Law 95-604

Title list of documents made publicly available, January 1--31, 1994. Volume 16, No. 1

Energy Technology Data Exchange (ETDEWEB)

None

1994-03-01

This document is a monthly publication containing descriptions of information received and generated by the US Nuclear Regulatory Commission (NRC). This information includes (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials, and (2) nondocketed material received and generated by NRC pertinent to its role as a regulator agency. The following indexes are included: Personal Author, Corporate Source, Report Number, and Cross Reference of Enclosures to Principal Documents.

Low-level radioactive waste from commercial nuclear reactors. Volume 3. Bibliographic abstracts of significant source documents. Part 1. Open-literature abstracts for low-level radioactive waste

International Nuclear Information System (INIS)

Bowers, M.K.; Rodgers, B.R.; Jolley, R.L.

1986-05-01

The overall task of this program was to provide an assessment of currently available technology for treating commercial low-level radioactive waste (LLRW), to initiate development of a methodology for choosing one technology for a given application, and to identify research needed to improve current treatment techniques and decision methodology. The resulting report is issued in four volumes. Volume 3 of this series is a collection of abstracts of most of the reference documents used for this study. Because of the large volume of literature, the abstracts have been printed in two separate parts. Volume 3, part 1 presents abstracts of the open literature relating to LLRW treatment methodologies. Some of these references pertain to treatment processes for hazardous wastes that may also be applicable to LLRW management. All abstracts have been limited to 21 lines (for brevity), but each abstract contains sufficient information to enable the reader to determine the potential usefulness of the source document and to locate each article. The abstracts are arranged alphabetically by author or organization, and indexed by keyword

Low-level radioactive waste from commercial nuclear reactors. Volume 3. Bibliographic abstracts of significant source documents. Part 1. Open-literature abstracts for low-level radioactive waste

Energy Technology Data Exchange (ETDEWEB)

Bowers, M.K.; Rodgers, B.R.; Jolley, R.L.

1986-05-01

The overall task of this program was to provide an assessment of currently available technology for treating commercial low-level radioactive waste (LLRW), to initiate development of a methodology for choosing one technology for a given application, and to identify research needed to improve current treatment techniques and decision methodology. The resulting report is issued in four volumes. Volume 3 of this series is a collection of abstracts of most of the reference documents used for this study. Because of the large volume of literature, the abstracts have been printed in two separate parts. Volume 3, part 1 presents abstracts of the open literature relating to LLRW treatment methodologies. Some of these references pertain to treatment processes for hazardous wastes that may also be applicable to LLRW management. All abstracts have been limited to 21 lines (for brevity), but each abstract contains sufficient information to enable the reader to determine the potential usefulness of the source document and to locate each article. The abstracts are arranged alphabetically by author or organization, and indexed by keyword.

LLCEDATA and LLCECALC for Windows version 1.0, Volume 1: User's manual

International Nuclear Information System (INIS)

McFadden, J.G.

1998-01-01

LLCEDATA and LLCECALC for Windows are user-friendly computer software programs that work together to determine the proper waste designation, handling, and disposition requirements for Long Length Contaminated Equipment (LLCE). LLCEDATA reads from a variety of data bases to produce an equipment data file (EDF) that represents a snapshot of both the LLCE and the tank it originates from. LLCECALC reads the EDF and a gamma assay (AV2) file that is produced by the Flexible Receiver Gamma Energy Analysis System. LLCECALC performs corrections to the AV2 file as it is being read and characterizes the LLCE. Both programs produce a variety of reports, including a characterization report and a status report. The status report documents each action taken by the user, LLCEDATA, and LLCECALC. Documentation for LLCEDATA and LLCECALC for Windows is available in three volumes. Volume 1 is a user's manual, which is intended as a quick reference for both LLCEDATA and LLCECALC. Volume 2 is a technical manual, and Volume 3 is a software verification and validation document

Impact of an electronic health record operating room management system in ophthalmology on documentation time, surgical volume, and staffing.

Science.gov (United States)

Sanders, David S; Read-Brown, Sarah; Tu, Daniel C; Lambert, William E; Choi, Dongseok; Almario, Bella M; Yackel, Thomas R; Brown, Anna S; Chiang, Michael F

2014-05-01

Although electronic health record (EHR) systems have potential benefits, such as improved safety and quality of care, most ophthalmology practices in the United States have not adopted these systems. Concerns persist regarding potential negative impacts on clinical workflow. In particular, the impact of EHR operating room (OR) management systems on clinical efficiency in the ophthalmic surgery setting is unknown. To determine the impact of an EHR OR management system on intraoperative nursing documentation time, surgical volume, and staffing requirements. For documentation time and circulating nurses per procedure, a prospective cohort design was used between January 10, 2012, and January 10, 2013. For surgical volume and overall staffing requirements, a case series design was used between January 29, 2011, and January 28, 2013. This study involved ophthalmic OR nurses (n = 13) and surgeons (n = 25) at an academic medical center. Electronic health record OR management system implementation. (1) Documentation time (percentage of operating time documenting [POTD], absolute documentation time in minutes), (2) surgical volume (procedures/time), and (3) staffing requirements (full-time equivalents, circulating nurses/procedure). Outcomes were measured during a baseline period when paper documentation was used and during the early (first 3 months) and late (4-12 months) periods after EHR implementation. There was a worsening in total POTD in the early EHR period (83%) vs paper baseline (41%) (P system implementation was associated with worsening of intraoperative nursing documentation time especially in shorter procedures. However, it is possible to implement an EHR OR management system without serious negative impacts on surgical volume and staffing requirements.

High-level waste storage tank farms/242-A evaporator Standards/Requirements Identification Document (S/RID), Volume 4

Energy Technology Data Exchange (ETDEWEB)

1994-04-01

The High-Level Waste Storage Tank Farms/242-A Evaporator Standards/Requirements Identification Document (S/RID) is contained in multiple volumes. This document (Volume 4) presents the standards and requirements for the following sections: Radiation Protection and Operations.

High-level waste storage tank farms/242-A evaporator Standards/Requirements Identification Document (S/RID), Volume 4

International Nuclear Information System (INIS)

1994-04-01

The High-Level Waste Storage Tank Farms/242-A Evaporator Standards/Requirements Identification Document (S/RID) is contained in multiple volumes. This document (Volume 4) presents the standards and requirements for the following sections: Radiation Protection and Operations

High-level waste storage tank farms/242-A evaporator Standards/Requirements Identification Document (S/RID), Volume 5

International Nuclear Information System (INIS)

1994-04-01

The High-Level Waste Storage Tank Farms/242-A Evaporator Standards/Requirements Identification Document (S/RID) is contained in multiple volumes. This document (Volume 5) outlines the standards and requirements for the Fire Protection and Packaging and Transportation sections

LLCEDATA and LLCECALC for Windows version 1.0, Volume 1: User`s manual

Energy Technology Data Exchange (ETDEWEB)

McFadden, J.G.

1998-09-04

LLCEDATA and LLCECALC for Windows are user-friendly computer software programs that work together to determine the proper waste designation, handling, and disposition requirements for Long Length Contaminated Equipment (LLCE). LLCEDATA reads from a variety of data bases to produce an equipment data file (EDF) that represents a snapshot of both the LLCE and the tank it originates from. LLCECALC reads the EDF and a gamma assay (AV2) file that is produced by the Flexible Receiver Gamma Energy Analysis System. LLCECALC performs corrections to the AV2 file as it is being read and characterizes the LLCE. Both programs produce a variety of reports, including a characterization report and a status report. The status report documents each action taken by the user, LLCEDATA, and LLCECALC. Documentation for LLCEDATA and LLCECALC for Windows is available in three volumes. Volume 1 is a user`s manual, which is intended as a quick reference for both LLCEDATA and LLCECALC. Volume 2 is a technical manual, and Volume 3 is a software verification and validation document.

User's guide for PRISM (Plant Risk Status Information Management System) Arkansas Nuclear One-Unit 1: Volume 1, Program for inspectors

International Nuclear Information System (INIS)

Campbell, D.J.; Guthrie, V.H.; Kirchner, J.R.; Kirkman, J.Q.; Paula, H.M.; Ellison, B.C.; Dycus, F.M.; Farquharson, J.A.; Flanagan, G.F.

1988-03-01

This user's guide is a two-volume document designed to teach NRC inspectors and NRC regulators how to access probabilistic risk assessment information from the two Plant Risk Status Information Management System (PRISIM) programs developed for Arkansas Nuclear One -- Unit One (ANO-1). This document, Volume 1, describes how the PRA information available in Version 1.0 of PRISIM is useful for planning inspections. Using PRISIM, inspectors can quickly access PRA information and use that information to update risk analysis results, reflecting a plant's status at any particular time. Both volumes are stand-alone documents, and each volume presents several sample computer sessions designed to lead the user through a variety of PRISIM applications used to obtain PRA-related information for monitoring and controlling plant risk

Evaluation of potential severe accidents during low power and shutdown operations at Surry, Unit 1: Analysis of core damage frequency from internal events during mid-loop operations. Appendix E (Sections E.9-E.16), Volume 2, Part 3B

International Nuclear Information System (INIS)

Chu, T.L.; Musicki, Z.; Kohut, P.; Yang, J.; Bozoki, G.; Hsu, C.J.; Diamond, D.J.; Wong, S.M.; Bley, D.; Johnson, D.

1994-06-01

Traditionally, probabilistic risk assessments (PRA) of severe accidents in nuclear power plants have considered initiating events potentially occurring only during full power operation. Some previous screening analyses that were performed for other modes of operation suggested that risks during those modes were small relative to full power operation. However, more recent studies and operational experience have implied that accidents during low power and shutdown could be significant contributors to risk. Two plants, Surry (pressurized water reactor) and Grand Gulf (boiling water reactor), were selected as the plants to be studied. The objectives of the program are to assess the risks of severe accidents initiated during plant operational states other than full power operation and to compare the estimated core damage frequencies, important accident sequences and other qualitative and quantitative results with those accidents initiated during full power operation as assessed in NUREG-1150. The scope of the program includes that of a level-3 PRA. In phase 2, mid-loop operation was selected as the plant configuration to be analyzed based on the results of the phase 1 study. The objective of the phase 2 study is to perform a detailed analysis of the potential accident scenarios that may occur during mid-loop operation, and compare the results with those of NUREG-1150. The scope of the level-1 study includes plant damage state analysis, and uncertainty analysis. Volume 1 summarizes the results of the study. Internal events analysis is documented in Volume 2. It also contains an appendix that documents the part of the phase 1 study that has to do with POSs other than mid-loop operation. Internal fire and internal flood analyses are documented in Volumes 3 and 4. A separate study on seismic analysis, documented in Volume 5, was performed for the NRC by Future Resources Associates, Inc. Volume 6 documents the accident progression, source terms, and consequence analysis

Evaluation of potential severe accidents during low power and shutdown operations at Surry, Unit 1: Analysis of core damage frequency from internal events during mid-loop operations. Appendix E (Sections E.9-E.16), Volume 2, Part 3B

Energy Technology Data Exchange (ETDEWEB)

Chu, T.L.; Musicki, Z.; Kohut, P.; Yang, J.; Bozoki, G.; Hsu, C.J.; Diamond, D.J.; Wong, S.M. [Brookhaven National Lab., Upton, NY (United States); Bley, D.; Johnson, D. [PLG Inc., Newport Beach, CA (United States)] [and others

1994-06-01

Traditionally, probabilistic risk assessments (PRA) of severe accidents in nuclear power plants have considered initiating events potentially occurring only during full power operation. Some previous screening analyses that were performed for other modes of operation suggested that risks during those modes were small relative to full power operation. However, more recent studies and operational experience have implied that accidents during low power and shutdown could be significant contributors to risk. Two plants, Surry (pressurized water reactor) and Grand Gulf (boiling water reactor), were selected as the plants to be studied. The objectives of the program are to assess the risks of severe accidents initiated during plant operational states other than full power operation and to compare the estimated core damage frequencies, important accident sequences and other qualitative and quantitative results with those accidents initiated during full power operation as assessed in NUREG-1150. The scope of the program includes that of a level-3 PRA. In phase 2, mid-loop operation was selected as the plant configuration to be analyzed based on the results of the phase 1 study. The objective of the phase 2 study is to perform a detailed analysis of the potential accident scenarios that may occur during mid-loop operation, and compare the results with those of NUREG-1150. The scope of the level-1 study includes plant damage state analysis, and uncertainty analysis. Volume 1 summarizes the results of the study. Internal events analysis is documented in Volume 2. It also contains an appendix that documents the part of the phase 1 study that has to do with POSs other than mid-loop operation. Internal fire and internal flood analyses are documented in Volumes 3 and 4. A separate study on seismic analysis, documented in Volume 5, was performed for the NRC by Future Resources Associates, Inc. Volume 6 documents the accident progression, source terms, and consequence analysis.

Human-system interface design review guideline -- Process and guidelines: Final report. Revision 1, Volume 1

International Nuclear Information System (INIS)

1996-06-01

NUREG-0700, Revision 1, provides human factors engineering (HFE) guidance to the US Nuclear Regulatory Commission staff for its: (1) review of the human system interface (HSI) design submittals prepared by licensees or applications for a license or design certification of commercial nuclear power plants, and (2) performance of HSI reviews that could be undertaken as part of an inspection or other type of regulatory review involving HSI design or incidents involving human performance. The guidance consists of a review process and HFE guidelines. The document describes those aspects of the HSI design review process that are important to the identification and resolution of human engineering discrepancies that could adversely affect plant safety. Guidance is provided that could be used by the staff to review an applicant's HSI design review process or to guide the development of an HSI design review plan, e.g., as part of an inspection activity. The document also provides detailed HFE guidelines for the assessment of HSI design implementations. NUREG-0700, Revision 1, consists of three stand-alone volumes. Volume 1 consists of two major parts. Part 1 describes those aspects of the review process of the HSI design that are important to identifying and resolving human engineering discrepancies. Part 2 contains detailed guidelines for a human factors engineering review which identify criteria for assessing the implementation of an applicant's or licensee's HSI design

Data collection system. Volume 1, Overview and operators manual; Volume 2, Maintenance manual; Appendices

Energy Technology Data Exchange (ETDEWEB)

Caudell, R.B.; Bauder, M.E.; Boyer, W.B.; French, R.E.; Isidoro, R.J.; Kaestner, P.C.; Perkins, W.G.

1993-09-01

Sandia National Laboratories (SNL) Instrumentation Development Department was tasked by the Defense Nuclear Agency (DNA) to record data on Tektronix RTD720 Digitizers on the HUNTERS TROPHY field test conducted at the Nevada Test Site (NTS) on September 18, 1992. This report contains a overview and description of the computer hardware and software that was used to acquire, reduce, and display the data. The document is divided into two volumes: an overview and operators manual (Volume 1) and a maintenance manual (Volume 2).

Underground Test Area Subproject Phase I Data Analysis Task. Volume VIII - Risk Assessment Documentation Package

Energy Technology Data Exchange (ETDEWEB)

None

1996-12-01

Volume VIII of the documentation for the Phase I Data Analysis Task performed in support of the current Regional Flow Model, Transport Model, and Risk Assessment for the Nevada Test Site Underground Test Area Subproject contains the risk assessment documentation. Because of the size and complexity of the model area, a considerable quantity of data was collected and analyzed in support of the modeling efforts. The data analysis task was consequently broken into eight subtasks, and descriptions of each subtask's activities are contained in one of the eight volumes that comprise the Phase I Data Analysis Documentation.

High-level waste storage tank farms/242-A evaporator Standards/Requirements Identification Document (S/RID), Volume 2

International Nuclear Information System (INIS)

1994-04-01

The High-Level Waste Storage Tank Farms/242-A Evaporator Standards/Requirements Document (S/RID) is contained in multiple volumes. This document (Volume 2) presents the standards and requirements for the following sections: Quality Assurance, Training and Qualification, Emergency Planning and Preparedness, and Construction

High-level waste storage tank farms/242-A evaporator Standards/Requirements Identification Document (S/RID), Volume 2

Energy Technology Data Exchange (ETDEWEB)

1994-04-01

The High-Level Waste Storage Tank Farms/242-A Evaporator Standards/Requirements Document (S/RID) is contained in multiple volumes. This document (Volume 2) presents the standards and requirements for the following sections: Quality Assurance, Training and Qualification, Emergency Planning and Preparedness, and Construction.

PFP MICON DCS computer software documentation

Energy Technology Data Exchange (ETDEWEB)

Silvan, G.R.

1996-03-26

This document contains the complete printout of the MICON A/S system configuration used in the Plutonium Finishing Plant. The document is divided into several volumes. Volume 1 covers the workstation display and configuration. All other volumes contain the controller configurations, or programs.

PFP MICON DCS computer software documentation

International Nuclear Information System (INIS)

Silvan, G.R.

1996-01-01

This document contains the complete printout of the MICON A/S system configuration used in the Plutonium Finishing Plant. The document is divided into several volumes. Volume 1 covers the workstation display and configuration. All other volumes contain the controller configurations, or programs

Title List of Documents Made Publicly Available, January 1-31, 1986. Volume 8, No. 1

International Nuclear Information System (INIS)

1986-03-01

The Title List of Documents Made Publicly Available is a monthly publication. It contains descriptions of the information received and generated by the US Nuclear Regulatory Commission (NRC). This information includes: (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials; and (2) nondocketed material received and generated by NRC pertinent to its role as a regulatory agency. As used here, docketed does not refer to Court dockets; it refers to the system by which NRC maintains its regulatory records. This series of documents is indexed by a Personal Author Index, a Corporate Source Index, and a Report Number Index

High level waste storage tank farms/242-A evaporator Standards/Requirements Identification Document (S/RID), Volume 6

Energy Technology Data Exchange (ETDEWEB)

1994-04-01

The High-Level Waste Storage Tank Farms/242-A Evaporator Standards/Requirements Identification Document (S/RID) is contained in multiple volumes. This document (Volume 6) outlines the standards and requirements for the sections on: Environmental Restoration and Waste Management, Research and Development and Experimental Activities, and Nuclear Safety.

High level waste storage tank farms/242-A evaporator Standards/Requirements Identification Document (S/RID), Volume 6

International Nuclear Information System (INIS)

1994-04-01

The High-Level Waste Storage Tank Farms/242-A Evaporator Standards/Requirements Identification Document (S/RID) is contained in multiple volumes. This document (Volume 6) outlines the standards and requirements for the sections on: Environmental Restoration and Waste Management, Research and Development and Experimental Activities, and Nuclear Safety

Human-system interface design review guideline -- Process and guidelines: Final report. Revision 1, Volume 1

Energy Technology Data Exchange (ETDEWEB)

None

1996-06-01

NUREG-0700, Revision 1, provides human factors engineering (HFE) guidance to the US Nuclear Regulatory Commission staff for its: (1) review of the human system interface (HSI) design submittals prepared by licensees or applications for a license or design certification of commercial nuclear power plants, and (2) performance of HSI reviews that could be undertaken as part of an inspection or other type of regulatory review involving HSI design or incidents involving human performance. The guidance consists of a review process and HFE guidelines. The document describes those aspects of the HSI design review process that are important to the identification and resolution of human engineering discrepancies that could adversely affect plant safety. Guidance is provided that could be used by the staff to review an applicant`s HSI design review process or to guide the development of an HSI design review plan, e.g., as part of an inspection activity. The document also provides detailed HFE guidelines for the assessment of HSI design implementations. NUREG-0700, Revision 1, consists of three stand-alone volumes. Volume 1 consists of two major parts. Part 1 describes those aspects of the review process of the HSI design that are important to identifying and resolving human engineering discrepancies. Part 2 contains detailed guidelines for a human factors engineering review which identify criteria for assessing the implementation of an applicant`s or licensee`s HSI design.

Underground Test Area Subproject Phase I Data Analysis Task. Volume VII - Tritium Transport Model Documentation Package

Energy Technology Data Exchange (ETDEWEB)

None

1996-12-01

Volume VII of the documentation for the Phase I Data Analysis Task performed in support of the current Regional Flow Model, Transport Model, and Risk Assessment for the Nevada Test Site Underground Test Area Subproject contains the tritium transport model documentation. Because of the size and complexity of the model area, a considerable quantity of data was collected and analyzed in support of the modeling efforts. The data analysis task was consequently broken into eight subtasks, and descriptions of each subtask's activities are contained in one of the eight volumes that comprise the Phase I Data Analysis Documentation.

NRC review of Electric Power Research Institute's advanced light water reactor utility requirements document. Passive plant designs, chapter 1, project number 669

International Nuclear Information System (INIS)

1994-08-01

The Electric Power Research Institute (EPRI) is preparing a compendium of technical requirements, referred to as the open-quotes Advanced Light Water Reactor [ALWR] Utility Requirements Documentclose quotes, that is acceptable to the design of an ALWR power plant. When completed, this document is intended to be a comprehensive statement of utility requirements for the design, construction, and performance of an ALWR power plant for the 1990s and beyond. The Requirements Document consists of three volumes. Volume 1, open-quotes ALWR Policy and Summary of Top-Tier Requirementsclose quotes, is a management-level synopsis of the Requirements Document, including the design objectives and philosophy, the overall physical configuration and features of a future nuclear plant design, and the steps necessary to take the proposed ALWR design criteria beyond the conceptual design state to a completed, functioning power plant. Volume II consists of 13 chapters and contains utility design requirements for an evolutionary nuclear power plant [approximately 1350 megawatts-electric (MWe)]. Volume III contains utility design requirements for nuclear plants for which passive features will be used in their designs (approximately 600 MWe). In April 1992, the staff of the Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, issued Volume 1 and Volume 2 (Parts 1 and 2) of its safety evaluation report (SER) to document the results of its review of Volumes 1 and 2 of the Requirements Document. Volume 1, open-quotes NRC Review of Electric Power Research Institute's Advanced Light Water Reactor Utility Requirements Document - Program Summaryclose quotes, provided a discussion of the overall purpose and scope of the Requirements Document, the background of the staff's review, the review approach used by the staff, and a summary of the policy and technical issues raised by the staff during its review

M-area hazardous waste management facility groundwater monitoring and corrective-action report, First quarter 1995, Volume 1

International Nuclear Information System (INIS)

1995-05-01

This report, in three volumes, describes the ground water monitoring and c corrective-action program at the M-Area Hazardous Waste Management Facility (HWMF) at the Savannah River Site (SRS) during the fourth quarter 1994 and first quarter 1995. Concise description of the program and considerable data documenting the monitoring and remedial activities are included in the document. This is Volume 1 covering the following topics: sampling and results; hydrogeologic assessment; water quality assessment; effectiveness of the corrective-action program; corrective-action system operation and performance; monitoring and corrective-action program assessment; proposed monitoring and corrective-action program modifications. Also included are the following appendicies: A-standards; B-flagging criteria; C-figures; D-monitoring results tables; E-data quality/usability assessment

User's guide for PRISM (Plant Risk Status Information Management System) Arkansas Nuclear One-Unit 1: Volume 1, Program for inspectors

Energy Technology Data Exchange (ETDEWEB)

Campbell, D.J.; Guthrie, V.H.; Kirchner, J.R.; Kirkman, J.Q.; Paula, H.M.; Ellison, B.C.; Dycus, F.M.; Farquharson, J.A.; Flanagan, G.F.

1988-03-01

This user's guide is a two-volume document designed to teach NRC inspectors and NRC regulators how to access probabilistic risk assessment information from the two Plant Risk Status Information Management System (PRISIM) programs developed for Arkansas Nuclear One -- Unit One (ANO-1). This document, Volume 1, describes how the PRA information available in Version 1.0 of PRISIM is useful for planning inspections. Using PRISIM, inspectors can quickly access PRA information and use that information to update risk analysis results, reflecting a plant's status at any particular time. Both volumes are stand-alone documents, and each volume presents several sample computer sessions designed to lead the user through a variety of PRISIM applications used to obtain PRA-related information for monitoring and controlling plant risk.

Programa Estrategico do desenvolvimento 1968-70: Area Estrategica IX. Infra-estructura Social. Educacao e Recursos Humanos, 1 e 2 (Strategic Development Program 1968-1970: Strategic Area IX. Education and Human Resources, Volumes 1 & 2).

Science.gov (United States)

Brazil.

This document is an English-language abstract (approximately 1,500 words) of a two volume work dealing with education and human resources as part of the Brazilian Government's Strategic Development Program 1968-70. It offers an integral view of education as an instrument of social transformation and an exposition of the quantitative and…

Comparative ranking of 0. 1-10 MW/sub e/ solar thermal electric power systems. Volume II. Supporting data. Final report

Energy Technology Data Exchange (ETDEWEB)

Thornton, J.P.; Brown, K.C.; Finegold, J.G.; Gresham, J.B.; Herlevich, F.A.; Kriz, T.A.

1980-07-01

This report is part of a two-volume set summarizing the results of a comparative ranking of generic solar thermal concepts designed specifically for electric power generation. The original objective of the study was to project the mid-1990 cost and performance of selected generic solar thermal electric power systems for utility applications and to rank these systems by criteria that reflect their future commercial acceptance. This study considered plants with rated capacities of 1-10 MW/sub e/, operating over a range of capacity factors from the no-storage case to 0.7 and above. Later, the study was extended to include systems with capacities from 0.1 to 1 MW/sub e/, a range that is attractive to industrial and other nonutility applications. Volume I summarizes the results for the full range of capacities from 0.1 to 1.0 MW/sub e/. Volume II presents data on the performance and cost and ranking methodology.

Waste Management System Requirement document

International Nuclear Information System (INIS)

1990-04-01

This volume defines the top level technical requirements for the Monitored Retrievable Storage (MRS) facility. It is designed to be used in conjunction with Volume 1, General System Requirements. Volume 3 provides a functional description expanding the requirements allocated to the MRS facility in Volume 1 and, when appropriate, elaborates on requirements by providing associated performance criteria. Volumes 1 and 3 together convey a minimum set of requirements that must be satisfied by the final MRS facility design without unduly constraining individual design efforts. The requirements are derived from the Nuclear Waste Policy Act of 1982 (NWPA), the Nuclear Waste Policy Amendments Act of 1987 (NWPAA), the Environmental Protection Agency's (EPA) Environmental Standards for the Management and Disposal of Spent Nuclear Fuel (40 CFR 191), NRC Licensing Requirements for the Independent Storage of Spent Nuclear and High-Level Radioactive Waste (10 CFR 72), and other federal statutory and regulatory requirements, and major program policy decisions. This document sets forth specific requirements that will be fulfilled. Each subsequent level of the technical document hierarchy will be significantly more detailed and provide further guidance and definition as to how each of these requirements will be implemented in the design. Requirements appearing in Volume 3 are traceable into the MRS Design Requirements Document. Section 2 of this volume provides a functional breakdown for the MRS facility. 1 tab

Quality and Capacity Document 2011. Part 1; Kwaliteits- en Capaciteitsdocument 2011. Deel 1

Energy Technology Data Exchange (ETDEWEB)

NONE

2012-01-15

In accordance with Article 21 of the Dutch Electricity Law 1998 this quality and capacity document was drafted. The document describes (a) the level of quality which is aimed at and the scores over the last years; (b) the quality management system; (c) the estimated results of the total need for transport for the period 2012-2021; (d) bottlenecks and solutions required to meet the demand for future transport capacity; and (e) measures to be taken for maintenance and replacements. This document comprises chapters 1-5. In parts 2, 3 and 4 you can find the rest of the chapters [Dutch] Conform artikel 21 van de Elektriciteitswet 1998 is het titel document opgesteld. In dit document wordt en worden door TenneT (a) aangegeven welk kwaliteitsniveau wordt nagestreefd en wat de scores in de laatste drie jaar zijn geweest; (b) het kwaliteitbeheerssysteem beschreven; (c) de resultaten van de raming van de totale transportbehoefte beschreven voor de periode 2012-2021; (d) de knelpunten en oplossingen beschreven die nodig zijn om in de behoefte aan de toekomstige transportcapaciteit te kunnen voldoen; en (e) de maatregelen beschreven inzake vervanging en onderhoud. Dit document bevat de hoofdstukken 1-5. In de delen 2, 3 en 4 kunt u de overige hoofdstukken vinden.

Spectrum '86: Proceedings: Volume 1

International Nuclear Information System (INIS)

Pope, J.M.; Leonard, I.M.; Mayer, E.J.

1987-07-01

This document, Volume 1 of two, contains 100 papers on various aspects of Radioactive Waste Management. Session topics include: nuclear success stories; low-level waste-grout; filtration and ion exchange, qualification, and pretreatment; solid waste treatment/endash/special grouts, and incineration; equipment design/endash/remote technology, and special equipment; high-level waste/endash/international vitrification projects, plans and system testing, product performance, meltor and product testing, off-gas behavior and processing. Individual reports were processed separately for the data bases

Resource Conservation and Recovery Act ground-water monitoring projects for Hanford Facilities: Progress report for the period July 1 to September 30, 1989 - Volume 1 - Text

Energy Technology Data Exchange (ETDEWEB)

Smith, R.M.; Bates, D.J.; Lundgren, R.E.

1989-12-01

This is Volume 1 of a two-volume document that describes the progress of 14 Hanford Site ground-water monitoring projects for the period July 1 to September 30, 1989. This volume discusses the projects; Volume 2 provides as-built diagrams, completion/inspection reports, drilling logs, and geophysical logs for wells drilled, completed, or logged during this period. Volume 2 can be found on microfiche in the back pocket of Volume 1. The work described in this document is conducted by the Pacific Northwest Laboratory under the management of Westinghouse Hanford Company for the US Department of Energy. Concentrations of ground-water constituents are compared to federal drinking water standards throughout this document for reference purposes. All drinking water supplied from the sampled aquifer meets regulatory standards for drinking water quality.

Human-system interface design review guideline -- Reviewer`s checklist: Final report. Revision 1, Volume 2

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-06-01

NUREG-0700, Revision 1, provides human factors engineering (HFE) guidance to the US Nuclear Regulatory Commission staff for its: (1) review of the human system interface (HSI) design submittals prepared by licensees or applications for a license or design certification of commercial nuclear power plants, and (2) performance of HSI reviews that could be undertaken as part of an inspection or other type of regulatory review involving HSI design or incidents involving human performance. The guidance consists of a review process and HFE guidelines. The document describes those aspects of the HSI design review process that are important to the identification and resolution of human engineering discrepancies that could adversely affect plant safety. Guidance is provided that could be used by the staff to review an applicant`s HSI design review process or to guide the development of an HSI design review plan, e.g., as part of an inspection activity. The document also provides detailed HFE guidelines for the assessment of HSI design implementations. NUREG-0700, Revision 1, consists of three stand-alone volumes. Volume 2 is a complete set of the guidelines contained in Volume 1, Part 2, but in a checklist format that can be used by reviewers to assemble sets of individual guidelines for use in specific design reviews. The checklist provides space for reviewers to enter guidelines evaluations and comments.

An Integrated Multimedia Approach to Cultural Heritage e-Documents

NARCIS (Netherlands)

Smeulders, A.W.M.; Hardman, H.L.; Schreiber, G.; Geusebroek, J.M.

2002-01-01

We discuss access to e-documents from three different perspectives beyond the plain keyword web-search of the entire document. The first one is the situation-depending delivery of multimedia documents adapting the preferred form (picture, text, speech) to the available information capacity or need

Environmental resource document for the Idaho National Engineering Laboratory. Volume 1

Energy Technology Data Exchange (ETDEWEB)

Irving, J.S.

1993-07-01

This document contains information related to the environmental characterization of the Idaho National Engineering Laboratory (INEL). The INEL is a major US Department of Energy facility in southeastern Idaho dedicated to nuclear research, waste management, environmental restoration, and other activities related to the development of technology. Environmental information covered in this document includes land, air, water, and ecological resources; socioeconomic characteristics and land use; and cultural, aesthetic, and scenic resources.

Pesquisa documental: pistas teóricas e metodológicas

Directory of Open Access Journals (Sweden)

Jackson Ronie Sá-Silva

2015-05-01

Full Text Available O objetivo deste artigo é apresentar alguns apontamentos teóricos e metodológicos sobre a pesquisa documental. Ao fazermos essa exposição pública, por meio de ensaio bibliográfico, queremos provocar o debate sobre a utilização desse procedimento no cotidiano das pesquisas de estudantes, professores e pesquisadores. Primeiramente, conceituamos a pesquisa documental, apresentando as similaridades e diferenças entre esta e a pesquisa bibliográfica, para, em seguida, discutirmos o conceito de documento. Na seqüência, abordamos os critérios metodológicos de pré-análise do documento escrito e, por fim, apresentamos as etapas da análise documental.

Title list of documents made publicly available: February 1--28, 1995. Volume 17, Number 2

International Nuclear Information System (INIS)

1995-04-01

This monthly publication contains descriptions of the information received and generated by the US Nuclear Regulatory Commission (NRC). This information includes (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials and (2) nondocketed material received and generated by NRC pertinent to its role as a regulatory agency. As used here, docketed refers to the system by which NRC maintains its regulatory records. This series of documents is indexed by a Personal Author Index, a Corporate Source Index, and a Report Number Index. NRC documents that are publicly available may be examined without charge at the NRC Public Document Room (PDR)

Title list of documents made publicly available: February 1--28, 1995. Volume 17, Number 2

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-04-01

This monthly publication contains descriptions of the information received and generated by the US Nuclear Regulatory Commission (NRC). This information includes (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials and (2) nondocketed material received and generated by NRC pertinent to its role as a regulatory agency. As used here, docketed refers to the system by which NRC maintains its regulatory records. This series of documents is indexed by a Personal Author Index, a Corporate Source Index, and a Report Number Index. NRC documents that are publicly available may be examined without charge at the NRC Public Document Room (PDR).

Sandia National Laboratories/New Mexico Environmental Information Document - Volume 1

Energy Technology Data Exchange (ETDEWEB)

BAYLISS, LINDA S.; GUERRERO, JOSEPH V.; JOHNS, WILLIAM H.; KUZIO, KENNETH A.; BAILEY-WHITE, BRENDA E.

1999-09-01

This Sandia National Laboratories/New Mexico Environmental Information Document (EID) compiles information on the existing environment, or environmental baseline, for SNUNM. Much of the information is drawn from existing reports and databases supplemented by new research and data. The SNL/NM EID, together with the Sandia National Laboratories/New Mexico Facilities and Safety Information Document, provide a basis for assessing the environment, safety, and health aspects of operating selected facilities at SNL/NM. The environmental baseline provides a record of the existing physical, biological, and socioeconomic environment at SNL/NLM prior to being altered (beneficially or adversely) by proposed programs or projects. More specifically, the EID provides information on the following topics: Geology; Land Use; Hydrology and Water Resources; Air Quality and Meteorology; Ecology; Noise and Vibration; Cultural Resources; Visual Resources; Socioeconomic and Community Services; Transportation; Material Management; Waste Management; and Regulatory Requirements.

Title list of documents made publicly available: August 1--31, 1997. Volume 19, Number 8

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-10-01

This document is a monthly publication containing descriptions of information received and generated by the US Nuclear Regulatory Commission (NRC). This information includes (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials and (2) nondocketed material received and generated by NRC pertinent to its role as a regulatory agency. The following indexes are included: Personal Author, Corporate Source, Report Number, and Cross Reference of Enclosures to Principal Documents.

Title list of documents made publicly available, May 1-31, 1986. Volume 8, No. 5

International Nuclear Information System (INIS)

1986-07-01

This document is a monthly publication containing descriptions of information received and generated by the USNRC. This information includes: (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials, and (2) nondocketed material received and generated by NRC pertinent to its role as a regulatory agency. The following indexes are included: Personal Author Index, Corporate Source Index, Report Number Index, and Cross Reference to Principal Documents Index

Title list of documents made publicly available: August 1-31, 1997. Volume 19, Number 8

International Nuclear Information System (INIS)

1997-10-01

This document is a monthly publication containing descriptions of information received and generated by the US Nuclear Regulatory Commission (NRC). This information includes (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials and (2) nondocketed material received and generated by NRC pertinent to its role as a regulatory agency. The following indexes are included: Personal Author, Corporate Source, Report Number, and Cross Reference of Enclosures to Principal Documents

Title List of Documents Made Publicly Available, August 1-31, 1986. Volume 8, No. 8

International Nuclear Information System (INIS)

1986-10-01

This document is a monthly publication containing descriptions of information received and generated by the US NRC. This information includes (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials, and (2) nondocketed material received and generated by NRC pertinent to its role as a regulatory agency. The following indexes are included: Personal Author Index, Corporate Source Index, Report Number Index, and Cross Reference to Principal Documents Index

Title list of documents made publicly available, April 1-30, 1986. Volume 8, No. 4

International Nuclear Information System (INIS)

1986-06-01

This document is a monthly publication containing descriptions of information received and generated by the US NRC. This information includes: (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials, and (2) nondocketed material received and generated by NRC pertinent to its role as a regulatory agency. The following indexes are included: Personal Author Index, Corporate Source Index, Report Number Index, and Cross Reference to Principal Documents Index

Title list of documents made publicly available: November 1--30, 1997. Volume 19, Number 11

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-01-01

This document is a monthly publication containing descriptions of information received and generated by the US Nuclear Regulatory Commission (NRC). This information includes (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials and (2) nondocketed material received and generated by NRC pertinent to its role as a regulatory agency. The following indexes are included: Personal Author, Corporate source, Report Number, and Cross Reference of Enclosures to Principal Documents.

Title list of documents made publicly available: November 1--30, 1997. Volume 19, Number 11

International Nuclear Information System (INIS)

1998-01-01

This document is a monthly publication containing descriptions of information received and generated by the US Nuclear Regulatory Commission (NRC). This information includes (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials and (2) nondocketed material received and generated by NRC pertinent to its role as a regulatory agency. The following indexes are included: Personal Author, Corporate source, Report Number, and Cross Reference of Enclosures to Principal Documents

Title List of documents made publicly available, September 1--30, 1993. Volume 15, No. 9

Energy Technology Data Exchange (ETDEWEB)

1993-11-01

This document is a monthly publication containing descriptions of information received and generated by the US Nuclear Regulatory Commission (NRC). This information includes (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials, and (2) nondocketed material received and generated by NRC pertinent to its role as a regulatory agency. The following indexes are included: Personal Author, Corporate Source, Report Number, and Cross Reference of Enclosures to Principals Documents.

Title list of documents made publicly available: Volume 10, No. 10: October 1--31, 1988

International Nuclear Information System (INIS)

1989-01-01

This document is a monthly publication containing descriptions of information received and generated by the US Nuclear Regulatory Commission (NRC). This information includes (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials, and (2) nondocketed material received and generated by NRC pertinent to its role as a regulatory agency. The following indexes are included: Personal Author, Corporate Source, Report Number, and Cross Reference to Principal Documents

Title list of documents made publicly available: December 1--31, 1996. Volume 18, Number 12

International Nuclear Information System (INIS)

1997-03-01

This document is a monthly publication containing descriptions of information received and generated by the US Nuclear Regulatory Commission (NRC). This information includes (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials, and (2) nondocketed material received and generated by NRC pertinent to its role as a regulatory agency. The following indexes are included: Personal Author, Corporate Source, Report Number, and Cross Reference of Enclosures to Principal Documents

Title list of documents made publicly available: December 1--31, 1996. Volume 18, Number 12

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-03-01

This document is a monthly publication containing descriptions of information received and generated by the US Nuclear Regulatory Commission (NRC). This information includes (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials, and (2) nondocketed material received and generated by NRC pertinent to its role as a regulatory agency. The following indexes are included: Personal Author, Corporate Source, Report Number, and Cross Reference of Enclosures to Principal Documents.

Title list of documents made publicly available, December 1--31, 1995. Volume 17, No. 12

International Nuclear Information System (INIS)

1996-02-01

This document is a monthly publication containing descriptions of information received and generated by the US Nuclear Regulatory Commission (NRC). This information includes (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials, and (2) nondocketed material received and generated by NRC pertinent to its role as a regulatory agency. The following indexes are included: Personal Author, Corporate Source, Report Number, and Cross Reference of Enclosures to Principal Documents

Title list of documents made publicly available, September 1--30, 1995. Volume 17, No. 9

International Nuclear Information System (INIS)

1995-11-01

This document is a monthly publication containing descriptions of information received and generated by the US Nuclear Regulatory Commission (NRC). This information includes (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials, and (2) nondocketed material received and generated by NRC pertinent to its role as a regulatory agency. The following indexes are included: Personal Author, Corporate Source, Report Number, and Cross Reference of Enclosures to Principal Documents

Title list of documents made publicly available, December 1--31, 1995. Volume 17, No. 12

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-02-01

This document is a monthly publication containing descriptions of information received and generated by the US Nuclear Regulatory Commission (NRC). This information includes (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials, and (2) nondocketed material received and generated by NRC pertinent to its role as a regulatory agency. The following indexes are included: Personal Author, Corporate Source, Report Number, and Cross Reference of Enclosures to Principal Documents.

Title list of documents made publicly available, December 1--31, 1991. Volume 13, No. 12

Energy Technology Data Exchange (ETDEWEB)

None

1992-02-01

This document is a monthly containing descriptions of information received and generated by the US Nuclear Regulatory Commission (NRC). This information includes (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials, and (2) nondocketed material received and generated by NRC pertinent to its role as a regulatory agency. The following indexes are included: Personal Author, Corporate Source, Report Number, and Cross Reference of Enclosures to Principal Documents.

Characterization of radioactive waste forms. Volume 1

International Nuclear Information System (INIS)

Brodersen, K.; Nilsson, K.

1989-01-01

This document is the second yearbook for Task 3 of the European Communities 1985-89 programme of research on radioactive waste management and disposal carried out by public organizations and private firms in the Community through costsharing contracts with the Commission of the European Communities. The report, in two volumes, describes progress made in 1987 within the field of Task 3: Testing and evaluation of conditioned waste and engineered barriers. The first volume of the report covers Item 3.1 Characterization of low and medium-level radioactive waste forms and Item 3.5 Development of test methods for quality assurance. The second volume covers Item 3.2: High-level and alpha waste characterization and Item 3.3: Other engineered barriers. Item 3.4 on the round robin study will be treated in a separate report

Waste retrieval sluicing system campaign number 1 solids volume transferred calculation

International Nuclear Information System (INIS)

BAILEY, J.W.

1999-01-01

This calculation has been prepared to document the volume of sludge removed from tank 241-C-106 during Waste Retrieval Sluicing System (WRSS) Sluicing Campaign No.1. This calculation will be updated, if necessary, to incorporate new data. This calculation supports the declaration of completion of WRSS Campaign No.1 and, as such, is also the documentation for completion of Performance Agreement TWR 1.2.1 , C-106 Sluicing Performance Expectations. It documents the performance of all the appropriate tank 241-C-106 mass transfer verifications, evaluations, and appropriate adjustments discussed in HNF-SD-WM-PROC-021, Chapter 23, ''Process Engineering Calculations for Tank 241-C-106 Sluicing and Retrieval''

Waste retrieval sluicing system campaign number 1 solids volume transferred calculation

International Nuclear Information System (INIS)

BAILEY, J.W.

1999-01-01

This calculation has been prepared to document the volume of sludge removed from tank 241-C-106 during Waste Retrieval Sluicing System (WRSS) Sluicing Campaign No.1. This calculation will be updated, if necessary, to incorporate new data. This calculation supports the declaration of completion of WRSS Campaign No.1 and, as such, is also the documentation for completion of Performance Agreement TWR 1.2.1 C-106 Sluicing Performance Expectations. It documents the performance of all the appropriate tank 241-C-106 mass transfer verifications, evaluations, and appropriate adjustments discussed in HNF-SD-WM-PROC-021, Chapter 23, ''Process Engineering Calculations for Tank 241-C-106 Sluicing and Retrieval''

Hanford spent nuclear fuel project recommended path forward, volume III: Alternatives and path forward evaluation supporting documentation

International Nuclear Information System (INIS)

Fulton, J.C.

1994-10-01

Volume I of the Hanford Spent Nuclear Fuel Project - Recommended Path Forward constitutes an aggressive series of projects to construct and operate systems and facilities to safely retrieve, package, transport, process, and store K Basins fuel and sludge. Volume II provided a comparative evaluation of four Alternatives for the Path Forward and an evaluation for the Recommended Path Forward. Although Volume II contained extensive appendices, six supporting documents have been compiled in Volume III to provide additional background for Volume II

Pediatric eMental healthcare technologies: a systematic review of implementation foci in research studies, and government and organizational documents.

Science.gov (United States)

Gehring, Nicole D; McGrath, Patrick; Wozney, Lori; Soleimani, Amir; Bennett, Kathryn; Hartling, Lisa; Huguet, Anna; Dyson, Michele P; Newton, Amanda S

2017-06-21

Researchers, healthcare planners, and policymakers convey a sense of urgency in using eMental healthcare technologies to improve pediatric mental healthcare availability and access. Yet, different stakeholders may focus on different aspects of implementation. We conducted a systematic review to identify implementation foci in research studies and government/organizational documents for eMental healthcare technologies for pediatric mental healthcare. A search of eleven electronic databases and grey literature was conducted. We included research studies and documents from organization and government websites if the focus included eMental healthcare technology for children/adolescents (0-18 years), and implementation was studied and reported (research studies) or goals/recommendations regarding implementation were made (documents). We assessed study quality using the Mixed Methods Appraisal Tool and document quality using the Appraisal of Guidelines for Research & Evaluation II. Implementation information was grouped according to Proctor and colleagues' implementation outcomes-acceptability, adoption, appropriateness, cost, feasibility, fidelity, penetration, and sustainability-and grouped separately for studies and documents. Twenty research studies and nine government/organizational documents met eligibility criteria. These articles represented implementation of eMental healthcare technologies in the USA (14 studies), United Kingdom (2 documents, 3 studies), Canada (2 documents, 1 study), Australia (4 documents, 1 study), New Zealand (1 study), and the Netherlands (1 document). The quality of research studies was excellent (n = 11), good (n = 6), and poor (n = 1). These eMental health studies focused on the acceptability (70%, n = 14) and appropriateness (50%, n = 10) of eMental healthcare technologies to users and mental healthcare professionals. The quality of government and organizational documents was high (n = 2), medium (n = 6

Development of the NRC`s Human Performance Investigation Process (HPIP). Volume 3, Development documentation

Energy Technology Data Exchange (ETDEWEB)

Paradies, M.; Unger, L. [System Improvements, Inc., Knoxville, TN (United States); Haas, P.; Terranova, M. [Concord Associates, Inc., Knoxville, TN (United States)

1993-10-01

The three volumes of this report detail a standard investigation process for use by US Nuclear Regulatory Commission (NRC) personnel when investigating human performance related events at nuclear power plants. The process, called the Human Performance Investigation Process (HPIP), was developed to meet the special needs of NRC personnel, especially NRC resident and regional inspectors. HPIP is a systematic investigation process combining current procedures and field practices, expert experience, NRC human performance research, and applicable investigation techniques. The process is easy to learn and helps NRC personnel perform better field investigations of the root causes of human performance problems. The human performance data gathered through such investigations provides a better understanding of the human performance issues that cause events at nuclear power plants. This document, Volume III, is a detailed documentation of the development effort and the pilot training program.

LLCEDATA and LLCECALC for Windows version 1.0, Volume 2: Technical manual

Energy Technology Data Exchange (ETDEWEB)

McFadden, J.G.

1998-09-04

LLCEDATA and LLCECALC for Windows are user-friendly computer software programs that work together to determine the proper waste designation, handling, and disposition requirements for Long Length Contaminated Equipment (LLCE). LLCEDATA reads from a variety of databases to produce an equipment data file (EDF) that represents a snapshot of both the LLCE and the tank from which it originates. LLCECALC reads the EDF and the gamma assay (AV2) file that is produced by the Flexible Receiver Gamma Energy Analysis System. LLCECALC performs corrections to the AV2 file as it is being read and characterizes the LLCE Both programs produce a variety of reports, including a characterization report and a status report. The status report documents each action taken by the user, LLCEDA TA, and LLCECALC. Documentation for LLCEDA TA and LLCECALC for Windows is available in three volumes. Volume 1 is a user`s manual, which is intended as a quick reference for both LLCEDATA and LLCECALC. Volume 2 is a technical manual, which documents LLCEDATA and LLCECALCs methodology, structure, and format, provides sample calculations; discusses system limitations; and provides recommendations to the LLCE process. Volume 3 is a software verification and validation document LLCEDATA and LLCECALC for Windows are sponsored by the U.S.Department of Energy. They were developed and are maintained by Engineering, Waste Management Federal Services, Inc., Northwest Operations. Copies of the software and documentation are available by contacting Engineering, Waste Management Federal Services, Inc., Northwest Operations, Richland, Washington.

Standard technical specifications: Combustion engineering plants. Volume 1, Revision 1: Specifications

International Nuclear Information System (INIS)

1995-04-01

This report documents the results of the combined effort of the NRC and the industry to produce improved Standard Technical Specifications (STS), Revision 1 for Combustion Engineering Plants. The changes reflected in Revision 1 resulted from the experience gained from license amendment applications to convert to these improved STS or to adopt partial improvements to existing technical specifications. This NUREG is the result of extensive public technical meetings and discussions between the Nuclear Regulatory Commission (NRC) staff and various nuclear power plant licensees, Nuclear Steam Supply System (NSSS) Owners Groups, NSSS vendors, and the Nuclear Energy Institute (NEI). The improved STS were developed based on the criteria in the Final Commission Policy Statement on Technical Specifications Improvements for Nuclear Power Reactors, dated July 22, 1993. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. Volume 1 contains the Specifications for all chapters and sections of the improved STS. Volume 2 contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1--3.3 of the improved STS. Volume 3 contains the Bases for Sections 3.4--3.9 of the improved STS

Sharing and Adaptation of Educational Documents in E-Learning

Directory of Open Access Journals (Sweden)

Chekry Abderrahman

2012-03-01

Full Text Available Few documents can be reused among the huge number of the educational documents on the web. The exponential increase of these documents makes it almost impossible to search for relevant documents. In addition to this, e-learning is designed for public users who have different levels of knowledge and varied skills so they should be given a content that sees to their needs. This work is about adapting the content of learning with learners preferences, and give the teachers the ability to reuse a given content.

Ground-water monitoring compliance projects for Hanford Site Facilities: Progress report for the period April 1--June 30, 1988: Volume 1, Text

International Nuclear Information System (INIS)

1988-09-01

This is Volume 1 of a two-volume set of documents that describes the progress of 10 Hanford Site ground-water monitoring projects for the period April 1 to June 30, 1988. This volume discusses the projects; Volume 2 provides as-built diagrams, drilling logs, and geophysical logs for wells drilled during this period in the 100-N Area and near the 216-A-36B Crib

SCALE: A modular code system for performing standardized computer analyses for licensing evaluation. Functional modules F1--F8 -- Volume 2, Part 1, Revision 4

Energy Technology Data Exchange (ETDEWEB)

Greene, N.M.; Petrie, L.M.; Westfall, R.M.; Bucholz, J.A.; Hermann, O.W.; Fraley, S.K. [Oak Ridge National Lab., TN (United States)

1995-04-01

SCALE--a modular code system for Standardized Computer Analyses Licensing Evaluation--has been developed by Oak Ridge National Laboratory at the request of the US Nuclear Regulatory Commission. The SCALE system utilizes well-established computer codes and methods within standard analysis sequences that (1) allow an input format designed for the occasional user and/or novice, (2) automate the data processing and coupling between modules, and (3) provide accurate and reliable results. System development has been directed at problem-dependent cross-section processing and analysis of criticality safety, shielding, heat transfer, and depletion/decay problems. Since the initial release of SCALE in 1980, the code system has been heavily used for evaluation of nuclear fuel facility and package designs. This revision documents Version 4.2 of the system. The manual is divided into three volumes: Volume 1--for the control module documentation; Volume 2--for functional module documentation; and Volume 3--for documentation of the data libraries and subroutine libraries.

SCALE: A modular code system for performing standardized computer analyses for licensing evaluation. Functional modules F1--F8 -- Volume 2, Part 1, Revision 4

International Nuclear Information System (INIS)

Greene, N.M.; Petrie, L.M.; Westfall, R.M.; Bucholz, J.A.; Hermann, O.W.; Fraley, S.K.

1995-04-01

SCALE--a modular code system for Standardized Computer Analyses Licensing Evaluation--has been developed by Oak Ridge National Laboratory at the request of the US Nuclear Regulatory Commission. The SCALE system utilizes well-established computer codes and methods within standard analysis sequences that (1) allow an input format designed for the occasional user and/or novice, (2) automate the data processing and coupling between modules, and (3) provide accurate and reliable results. System development has been directed at problem-dependent cross-section processing and analysis of criticality safety, shielding, heat transfer, and depletion/decay problems. Since the initial release of SCALE in 1980, the code system has been heavily used for evaluation of nuclear fuel facility and package designs. This revision documents Version 4.2 of the system. The manual is divided into three volumes: Volume 1--for the control module documentation; Volume 2--for functional module documentation; and Volume 3--for documentation of the data libraries and subroutine libraries

Proposed Site Treatment Plan (PSTP). Volumes 1 and 2 and Reference Document

Energy Technology Data Exchange (ETDEWEB)

Helmich, E.; Noller, D.K.; Wierzbicki, K.S.; Bailey, L.L.

1994-12-22

The Compliance Plan Volume provides overall schedules with target dates for achieving compliance with the land disposal restrictions (LDR) and contains procedures to establish milestones to be enforced under the Order. Information regarding the technical evaluation of treatment options for SRS mixed wastes is contained in the Background Volume and is provided for informational purposes only.

Information architecture. Volume 2, Part 1: Baseline analysis summary

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-12-01

The Department of Energy (DOE) Information Architecture, Volume 2, Baseline Analysis, is a collaborative and logical next-step effort in the processes required to produce a Departmentwide information architecture. The baseline analysis serves a diverse audience of program management and technical personnel and provides an organized way to examine the Department`s existing or de facto information architecture. A companion document to Volume 1, The Foundations, it furnishes the rationale for establishing a Departmentwide information architecture. This volume, consisting of the Baseline Analysis Summary (part 1), Baseline Analysis (part 2), and Reference Data (part 3), is of interest to readers who wish to understand how the Department`s current information architecture technologies are employed. The analysis identifies how and where current technologies support business areas, programs, sites, and corporate systems.

Documentation and archiving of the Space Shuttle wind tunnel test data base. Volume 1: Background and description

Science.gov (United States)

Romere, Paul O.; Brown, Steve Wesley

1995-01-01

Development of the space shuttle necessitated an extensive wind tunnel test program, with the cooperation of all the major wind tunnels in the United States. The result was approximately 100,000 hours of space shuttle wind tunnel testing conducted for aerodynamics, heat transfer, and structural dynamics. The test results were converted into Chrysler DATAMAN computer program format to facilitate use by analysts, a very cost effective method of collecting the wind tunnel test results from many test facilities into one centralized location. This report provides final documentation of the space shuttle wind tunnel program. The two-volume set covers evolution of space shuttle aerodynamic configurations and gives wind tunnel test data, titles of wind tunnel data reports, sample data sets, and instructions for accessing the digital data base.

Results of site validation experiments. Volume II. Supporting documents 5 through 14

Energy Technology Data Exchange (ETDEWEB)

1983-01-01

Volume II contains the following supporting documents: Summary of Geologic Mapping of Underground Investigations; Logging of Vertical Coreholes - ''Double Box'' Area and Exploratory Drift; WIPP High Precision Gravity Survey; Basic Data Reports for Drillholes, Brine Content of Facility Internal Strata; Mineralogical Content of Facility Interval Strata; Location and Characterization of Interbedded Materials; Characterization of Aquifers at Shaft Locations; and Permeability of Facility Interval Strate.

Title list of documents made publicly available, March 1--31, 1998. Volume 20, Number 3

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-05-01

The Title List of Documents Made Publicly Available is a monthly publication. It describes the information received and published by the US Nuclear Regulatory Commission (NRC). This information includes (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials and (2) nondocketed material received and published by NRC pertinent to its role as a regulatory agency. As used here, docketed does not refer to Court dockets; it refers to the system by which NRC maintains its regulatory records. This series of documents is indexed by a personal author index, a corporate source index, and a report number index.

Title list of documents made publicly available, March 1--31, 1998. Volume 20, Number 3

International Nuclear Information System (INIS)

1998-05-01

The Title List of Documents Made Publicly Available is a monthly publication. It describes the information received and published by the US Nuclear Regulatory Commission (NRC). This information includes (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials and (2) nondocketed material received and published by NRC pertinent to its role as a regulatory agency. As used here, docketed does not refer to Court dockets; it refers to the system by which NRC maintains its regulatory records. This series of documents is indexed by a personal author index, a corporate source index, and a report number index

Title list of documents made publicly available, March 1--31, 1995: Volume 17, No. 3

International Nuclear Information System (INIS)

1995-05-01

The Title List of Documents Made Publicly Available is a monthly publication. It contains descriptions of the information received and generated by the US Nuclear Regulatory Commission (NRC). This information includes (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials and (2) nondocketed material received and generated by NRC pertinent to its role as a regulatory agency. As used here, docketed does not refer to Court dockets; it refers to the system by which NRC maintains its regulatory records. This series of documents is indexed by a Personal Author Index, a Corporate Source Index, and a Report Number Index. The docketed information contained in the Title List includes the information formerly issued through the Department of Energy publication Power Reactor Docket Information, last published in January 1979. NRC documents that are publicly available may be examined without charge at the NRC Public Document Room (PDR). Duplicate copies may be obtained for a fee. Standing orders for certain categories of documents are also available. Clients may search for and order desired titles through the PDR computerized Bibliographic Retrieval System, which is accessible both at the PDR and remotely. The PDR is staffed by professional technical librarians, who provide reference assistance to users. See NOTES at the end of the preface for information about reaching the PDR. Microfiche of the docketed information listed in the Title List is available for sale on a subscription basis from the National Technical Information Service (NTIS)

Title list of documents made publicly available, March 1--31, 1995: Volume 17, No. 3

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-05-01

The Title List of Documents Made Publicly Available is a monthly publication. It contains descriptions of the information received and generated by the US Nuclear Regulatory Commission (NRC). This information includes (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials and (2) nondocketed material received and generated by NRC pertinent to its role as a regulatory agency. As used here, docketed does not refer to Court dockets; it refers to the system by which NRC maintains its regulatory records. This series of documents is indexed by a Personal Author Index, a Corporate Source Index, and a Report Number Index. The docketed information contained in the Title List includes the information formerly issued through the Department of Energy publication Power Reactor Docket Information, last published in January 1979. NRC documents that are publicly available may be examined without charge at the NRC Public Document Room (PDR). Duplicate copies may be obtained for a fee. Standing orders for certain categories of documents are also available. Clients may search for and order desired titles through the PDR computerized Bibliographic Retrieval System, which is accessible both at the PDR and remotely. The PDR is staffed by professional technical librarians, who provide reference assistance to users. See NOTES at the end of the preface for information about reaching the PDR. Microfiche of the docketed information listed in the Title List is available for sale on a subscription basis from the National Technical Information Service (NTIS).

IDC System Specification Document Version 1.1.

Energy Technology Data Exchange (ETDEWEB)

Harris, James M. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Lober, Randall R. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

2015-02-01

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 V1.1 2/2015 IDC Reengineering Project Team Iteration I2 Review Comments M. Harris

Standard technical specifications General Electric plants, BWR/6. Volume 1, Revision 1

International Nuclear Information System (INIS)

1995-04-01

This report documents the results of the combined effort of the NRC and the industry to produce improved Standard Technical Specifications (STS), Revision 1 for General Electric BWR/6 Plants. The changes reflected in Revision 1 resulted from the experience gained from license amendment applications to convert to these improved STS or to adopt partial improvements to existing technical specifications. This NUREG is the result of extensive public technical meetings and discussions between the Nuclear Regulatory Commission (NRC) staff and various nuclear power plant licensees, Nuclear Steam Supply System (NSSS) Owners Groups, NSSS vendors, and the Nuclear Energy Institute (NEI). The improved STS were developed based on the criteria in the Final Commission Policy Statement on Technical Specifications Improvements for Nuclear Power Reactors, dated July 22, 1993. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. Volume 1 contains the Specifications for all chapters and sections of the improved STS. Volume 2 contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1--3.3 of the improved STS. Volume 3 contains the Bases for Sections 3.4--3.10 of the improved STS

242-A Campaign 94-1 post run document

International Nuclear Information System (INIS)

Guthrie, M.D.

1994-01-01

The purpose of this post-run document is to summarize the results of 242-A Evaporator Campaign 94-1 as required. Campaign 94-1 represents the first Evaporator operation since 1989, following completion of the B-534 upgrades and Liquid Effluent Retention Facility (LERF) construction. The purpose of Campaign 94-1 was to concentrate dilute waste from TK-102-AW, TK-106-AW, and TK-103-AP. From an available 2.87 million gallon feedstock of dilute waste contained in 102-AW, 106-AW and 103-AP, an overall Waste Volume Reduction (WVR) of 2.39 million gallons (83% WVRF) was achieved. At the completion of the campaign, approximately 477,000 gallons of dilute double-shell slurry feed (DDSSF) was produced with a SpG. of 1.25--1.30. Total process condensate discharged to LERF was 3.09 million gallons, achieving a condensate/WVR ratio of 1.29. Throughput for Campaign 94-1 was 5.27 million gallons. Total steam condensate and cooling water discharge to B-pond was 4.7 and 216 million gallons respectively. The evaporator operated approximately 43 days of the 60 day campaign for a total operating efficiency of 73%. Campaign 94-1 was completed without any discharge limit, Operating Specification Document, or Operational Safety Requirement violations. Major problems encountered during the run included the following: (1) high CA1 deentrainment pad dP's caused by foaming, (2) condensate pump P-C100 failure, and (3) ion exchange column dP's and efficiency

SCALE-4 analysis of pressurized water reactor critical configurations. Volume 1: Summary

International Nuclear Information System (INIS)

DeHart, M.D.

1995-03-01

The requirements of ANSI/ANS 8.1 specify that calculational methods for away-from-reactor criticality safety analyses be validated against experimental measurements. If credit is to be taken for the reduced reactivity of burned or spent fuel relative to its original fresh composition, it is necessary to benchmark computational methods used in determining such reactivity worth against spent fuel reactivity measurements. This report summarizes a portion of the ongoing effort to benchmark away-from-reactor criticality analysis methods using critical configurations from commercial pressurized water reactors (PWR). The analysis methodology utilized for all calculations in this report is based on the modules and data associated with the SCALE-4 code system. Each of the five volumes comprising this report provides an overview of the methodology applied. Subsequent volumes also describe in detail the approach taken in performing criticality calculations for these PWR configurations: Volume 2 describes criticality calculations for the Tennessee Valley Authority's Sequoyah Unit 2 reactor for Cycle 3; Volume 3 documents the analysis of Virginia Power's Surry Unit 1 reactor for the Cycle 2 core; Volume 4 documents the calculations performed based on GPU Nuclear Corporation's Three Mile Island Unit 1 Cycle 5 core; and, lastly, Volume 5 describes the analysis of Virginia Power's North Anna Unit 1 Cycle 5 core. Each of the reactor-specific volumes provides the details of calculations performed to determine the effective multiplication factor for each reactor core for one or more critical configurations using the SCALE-4 system; these results are summarized in this volume. Differences between the core designs and their possible impact on the criticality calculations are also discussed. Finally, results are presented for additional analyses performed to verify that solutions were sufficiently converged

Advisory Committee on human radiation experiments. Final report, Supplemental Volume 2. Sources and documentation

International Nuclear Information System (INIS)

1995-01-01

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

Advisory Committee on human radiation experiments. Final report, Supplemental Volume 2. Sources and documentation

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-01-01

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.

Nuclear regulatory legislation, 104th Congress, Volume 1, No. 4

International Nuclear Information System (INIS)

1997-12-01

This document is the first of two volumes compiling statutes and material pertaining to nuclear regulatory legislation through the 104th Congress, 2nd Session. It is intended for use as a U.S. Nuclear Regulatory Commission (NRC) internal resource document. Legislative information reproduced in this document includes portions of the Atomic Energy Act, Energy Reorganization Act, Low-Level Radioactive Waste Policy Amendments Act, and Nuclear Waste Policy Act. Other information included in this volume pertains to NRC user fees, NRC authorizations, the Inspector General Act, and the Administrative Procedure Act

Nuclear regulatory legislation, 104th Congress, Volume 1, No. 4

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-12-01

This document is the first of two volumes compiling statutes and material pertaining to nuclear regulatory legislation through the 104th Congress, 2nd Session. It is intended for use as a U.S. Nuclear Regulatory Commission (NRC) internal resource document. Legislative information reproduced in this document includes portions of the Atomic Energy Act, Energy Reorganization Act, Low-Level Radioactive Waste Policy Amendments Act, and Nuclear Waste Policy Act. Other information included in this volume pertains to NRC user fees, NRC authorizations, the Inspector General Act, and the Administrative Procedure Act.

Classification of e-government documents based on cooperative expression of word vectors

Science.gov (United States)

Fu, Qianqian; Liu, Hao; Wei, Zhiqiang

2017-03-01

The effective document classification is a powerful technique to deal with the huge amount of e-government documents automatically instead of accomplishing them manually. The word-to-vector (word2vec) model, which converts semantic word into low-dimensional vectors, could be successfully employed to classify the e-government documents. In this paper, we propose the cooperative expressions of word vector (Co-word-vector), whose multi-granularity of integration explores the possibility of modeling documents in the semantic space. Meanwhile, we also aim to improve the weighted continuous bag of words model based on word2vec model and distributed representation of topic-words based on LDA model. Furthermore, combining the two levels of word representation, performance result shows that our proposed method on the e-government document classification outperform than the traditional method.

LLCEDATA and LLCECALC for Windows version 1.0, Volume 3: Software verification and validation

International Nuclear Information System (INIS)

McFadden, J.G.

1998-01-01

LLCEDATA and LLCECALC for Windows are user-friendly computer software programs that work together to determine the proper waste designation, handling, and disposition requirements for Long Length Contaminated Equipment (LLCE). LLCEDATA reads from a variety of data bases to produce an equipment data file(EDF) that represents a snapshot of both the LLCE and the tank from which it originates. LLCECALC reads the EDF and the gamma assay file (AV2) that is produced by the flexible Receiver Gamma Energy Analysis System. LLCECALC performs corrections to the AV2 file as it is being read and characterizes the LLCE. Both programs produce a variety of reports, including a characterization report and a status report. The status report documents each action taken by the user, LLCEDATA, and LLCECALC. Documentation for LLCEDATA and LLCECALC for Windows is available in three volumes. Volume 1 is a user's manual, which is intended as a quick reference for both LLCEDATA and LLCECALC. Volume 2 is a technical manual, which discusses system limitations and provides recommendations to the LLCE process. Volume 3 documents LLCEDATA and LLCECALC's verification and validation. Two of the three installation test cases, from Volume 1, are independently confirmed. Data bases used in LLCEDATA are verified and referenced. Both phases of LLCECALC process gamma and characterization, are extensively tested to verify that the methodology and algorithms used are correct

Title list of documents made publicly available: May 1--31, 1997. Volume 19, Number 5

International Nuclear Information System (INIS)

1997-07-01

The Title List of Documents Made Publicly Available is a monthly publication. It describes the information received and published by the US Nuclear Regulatory Commission (NRC). This information includes (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials and (2) non-docketed material received and published by NRC pertinent to its role as a regulatory agency. As used here, docketed does not refer to Court dockets; it refers to the system by which NRC maintains its regulatory records. This series of documents is indexed by a Personal Author Index, a Corporate Source Index, and a Report Number Index

Title list of documents made publicly available: October 1--31, 1994. Volume 16, Number 10

Energy Technology Data Exchange (ETDEWEB)

1994-12-01

The Title List of Documents Made Publicly Available is a monthly publication. It contains descriptions of the information received and generated by the US Nuclear Regulatory Commission (NRC). This information includes (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials and (2) nondocketed material received and generated by NRC pertinent to its role as a regulatory agency. As used here, docketed does not refer to Court dockets; it refers to the system by which NRC maintains its regulatory records. This series of documents is indexed by a Personal Author Index, a Corporate Source Index, and a Report Number Index.

Title list of documents made publicly available June 1-30, 1984. Volume 6, No. 6

International Nuclear Information System (INIS)

1984-08-01

The Title List of Documents Made Publicly Available is a monthly publication. It contains descriptions of the information received and generated by the US Nuclear Regulatory Commission (NRC). This information includes: (1) docketed material asociated with civilian nuclear power plants and other uses of radioactive materials; and (2) nondocketed material received and generated by NRC pertinent to its role as a regulatory agency. As used here, docketed does not refer to Court dockets; it refers to the system by which NRC maintains its regulatory records. This series of documents is indexed by a Personal Author Index, a Corporate Source Index, and a Report Number Index

Title list of documents made publicly available: May 1--31, 1997. Volume 19, Number 5

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-07-01

The Title List of Documents Made Publicly Available is a monthly publication. It describes the information received and published by the US Nuclear Regulatory Commission (NRC). This information includes (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials and (2) non-docketed material received and published by NRC pertinent to its role as a regulatory agency. As used here, docketed does not refer to Court dockets; it refers to the system by which NRC maintains its regulatory records. This series of documents is indexed by a Personal Author Index, a Corporate Source Index, and a Report Number Index.

Title list of documents made publicly available. February 1-28, 1986. Volume 8, No. 2

International Nuclear Information System (INIS)

1986-04-01

The Title List of Documents Made Publicly Available is a monthly publication. It contains descriptions of the information received and generated by the US Nuclear Regulatory Commission (NRC). This information includes (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials and (2) nondocketed material received and generated by NRC pertinent to its role as a regulatory agency. As used here, docketed does not refer to Court dockets; it refers to the system by which NRC maintains its regulatory records. This series of documents is indexed by a Personal Author Index, a Corporate Source Index, and a Report Number Index

Title list of documents made publicly available, December 1--31, 1993, Volume 15, No. 12

International Nuclear Information System (INIS)

1994-02-01

The Title List of Documents Made Publicly Available is a monthly publication. It contains descriptions of the information received and generated by the U.S. Nuclear Regulatory Commission (NRC). This information includes (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials and (2) nondocketed material received and generated by NRC pertinent to its role as a regulatory agency. As used here, docketed does not refer to Court dockets; it refers to the system by which NRC maintains its regulatory records. This series of documents is indexed by a Personal Author Index, a Corporate Source Index, and a Report Number Index

Title list of documents made publicly available, December 1--31, 1993, Volume 15, No. 12

Energy Technology Data Exchange (ETDEWEB)

NONE

1994-02-01

The Title List of Documents Made Publicly Available is a monthly publication. It contains descriptions of the information received and generated by the U.S. Nuclear Regulatory Commission (NRC). This information includes (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials and (2) nondocketed material received and generated by NRC pertinent to its role as a regulatory agency. As used here, docketed does not refer to Court dockets; it refers to the system by which NRC maintains its regulatory records. This series of documents is indexed by a Personal Author Index, a Corporate Source Index, and a Report Number Index.

Title list of documents made publicly available: February 1--29, 1996. Volume 18, Number 2

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-04-01

The Title List of Documents Made Publicly Available is a monthly publication. It contains descriptions of the information received and generated by the US Nuclear Regulatory Commission (NRC). This information includes (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials and (2) nondocketed material received and generated by NRC pertinent to its role as a regulatory agency. As used here, docketed does not refer to Court dockets; it refers to the system by which NRC maintains its regulatory records. This series of documents is indexed by a Personal Author Index, a Corporate Source Index, and a Report Number Index.

Title list of documents made publicly available: February 1--29, 1996. Volume 18, Number 2

International Nuclear Information System (INIS)

1996-04-01

The Title List of Documents Made Publicly Available is a monthly publication. It contains descriptions of the information received and generated by the US Nuclear Regulatory Commission (NRC). This information includes (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials and (2) nondocketed material received and generated by NRC pertinent to its role as a regulatory agency. As used here, docketed does not refer to Court dockets; it refers to the system by which NRC maintains its regulatory records. This series of documents is indexed by a Personal Author Index, a Corporate Source Index, and a Report Number Index

Title list of documents made publicly available: October 1--31, 1994. Volume 16, Number 10

International Nuclear Information System (INIS)

1994-12-01

The Title List of Documents Made Publicly Available is a monthly publication. It contains descriptions of the information received and generated by the US Nuclear Regulatory Commission (NRC). This information includes (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials and (2) nondocketed material received and generated by NRC pertinent to its role as a regulatory agency. As used here, docketed does not refer to Court dockets; it refers to the system by which NRC maintains its regulatory records. This series of documents is indexed by a Personal Author Index, a Corporate Source Index, and a Report Number Index

Title list of documents made publicly available, March 1-31, 1986. Volume 8, No. 3

International Nuclear Information System (INIS)

1986-05-01

The Title List of Documents Made Publicly Available is a monthly publication. It contains descriptions of the information received and generated by the US Nuclear Regulatory Commission (NRC). This information includes (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials and (2) nondocketed material received and generated by NRC pertinent to its role as a regulatory agency. As used here, docketed does not refer to Court dockets; it refers to the system by which NRC maintains its regulatory records. This series of documents is indexed by a Personal Author Index, a Corporate Source Index, and a Report Number Index

Integrating model of the Project Independence Evaluation System. Volume VI. Data documentation. Part I

Energy Technology Data Exchange (ETDEWEB)

Allen, B J

1979-02-01

This documentation describes the PIES Integrating Model as it existed on January 1, 1978. This volume contains two chapters. In Chapter I, Overview, the following subjects are briefly described: supply data, EIA projection series and scenarios, demand data and assumptions, and supply assumptions - oil and gas availabilities. Chapter II contains supply and demand data tables and sources used by the PIES Integrating Model for the mid-range scenario target years 1985 and 1990. Tabulated information is presented for demand, price, and elasticity data; coal data; imports data; oil and gas data; refineries data; synthetics, shale, and solar/geothermal data; transportation data; and utilities data.

Provable Fair Document Exchange Protocol with Transaction Privacy for E-Commerce

OpenAIRE

Ren-Junn Hwang; Chih-Hua Lai

2015-01-01

Transaction privacy has attracted a lot of attention in the e-commerce. This study proposes an efficient and provable fair document exchange protocol with transaction privacy. Using the proposed protocol, any untrusted parties can fairly exchange documents without the assistance of online, trusted third parties. Moreover, a notary only notarizes each document once. The authorized document owner can exchange a notarized document with different parties repeatedly without disclosing the origin o...

SCALE: A modular code system for performing standardized computer analyses for licensing evaluation. Control modules -- Volume 1, Revision 4

Energy Technology Data Exchange (ETDEWEB)

Landers, N.F.; Petrie, L.M.; Knight, J.R. [Oak Ridge National Lab., TN (United States)] [and others

1995-04-01

SCALE--a modular code system for Standardized Computer Analyses Licensing Evaluation--has been developed by Oak Ridge National Laboratory at the request of the US Nuclear Regulatory Commission. The SCALE system utilizes well-established computer codes and methods within standard analysis sequences that (1) allow an input format designed for the occasional user and/or novice, (2) automate the data processing and coupling between modules, and (3) provide accurate and reliable results. System development has been directed at problem-dependent cross-section processing and analysis of criticality safety, shielding, heat transfer, and depletion/decay problems. Since the initial release of SCALE in 1980, the code system has been heavily used for evaluation of nuclear fuel facility and package designs. This revision documents Version 4.2 of the system. This manual is divided into three volumes: Volume 1--for the control module documentation, Volume 2--for the functional module documentation, and Volume 3 for the documentation of the data libraries and subroutine libraries.

SCALE: A modular code system for performing standardized computer analyses for licensing evaluation. Control modules -- Volume 1, Revision 4

International Nuclear Information System (INIS)

Landers, N.F.; Petrie, L.M.; Knight, J.R.

1995-04-01

SCALE--a modular code system for Standardized Computer Analyses Licensing Evaluation--has been developed by Oak Ridge National Laboratory at the request of the US Nuclear Regulatory Commission. The SCALE system utilizes well-established computer codes and methods within standard analysis sequences that (1) allow an input format designed for the occasional user and/or novice, (2) automate the data processing and coupling between modules, and (3) provide accurate and reliable results. System development has been directed at problem-dependent cross-section processing and analysis of criticality safety, shielding, heat transfer, and depletion/decay problems. Since the initial release of SCALE in 1980, the code system has been heavily used for evaluation of nuclear fuel facility and package designs. This revision documents Version 4.2 of the system. This manual is divided into three volumes: Volume 1--for the control module documentation, Volume 2--for the functional module documentation, and Volume 3 for the documentation of the data libraries and subroutine libraries

Present status of the EUR document the challenge of new incorporations

International Nuclear Information System (INIS)

Alomar, F.

1998-01-01

EUR (European Utilities Requirements) Document is in process, with DTN's active participation since the beginning. Two new Utilities representing non-European Union Countries (Switzerland and Russia) have joined the EUR Document Group of Sponsoring Utilities, whose members up to now belonged to nine utilities from European Union Countries. Although, in general terms, this incorporation is enriching, this late arrival does present problems due to the fact that the document is now under discussion the incorporation of different technological practices, and last but not least, different Licensing Approaches. Should be remembered that currently an overall review by the different Regulatory Bodies is in process and an intervention by the E.C. is being prepared. Both inside and outside of the European Continent, other Utilities have also shown their interest in the EUR Document. EUR Document Volume 3 sets a compliance evaluation between Projects from different Nuclear Island Manufactures and EUR's Top Tier Requirements (established in Volume 1) and Detailed Requirements (established in Volume 2). Presently a comparison is being carried out for three Nuclear Island Suppliers: ABB, NPI (KWU and Framatome Joint Venture) and Westinghouse. In the near future it is foreseen to initiate compliance evaluation for two more N.I. suppliers: General Electric and Rosenergatom. Challenges of these new incorporations are analyzed in what follows. (Author)

NRC review of Electric Power Research Institute's Advanced Light Water Reactor Utility Requirements Document - Evolutionary plant designs, Chapter 1, Project No. 669

International Nuclear Information System (INIS)

1992-08-01

The staff of the US Nuclear Regulatory Commission has prepared Volume 2 (Parts 1 and 2) of a safety evaluation report (SER), ''NRC Review of Electric Power Research Institute's Advanced Light Water Reactor Utility Requirements Document -- Evolutionary Plant Designs,'' to document the results of its review of the Electric Power Research Institute's ''Advanced Light Water Reactor Utility Requirements Document.'' This SER gives the results of the staff's review of Volume II of the Requirements Document for evolutionary plant designs, which consists of 13 chapters and contains utility design requirements for an evolutionary nuclear power plant (approximately 1300 megawatts-electric)

ENDF/B summary documentation

International Nuclear Information System (INIS)

Garber, D.

1975-10-01

Descriptions of the evaluations contained in the ENDF/B library are given. The summary documentation presented is intended to be a more detailed description than the (File 1) comments contained in the computer-readable data files, but not so detailed as the formal reports describing each ENDF/B evaluation. The documentations were written by the CSEWG evaluators and compiled by NNCSC. Selected materials which comprise this volume include from 1 H to 244 Cm

Building America Best Practices Series Volume 8: Builders Challenge Quality Criteria Support Document

Energy Technology Data Exchange (ETDEWEB)

Baechler, Michael C.; Bartlett, Rosemarie; Gilbride, Theresa L.

2010-11-01

The U.S. Department of Energy (DOE) has posed a challenge to the homebuilding industry—to build 220,000 high-performance homes by 2012. Through the Builders Challenge, participating homebuilders will have an easy way to differentiate their best energy-performing homes from other products in the marketplace, and to make the benefits clear to buyers. This document was prepared by Pacific Northwest National Laboratory for DOE to provide guidance to U.S. home builders who want to accept the challenge. To qualify for the Builders Challenge, a home must score 70 or less on the EnergySmart Home Scale (E-Scale). The E-scale is based on the well-established Home Energy Rating System (HERS) index, developed by the Residential Energy Services Network (RESNET). The E-scale allows homebuyers to understand – at a glance – how the energy performance of a particular home compares with the performance of others. To learn more about the index and HERS Raters, visit www.natresnet.org. Homes also must meet the Builders Challenge criteria described in this document. To help builders meet the Challenge, guidance is provided in this report for each of the 29 criteria. Included with guidance for each criteria are resources for more information and references for relevant codes and standards. The Builders Challenge Quality Criteria were originally published in Dec. 2008. They were revised and published as PNNL-18009 Rev 1.2 in Nov. 2009. This is version 1.3, published Nov 2010. Changes from the Nov 2009 version include adding a title page and updating the Energy Star windows critiera to the Version 5.0 criteria approved April 2009 and effective January 4, 2010. This document and other information about the Builders Challenge is available on line at www.buildingamerica.gov/challenge.

Title list of documents made publicly available: January 1--31, 1996. Volume 18, Number 1

International Nuclear Information System (INIS)

1996-03-01

This monthly publication contains descriptions of the information received and generated by the US Nuclear Regulatory Commission (NRC). This information includes (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials and (2) nondocketed material received and generated by NRC pertinent to its role as a regulatory agency. As used here, docketed refers to the system by which NRC maintains its regulatory records. This series of documents is indexed by a Personal Author Index, a Corporate Source Index, and a Report Number Index. Some of the topics relate to: low-level radioactive disposal sites, source material, production and utilization facilities, special nuclear material, packaging and transport and spent fuel storage

Title list of documents made publicly available: January 1--31, 1996. Volume 18, Number 1

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-03-01

This monthly publication contains descriptions of the information received and generated by the US Nuclear Regulatory Commission (NRC). This information includes (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials and (2) nondocketed material received and generated by NRC pertinent to its role as a regulatory agency. As used here, docketed refers to the system by which NRC maintains its regulatory records. This series of documents is indexed by a Personal Author Index, a Corporate Source Index, and a Report Number Index. Some of the topics relate to: low-level radioactive disposal sites, source material, production and utilization facilities, special nuclear material, packaging and transport and spent fuel storage.

1. What is E-Commerce?

Indian Academy of Sciences (India)

Home; Journals; Resonance – Journal of Science Education; Volume 5; Issue 10. Electronic Commerce - What is E-Commerce? V Rajaraman. Series Article Volume 5 Issue 10 October 2000 pp 13-23 ... Author Affiliations. V Rajaraman1. IBM Professor of Information Technology, JNCASR, Bangalore 560 064, India.

Circuiti ad impulsi e digitali volume di aggiornamento

CERN Document Server

Millman, Jacob

1967-01-01

Questo terzo volume "Circuiti ad impulsi e digitali" contiene la traduzione di parte degli argomenti trattati nel volume "Pulse, digital and switching waveforms" degli autori J. Millman e H. Taub edito dalla Mc Graw-Hill Book Company nel 1965. Gli autori nella presentazione del volume inglese dichiarano di averlo originariamente previsto come una seconda edizione di "Pulse and digital circuits" di cui i primi due volumi delle Edizioni Bizzarri sono la traduzione.

Automotive Manufacturing Assessment System : Volume 1. Master Product Schedules.

Science.gov (United States)

1999-11-01

Volume I is part of a four volume set documenting areas of research resulting from the development of the Automotive Manufacturing Assessment System (AMAS) for the DOT/Transportation Systems Center. AMAS was designed to assist in the evaluation of in...

Data package for the Low-Level Waste Disposal Development and Demonstration Program environmental impact statement: Volume 2, Appendices E-O

Energy Technology Data Exchange (ETDEWEB)

Ketelle, R.H.

1988-09-01

This volume contains 11 appendices to the main document in Volume 1. Topics in Volume 2 include hydrologic data for a proposed solid waste storage area, soil characterizations, well logs, surface water discharge data, water quality data, atmospheric precipitation and stream flow, a small mammal survey, and general ecological information. (TEM)

Standard technical specifications: General Electric plants, BWR/4. Volume 1, Revision 1: Specifications

International Nuclear Information System (INIS)

1995-04-01

This report documents the results of the combined effort of the NRC and the industry to produce improved Standard Technical Specifications (STS), Revision 1 for General Electric BWR/4 Plants. The changes reflected in Revision 1 resulted from the experience gained from license amendment applications to convert to these improved STS or to adopt partial improvements to existing technical specifications. This NUREG is the result of extensive public technical meetings and discussions between the Nuclear Regulatory Commission (NRC) staff and various nuclear power plant licensees, Nuclear Steam Supply System (NSSS) Owners Groups, NSSS vendors, and the Nuclear Energy Institute (NEI). The improved STS were developed based on the criteria in the Final Commission Policy Statement on Technical Specifications Improvements for Nuclear Power Reactors, dated July 22, 1993. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. Volume 1 contains the Specifications for all chapters and sections of the improved STS. Volume 2 contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1--3.3 of the improved STS. Volume 3 contains the Bases for Sections 3.4--3.10 of the improved STS

East African Journal of Sciences (2015) Volume 9 (1) 41-48 Effect of ...

African Journals Online (AJOL)

tosheba

East African Journal of Sciences (2015). Volume 9 (1) 41-48 ... but no significant difference was observed amongst them. Queen .... used method of termite management in western. Ethiopia ..... Ethiopia. Working Document Series 68, ICRA,.

Metodologia para estudo do volume e densidade absoluta da placenta humana de termo

Directory of Open Access Journals (Sweden)

Del Nero Ulisses

2002-01-01

Full Text Available OBJETIVO: comparar duas metodologias para o cálculo do volume placentário em gestações normais de termo: a do princípio de Arquimedes e a do volume do cilindro, para estimar a densidade absoluta da placenta. Definir a metodologia mais adequada para o cálculo do volume e densidade placentários, que se relacione com o peso e classificação do recém-nascido. MÉTODOS: foram estudadas 50 placentas provenientes de gestações de termo sem complicações e calculados o volume e a densidade absoluta placentários: a pelo princípio de Arquimedes e b na suposição de que a placenta seria uma secção de cilindro com duas alturas diferentes do bolo placentário: com a altura média e com a altura da média aritmética do centro e extremidades. As densidades absolutas placentárias foram calculadas pelo quociente entre o peso ao ar da placenta e os diferentes volumes. RESULTADOS: a maioria das gestantes eram multíparas, idade média de 25,4 anos, volume placentário médio entre 547,8 e 610 cmsuperscript three e densidade média entre 0,94 e 1,14 g/cmsuperscript three, dependendo da metodologia empregada. CONCLUSÕES: a metodologia mais adequada para estimar o volume placentário no termo foi a do princípio de Arquimedes, pela melhor correlação com o peso dos recém-nascidos, o índice placentário e a classificação do peso dos recém-nascidos em relação à idade gestacional.

Plasma Interactions with Spacecraft. Volume 2, NASCAP-2K Scientific Documentation for Version 4.1

Science.gov (United States)

2011-04-15

surface is taken as the equipotential surface at  = ±ln2. This choice is made because the attracted species is absorbed by the sheath, so we have only...spacecraft-generated plasma environments on spacecraft systems. This document describes the physics and numeric models used in the surface charging...2 2.1 Surface Charging from Orbit Limited Currents

Title list of documents made publicly available, October 1 through 31, 1985. Volume 7, No. 10

International Nuclear Information System (INIS)

1985-11-01

This Title List of Documents Made Publicly Available is a monthly publication containing descriptions of the information received and generated by the US Nuclear Regulatory Commission (NRC) during October 1985. This information includes (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials and (2) nondocketed material received and generated by NRC pertinent to its role as a regulatory agency. As used here, docketed does not refer to Court dockets; it refers to the system by which NRC maintains its regulatory records. This series of documents is indexed by a Personal Author Index, a Corporate Source Index, and a Report Number Index

KCNQ1 channels sense small changes in cell volume

DEFF Research Database (Denmark)

Grunnet, Morten; Jespersen, Thomas; MacAulay, Nanna

2003-01-01

Many important physiological processes involve changes in cell volume, e.g. the transport of salt and water in epithelial cells and the contraction of cardiomyocytes. In this study, we show that voltage-gated KCNQ1 channels, which are strongly expressed in epithelial cells or cardiomyocytes......, and KCNQ4 channels, expressed in hair cells and the auditory tract, are tightly regulated by small cell volume changes when co-expressed with aquaporin 1 water-channels (AQP1) in Xenopus oocytes. The KCNQ1 and KCNQ4 current amplitudes precisely reflect the volume of the oocytes. By contrast, the related...... KCNQ2 and KCNQ3 channels, which are prominently expressed in neurons, are insensitive to cell volume changes. The sensitivity of the KCNQ1 and KCNQ4 channels to cell volume changes is independent of the presence of the auxiliary KCNE1-3 subunits, although modulated by KCNE1 in the case of KCNQ1...

SEL/Project Language. Level II, Kindergarten, Volume I (Lessons 1-16).

Science.gov (United States)

Valladares, Ann E.; And Others

The document is an intervention curriculum guide designed to facilitate the initial adjustment of disadvantaged Southeastern children to kindergarten or first grade. The major emphasis is on the teaching of language skills in combination with subject matter learning using a language-experience approach. This volume contains Lessons 1-16 of a…

Title list of documents made publicly available, November 1-30, 1985. Volume 7, No. 11

International Nuclear Information System (INIS)

1985-12-01

The Title List of Documents Made Publicly Available contains descriptions of the information received and generated by the US Nuclear Regulatory Commission (NRC) during November 1985. This information includes: (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials and (2) nondocketed material received and generated by NRC pertinent to its role as a regulatory agency

Detailed requirements document for the Interactive Financial Management System (IFMS), volume 1

Science.gov (United States)

Dodson, D. B.

1975-01-01

The detailed requirements for phase 1 (online fund control, subauthorization accounting, and accounts receivable functional capabilities) of the Interactive Financial Management System (IFMS) are described. This includes information on the following: systems requirements, performance requirements, test requirements, and production implementation. Most of the work is centered on systems requirements, and includes discussions on the following processes: resources authority, allotment, primary work authorization, reimbursable order acceptance, purchase request, obligation, cost accrual, cost distribution, disbursement, subauthorization performance, travel, accounts receivable, payroll, property, edit table maintenance, end-of-year, backup input. Other subjects covered include: external systems interfaces, general inquiries, general report requirements, communication requirements, and miscellaneous. Subjects covered under performance requirements include: response time, processing volumes, system reliability, and accuracy. Under test requirements come test data sources, general test approach, and acceptance criteria. Under production implementation come data base establishment, operational stages, and operational requirements.

Probabilistic accident consequence uncertainty analysis: Food chain uncertainty assessment. Volume 1: Main report

Energy Technology Data Exchange (ETDEWEB)

Brown, J. [National Radiological Protection Board (United Kingdom); Goossens, L.H.J.; Kraan, B.C.P. [Delft Univ. of Technology (Netherlands)] [and others

1997-06-01

This volume is the first of a two-volume document that summarizes a joint project conducted by the US Nuclear Regulatory Commission and the European Commission to assess uncertainties in the MACCS and COSYMA probabilistic accident consequence codes. These codes were developed primarily for estimating the risks presented by nuclear reactors based on postulated frequencies and magnitudes of potential accidents. This document reports on an ongoing project to assess uncertainty in the MACCS and COSYMA calculations for the offsite consequences of radionuclide releases by hypothetical nuclear power plant accidents. A panel of sixteen experts was formed to compile credible and traceable uncertainty distributions for food chain variables that affect calculations of offsite consequences. The expert judgment elicitation procedure and its outcomes are described in these volumes. Other panels were formed to consider uncertainty in other aspects of the codes. Their results are described in companion reports. Volume 1 contains background information and a complete description of the joint consequence uncertainty study. Volume 2 contains appendices that include (1) a summary of the MACCS and COSYMA consequence codes, (2) the elicitation questionnaires and case structures for both panels, (3) the rationales and results for the panels on soil and plant transfer and animal transfer, (4) short biographies of the experts, and (5) the aggregated results of their responses.

Probabilistic accident consequence uncertainty analysis: Food chain uncertainty assessment. Volume 1: Main report

International Nuclear Information System (INIS)

Brown, J.; Goossens, L.H.J.; Kraan, B.C.P.

1997-06-01

This volume is the first of a two-volume document that summarizes a joint project conducted by the US Nuclear Regulatory Commission and the European Commission to assess uncertainties in the MACCS and COSYMA probabilistic accident consequence codes. These codes were developed primarily for estimating the risks presented by nuclear reactors based on postulated frequencies and magnitudes of potential accidents. This document reports on an ongoing project to assess uncertainty in the MACCS and COSYMA calculations for the offsite consequences of radionuclide releases by hypothetical nuclear power plant accidents. A panel of sixteen experts was formed to compile credible and traceable uncertainty distributions for food chain variables that affect calculations of offsite consequences. The expert judgment elicitation procedure and its outcomes are described in these volumes. Other panels were formed to consider uncertainty in other aspects of the codes. Their results are described in companion reports. Volume 1 contains background information and a complete description of the joint consequence uncertainty study. Volume 2 contains appendices that include (1) a summary of the MACCS and COSYMA consequence codes, (2) the elicitation questionnaires and case structures for both panels, (3) the rationales and results for the panels on soil and plant transfer and animal transfer, (4) short biographies of the experts, and (5) the aggregated results of their responses

Technical support document for land application of sewage sludge. Volume 1. Final report

International Nuclear Information System (INIS)

Jones, A.; Beyer, L.; Rookwood, M.; Pacenka, J.; Bergin, J.

1992-11-01

The document provides the technical background and justification for the U.S. Environmental Protection Agency's (EPA) final regulation (40 CFR Part 503) covering the land application of sewage sludge. The document summarizes current practices in land application and presents data supporting the risk assessment methodology used to derive human health and environmental risk-based limits for contaminants in land applied sewage sludge. The management practices associated with land application are outlined and the different pathways by which contaminants reach highly-exposed individuals (HEIs) through land application are discussed

Evaluation of potential severe accidents during low power and shutdown operations at Surry: Unit 1, Volume 1

International Nuclear Information System (INIS)

Chu, T.L.; Pratt, W.T.

1995-10-01

This document contains a summarization of the results and insights from the Level 1 accident sequence analyses of internally initiated events, internally initiated fire and flood events, seismically initiated events, and the Level 2/3 risk analysis of internally initiated events (excluding fire and flood) for Surry, Unit 1. The analysis was confined to mid-loop operation, which can occur during three plant operational states (identified as POSs R6 and R10 during a refueling outage, and POS D6 during drained maintenance). The report summarizes the Level 1 information contained in Volumes 2--5 and the Level 2/3 information contained in Volume 6 of NUREG/CR-6144

Evaluation of potential severe accidents during low power and shutdown operations at Surry: Unit 1, Volume 1

Energy Technology Data Exchange (ETDEWEB)

Chu, T.L.; Pratt, W.T. [eds.; Musicki, Z. [Brookhaven National Lab., Upton, NY (United States)

1995-10-01

This document contains a summarization of the results and insights from the Level 1 accident sequence analyses of internally initiated events, internally initiated fire and flood events, seismically initiated events, and the Level 2/3 risk analysis of internally initiated events (excluding fire and flood) for Surry, Unit 1. The analysis was confined to mid-loop operation, which can occur during three plant operational states (identified as POSs R6 and R10 during a refueling outage, and POS D6 during drained maintenance). The report summarizes the Level 1 information contained in Volumes 2--5 and the Level 2/3 information contained in Volume 6 of NUREG/CR-6144.

Exploring the Unknown: Selected Documents in the History of the U.S. Civil Space Program. Volume 4; Accessing Space

Science.gov (United States)

Logsdon, John M. (Editor); Williamson, Ray A. (Editor); Launius, Roger D. (Editor); Acker, Russell J. (Editor); Garber, Stephen J. (Editor); Friedman, Jonathan L. (Editor)

1999-01-01

The documents selected for inclusion in this volume are presented in four major chapters, each covering a particular aspect of access to space and the manner in which it has developed over time. These chapters focus on the evolution toward the giant Saturn V rocket, the development of the Space Shuttle, space transportation commercialization, and future space transportation possibilities. Each chapter in this volume is introduced by an overview essay, prepared by individuals who are particularly well qualified to write on the topic. In the main, these essays are intended to introduce and complement the documents in the chapter and to place them, for the most part, in a chronological and substantive context. Each essay contains references to the documents in the chapter it introduces, and many also contain references to documents in other chapters of the collection. These introductory essays are the responsibility of their individual authors, and the views and conclusions contained therein do not necessarily represent the opinions of either George Washington University or NASA.

Title list of documents made publicly available, July 1--31, 1996: Volume 18, No. 7

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-09-01

This monthly publication describes information received and published by US NRC. This information includes (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials and (2) nondocketed material received and published by NRC pertinent to its role as a regulatory agency. Following indexes are included: personal author, corporate source, report number, and cross reference of enclosures to principal documents.

Title list of documents made publicly available, July 1--31, 1996: Volume 18, No. 7

International Nuclear Information System (INIS)

1996-09-01

This monthly publication describes information received and published by US NRC. This information includes (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials and (2) nondocketed material received and published by NRC pertinent to its role as a regulatory agency. Following indexes are included: personal author, corporate source, report number, and cross reference of enclosures to principal documents

Provable Fair Document Exchange Protocol with Transaction Privacy for E-Commerce

Directory of Open Access Journals (Sweden)

Ren-Junn Hwang

2015-04-01

Full Text Available Transaction privacy has attracted a lot of attention in the e-commerce. This study proposes an efficient and provable fair document exchange protocol with transaction privacy. Using the proposed protocol, any untrusted parties can fairly exchange documents without the assistance of online, trusted third parties. Moreover, a notary only notarizes each document once. The authorized document owner can exchange a notarized document with different parties repeatedly without disclosing the origin of the document or the identities of transaction participants. Security and performance analyses indicate that the proposed protocol not only provides strong fairness, non-repudiation of origin, non-repudiation of receipt, and message confidentiality, but also enhances forward secrecy, transaction privacy, and authorized exchange. The proposed protocol is more efficient than other works.

Site Environmental Report for 1999 - Volume 1

Energy Technology Data Exchange (ETDEWEB)

Ruggieri, M

2000-08-12

Each year, Ernest Orlando Lawrence Berkeley National Laboratory prepares an integrated report on its environmental programs to satisfy the requirements of United States Department of Energy Order 231.1. The Site Environmental Report for 1999 is intended to summarize Berkeley Lab's compliance with environmental standards and requirements, characterize environmental management efforts through surveillance and monitoring activities, and highlight significant programs and efforts for calendar year 1999. The report is separated into two volumes. Volume I contains a general overview of the Laboratory, the status of environmental programs, and summary results from surveillance and monitoring activities. Each chapter in Volume I begins with an outline of the sections that follow, including any tables or figures found in the chapter. Readers should use section numbers (e.g., {section}1.5) as navigational tools to find topics of interest in either the printed or the electronic version of the report. Volume II contains the individual data results from monitoring programs.

Identification of sites within the Palo Duro Basin. Volume 1. Palo Duro Location A

International Nuclear Information System (INIS)

1984-11-01

This three-volume document narrows to two sites for continued investigations for potential nuclear waste repository sites in the Palo Duro Basin of the Texas Panhandle. Volume 1 narrows a site previously identified in Deaf Smith County, Texas; Volume 2 narrows a site previously identified in Swisher County, Texas; and Volume 3 contains responses to comments received regarding the drafts of Volumes 1 and 2 (BMI/ONWI-531). These volumes discuss the methodology and logic used as well as the results that narrowed these sites. Each of the 10 site performance criteria was divided into descriptors related to site performance characteristics. Each descriptor was evaluated by a systematic logic to determine if it could be used as a discriminator. Then more- and less-preferred areas for groups of discriminators were defined and composite maps were prepared and evaluated to identify the sites

Title list of documents made publicly available, March 1-31, 1983. Volume 5, No. 3

International Nuclear Information System (INIS)

1983-03-01

The Title List of Documents Made Publicly Available is a monthly publication. It contains descriptions of the information received and generated by the US Nuclear Regulatory Commission (NRC). This information includes (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials and (2) nondocketed material received and generated by NRC pertinent to its role as a regulatory agency. As used here, docketed does not refer to Court dockets; it refers to the system by which NRC maintains its regulatory records. This series of documents is indexed by a Personal Author Index, a Corporate Source Index, and a Report Number Index. The docketed information contained in the Title List includes the information formerly issued through the Department of Energy publication Power Reactor Docket Information, last published in January 1979. Microfiche of the docketed information listed in the Title List is available for sale on a subscription basis from the National Technical Inforation Service (NTIS)

Title list of documents made publicly available, February 1-29, 1980. Volume 2, Number 2. Monthly report

International Nuclear Information System (INIS)

1980-04-01

The document is a monthly publication containing descriptions of information received and generated by the U.S. NRC. This information includes (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials and (2) nondocketed material received and generated by NRC pertinent to its role as a regulatory agency. The docketed information includes information formerly issued through U.S. Department of Energy's Technical Information Center under the title Power Reactor Docket Information (PRDI). This document replaces PRDI, which will no longer be prepared. It is indexed by a Personal Author Index, Corporate Source Index, and Report Number Index

Measurement and correlation of excess molar volumes for mixtures of 1-propanol and aromatic hydrocarbons

International Nuclear Information System (INIS)

Gahlyan, Suman; Rani, Manju; Maken, Sanjeev Kumar; Lee, Inkyu; Moon, Il

2015-01-01

Excess molar volumes (V m E ) have been measured at 303.15 K for 1-propanol+benzene or toluene or o- or m- or p-xylene mixtures using V-shape dilatometer. The V m E values, for an equimolar composition, vary in the order: benzene>toluene-m-xylene>o-xylene>p-xylene. The V m E data have been used to calculate partial molar volumes, excess partial molar volumes, and apparent molar volumes of 1-propanol and aromatic hydrocarbons over the entire range of composition. The excess volume data have also been interpreted in terms of graph-theoretical approach and Prigogine-Flory-Patterson theory (PFP). While PFP theory fails to predict the V m E values for systems with s-shaped V m E versus x 1 graph, the V m E values calculated by graph theory compare reasonably well with the corresponding experimental values. This graph theory analysis has further yielded information about the state of aggregation of pure components as well as of the mixtures

Estoque e crescimento em volume, biomassa, carbono e dióxido de carbono em Floresta Estacional Semidecidual

Directory of Open Access Journals (Sweden)

Agostinho Lopes de Souza

2011-12-01

Full Text Available O objetivo deste trabalho foi estimar o estoque e o crescimento em volume (V, biomassa (B, carbono (C e dióxido de carbono (CO2 em Floresta Estacional Semidecidual no Vale do Rio Doce, em Minas Gerais. Foram utilizados dados de inventários do estrato arbóreo (DAP > 5,0 cm, cujas parcelas permanentes foram medidas em 2002 e 2007, em estágios médio (Mata 1 e avançado (Mata 2 de regeneração da vegetação secundária. Com base no inventário de 2002, foram selecionadas espécies que apresentavam maiores percentuais em volume e no mínimo cinco indivíduos para determinar as densidades básicas da madeira e da casca. A média da densidade básica da madeira foi de 0,65 g.cm-3 e da casca, igual a 0,49 g.cm-3. Os estoques e os crescimentos em V, B, C e CO2 foram estimados nos dois estágios, Mata 1 e Mata 2. Pelo fato de as matas se encontrarem em estágios médio e avançado de regeneração, respectivamente, elas apresentavam estruturas, estoques e crescimentos distintos.

Human-system interface design review guideline -- Review software and user's guide: Final report. Revision 1, Volume 3

International Nuclear Information System (INIS)

1996-06-01

NUREG-0700, Revision 1, provides human factors engineering (HFE) guidance to the US Nuclear Regulatory Commission staff for its: (1) review of the human system interface (HSI) design submittals prepared by licensees or applications for a license or design certification of commercial nuclear power plants, and (2) performance of HSI reviews that could be undertaken as part of an inspection or other type of regulatory review involving HSI design or incidents involving human performance. The guidance consists of a review process and HFE guidelines. The document describes those aspects of the HSI design review process that are important to the identification and resolution of human engineering discrepancies that could adversely affect plant safety. Guidance is provided that could be used by the staff to review an applicant's HSI design review process or to guide the development of an HSI design review plan, e.g., as part of an inspection activity. The document also provides detailed HFE guidelines for the assessment of HSI design implementations. NUREG-0700, Revision 1, consists of three stand-alone volumes. Volume 3 contains an interactive software application of the NUREG-0700, Revision 1 guidance and a user's guide for this software. The software supports reviewers during review preparation, evaluation design using the human factors engineering guidelines, and in report preparation. The user's guide provides system requirements and installation instructions, detailed explanations of the software's functions and features, and a tutorial on using the software

47 CFR 1.355 - Documents in foreign language.

Science.gov (United States)

2010-10-01

... 47 Telecommunication 1 2010-10-01 2010-10-01 false Documents in foreign language. 1.355 Section 1... Proceedings Evidence § 1.355 Documents in foreign language. Every document, exhibit, or other paper written in a language other than English, which shall be filed in any proceeding, or in response to any order...

Response to comments background document for the Third Third land-disposal restrictions proposed rule November 22, 1989 (54 FR 48372). Volume 2-2. Capacity-related comments

International Nuclear Information System (INIS)

1990-01-01

On November 22, 1989, the Environmental Protection Agency (EPA, the Agency) proposed a rule to prohibit the land disposal of the final third of the schedule of restricted hazardous wastes, known as the Third Third (see 54 Federal Register 48372). The proposal outlined treatment standards and effective dates of prohibition for these wastes as well as for some First and Second Third soft hammer wastes, characteristic wastes, certain waste groups (e.g., multi-source leachate, radioactive mixed waste), and newly listed wastes. The proposed rule was issued pursuant to the 1984 Hazardous and Solid Waste Amendments (HSWA) to the Resource Conservation and Recovery Act (RCRA). The Agency requested public comment on the proposal. The regulated community, environmental organizations, trade associations, State and Federal agencies, and concerned citizens submitted over 300 written letters on the proposed rule. EPA developed three volumes of a comment response document. This document (Volume 2 of 3) presents a summary of and responses to capacity-related comments received by the EPA docket clerk in response to the proposed rule. The comments have been divided into 17 chapters, each addressing specific comment categories. This volume contains Chapters 8-12. These chapters discuss mercury wastes, other metals, F, K, U, and P wastes, KO48-KO52 wastes, and deepwell injected wastes

In Situ Soil Venting - Full Scale Test, Hill AFB. Volume 3. Guidance Document, Literature Review

Science.gov (United States)

1991-08-01

calculations of hydrocarbon removal efficiency ( Section V.J). 2. Aurea Becncath Tank Excavation The area bcncath the tank excavation was subdivided into...Capt. Michael Elliott, Mr. Doug Downey, and Capt. Edward Marchand. Section V.E. of this document consists of the text of ’Enhanced Biodegrzdation...Environics Division (The reverse of this page is blank) TABLE OF CONTENTS Section Title Page I INTRODUCTION ......................................... 1 A

47 CFR 1.14 - Citation of Commission documents.

Science.gov (United States)

2010-10-01

... 47 Telecommunication 1 2010-10-01 2010-10-01 false Citation of Commission documents. 1.14 Section... Rules of Practice and Procedure General § 1.14 Citation of Commission documents. The appropriate reference to the FCC Record shall be included as part of the citation to any document that has been printed...

Measurement and correlation of excess molar volumes for mixtures of 1-propanol and aromatic hydrocarbons

Energy Technology Data Exchange (ETDEWEB)

Gahlyan, Suman; Rani, Manju; Maken, Sanjeev Kumar [Deenbandhu Chhotu Ram University of Science and Technology, Murthal (India); Lee, Inkyu; Moon, Il [Yonsei University, Seoul (Korea, Republic of)

2015-01-15

Excess molar volumes (V{sub m}{sup E} ) have been measured at 303.15 K for 1-propanol+benzene or toluene or o- or m- or p-xylene mixtures using V-shape dilatometer. The V{sub m}{sup E} values, for an equimolar composition, vary in the order: benzene>toluene-m-xylene>o-xylene>p-xylene. The V{sub m}{sup E} data have been used to calculate partial molar volumes, excess partial molar volumes, and apparent molar volumes of 1-propanol and aromatic hydrocarbons over the entire range of composition. The excess volume data have also been interpreted in terms of graph-theoretical approach and Prigogine-Flory-Patterson theory (PFP). While PFP theory fails to predict the V{sub m}{sup E} values for systems with s-shaped V{sub m}{sup E} versus x{sub 1} graph, the V{sub m}{sup E} values calculated by graph theory compare reasonably well with the corresponding experimental values. This graph theory analysis has further yielded information about the state of aggregation of pure components as well as of the mixtures.

Superconducting Super Collider: Final environmental impact statement: Volume 2, Comment/response document: Summary and index

International Nuclear Information System (INIS)

1988-12-01

This volume is divided into five parts as follows: Summary and Index; Letters submitted by commenters in response to the Draft Environmental Impact Statement (DEIS) from date of issue through October 17, 1988; Transcripts of testimony at the public hearings conducted by the DOE in the vicinity of each site alternative; Letters postmarked after October 17, 1988; and Comment responses to both the letters and the testimony. This summary and index is published as a guide to the reader in reviewing this document. The summary is of the approximately 7000 comments received by the DOE from a total of about 5700 commenters. It was prepared as a general reference and guide to the readers of this volume. The Index follows the summary. The first index is an alphabetical listing of commenters (of both letters and transcripts) and indicates the number each commenter was assigned. The commenter numbers guide the reader to DOE comment responses in Volume 2B which are in numerical order

User's guide for PRISIM (Plant Risk Status Information Management System) Arkansas Nuclear One--Unit 1: Volume 2, Program for regulators

Energy Technology Data Exchange (ETDEWEB)

Campbell, D.J.; Guthrie, V.H.; Kirchner, J.R.; Kirkman, J.Q.; Paula, H.M.; Ellison, B.C.; Dycus, F.M.; Farquharson, J.A.; Flanagan, G.F.

1988-03-01

This user's guide is a two-volume document designed to teach NRC inspectors and NRC regulators how to access probabilistic risk assessment information from the two Plant Risk Status Information Management System (PRISIM) programs developed for Arkansas Nuclear One--Unit One (ANA-1). This document, Volume 2, describes how the PRA information available in Version 2.0 of PRISIM is useful as an evaluation tool for regulatory activities. Using PRISIM is useful as an evaluation tool for regulatory activities. Using PRISIM, regulators can both access PRA information and modify the information to assess the impact these changes may have on plant safety. Each volume is a stand-alone document.

Applications for electronic documents

International Nuclear Information System (INIS)

Beitel, G.A.

1995-01-01

This paper discusses the application of electronic media to documents, specifically Safety Analysis Reports (SARs), prepared for Environmental Restoration and Waste Management (ER ampersand WM) programs being conducted for the Department of Energy (DOE) at the Idaho National Engineering Laboratory (INEL). Efforts are underway to upgrade our document system using electronic format. To satisfy external requirements (DOE, State, and Federal), ER ampersand WM programs generate a complement of internal requirements documents including a SAR and Technical Safety Requirements along with procedures and training materials. Of interest, is the volume of information and the difficulty in handling it. A recently prepared ER ampersand WM SAR consists of 1,000 pages of text and graphics; supporting references add 10,000 pages. Other programmatic requirements documents consist of an estimated 5,000 pages plus references

Vapor-Liquid Equilibrium in the Mixture 1,1-Difluoroethane C2H4F2 + C4H8 2-Methylpropene (EVLM1131, LB5730_E)

Science.gov (United States)

Cibulka, I.; Fontaine, J.-C.; Sosnkowska-Kehiaian, K.; Kehiaian, H. V.

This document is part of Subvolume A 'Binary Liquid Systems of Nonelectrolytes I' of Volume 26 'Heats of Mixing, Vapor-Liquid Equilibrium, and Volumetric Properties of Mixtures and Solutions' of Landolt-Börnstein Group IV 'Physical Chemistry'. It contains the Chapter 'Vapor-Liquid Equilibrium in the Mixture 1,1-Difluoroethane C2H4F2 + C4H8 2-Methylpropene (EVLM1131, LB5730_E)' providing data from direct measurement of pressure and mole fraction in vapor phase at variable mole fraction in liquid phase and constant temperature.

Oak Ridge K-25 Site Technology Logic Diagram. Volume 1, Technology evaluation

Energy Technology Data Exchange (ETDEWEB)

Fellows, R.L. [ed.

1993-02-26

The Oak Ridge K-25 Technology Logic Diagram (TLD), a decision support tool for the K-25 Site, was developed to provide a planning document that relates environmental restoration and waste management problems at the Oak Ridge K-25 Site to potential technologies that can remediate these problems. The TLD technique identifies the research necessary to develop these technologies to a state that allows for technology transfer and application to waste management, remedial action, and decontamination and decommissioning activities. The TLD consists of four separate volumes-Vol. 1, Vol. 2, Vol. 3A, and Vol. 3B. This Volume, Volume 1 provides introductory and overview information about the TLD. Volume 2 contains logic diagrams. Volume 3 has been divided into two separate volumes to facilitate handling and use. This volume is divided into ten chapters. The first chapter is a brief introduction, and the second chapter details the technical approach of the TLD. These categories are the work activities necessary for successful decontamination and decommissioning, waste management, and remedial action of the K-25 Site. The categories are characterization, decontamination, dismantlement, robotics and automation, remedial action, and waste management. Materials disposition is addressed in Chap. 9. The final chapter contains regulatory compliance information concerning waste management, remedial action, and decontamination and decommissioning.

Efeitos da ELTGOL e do Flutter® nos volumes pulmonares dinâmicos e estáticos e na remoção de secreção de pacientes com bronquiectasia Effects of ELTGOL and Flutter VRP1® on the dynamic and static pulmonary volumes and on the secretion clearance of patients with bronchiectasis

Directory of Open Access Journals (Sweden)

Fernando S. Guimarães

2012-04-01

Full Text Available Contextualização: Embora a fisioterapia respiratória seja considerada fundamental para o tratamento de pacientes hipersecretivos, há poucas evidências acerca de seus efeitos fisiológicos e terapêuticos em indivíduos com bronquiectasia. Objetivos: Avaliar os efeitos fisiológicos imediatos da ELTGOL e do Flutter® nos volumes pulmonares dinâmicos e estáticos em pacientes com bronquiectasia e, secundariamente, determinar o efeito dessas técnicas na remoção de secreção brônquica. Métodos: Participaram do estudo pacientes com diagnóstico clínico e radiológico de bronquiectasia. Os pacientes foram submetidos a três intervenções de forma randomizada e com um intervalo (washout de uma semana entre elas. Inicialmente os pacientes inalaram dois jatos de 100µcg de salbutamol. Após 5 minutos de tosse iniciais e após 5 minutos de tosse que sucederam o protocolo controle e as intervenções (ELTGOL e Flutter®, os pacientes realizaram as avaliações dos volumes pulmonares dinâmicos e estáticos por meio da espirometria e pletismografia corporal. A secreção expectorada foi coletada durante as intervenções e durante a segunda série de tosse, sendo quantificada por meio de seu peso seco. Resultados: Foram avaliados dez pacientes, dois do sexo masculino e oito do sexo feminino (média de idade de 55,9±18,1 anos. Após a utilização do Flutter® e da ELTGOL, observou-se diminuição significativa do volume residual (VR, da capacidade residual funcional (CRF e da CPT (pBackground: Although respiratory physical therapy is considered fundamental in the treatment of hypersecretive patients, there is little evidence of its physiological and therapeutic effects in bronchiectasis patients. Objective: To evaluate the acute physiological effects of ELTGOL and Flutter VRP1® in dynamic and static lung volumes in patients with bronchiectasis and, secondarily, to study the effect of these techniques in sputum elimination. Methods: Patients

EUDISED: European Documentation and Information System for Education. Volume II, National Reports.

Science.gov (United States)

Council of Europe, Strasbourg (France). Documentation Center for Education in Europe.

This study briefly describes the documentation and information projects of seven nations, stressing their use in the field of education. The sections are: (1) automated documentation and the human sciences in France, (2) documentation for education and the social sciences in the Federal Republic of Germany, (3) mechanized projects in library work…

A general multiblock Euler code for propulsion integration. Volume 1: Theory document

Science.gov (United States)

Chen, H. C.; Su, T. Y.; Kao, T. J.

1991-01-01

A general multiblock Euler solver was developed for the analysis of flow fields over geometrically complex configurations either in free air or in a wind tunnel. In this approach, the external space around a complex configuration was divided into a number of topologically simple blocks, so that surface-fitted grids and an efficient flow solution algorithm could be easily applied in each block. The computational grid in each block is generated using a combination of algebraic and elliptic methods. A grid generation/flow solver interface program was developed to facilitate the establishment of block-to-block relations and the boundary conditions for each block. The flow solver utilizes a finite volume formulation and an explicit time stepping scheme to solve the Euler equations. A multiblock version of the multigrid method was developed to accelerate the convergence of the calculations. The generality of the method was demonstrated through the analysis of two complex configurations at various flow conditions. Results were compared to available test data. Two accompanying volumes, user manuals for the preparation of multi-block grids (vol. 2) and for the Euler flow solver (vol. 3), provide information on input data format and program execution.

Varicocele e volume testicular em adolescentes e adultos jovens portadores de esquistossomose hepatoesplênica cirúrgica

Directory of Open Access Journals (Sweden)

Brandt Frederico Teixeira

2003-01-01

Full Text Available OBJETIVO: Avaliar o volume testicular e a prevalência de varicocele em adolescentes e adultos jovens portadores de esquistossomose na forma hepatoesplênica associada a varizes sangrentas de esôfago. MÉTODOS: O estudo envolveu 22 adolescentes masculinos com esquistossomose na forma descrita, submetidos à esplenectomia, ligadura da veia gástrica esquerda e auto-implante de tecido esplênico no grande omento quando crianças. O tempo médio de seguimento foi de 4 anos após a intervenção. O grupo de voluntários sadios foi de adolescentes de uma escola na mesma região onde os casos operados viviam. Eles foram selecionados de forma randomizada, considerando a faixa de idade, características epidemiológicas e não serem infestados por equistossomose. Todos os participantes possuíam história clínica completa e foram submetidos a exame físico e ultra-sonográfico. Foi dado atenção especial as características sexuais, ultra-sonografia testicular e dopplerfluxometria das veias espermáticas. RESULTADOS: Dos pacientes classificados como adultos pela idade cronológica, 53,8% tinham genitais com características infantis. A incidência de varicocele foi igual a 61,5% no grupo afetado e 40% no grupo controle, sem diferença estatística entre os grupos (x 2 =1,77; g.1.=1; p=0,18 3 p Fisher=0,16, acometendo predominantemente o testículo esquerdo, em ambos os grupos. CONCLUSÃO: Pacientes com doença esquistossomótica cirúrgica tinham significante déficit no desenvolvimento puberal e genital, no volume testicular, especialmente do lado esquerdo, e alta prevalência de varicocele (61.5% sem uma associação direta com atrofia testicular.

Title list of documents made publicly available: September 1--30, 1996. Volume 18, Number 9

International Nuclear Information System (INIS)

1996-11-01

The report describes the information received and published by the US Nuclear Regulatory Commission (NRC). This information includes (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials and (2) non-docketed material received and published by NRC pertinent to its role as a regulatory agency. As used here, docketed does not refer to Court dockets; it refers to the system by which NRC maintains its regulatory records. This series of documents is indexed by a Personal Author Index, a Corporate Source Index, and a Report Number Index

Title list of documents made publicly available: April 1--30, 1996. Volume 18, Number 4

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-06-01

This publication describes the information received and published by the US Nuclear Regulatory Commission (NRC). This information includes (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials and (2) non-docketed material received and published by NRC pertinent to its role as a regulatory agency. As used here, docketed does not refer to Court dockets; it refers to the system by which NRC maintains its regulatory records. This series of documents is indexed by a Personal Author Index, a Corporate Source Index, and a Report Number Index.

Title list of documents made publicly available: April 1--30, 1996. Volume 18, Number 4

International Nuclear Information System (INIS)

1996-06-01

This publication describes the information received and published by the US Nuclear Regulatory Commission (NRC). This information includes (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials and (2) non-docketed material received and published by NRC pertinent to its role as a regulatory agency. As used here, docketed does not refer to Court dockets; it refers to the system by which NRC maintains its regulatory records. This series of documents is indexed by a Personal Author Index, a Corporate Source Index, and a Report Number Index

Title list of documents made publicly available: June 1--30, 1995. Volume 17, Number 6

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-08-01

This monthly publication contains descriptions of the information received and generated by the US Nuclear Regulatory Commission (NRC). This information includes (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials and (2) nondocketed material received and generated by NRC pertinent to its role as a regulatory agency. As used here, docketed does not refer to Court dockets; it refers to the system by which NRC maintains its regulatory records. This series of documents is indexed by a Personal Author Index, a Corporate Source Index, and a Report Number Index.

Title list of documents made publicly available: June 1--30, 1995. Volume 17, Number 6

International Nuclear Information System (INIS)

1995-08-01

This monthly publication contains descriptions of the information received and generated by the US Nuclear Regulatory Commission (NRC). This information includes (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials and (2) nondocketed material received and generated by NRC pertinent to its role as a regulatory agency. As used here, docketed does not refer to Court dockets; it refers to the system by which NRC maintains its regulatory records. This series of documents is indexed by a Personal Author Index, a Corporate Source Index, and a Report Number Index

Title list of documents made publicly available: September 1--30, 1996. Volume 18, Number 9

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-11-01

The report describes the information received and published by the US Nuclear Regulatory Commission (NRC). This information includes (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials and (2) non-docketed material received and published by NRC pertinent to its role as a regulatory agency. As used here, docketed does not refer to Court dockets; it refers to the system by which NRC maintains its regulatory records. This series of documents is indexed by a Personal Author Index, a Corporate Source Index, and a Report Number Index.

Site Environmental Report for 2002, Volume 1

Energy Technology Data Exchange (ETDEWEB)

Pauer, Ron

2003-07-01

Each year, Ernest Orlando Lawrence Berkeley National Laboratory prepares an integrated report on its environmental programs to satisfy the requirements of United States Department of Energy Order 231.1. The ''Site Environmental Report for 2002'' summarizes Berkeley Lab's compliance with environmental standards and requirements, characterizes environmental management efforts through surveillance and monitoring activities, and highlights significant programs and efforts for calendar year 2002. Throughout this report, Ernest Orlando Lawrence Berkeley National Laboratory is referred to as ''Berkeley Lab,'' ''the Laboratory,'' ''Lawrence Berkeley National Laboratory,'' and ''LBNL.'' The report is separated into two volumes. Volume I contains a general overview of the Laboratory, the status of environmental programs, and summarized results from surveillance and monitoring activities. Volume II contains individual data results from the monitoring programs. This year, the ''Site Environmental Report'' was distributed on a CD in PDF format that includes Volume I, Volume II, and related documents. The report is also available on the Web at http://www.lbl.gov/ehs/esg/. The report follows the Laboratory's policy of using the International System of Units (SI), also known as the metric system of measurements. Whenever possible, results are additionally reported using the more conventional (non-SI) system of measurements because this system is referenced by some current regulatory standards and is more familiar to some readers. The tables included at the end of the Glossary are intended to help readers understand the various prefixes used with SI units of measurement and convert these units from one system to the other.

Safeguarding critical e-documents implementing a program for securing confidential information assets

CERN Document Server

Smallwood, Robert F

2012-01-01

Practical, step-by-step guidance for corporations, universities and government agencies to protect and secure confidential documents and business records Managers and public officials are looking for technology and information governance solutions to "information leakage" in an understandable, concise format. Safeguarding Critical E-Documents provides a road map for corporations, governments, financial services firms, hospitals, law firms, universities and other organizations to safeguard their internal electronic documents and private communications.Provides practical, step-by-step guidance o

Elmo Bumpy Torus proof of principle, Phase II: Title 1 report. Volume VII. Cryogenic system

International Nuclear Information System (INIS)

Poteat, T.J.

1982-01-01

This document, Volume VII EBT-P Cryogenic System Title I Design Report, describes the system that resulted from the Title I Preliminary Design effort. It is a self-contained document that can be read apart from the other Volumes comprising the EBT-P Title I Report. This document is a contract deliverable item and provides the detail necessary to support the Cryogenic System design contained in the EBT-P Baseline Design Data Book

Viability Assessment Volume 2

International Nuclear Information System (INIS)

1998-01-01

This volume describes the major design features of the Monitored Geologic Repository. This document is not intended to provide an exhaustive, detailed description of the repository design. Rather, this document summarizes the major systems and primary elements of the design that are radiologically significant, and references the specific technical documents and design analyses wherein the details can be found. Not all portions of the design are at the same level of completeness. Highest priority has been given to assigning resources to advance the design of the Monitored Geologic Repository features that are important to radiological safety and/or waste isolation and for which there is no NRC licensing precedent. Those features that are important to radiological safety and/or waste isolation, but for which there is an NRC precedent, receive second priority. Systems and features that have no impact on radiological safety or waste isolation receive the lowest priority. This prioritization process, referred to as binning, is discussed in more detail in Section 2.3. Not every subject discussed in this volume is given equal treatment with regard to the level of detail provided. For example, less detail is provided for the surface facility design than for the subsurface and waste package designs. This different level of detail is intentional. Greater detail is provided for those functions, structures, systems, and components that play key roles with regard to protecting radiological health and safety and that are not common to existing nuclear facilities already licensed by NRC. A number of radiological subjects are not addressed in the VA, (e.g., environmental qualification of equipment). Environmental qualification of equipment and other radiological safety considerations will be addressed in the LA. Non-radiological safety considerations such as silica dust control and other occupational safety considerations are considered equally important but are not addressed in

Gaia DR1 documentation

Science.gov (United States)

van Leeuwen, F.; de Bruijne, J. H. J.; Arenou, F.; Comoretto, G.; Eyer, L.; Farras Casas, M.; Hambly, N.; Hobbs, D.; Salgado, J.; Utrilla Molina, E.; Vogt, S.; van Leeuwen, M.; Abreu, A.; Altmann, M.; Andrei, A.; Babusiaux, C.; Bastian, U.; Biermann, M.; Blanco-Cuaresma, S.; Bombrun, A.; Borrachero, R.; Brown, A. G. A.; Busonero, D.; Busso, G.; Butkevich, A.; Cantat-Gaudin, T.; Carrasco, J. M.; Castañeda, J.; Charnas, J.; Cheek, N.; Clementini, G.; Crowley, C.; Cuypers, J.; Davidson, M.; De Angeli, F.; De Ridder, J.; Evans, D.; Fabricius, C.; Findeisen, K.; Fleitas, J. M.; Gracia, G.; Guerra, R.; Guy, L.; Helmi, A.; Hernandez, J.; Holl, B.; Hutton, A.; Klioner, S.; Lammers, U.; Lecoeur-Taïbi, I.; Lindegren, L.; Luri, X.; Marinoni, S.; Marrese, P.; Messineo, R.; Michalik, D.; Mignard, F.; Montegriffo, P.; Mora, A.; Mowlavi, N.; Nienartowicz, K.; Pancino, E.; Panem, C.; Portell, J.; Rimoldini, L.; Riva, A.; Robin, A.; Siddiqui, H.; Smart, R.; Sordo, R.; Soria, S.; Turon, C.; Vallenari, A.; Voss, H.

2017-12-01

94000 Hipparcos stars in the primary data set, the proper motion standard errors are much smaller, at about 0.06 mas yr^-1. For the secondary astrometric data set, the typical standard error on the positions is 10 mas. The median standard errors on the mean G-band magnitudes range from the milli-magnitude level to 0.03 mag over the magnitude range 5 to 20.7. The DPAC undertook an extensive validation of Gaia DR1 which confirmed that this data release represents a major advance in the mapping of the skies and the availability of basic stellar data that form the foundation of observational astrophysics. However, as a consequence of the very preliminary nature of this first Gaia data release, there are a number of important limitations to the data quality. These limitations are documented in the Astronomy & Astrophysics papers that accompany Gaia DR1, with further information provided in this documentation. The reader is strongly encouraged to read about these limitations and to carefully consider them before drawing conclusions from the data. This Gaia DR1 documentation complements the peer-reviewed papers that accompany the release in a Special Issue of Astronomy & Astrophysics. The papers form the primary documentation for the data release and they are frequently referenced throughout the text.

The environmental impact statement for the Nevada Test Site and off-site locations in the State of Nevada. Volume 1, Appendices A-F

International Nuclear Information System (INIS)

1996-01-01

This volume contains appendices to the named document. The Appendices are entitled (A) Description of Projects and Activities, (2) Federal Register Notice, (C) Relevant Regulatory Requirements, (D) Distribution Lists, (E) Impact Assessment Methods, and (F) Project-Specific Environmental Analysis

Viability Assessment Volume 1

International Nuclear Information System (INIS)

1998-01-01

Since May 1996, under its draft Civilian Radioactive Waste Management Program Plan (DOE 1996), DOE has been carrying out a 5-year program of work to support the decision in 2001 by the Secretary of Energy on whether or not to recommend the site to the President. Part of this program was to address major unresolved technical issues and to complete an assessment of the viability of the Yucca Mountain site by 1998. Affirming the DOE plans, Congress directed DOE in the 1997 Energy and Water Development Appropriations Act to provide a viability assessment of the Yucca Mountain site to Congress and the President. This Viability Assessment (VA) document is the DOE report to Congress and the President. They are expected to use the VA to make an informed decision about program direction and funding. Drawing on 15 years of scientific investigation and design work at Yucca Mountain, the VA summarizes a large technical basis of field investigations, laboratory tests, models, analyses, and engineering, described in cited references. The VA identifies the major uncertainties relevant to the technical defensibility of DOE analyses and designs, the DOE approach to managing these uncertainties, and the status of work toward the site recommendation and LA. The VA also identifies DOE plans for the remaining work, and the estimated costs of completing an LA and constructing and operating a repository. The attention to uncertainties is important because DOE must evaluate how the repository will perform during the next 10,000 years or longer. Uncertainties exist because of variability in the natural (geologic and hydrologic) systems at Yucca Mountain and because of imperfect scientific understanding of the natural processes that might affect the repository system. This is Volume 1 and it covers, Introduction and Site Characteristics, includes a high-level summary of the results of the VA and some additional background information. (The overview is bound separately.) Section 1 of Volume

Prototype development and demonstration for response, emergency staging, communications, uniform management, and evacuation (R.E.S.C.U.M.E.) : R.E.S.C.U.M.E. prototype system design document.

Science.gov (United States)

2014-04-01

This report documents the System Design Document (SDD) for the prototype development and demonstration of the : Response, Emergency Staging, Communications, Uniform Management, and Evacuation (R.E.S.C.U.M.E.) application : bundle, with a focus on the...

Title list of documents made publicly available, September 1--30, 1994. Volume 16, No. 9

International Nuclear Information System (INIS)

1994-11-01

This document is a monthly publication containing descriptions of information received and generated by the US Nuclear Regulatory Commission (NRC). This information includes docketed material associated with civilian nuclear power plants and other uses of radioactive materials, and nondocketed material received and generated by NRC pertinent to its role as a regulatory agency. The following indexes are included: Personal Author, Corporate Source, Report Number, and Cross Reference of Enclosures to Principal Documents

Title list of documents made publicly available, November 1--30, 1994. Volume 16, No. 11

International Nuclear Information System (INIS)

1995-01-01

This document is a monthly publication containing descriptions of information received and generated by the US Nuclear Regulatory Commission (NRC). This information includes docketed material associated with civilian nuclear power plants and other uses of radioactive materials, and nondocketed material received and generated by NRC pertinent to its role as a regulatory agency. The following indexes are included: Personal Author, Corporate Source, Report Number, and Cross Reference of Enclosures to Principal Documents

Title list of documents made publicly available, September 1--30, 1994. Volume 16, No. 9

Energy Technology Data Exchange (ETDEWEB)

1994-11-01

This document is a monthly publication containing descriptions of information received and generated by the US Nuclear Regulatory Commission (NRC). This information includes docketed material associated with civilian nuclear power plants and other uses of radioactive materials, and nondocketed material received and generated by NRC pertinent to its role as a regulatory agency. The following indexes are included: Personal Author, Corporate Source, Report Number, and Cross Reference of Enclosures to Principal Documents.

Title list of documents made publicly available, November 1--30, 1994. Volume 16, No. 11

Energy Technology Data Exchange (ETDEWEB)

1995-01-01

This document is a monthly publication containing descriptions of information received and generated by the US Nuclear Regulatory Commission (NRC). This information includes docketed material associated with civilian nuclear power plants and other uses of radioactive materials, and nondocketed material received and generated by NRC pertinent to its role as a regulatory agency. The following indexes are included: Personal Author, Corporate Source, Report Number, and Cross Reference of Enclosures to Principal Documents.

Title list of documents made publicly available, July 1--31, 1994. Volume 16, No. 7

International Nuclear Information System (INIS)

1994-11-01

This document is a monthly publication containing descriptions of information received and generated by the US Nuclear Regulatory Commission (NRC). This information includes docketed material associated with civilian nuclear power plants and other uses of radioactive materials, and nondocketed material received and generated by NRC pertinent to its role as a regulatory agency. The following indexes are included: Personal Author, Corporate Source, Report Number, and Cross Reference of Enclosures to Principal Documents

Title list of documents made publicly available, August 1--31, 1993. Volume 15, No. 8

Energy Technology Data Exchange (ETDEWEB)

1993-10-01

This document is a monthly publication containing descriptions of information received and generated by the US Nuclear Regulatory commission (NRC). This information includes docketed material associated with civilian nuclear power plants and other uses of radioactive materials, and nondocketed material received and generated by NRC pertinent to its role as a regulatory agency. The following indexes are included: Personal Author corporate Source, Report Number, and Cross Reference of Enclosures to Principal Documents.

Title list of documents made publicly available, August 1--31, 1994. Volume 16, No. 8

International Nuclear Information System (INIS)

1994-11-01

This document is a monthly publication containing descriptions of information received and generated by the US Nuclear Regulatory Commission (NRC). This information includes docketed material associated with civilian nuclear power plants and other uses of radioactive materials and nondocketed material received and generated by NRC pertinent to its role as a regulatory agency. The following indexes are included: Personal Author, Corporate Source, Report Number, and Cross Reference of Enclosures to Principal Documents

Graphics Standards in the Computer-aided Acquisition and Logistic Support (CALS) Program, Fiscal Year 1989. Volume 1. Test Requirements Document and Extended CGM (CGEM)

Science.gov (United States)

1990-07-01

at the firet meng in Munich, it was foyud isthere exis•s some avedap between the stated goals of• • DG Standards and t•e CGt e SG con ded t in cumin ... stressing importance of liaison and harmonization with closely related groups; Japan - making suggestions that the NWI and Requirements Document be improved

Volume Morto: performance e corporeidade

Directory of Open Access Journals (Sweden)

Eloísa Brantes Mendes

Full Text Available Resumo O processo de pesquisa e criação do espetáculo Volume Morto é o campo de partida deste relato sobre performance, memória corporal e relações estético-políticas implicadas na trajetória artística do Coletivo Líquida Ação desde 2007. A presença da água como elemento vital, utilizada nas performances de intervenção urbana, faz parte da proposta artística deste coletivo que problematiza as fronteiras entre visibilidades e invisibilidades da cidade habitada. A água, ligada às múltiplas temporalidades da experiência corpo-espaço na ação performática, também vai ao encontro das práticas de convívio e produção artística, voltadas para a sustentabilidade do próprio coletivo como espaço de pesquisa independente.

Assistência de ar e volumes de aplicação na deposição de calda e no controle do arroz vermelho (Oryza sativa L. Air assistance and volume of application in spray deposition and in red rice control (Oryza sativa L.

Directory of Open Access Journals (Sweden)

Leopoldo L. S. Vigano

2007-12-01

Full Text Available O trabalho teve como objetivo avaliar o efeito da assistência de ar junto à barra pulverizadora e de três volumes de pulverização na dessecação e deposição da calda em arroz vermelho, sob cultivo de nabo forrageiro, em áreas de recuperação de várzeas, utilizando o herbicida paraquat e o corante Azul Brilhante, respectivamente. Os volumes de pulverização foram 100; 200 e 300 L ha-1 da solução aquosa, contendo corante alimentício (1.500 mg L-1. Com ou sem a assistência de ar junto à barra, foram utilizadas pontas de pulverização de jato plano tipo AXI 110015 à pressão de 117,3 kPa, AXI 11002 e AXI 11003 a 276 kPa. A avaliação da deposição da pulverização deu-se em folhas de plantas de arroz vermelho. Os maiores volumes (200 e 300 L ha-1 pulverizados com a assistência de ar junto à barra pulverizadora proporcionaram maiores depósitos do corante em relação ao volume de 100 L ha-1. Não foram constatadas diferenças na deposição do corante para os volumes pulverizados, sem a assistência de ar junto à barra, tampouco entre os volumes de 200 e 300 L ha-1 com a assistência de ar junto à barra. As maiores percentagens de controle do arroz vermelho foram obtidas com a assistência de ar junto à barra, independentemente do volume pulverizado, equivalendo-se ao controle obtido com 300 L ha-1, sem o uso dessa tecnologia.The aim of this research was to evaluate the effect of air-assistance on spraying at three volumes in spray deposition and control of red rice under fodder radish cultivation. To evaluate the control of this weed and spray deposition were used paraquat herbicide and a Brilliant Blue dye, respectively. The three spraying volumes were 100, 200 and 300 L ha-1, using a tracer dye at 1,500 mg L-1. Both solutions and volumes were sprayed with flat fan nozzles AXI 110015 at 117.3 kPa, AXI 11002 and AXI 11003 at 276 kPa, respectively, with and without air-assistance on the boom. The evaluation of deposition

Draft no-migration variance petition. Volume 1

International Nuclear Information System (INIS)

1995-01-01

The Department of Energy is responsible for the disposition of transuranic (TRU) waste generated by national defense-related activities. Approximately 2,6 million cubic feet of these waste have been generated and are stored at various facilities across the country. The Waste Isolation Pilot Plant (WIPP), was sited and constructed to meet stringent disposal requirements. In order to permanently dispose of TRU waste, the DOE has elected to petition the US EPA for a variance from the Land Disposal Restrictions of RCRA. This document fulfills the reporting requirements for the petition. This report is Volume 1 which discusses the regulatory frame work, site characterization, facility description, waste description, environmental impact analysis, monitoring, quality assurance, long-term compliance analysis, and regulatory compliance assessment

Environmental Sensitivity Index (ESI) Atlas: East Florida, maps in portable document format, Volume 1, Volume 2 (NODC Accession 0004150)

Data.gov (United States)

National Oceanic and Atmospheric Administration, Department of Commerce — This data set comprises the Environmental Sensitivity Index (ESI) maps in Portable Document Format (.PDF) for the shoreline of East Florida (to encompass the coastal...

Standard Technical Specifications General Electric plants, BWR/4:Bases (Sections 3.4-3.10). Volume 3, Revision 1

International Nuclear Information System (INIS)

1995-04-01

This report documents the results of the combined effort of the NRC and the industry to produce improved Standard Technical Specifications (STS), Revision 1 for General Electric BWR/4 Plants. The changes reflected in Revision 1 resulted from the experience gained from license amendment applications to convert to these improved STS or to adopt partial improvements to existing technical specifications. This NUREG is the result of extensive public technical meetings and discussions between the Nuclear Regulatory Commission (NRC) staff and various nuclear power plant licensees, Nuclear Steam Supply System (NSSS) Owners Groups, NSSS vendors, and the Nuclear Energy Institute (NEI). The improved STS were developed based on the criteria in the Final Commission Policy Statement on Technical Specifications Improvements for Nuclear Power Reactors, dated July 22, 1993. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. Volume 1 contains the specifications for all chapters and sections of the improved STS. Volume 2 contains he Bases for Chapters 2.0 and 3.0, and Sections 3.1-3.3 of the improved STS. This document, Volume 3, contains the Bases for Sections 3.4-3.10 of the improved STS

Brookhaven National Laboratory 2008 Site Environment Report Volume 1

Energy Technology Data Exchange (ETDEWEB)

Brookhaven National Laboratory

2009-10-01

Brookhaven National Laboratory (BNL) prepares an annual Site Environmental Report (SER) in accordance with DOE Order 231.1A, Environment, Safety and Health Reporting of the U.S. Department of Energy. The report is written to inform the public, regulators, employees, and other stakeholders of the Laboratory's environmental performance during the calendar year in review. Volume I of the SER summarizes environmental data; environmental management performance; compliance with applicable DOE, federal, state, and local regulations; and performance in restoration and surveillance monitoring programs. BNL has prepared annual SERs since 1971 and has documented nearly all of its environmental history since the Laboratory's inception in 1947. Volume II of the SER, the Groundwater Status Report, also is prepared annually to report on the status of and evaluate the performance of groundwater treatment systems at the Laboratory. Volume II includes detailed technical summaries of groundwater data and its interpretation, and is intended for internal BNL users, regulators, and other technically oriented stakeholders. A brief summary of the information contained in Volume II is included in this volume in Chapter 7, Groundwater Protection. Both reports are available in print and as downloadable files on the BNL web page at http://www.bnl.gov/ewms/ser/. An electronic version on compact disc is distributed with each printed report. In addition, a summary of Volume I is prepared each year to provide a general overview of the report, and is distributed with a compact disc containing the full report.

Sequence Coding and Search System for licensee event reports: user's guide. Volume 1, Revision 1

International Nuclear Information System (INIS)

Greene, N.M.; Mays, G.T.; Johnson, M.P.

1985-04-01

Operating experience data from nuclear power plants are essential for safety and reliability analyses, especially analyses of trends and patterns. The licensee event reports (LERs) that are submitted to the Nuclear Regulatory Commission (NRC) by the nuclear power plant utilities contain much of this data. The NRC's Office for Analysis and Evaluation of Operational Data (AEOD) has developed, under contract with NSIC, a system for codifying the events reported in the LERs. The primary objective of the Sequence Coding and Search System (SCSS) is to reduce the descriptive text of the LERs to coded sequences that are both computer-readable and computer-searchable. This system provides a structured format for detailed coding of component, system, and unit effects as well as personnel errors. The database contains all current LERs submitted by nuclear power plant utilities for events occurring since 1981 and is updated on a continual basis. This four volume report documents and describes SCSS in detail. Volume 1 is a User's Guide for searching the SCSS database. This volume contains updated material through February 1985 of the working version of ORNL/NSIC-223, Vol. 1

Macrochain configuration, stucture of free volume and transport properties of poly(1-trimethylsilyl-1-propyne) and poly(1-trimethylgermyl-1-propyne)

KAUST Repository

Matson, Samira M.

2012-08-01

The relationship between poly(1-trimethylsilyl-1-propyne) (PTMSP) and poly(1-trimethylger- myl-1-propyne) (PTMGP) microstructure, gas permeability and structure of free volume is reported. n-Butane/methane mixed-gas permeation properties of PTMSP and PTMGP membranes with different cis-/trans-composition have been investigated. The n-butane/methane selectivities for mixed gas are by an order higher than the selectivities calculated from pure gas measurements (the mixed-gas n-butane/methane selectivities are 20-40 for PTMSP and 22-35 for PTMGP). Gas permeability and n-butane/methane selec- tivity essentially differ in polymers with different cis-/trans-composition. Positron annihilation lifetime spec- troscopy investigation of PTMSP and PTMGP with different microstructure has determined distinctions in total amount and structure of free volume, i.e. distribution of free volume elements. The correlation between total amount of free volume and gas transport parameters is established: PTMSP and PTMGP with bigger free volume exhibit higher n-butane permeability and mixed-gas n-butane/methane selectivity. Such behav- ior is discussed in relation to the submolecular structure of polymers with different microstructure and sorp- tion of n-butane in polymers with different free volume. © Pleiades Publishing, Ltd., 2012.

Weapons-grade plutonium dispositioning. Volume 1: Executive summary

International Nuclear Information System (INIS)

Parks, D.L.; Sauerbrun, T.J.

1993-06-01

The Secretary of Energy requested the National Academy of Sciences (NAS) Committee on International Security and Arms Control to evaluate dispositioning options for weapons-grade plutonium. The Idaho National Engineering Laboratory (INEL) assisted NAS in this evaluation by investigating the technical aspects of the dispositioning options and their capability for achieving plutonium annihilation levels greater than 90%. Additionally, the INEL investigated the feasibility of using plutonium fuels (without uranium) for disposal in existing light water reactors and provided a preconceptual analysis for a reactor specifically designed for destruction of weapons-grade plutonium. This four-volume report was prepared for NAS to document the findings of these studies. Volume 2 evaluates 12 plutonium dispositioning options. Volume 3 considers a concept for a low-temperature, low-pressure, low-power-density, low-coolant-flow-rate light water reactor that quickly destroys plutonium without using uranium or thorium. This reactor concept does not produce electricity and has no other mission than the destruction of plutonium. Volume 4 addresses neutronic performance, fabrication technology, and fuel performance and compatibility issues for zirconium-plutonium oxide fuels and aluminum-plutonium metallic fuels. This volumes gives summaries of Volumes 2--4

Delve: A Data Set Retrieval and Document Analysis System

KAUST Repository

Akujuobi, Uchenna Thankgod

2017-12-29

Academic search engines (e.g., Google scholar or Microsoft academic) provide a medium for retrieving various information on scholarly documents. However, most of these popular scholarly search engines overlook the area of data set retrieval, which should provide information on relevant data sets used for academic research. Due to the increasing volume of publications, it has become a challenging task to locate suitable data sets on a particular research area for benchmarking or evaluations. We propose Delve, a web-based system for data set retrieval and document analysis. This system is different from other scholarly search engines as it provides a medium for both data set retrieval and real time visual exploration and analysis of data sets and documents.

Mudas de pinheira em substrato com diferentes volumes tratado com esterco bovino e biofertilizante

Directory of Open Access Journals (Sweden)

Geffson Figueredo Dantas

2013-05-01

Full Text Available A pinheira é uma das mais importantes representantes das anonáceas, é cultivada na região do alto sertão paraibano sob regime de agricultura familiar sem adoção de práticas agronômicas. Nesse sentindo, um experimento foi desenvolvido, no período de agosto a dezembro de 2011, em ambiente telado na Universidade Estadual da Paraíba, Catolé do Rocha, Paraíba, para avaliar os efeitos de insumos orgânicos e volumes de substrato na formação de mudas de pinheira. O delineamento experimental foi inteiramente casualizado, em esquema fatorial 2x4x2, referente aos volumes de substrato de 1 e 2 L, quatro doses de esterco bovino aos níveis de 0; 25; 50 e 75% do volume, na presença e ausência de biofertilizante  bovino aplicado em volume correspondente a 10% do volume do substrato com três repetições. As variáveis avaliadas, aos 125 dias após a semeadura foram: altura de muda, diâmetro do colo, área foliar, matéria seca da parte aérea, matéria seca da raiz, matéria seca total e relação entre os valores da matéria seca das raízes e parte aérea das plantas. Pelos resultados obtidos, o esterco bovino com nível acima de 60% associado com o biofertilizante em substrato com 2L, resultou em maior crescimento e produção de matéria seca das mudas de pinheira.

Regular Topologies for Gigabit Wide-Area Networks. Volume 1

Science.gov (United States)

Shacham, Nachum; Denny, Barbara A.; Lee, Diane S.; Khan, Irfan H.; Lee, Danny Y. C.; McKenney, Paul

1994-01-01

In general terms, this project aimed at the analysis and design of techniques for very high-speed networking. The formal objectives of the project were to: (1) Identify switch and network technologies for wide-area networks that interconnect a large number of users and can provide individual data paths at gigabit/s rates; (2) Quantitatively evaluate and compare existing and proposed architectures and protocols, identify their strength and growth potentials, and ascertain the compatibility of competing technologies; and (3) Propose new approaches to existing architectures and protocols, and identify opportunities for research to overcome deficiencies and enhance performance. The project was organized into two parts: 1. The design, analysis, and specification of techniques and protocols for very-high-speed network environments. In this part, SRI has focused on several key high-speed networking areas, including Forward Error Control (FEC) for high-speed networks in which data distortion is the result of packet loss, and the distribution of broadband, real-time traffic in multiple user sessions. 2. Congestion Avoidance Testbed Experiment (CATE). This part of the project was done within the framework of the DARTnet experimental T1 national network. The aim of the work was to advance the state of the art in benchmarking DARTnet's performance and traffic control by developing support tools for network experimentation, by designing benchmarks that allow various algorithms to be meaningfully compared, and by investigating new queueing techniques that better satisfy the needs of best-effort and reserved-resource traffic. This document is the final technical report describing the results obtained by SRI under this project. The report consists of three volumes: Volume 1 contains a technical description of the network techniques developed by SRI in the areas of FEC and multicast of real-time traffic. Volume 2 describes the work performed under CATE. Volume 3 contains the source

Correlação do pH e volume salivares com sintomas laringofaríngeos

Directory of Open Access Journals (Sweden)

Costa Henrique Olival

2004-01-01

Full Text Available Apesar do grande entusiasmo despertado pelo avanço dos conceitos definidores do conjunto sintomático denominado refluxo laringofaríngeo (RLF, ainda é muito difícil, para o otorrinolaringologista, estabelecer com segurança se esta síndrome poderá ser considerada no futuro como uma doença semelhante ao refluxo gastroesofágico¹. A nosso ver, os sinais inflamatórios no segmento laringofaríngeo encontrados em alguns pacientes que apresentam phmetria com presença de pH abaixo de 4 na sonda proximal podem ser mimificados por outras situações que agridem a região, não sendo, portanto, patognomônicos de RLF. As condições de fluxo salivar, seu volume, clearence e alterações das condições eletrolíticas da saliva podem influenciar na capacidade de proteção da mucosa regional. OBJETIVO: Este estudo teve como principal objetivo observar a relação entre os sintomas laringofaríngeos de inflamação e o pH e volume salivares. FORMA DE ESTUDO: Observacional coorte com corte transversal. MATERIAL E MÉTODO: Foram estudados 59 sujeitos com idades variando de 24 a 76 anos, com média 50,5 anos, sendo 44 mulheres e 15 homens. Todos os pacientes responderam a questionário sobre sintomas laringofaríngeos e tiveram sua saliva coletada e seu volume e pH mensurados. RESULTADOS: O volume médio de saliva coletado no total de pacientes foi 4,3 ml, com o mínimo de 1,5 e um máximo de 7,5. O pH médio foi de 7,1, se estendendo de 6 a 8. Do total de sintomas apresentados, 31 pacientes apresentaram disfonia, 39 apresentaram pigarro, 2 dispnéia, 24 halitose, 4 caseo, 4 amigdalite de repetição, 6 problemas dento-gengivais, 9 aftas, 6 xerostomia, 12 glossodínia, 36 globus pharingeus, 2 odinofagia, 16 tosse e 8 disfagia. As diversas correlações entre pH, volume salivar e sintomas foram observadas mostrando, em alguns casos, forte correlação positiva ou negativa. CONCLUSÃO: O pH salivar, na dependência do volume salivar, pode ter forte

ANDRA - Referential Materials. Volume 1: Context and scope; Volume 2: Argillaceous materials; Volume 3: Cementitious materials; Volume 4: The corrosion of metallic materials

International Nuclear Information System (INIS)

2001-01-01

This huge document gathers four volumes. The first volume presents some generalities about materials used in the storage of radioactive materials (definition, design principle, current choices and corresponding storage components, general properties of materials and functions of the corresponding storage components, physical and chemical solicitations experienced by materials in a storage), and the structure and content of the other documents. The second volume addresses argillaceous materials. It presents some generalities about these materials in the context of a deep geological storage, and about their design. It presents and comments the crystalline and chemical, and physical and chemical characteristics of swelling argillaceous materials and minerals, describes how these swelling argillaceous materials are shaped and set up, presents and comments physical properties (hydraulic, mechanical and thermal properties) of these materials, comments and discusses the modelling of the geo-chemical behaviour, and their behaviour in terms of containment and transport of radionuclides. The third volume addresses cementitious materials. It presents some generalities about these materials in the context of a deep geological storage, and about their definition and specifications. It presents some more detailed generalities (cement definition and composition, hydration, microstructure of hydrated cements, adjuvants), presents and comments their physical properties (fresh concrete structure and influence of composition, main aimed properties in the hardened status, transfer, mechanical, and thermal properties, shaping and setting up of these materials, technical solutions for hydraulic works). The fourth volume addresses the corrosion of metallic materials. It presents some generalities about these materials in the context of a deep geological storage of radioactive materials. It presents metallic materials and discusses their corrosion behaviour. It describes the peculiarities

Title list of documents made publicly available. Volume 17, No. 10

International Nuclear Information System (INIS)

1995-12-01

This document is a monthly publication containing descriptions of information received and generated by the US Nuclear Regulatory Commission (NRC). This information includes (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials, and (2) nondocketed material received and generated by NRC pertinent to its role as a regulatory agency. The following indexes are included: Personal Author, Corporate Source, Report Number, and Cross Reference of Enclosures to Principal Documents

Title list of documents made publicly available. Volume 17, No. 10

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-12-01

This document is a monthly publication containing descriptions of information received and generated by the US Nuclear Regulatory Commission (NRC). This information includes (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials, and (2) nondocketed material received and generated by NRC pertinent to its role as a regulatory agency. The following indexes are included: Personal Author, Corporate Source, Report Number, and Cross Reference of Enclosures to Principal Documents.

Natural gas annual 1992: Volume 1

Energy Technology Data Exchange (ETDEWEB)

1993-11-22

This document provides information on the supply and disposition of natural gas to a wide audience including industry, consumers, Federal and State agencies, and education institutions. The 1992 data are presented in a sequence that follows natural gas (including supplemental supplies) from its production top its end use. Tables summarizing natural gas supply and disposition from 1988 to 1992 are given for each Census Division and each State. Annual historical data are shown at the national level. Volume 2 of this report presents State-level historical data.

Documentation for grants equal to tax model: Volume 3, Source code

International Nuclear Information System (INIS)

Boryczka, M.K.

1986-01-01

The GETT model is capable of forecasting the amount of tax liability associated with all property owned and all activities undertaken by the US Department of Energy (DOE) in site characterization and repository development. The GETT program is a user-friendly, menu-driven model developed using dBASE III/trademark/, a relational data base management system. The data base for GETT consists primarily of eight separate dBASE III/trademark/ files corresponding to each of the eight taxes (real property, personal property, corporate income, franchise, sales, use, severance, and excise) levied by State and local jurisdictions on business property and activity. Additional smaller files help to control model inputs and reporting options. Volume 3 of the GETT model documentation is the source code. The code is arranged primarily by the eight tax types. Other code files include those for JURISDICTION, SIMULATION, VALIDATION, TAXES, CHANGES, REPORTS, GILOT, and GETT. The code has been verified through hand calculations

Standard Technical Specifications General Electric plants, BWR/4: Bases (Sections 2.0-3.3). Volume 2, Revision 1

International Nuclear Information System (INIS)

1995-04-01

This report documents the results of the combined effort of the NRC and the industry produce improved Standard Technical Specifications (STS), Revision 1 for General Electric BWR/4 Plants. The changes reflected in Revision 1 resulted from the experience gained from license amendment applications to convert to these improved ST or to adopt partial improvements to existing technical specifications. This NUREG is the result of extensive public technical meetings and discussions between the Nuclear Regulatory Commission (NRC) staff and various nuclear power plant licensees, Nuclear Steam Supply System (NSSS) Owners Groups, NSSS vendors, and the Nuclear Energy Institute (NEI). The improved STS were developed based on the criteria in the Final Commission Policy Statement on Technical Specifications Improvements for Nuclear Power Reactors, dated July 22, 1993. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. Volume I contains the Specifications for all chapters and sections of the improved STS. This document, Volume 2, contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1-3.3 of the improved STS. Volume 3 contains the Bases for Sections 3.4-3.10 of the improved STS

Proceedings of the 1995 U.S. DOE hydrogen program review, Volume 1

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-09-01

This document containes reports from the proceedings of the 1995 U.S. DOE hydrogen program review. Reports are organized under the topics of systems analysis, utilization, storage, and production. This volume, Volume I, contains the reports concerned with systems analysis and utilization. Individual reports were processed separately for the DOE data bases.

A comparative study on effect of e-learning and instructor-led methods on nurses' documentation competency.

Science.gov (United States)

Abbaszadeh, Abbas; Sabeghi, Hakimeh; Borhani, Fariba; Heydari, Abbas

2011-01-01

Accurate recording of the nursing care indicates the care performance and its quality, so that, any failure in documentation can be a reason for inadequate patient care. Therefore, improving nurses' skills in this field using effective educational methods is of high importance. Since traditional teaching methods are not suitable for communities with rapid knowledge expansion and constant changes, e-learning methods can be a viable alternative. To show the importance of e-learning methods on nurses' care reporting skills, this study was performed to compare the e-learning methods with the traditional instructor-led methods. This was a quasi-experimental study aimed to compare the effect of two teaching methods (e-learning and lecture) on nursing documentation and examine the differences in acquiring competency on documentation between nurses who participated in the e-learning (n = 30) and nurses in a lecture group (n = 31). The results of the present study indicated that statistically there was no significant difference between the two groups. The findings also revealed that statistically there was no significant correlation between the two groups toward demographic variables. However, we believe that due to benefits of e-learning against traditional instructor-led method, and according to their equal effect on nurses' documentation competency, it can be a qualified substitute for traditional instructor-led method. E-learning as a student-centered method as well as lecture method equally promote competency of the nurses on documentation. Therefore, e-learning can be used to facilitate the implementation of nursing educational programs.

1 CFR 5.3 - Publication of other documents.

Science.gov (United States)

2010-01-01

... 1 General Provisions 1 2010-01-01 2010-01-01 false Publication of other documents. 5.3 Section 5.3 General Provisions ADMINISTRATIVE COMMITTEE OF THE FEDERAL REGISTER THE FEDERAL REGISTER GENERAL § 5.3 Publication of other documents. Whenever the Director of the Federal Register considers that publication of a...

Structure and drafting of safeguards regulatory documents

International Nuclear Information System (INIS)

Cole, R.J.; Bennett, C.A.; Edelhertz, H.; Wood, M.T.; Brown, R.J.; Roberts, F.P.

1977-09-01

This study develops hypothesis about the relation between the structure and drafting of safeguards regulatory documents and the ability of document users to understand and implement them in a way that reflects the intent and requirements of the NRC. Four decisions are needed to improve communication: (1) Should improvement of safeguards regulatory documents as communication instruments be an explicit NRC program. (2) What specific methods of communication should be the focus of improvement efforts. (3) What actions to improve communications are feasible and desirable. (4) How should the NRC divide its available effort and resources among desirable actions in order to provide the most effective communication through regulatory documents. This volume contains: introduction, conceptual bases, legal requirements, targets, choice of documents, preparation of documents, readability, and further study of recommended changes in structure and drafting

Ada (Trade Name) Bibliography. Volume 1.

Science.gov (United States)

1983-05-01

GLENN DOCUMENT NUMBER: 3268 TYPE: JOURNAL ARTICLE .5-., SCIENCE VOL 215 ISSUE 34 PP. 775-779S In this article, two principal themes are observed in...AINST LANAN RD NAY 83 ND9S-8-C-936 UNCLASSIFIED F/6 12/5 ML -4.4 ’-4-4----" ’°p..l i . d N N L. 131 t ’ll /II~ Ada Bibliography Volume I 95 𔃾- This...BUDAPEST,HUNGARY 4102 -01 ON THE TYPE CONCEPT OF ADA 6224 -03 UNORTHOGONALITIES IN THE IDENTIFICATION RULES IN ADA BACON, GLENN , IBM SANTA TERESA LABS

Plan for studies of subsurface radionuclide migration at the Radioactive Waste Management Complex of the Idaho National Engineering Laboratory. Volume 1 of 2

International Nuclear Information System (INIS)

1983-11-01

This document describes planned studies of subsurface radionuclide migration at the Radioactive Waste Management Complex of the Idaho National Engineering Laboratory. A plan is provided for each proposed study. The rational for arriving at the list of proposed studies is also presented. This document consists of two volumes. In the first volume, Sections 1 through 5 contain the introduction, the objectives of the proposed studies, and background information. The discussion is not comprehensive in detail; documents are referenced that discuss the background material in greater detail. Sections 6 through 9 identify and select the group of studies to be performed and discuss the peer review process. The second volume contains Appendices A and B, which present the assignment of responsibilities and the detailed plans, schedules, and costs for the proposed program

Fusion Technology 1996. Proceedings. Volume 1 and 2

International Nuclear Information System (INIS)

Varandas, C.; Serra, F.

1997-01-01

The objective of these proceedings was to provide a platform for the exchange of information on the design, construction and operation of fusion experiments. The technology which is being developed for the next step devices and fusion reactors was also covered. Sections in volume 1 concern (A) first wall, divertors and vacuum systems; (B) plasma heating and control; (C) plasma engineering and control; and (D) experimental systems. The sections in volume 2 deal with (E) magnet and related power supplies; (F) fuel cycle and tritium processing systems; (G) blanket technology/materials; (H) assembly, remote handling and waste management and storage; and (I) safety and environment, and reactor studies

International Energy Agency Building Energy Simulation Test and Diagnostic Method for Heating, Ventilating, and Air-Conditioning Equipment Models (HVAC BESTEST): Volume 2: Cases E300-E545.

Energy Technology Data Exchange (ETDEWEB)

Neymark J.; Judkoff, R.

2004-12-01

This report documents an additional set of mechanical system test cases that are planned for inclusion in ANSI/ASHRAE STANDARD 140. The cases test a program's modeling capabilities on the working-fluid side of the coil, but in an hourly dynamic context over an expanded range of performance conditions. These cases help to scale the significance of disagreements that are less obvious in the steady-state cases. The report is Vol. 2 of HVAC BESTEST Volume 1. Volume 1 was limited to steady-state test cases that could be solved with analytical solutions. Volume 2 includes hourly dynamic effects, and other cases that cannot be solved analytically. NREL conducted this work in collaboration with the Tool Evaluation and Improvement Experts Group under the International Energy Agency (IEA) Solar Heating and Cooling Programme Task 22.

Iraqi Perspectives Project. Saddam and Terrorism: Emerging Insights from Captured Iraqi Documents. Volume 1 (Redacted)

National Research Council Canada - National Science Library

Woods, Kevin M; Lacey, James

2007-01-01

Captured Iraqi documents have uncovered evidence that links the regime of Saddam Hussein to regional and global terrorism, including a variety of revolutionary, liberation, nationalist, and Islamic...

Advisory Committee on human radiation experiments. Supplemental Volume 2a, Sources and documentation appendices. Final report

International Nuclear Information System (INIS)

1995-01-01

This large document provides a catalog of the location of large numbers of reports pertaining to the charge of the Presidential Advisory Committee on Human Radiation Research and is arranged as a series of appendices. Titles of the appendices are Appendix A- Records at the Washington National Records Center Reviewed in Whole or Part by DoD Personnel or Advisory Committee Staff; Appendix B- Brief Descriptions of Records Accessions in the Advisory Committee on Human Radiation Experiments (ACHRE) Research Document Collection; Appendix C- Bibliography of Secondary Sources Used by ACHRE; Appendix D- Brief Descriptions of Human Radiation Experiments Identified by ACHRE, and Indexes; Appendix E- Documents Cited in the ACHRE Final Report and other Separately Described Materials from the ACHRE Document Collection; Appendix F- Schedule of Advisory Committee Meetings and Meeting Documentation; and Appendix G- Technology Note

Advisory Committee on human radiation experiments. Supplemental Volume 2a, Sources and documentation appendices. Final report

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-01-01

This large document provides a catalog of the location of large numbers of reports pertaining to the charge of the Presidential Advisory Committee on Human Radiation Research and is arranged as a series of appendices. Titles of the appendices are Appendix A- Records at the Washington National Records Center Reviewed in Whole or Part by DoD Personnel or Advisory Committee Staff; Appendix B- Brief Descriptions of Records Accessions in the Advisory Committee on Human Radiation Experiments (ACHRE) Research Document Collection; Appendix C- Bibliography of Secondary Sources Used by ACHRE; Appendix D- Brief Descriptions of Human Radiation Experiments Identified by ACHRE, and Indexes; Appendix E- Documents Cited in the ACHRE Final Report and other Separately Described Materials from the ACHRE Document Collection; Appendix F- Schedule of Advisory Committee Meetings and Meeting Documentation; and Appendix G- Technology Note.

Implementing US Department of Energy lessons learned programs. Volume 2

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-08-01

The DOE Lessons Learned Handbook is a two-volume publication developed to supplement the DOE Lessons Learned Standard (DOE-STD-7501-95) with information that will organizations in developing or improving their lessons learned programs. Volume 1 includes greater detail than the Standard in areas such as identification and documentation of lessons learned; it also contains sections on specific processes such as training and performance measurement. Volume 2 (this document) contains examples of program documents developed by existing lessons learned programs as well as communications material, functional categories, transmittal documents, sources of professional and industry lessons learned, and frequently asked questions about the Lessons Learned List Service.

Job Performance Tests for CH-53E Helicopter Mechanics. Volume 2: Administrative Duties and Job Knowledge Tests

Science.gov (United States)

1992-01-01

SUBTmI.E 5 FU.NDING NUMBERS Job Performance Tests for CII-53E Helicopter Miechanacs - Volume I1: Admiutstrative Duties and Job Knowlede Tests C - N...performance measures to Marine Corps personnel managers . training instructors, and interested researchers who may find them useful. This work comprises...Corps personnel managers , training instructors, and interested researchers who may find them useful. 3. This work comprises two parts: volume I

Computerising documentation

International Nuclear Information System (INIS)

Anon.

1992-01-01

The nuclear power generation industry is faced with public concern and government pressures over safety, efficiency and risk. Operators throughout the industry are addressing these issues with the aid of a new technology - technical document management systems (TDMS). Used for strategic and tactical advantage, the systems enable users to scan, archive, retrieve, store, edit, distribute worldwide and manage the huge volume of documentation (paper drawings, CAD data and film-based information) generated in building, maintaining and ensuring safety in the UK's power plants. The power generation industry has recognized that the management and modification of operation critical information is vital to the safety and efficiency of its power plants. Regulatory pressure from the Nuclear Installations Inspectorate (NII) to operate within strict safety margins or lose Site Licences has prompted the need for accurate, up-to-data documentation. A document capture and management retrieval system provides a powerful cost-effective solution, giving rapid access to documentation in a tightly controlled environment. The computerisation of documents and plans is discussed in this article. (Author)

Savannah River Site mixed waste Proposed Site Treatment Plan (PSTP). Volumes 1 and 2 and reference document: Revision 2

International Nuclear Information System (INIS)

Helmich, E.; Noller, D.K.; Wierzbicki, K.S.; Bailey, L.L.

1995-01-01

The DOE is required by the Resource Conservation and Recovery Act to prepare site treatment plans describing the development of treatment capacities and technologies for treating mixed waste. This proposed plan contains Savannah River Site's preferred options and schedules for constructing new facilities, and otherwise obtaining treatment for mixed wastes. The proposed plan consists of 2 volumes. Volume 1, Compliance Plan, identifies the capacity to be developed and the schedules as required. Volume 2, Background, provides a detailed discussion of the preferred options with technical basis, plus a description of the specific waste streams. Chapters are: Introduction; Methodology; Mixed low level waste streams; Mixed transuranic waste; High level waste; Future generation of mixed waste streams; Storage; Process for evaluation of disposal issues in support of the site treatment plans discussions; Treatment facilities and treatment technologies; Offsite waste streams for which SRS treatment is the Preferred Option (Naval reactor wastes); Summary information; and Acronyms and glossary. This revision does not contain the complete revised report, but only those pages that have been revised

European Science Notes. Volume 40, Number 1.

Science.gov (United States)

1986-01-01

Mass Spectrometry mers and copolymers of polyacrylate salt series edited by Professor J.F.J. Todd latex) rather than an inorganic or or- (University...changes in the popu- cy with two potassium dihydrogen phos- lation of a vibrational manifold were phate (KDP) crystals. Following a fil- determined by...AD-A162 235 EUROPEAN SCIENCE NOTES VOLUME 48 NUMBER I(U) OFFICE OF i/1 NAVAL RESEARCH LONDON (ENGLAND) L E SHAFFER JAN 86 UNCLASSIFIED F/G 5/2

Application Level Protocol Development for Library and Information Science Applications. Volume 1: Service Definition. Volume 2: Protocol Specification. Report No. TG.1.5; TG.50.

Science.gov (United States)

Aagaard, James S.; And Others

This two-volume document specifies a protocol that was developed using the Reference Model for Open Systems Interconnection (OSI), which provides a framework for communications within a heterogeneous network environment. The protocol implements the features necessary for bibliographic searching, record maintenance, and mail transfer between…

Excess Molar Volume and Apparent Molar Volume of Binary Mixtures of 2—Methyl—3—buten—2—ol with 1—Alcohol at 298.15K

Institute of Scientific and Technical Information of China (English)

LIUDixia; LIHaoran; 等

2002-01-01

Excess molar volumes (VmE) of binary mixtures of 2-methyl-3-buten-2-ol[CH3C(OH)(CH3)CHCH2] with four 1-alcohols:methanol,ethanol,1-propanol and 1-butanol at 298.15K and atmospheric pressure are derived from density measurements with a vibrating-tube densimeter.All the excess volumes are negative in the systems over the entire composition range. The results are correlated with the Redlich-Kister equation.The effects of chain length of 1-alcohols on VmE are discussed.The apparent molar volumes of 2-methyl-3-buten-2-ol and 1-alcohols are calculated respectively.

Sensors, Volume 1, Fundamentals and General Aspects

Science.gov (United States)

Grandke, Thomas; Ko, Wen H.

1996-12-01

'Sensors' is the first self-contained series to deal with the whole area of sensors. It describes general aspects, technical and physical fundamentals, construction, function, applications and developments of the various types of sensors. This volume deals with the fundamentals and common principles of sensors and covers the wide areas of principles, technologies, signal processing, and applications. Contents include: Sensor Fundamentals, e.g. Sensor Parameters, Modeling, Design and Packaging; Basic Sensor Technologies, e.g. Thin and Thick Films, Integrated Magnetic Sensors, Optical Fibres and Intergrated Optics, Ceramics and Oxides; Sensor Interfaces, e.g. Signal Processing, Multisensor Signal Processing, Smart Sensors, Interface Systems; Sensor Applications, e.g. Automotive: On-board Sensors, Traffic Surveillance and Control, Home Appliances, Environmental Monitoring, etc. This volume is an indispensable reference work and text book for both specialits and newcomers, researchers and developers.

The Effect of Volume of Transaction On The Intention Towards Tax E-filing

Directory of Open Access Journals (Sweden)

Aziz Saliza Abdul

2017-01-01

Full Text Available Volume of transaction is specifically referring to number of clients or return forms dealing by tax agents/preparers. This variable does play role even though there is less empirical evidence on this matter. This paper is basically to explore the effect of volume of transaction that could possibly influence the acceptance of tax e-filing system as it did in other areas of transaction i.e. court cases. Undoubtedly, it is proved to be significantly influenced the behavioural intention towards tax e-filing acceptability in Malaysia. The tax agents/preparers are randomly selected in this study from the list provided in the Inland Revenue Board of Malaysia (IRBM website. The responds are analysed via Partial Least Square (PLS method which produce the significant results among the low and high volume of transaction of tax e-filing which support the fact that volume does matter in the decision of acceptability of tax e-filing system in Malaysia.

F-35A Training Basing Environmental Impact Statement. Volume 2. Appendix D - Comment Response Document. Book 1

Science.gov (United States)

2012-06-01

Luke Forward F-35A Support Campaign Letter No. Last Name First Name City State 6360 Steider Opal Sun City West AZ 10131 Steiger Denise...mitigation? 2) The Preface re- N0-4 1016 HO assuring says "Readers who wish to quickly (emphasis mine !) review the document and compare the...of the Drafl EIS. ·~ )t)Ur mal!ng ~~to reoet"’C MINe I"’Itice$ abOut the r -3SA. T1~rw~ Bcl!ling EIS 1401 LU Final June 2012 F-35A

Addendum to the remedial investigation report on Bear Creek Valley Operable Unit 2 (Rust Spoil Area, Spoil Area 1, and SY-200 Yard) at the Oak Ridge Y-12 Plant Oak Ridge, Tennessee. Volume 1: Main text

International Nuclear Information System (INIS)

1995-04-01

This addendum to the Remedial Investigation (RI) Report on Bear Creek Valley Operable Unit (OU) 2 at the Oak Ridge Y-12 Plant was prepared in accordance with requirements under the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) for reporting the results of a site characterization for public review. This addendum is a supplement to a document that was previously issued in January 1995 and that provided the Environmental Restoration Program with information about the results of the 1993 investigation performed at OU 2. The January 1995 D2 version of the RI Report on Bear Creek Valley OU 2 included information on risk assessments that have evaluated impacts to human health and the environment. Information provided in the document formed the basis for the development of the Feasibility Study Report. This addendum includes revisions to four chapters of information that were a part of the document issued in January 1995. Specifically, it includes revisions to Chaps. 2, 3, 4, and 9. Volume 1 of this document is not being reissued in its entirety as a D3 version because only the four chapters just mentioned have been affected by requested changes. Note also that Volume 2 of this RI Report on Bear Creek Valley OU 2 is not being reissued in conjunction with Volume 1 of this document because there have been no changes requested or made to the previously issued version of Volume 2 of this document.

Title list of documents made publicly available. Volume 16, Number 5

Energy Technology Data Exchange (ETDEWEB)

1994-07-01

The Title List of Documents Made Publicly Available contains descriptions of the information received and generated by the US Nuclear Regulatory Commission (NRC). This information includes (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials and (2) nondocketed material received and generated by NRC pertinent to its role as a regulatory agency. As used here, docketed does not refer to Court dockets; it refers to the system by which NRC maintains its regulatory records. This series of documents is indexed by a Personal Author Index, a Corporate Source Index, and a Report Number Index.

Title list of documents made publicly available. Volume 16, Number 5

International Nuclear Information System (INIS)

1994-07-01

The Title List of Documents Made Publicly Available contains descriptions of the information received and generated by the US Nuclear Regulatory Commission (NRC). This information includes (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials and (2) nondocketed material received and generated by NRC pertinent to its role as a regulatory agency. As used here, docketed does not refer to Court dockets; it refers to the system by which NRC maintains its regulatory records. This series of documents is indexed by a Personal Author Index, a Corporate Source Index, and a Report Number Index

9th Pacific Basin Nuclear Conference. Nuclear energy, science and technology - Pacific partnership. Proceedings Volume 1

International Nuclear Information System (INIS)

1994-04-01

The theme of the 9th Pacific Basin Nuclear conference held in Sydney from 1-6 May 1994, embraced the use of the atom in energy production and in science and technology. The focus was on selected topics of current and ongoing interest to countries around the Pacific Basin. The two-volume proceedings include both invited and contributed papers. They have been indexed separately. This document, Volume 1 covers the following topics: Pacific partnership; perspectives on nuclear energy, science and technology in Pacific Basin countries; nuclear energy and sustainable development; economics of the power reactors; new power reactor projects; power reactor technology; advanced reactors; radioisotope and radiation technology; biomedical applications

Savannah River Site Environmental Monitoring Plan. Volume 1, Section 1000 Addendum: Revision 3

International Nuclear Information System (INIS)

Jannik, G.T.

1994-01-01

This document -- the Savannah River Site Environmental Monitoring Plan (SRS EM Plan) -- has been prepared according to guidance contained in the DOE 5400 Series orders, in 10 CFR 834, and in DOE/EH-0173T, Environmental Regulatory Guide for Radiological Effluent Monitoring and environmental Surveillance [DOE, 1991]. The SRS EM Plan's purpose is to define the criteria, regulations, and guideline requirements with which SRS will comply. These criteria and requirements are applicable to environmental monitoring activities performed in support of the SRS Environmental Monitoring Program (SRS EM Program), WSRC-3Q1-2, Volume 1, Section 1100. They are not applicable to monitoring activities utilized exclusively for process monitoring/control. The environmental monitoring program requirements documented in the SRS EM Plan incorporate all applicable should requirements of DOE/EH-0173T and expand upon them to include nonradiological environmental monitoring program requirements

MELCOR computer code manuals: Primer and user's guides, Version 1.8.3 September 1994. Volume 1

International Nuclear Information System (INIS)

Summers, R.M.; Cole, R.K. Jr.; Smith, R.C.; Stuart, D.S.; Thompson, S.L.; Hodge, S.A.; Hyman, C.R.; Sanders, R.L.

1995-03-01

MELCOR is a fully integrated, engineering-level computer code that models the progression of severe accidents in light water reactor nuclear power plants. MELCOR is being developed at Sandia National Laboratories for the US Nuclear Regulatory Commission as a second-generation plant risk assessment tool and the successor to the Source Term Code Package. A broad spectrum of severe accident phenomena in both boiling and pressurized water reactors is treated in MELCOR in a unified framework. These include: thermal-hydraulic response in the reactor coolant system, reactor cavity, containment, and confinement buildings; core heatup, degradation, and relocation; core-concrete attack; hydrogen production, transport, and combustion; fission product release and transport; and the impact of engineered safety features on thermal-hydraulic and radionuclide behavior. Current uses of MELCOR include estimation of severe accident source terms and their sensitivities and uncertainties in a variety of applications. This publication of the MELCOR computer code manuals corresponds to MELCOR 1.8.3, released to users in August, 1994. Volume 1 contains a primer that describes MELCOR's phenomenological scope, organization (by package), and documentation. The remainder of Volume 1 contains the MELCOR Users' Guides, which provide the input instructions and guidelines for each package. Volume 2 contains the MELCOR Reference Manuals, which describe the phenomenological models that have been implemented in each package

Site Environmental Report for 2004. Volume 1, Environment, Health, and Safety Division

Energy Technology Data Exchange (ETDEWEB)

None

2005-09-30

Each year, Ernest Orlando Lawrence Berkeley National Laboratory prepares an integrated report on its environmental programs to satisfy the requirements of United States Department of Energy Order 231.1A, Environment, Safety, and Health Reporting.1 The Site Environmental Report for 2004 summarizes Berkeley Lab’s environmental management performance, presents environmental monitoring results, and describes significant programs for calendar year 2004. (Throughout this report, Ernest Orlando Lawrence Berkeley National Laboratory is referred to as “Berkeley Lab,” “the Laboratory,” “Lawrence Berkeley National Laboratory,” and “LBNL.”) The report is separated into two volumes. Volume I contains an overview of the Laboratory, the status of environmental programs, and summarized results from surveillance and monitoring activities. Volume II contains individual data results from these activities. This year, the Site Environmental Report was distributed by releasing it on the Web from the Berkeley Lab Environmental Services Group (ESG) home page, which is located at http://www.lbl.gov/ehs/esg/. Many of the documents cited in this report also are accessible from the ESG Web page. CD and printed copies of this Site Environmental Report are available upon request.

NORDICOM. Bibliography of Nordic Mass Communication Literature. Document List/Index 1975:1.

Science.gov (United States)

Nordic Documentation Center for Mass Communication Research, Aarhus (Denmark).

This first annual bibliography of mass communications literature of Denmark, Finland, Norway, and Sweden includes documents published from 1970 to 1975. The Document List contains arbitrary entries for 758 books, periodicals, and publications of untraditional form--e.g., duplicated and mimeographed materials and working papers. Arranged by…

Forest structure and stem volume assessment based on airborne laser scanning / Avaliação da estrutura florestal e do volume de madeira a partir de laser aerotransportado

Directory of Open Access Journals (Sweden)

Markus Hollaus

2012-10-01

Full Text Available This paper presents a methodology for the derivation of structural parameters and stem volume in forests based on Airborne Laser Scanning (ALS data. We describe three different measures of horizontal and vertical canopy structure: (1 tree crown segmentation, (2 compactness of vegetation patches, and (3 vertical layering of vegetation patches and canopy cover. An empirical regression model for the derivation of stem volume from the ALS and forest inventory sample plot data is described and its results are validated with extensive reference data. Different study areas in Austria were used to illustrate the workflows. The presented study demonstrates the applicability of the proposed methods on study sites and ALS data of differing characteristics, as well as it points out the suitability of ALS as a tool for reliable wide area assessment of structural parameters and stem volume for forested areas.ResumoEsse artigo apresenta uma metodologia para derivação de parâmetros estruturais e de volume de madeira em florestas baseado em dados de Laser Scanner Aerotransportado (ALS. Nós descrevemos três diferentes medidas da estrutura horizontal e vertical da copa: (1 segmentação da copa da árvore, (2 compacidade das manchas de vegetação, (3 estratificação vertical das manchas de vegetação e cobertura do dossel. Um modelo empírico de regressão para derivar o volume de madeira fazendo uso de dados ALS e dados amostrais obtidos em inventário florestal é descrito e seus resultados são validados com extensivos dados de referência. Diferentes áreas na Áustria foram utilizadas para ilustrar o fluxo de trabalho. O estudo apresentado demonstra a aplicabilidade dos métodos propostos nas áreas de estudo e dos dados ALS de diferentes características, bem como aponta a adequação do ALS como ferramenta confiável para avaliação de parâmetros de estrutura e de volume de madeira de amplas áreas florestais.

Instrumentation and Controls Division progress report for the period July 1, 1988 to June 30, 1990. Volume 2

Energy Technology Data Exchange (ETDEWEB)

Klobe, L.E. [ed.

1990-12-01

The format of this Instrumentation and Controls Division progress report is a major departure from previous reports. This report has been published in two volumes instead of one, and the description of individual activities have been shortened considerably to make it easier document to scan and to read. Volume 1 of this report presents brief descriptions of a few highly significant programmatic and technological efforts representative of Instrumentation and Controls Division activities over the past two years. This volume contains information concerning the publications, presentations, and other professional activities and achievements of I&C Division staff members.

Title list of documents made publicly available. Volume 17, No. 5

International Nuclear Information System (INIS)

1995-07-01

The Title List of Documents Made Publicly Available is a monthly publication. It contains descriptions of the information received and generated by the US Nuclear Regulatory Commission (NRC). This information includes (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials and (3) nondocketed material received and generated by NRC pertinent to its role as a regulatory agency. As used here, docketed does not refer to Court dockets; it refers to the system by which NRC maintains its regulatory records. This series of documents is indexed by a Personal Author Index, a Corporate Source Index, and a Report Number Index

Title list of documents made publicly available. Volume 17, No. 7

International Nuclear Information System (INIS)

1995-09-01

The Title List of Documents Made Publicly Available is a monthly publication. It contains descriptions of the information received and generated by the US Nuclear Regulatory Commission (NRC). This information includes (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials and (2) nondocketed material received and generated by NRC pertinent to its role as a regulatory agency. As used here, docketed does not refer to Court dockets; it refers to the system by which NRC maintains its regulatory records. This series of documents is indexed by a Personal Author Index, a Corporate Source Index, and a Report Number Index

Title list of documents made publicly available. Volume 17, No. 5

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-07-01

The Title List of Documents Made Publicly Available is a monthly publication. It contains descriptions of the information received and generated by the US Nuclear Regulatory Commission (NRC). This information includes (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials and (3) nondocketed material received and generated by NRC pertinent to its role as a regulatory agency. As used here, docketed does not refer to Court dockets; it refers to the system by which NRC maintains its regulatory records. This series of documents is indexed by a Personal Author Index, a Corporate Source Index, and a Report Number Index.

Title list of documents made publicly available. Volume 17, No. 7

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-09-01

The Title List of Documents Made Publicly Available is a monthly publication. It contains descriptions of the information received and generated by the US Nuclear Regulatory Commission (NRC). This information includes (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials and (2) nondocketed material received and generated by NRC pertinent to its role as a regulatory agency. As used here, docketed does not refer to Court dockets; it refers to the system by which NRC maintains its regulatory records. This series of documents is indexed by a Personal Author Index, a Corporate Source Index, and a Report Number Index.

Technical basis to describe and document the use of the E-600 and SHP-380 detector

International Nuclear Information System (INIS)

Hensley, J.R.

1997-06-01

This technical basis document describes and documents the parameters under which the Eberline E-600 ratemeter and the associated SHP-380 detector can be operated to quantify alpha and beta contamination levels. 3 refs., 3 tabs

Petroleum supply annual 1994. Volume 1

International Nuclear Information System (INIS)

1995-01-01

The Petroleum Supply Annual (PSA) contains information on the supply and disposition of crude oil and petroleum products. The publication reflects data that were collected from the petroleum industry during 1994 through annual and monthly surveys. The PSA is divided into two volumes. This first volume contains four sections: Summary Statistics, Detailed Statistics, Refinery Capacity, and Oxygenate Capacity each with final annual data. The second volume contains final statistics for each month of 1994, and replaces data previously published in the Petroleum Supply Monthly (PSM). The tables in Volumes 1 and 2 are similarly numbered to facilitate comparison between them. Below is a description of each section in Volume 1 of the PSA

Fungicidas, doses e volumes de calda no controle químico da ferrugem da folha da aveia (Puccinia coronata f. sp. avenae Fungicides, rates and spray volumes in the chemical control of oats crown rust (Puccinia coronata f. sp. avenae

Directory of Open Access Journals (Sweden)

Ana R. de Oliveira

2007-01-01

Full Text Available A ferrugem da folha (Puccinia coronata f. sp. avenae é a doença mais destrutiva da aveia, e aplicações de fungicidas com volumes baixos de calda podem reduzir a eficácia do controle químico. O objetivo do trabalho foi avaliar a eficiência técnica e econômica de fungicidas, doses e volumes de calda no controle da ferrugem da folha da aveia. O experimento foi conduzido no ano de 2003, na área experimental da FAMV/UPF, com a cultivar de aveia UPFA-20. Os tratamentos foram compostos pelas combinações entre dois fungicidas (tebuconazole, Folicur, 0,75 L ha-1 e epoxiconazole + piraclostrobim, Opera, 0,5 L ha-1, quatro doses (40; 60; 80 e 100% da dose recomendada e dois volumes de calda (100 e 200 L ha-1. O delineamento experimental foi o de blocos casualizados, com esquema fatorial (2x4x2 e quatro repetições. Avaliaram-se a severidade, o controle da ferrugem, a massa do hectolitro, a massa de mil grãos e o rendimento de grãos, realizando-se análise econômica. O volume de calda de 200 L ha-1 proporcionou maiores níveis de controle da doença. As aplicações dos fungicidas com volume de 200 L ha-1 e meia dose ou com 100 L ha-1 e dose cheia proporcionam níveis de controle da ferrugem equivalentes. O resultado econômico difere entre fungicidas e independe do volume de calda. Os efeitos de doses dependem do fungicida.Crown rust (Puccinia coronata f. sp. avenae is the most important disease of oats in Brazil. In susceptible oat cultivars, fungicides are needed to control the disease efficiently. However, spray at low volumes may reduce fungicide performance significantly. A field experiment with the oat cultivar UPFA-20 was carried out at the FAMV/UPF to evaluate the influence of fungicides, rates, and spray volumes on the efficacy of the chemical control for crown rust. The tested treatments combined two fungicides (tebuconazole, Folicur, 0,75 L ha-1; epoxiconazole + pyraclostrobin, Opera, 0,5 L ha-1, four rates (40; 60; 80 and 100

Leak testing plan for the Oak Ridge National Laboratory liquid low-level waste systems (active tanks): Revision 2. Volume 1: Regulatory background and plan approach; Volume 2: Methods, protocols, and schedules; Volume 3: Evaluation of the ORNL/LT-823DP differential pressure leak detection method; Appendix to Revision 2: DOE/EPA/TDEC correspondence

Energy Technology Data Exchange (ETDEWEB)

Douglas, D.G.; Wise, R.F.; Starr, J.W.; Maresca, J.W. Jr. [Vista Research, Inc., Mountain View, CA (United States)

1994-11-01

This document, the Leak Testing Plan for the Oak Ridge National Laboratory Liquid Low-Level Waste System (Active Tanks), comprises three volumes. The first two volumes address the component-based leak testing plan for the liquid low-level waste system at Oak Ridge, while the third volume describes the performance evaluation of the leak detection method that will be used to test this system. Volume 1, describes that portion of the liquid low-level waste system at that will be tested; it provides the regulatory background, especially in terms of the requirements stipulated in the Federal Facilities Agreement, upon which the leak testing plan is based. Volume 1 also describes the foundation of the plan, portions of which were abstracted from existing federal documents that regulate the petroleum and hazardous chemicals industries. Finally, Volume 1 gives an overview the plan, describing the methods that will be used to test the four classes of components in the liquid low-level waste system. Volume 2 takes the general information on component classes and leak detection methods presented in Volume 1 and shows how it applies particularly to each of the individual components. A complete test plan for each of the components is presented, with emphasis placed on the methods designated for testing tanks. The protocol for testing tank systems is described, and general leak testing schedules are presented. Volume 3 describes the results of a performance evaluation completed for the leak testing method that will be used to test the small tanks at the facility (those less than 3,000 gal in capacity). Some of the details described in Volumes 1 and 2 are expected to change as additional information is obtained, as the viability of candidate release detection methods is proven in the Oak Ridge environment, and as the testing program evolves.

Leak testing plan for the Oak Ridge National Laboratory liquid low-level waste systems (active tanks): Revision 2. Volume 1: Regulatory background and plan approach; Volume 2: Methods, protocols, and schedules; Volume 3: Evaluation of the ORNL/LT-823DP differential pressure leak detection method; Appendix to Revision 2: DOE/EPA/TDEC correspondence

International Nuclear Information System (INIS)

Douglas, D.G.; Wise, R.F.; Starr, J.W.; Maresca, J.W. Jr.

1994-11-01

This document, the Leak Testing Plan for the Oak Ridge National Laboratory Liquid Low-Level Waste System (Active Tanks), comprises three volumes. The first two volumes address the component-based leak testing plan for the liquid low-level waste system at Oak Ridge, while the third volume describes the performance evaluation of the leak detection method that will be used to test this system. Volume 1, describes that portion of the liquid low-level waste system at that will be tested; it provides the regulatory background, especially in terms of the requirements stipulated in the Federal Facilities Agreement, upon which the leak testing plan is based. Volume 1 also describes the foundation of the plan, portions of which were abstracted from existing federal documents that regulate the petroleum and hazardous chemicals industries. Finally, Volume 1 gives an overview the plan, describing the methods that will be used to test the four classes of components in the liquid low-level waste system. Volume 2 takes the general information on component classes and leak detection methods presented in Volume 1 and shows how it applies particularly to each of the individual components. A complete test plan for each of the components is presented, with emphasis placed on the methods designated for testing tanks. The protocol for testing tank systems is described, and general leak testing schedules are presented. Volume 3 describes the results of a performance evaluation completed for the leak testing method that will be used to test the small tanks at the facility (those less than 3,000 gal in capacity). Some of the details described in Volumes 1 and 2 are expected to change as additional information is obtained, as the viability of candidate release detection methods is proven in the Oak Ridge environment, and as the testing program evolves

NRC review of Electric Power Research Institute's advanced light water reactor utility requirements document. Passive plant designs, chapters 2-13, project number 669

International Nuclear Information System (INIS)

1994-08-01

The Electric Power Research Institute (EPRI) is preparing a compendium of technical requirements, referred to as the open-quotes Advanced Light Water Reactor [ALWR] Utility Requirements Documentclose quotes, that is acceptable to the design of an ALWR power plant. When completed, this document is intended to be a comprehensive statement of utility requirements for the design, construction, and performance of an ALWR power plant for the 1990s and beyond. The Requirements Document consists of three volumes. Volume I, open-quotes ALWR Policy and Summary of Top-Tier Requirementsclose quotes, is a management-level synopsis of the Requirements Document, including the design objectives and philosophy, the overall physical configuration and features of a future nuclear plant design, and the steps necessary to take the proposed ALWR design criteria beyond the conceptual design state to a completed, functioning power plant. Volume II consists of 13 chapters and contains utility design requirements for an evolutionary nuclear power plant [approximately 1350 megawatts-electric (MWe)]. Volume III contains utility design requirements for nuclear plants for which passive features will be used in their designs (approximately 600 MWe). In April 1992, the staff of the Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, issued Volume 1 and Volume 2 (Parts 1 and 2) of its safety evaluation report (SER) to document the results of its review of Volumes 1 and 2 of the Requirements Document. Volume 1, open-quotes NRC Review of Electric Power Research Institute's Advanced Light Water Reactor Utility Requirements Document - Program Summaryclose quotes, provided a discussion of the overall purpose and scope of the Requirements Document, the background of the staff's review, the review approach used by the staff, and a summary of the policy and technical issues raised by the staff during its review

High integrity software for nuclear power plants: Candidate guidelines, technical basis and research needs. Main report, Volume 2

International Nuclear Information System (INIS)

Seth, S.; Bail, W.; Cleaves, D.; Cohen, H.; Hybertson, D.; Schaefer, C.; Stark, G.; Ta, A.; Ulery, B.

1995-06-01

The work documented in this report was performed in support of the US Nuclear Regulatory Commission to examine the technical basis for candidate guidelines that could be considered in reviewing and evaluating high integrity computer e following software development and assurance activities: Requirements specification; design; coding; verification and validation, inclukding static analysis and dynamic testing; safety analysis; operation and maintenance; configuration management; quality assurance; and planning and management. Each activity (framework element) was subdivided into technical areas (framework subelements). The report describes the development of approximately 200 candidate guidelines that span the entire ran e identification, categorization and prioritization of technical basis for those candidate guidelines; and the identification, categorization and prioritization of research needs for improving the technical basis. The report has two volumes: Volume 1, Executive Summary includes an overview of the framwork and of each framework element, the complete set of candidate guidelines, the results of the assessment of the technical basis for each candidate guideline, and a discussion of research needs that support the regulatory function; this document, Volume 2, is the main report

High integrity software for nuclear power plants: Candidate guidelines, technical basis and research needs. Main report, Volume 2

Energy Technology Data Exchange (ETDEWEB)

Seth, S.; Bail, W.; Cleaves, D.; Cohen, H.; Hybertson, D.; Schaefer, C.; Stark, G.; Ta, A.; Ulery, B. [Mitre Corp., McLean, VA (United States)

1995-06-01

The work documented in this report was performed in support of the US Nuclear Regulatory Commission to examine the technical basis for candidate guidelines that could be considered in reviewing and evaluating high integrity computer e following software development and assurance activities: Requirements specification; design; coding; verification and validation, inclukding static analysis and dynamic testing; safety analysis; operation and maintenance; configuration management; quality assurance; and planning and management. Each activity (framework element) was subdivided into technical areas (framework subelements). The report describes the development of approximately 200 candidate guidelines that span the entire ran e identification, categorization and prioritization of technical basis for those candidate guidelines; and the identification, categorization and prioritization of research needs for improving the technical basis. The report has two volumes: Volume 1, Executive Summary includes an overview of the framwork and of each framework element, the complete set of candidate guidelines, the results of the assessment of the technical basis for each candidate guideline, and a discussion of research needs that support the regulatory function; this document, Volume 2, is the main report.

Mod-5A Wind Turbine Generator Program Design Report. Volume 2: Conceptual and Preliminary Design, Book 1

Science.gov (United States)

1984-01-01

The design, development and analysis of the 7.3 MW MOD-5A wind turbine generator is documented. There are four volumes. In Volume 2, book 1 the requirements and criteria for the design are presented. The conceptual design studies, which defined a baseline configuration and determined the weights, costs and sizes of each subsystem, are described. The development and optimization of the wind turbine generator are presented through the description of the ten intermediate configurations between the conceptual and final designs. Analyses of the system's load and dynamics are presented.

The opening of the Mexican electric sector to foreign investment. Volume 1; La apertura externa en el sector electrico Mexicano. Volumen 1

Energy Technology Data Exchange (ETDEWEB)

Quintanilla Martinez, Juan [eds.] [Universidad Nacional Autonoma de Mexico, Mexico, D. F. (Mexico)

1997-12-31

This document is the first one of three volumes of the 1. Seminar on the Current Conditions and Perspectives of the Electric Sector in Mexico, organized by the Programa Universitario de Energia and the Instituto de Investigaciones Economicas (University Program of Energy and the Institute of Economic Research, both of them agencies of the Universidad Nacional Autonoma de Mexico (UNAM)). The titles of the three volumes are the following: Volume 1.- The opening of the Mexican Electric Sector to foreign investment. Volume 2.- Concrete innovation and technological learning experiences at the Luz y Fuerza del Centro enterprise. Volume 3.- The Electric Energy and the Environment in Mexico. This first volume deals on the World tendencies towards the privatization; the new financing techniques and the reorganization of the Mexican electric industry; the electric rates in the residential sector; the distribution of the income and the electricity expense in Mexican homes, the privatization of the energy in Mexico and the production costs in generation projects planning. These documents were formulated by specialists of the Electric Sector, from the Electric Sector itself as well as from academic entities, public and private [Espanol] Este documento constituye el primero de tres volumenes del Primer Seminario sobre Situacion y Perspectivas del Sector Electrico en Mexico, organizado por el Programa Universitario de Energia y el Instituto de Investigaciones Economicas, ambas dependencias de la Universidad Nacional Autonoma de Mexico (UNAM). Los titulos de los tres volumenes son los siguientes: volumen 1: La apertura externa del sector electrico mexicano, volumen 2: Experiencias concretas de innovacion y aprendizaje tecnologico en la empresa Luz y Fuerza del Centro, volumen 3: Energia electrica y medio ambiente en Mexico. Este primer volumen trata sobre las tendencias mundiales hacia la privatizacion; las nuevas tecnicas de financiamiento y reorganizacion de la industria

High-level waste borosilicate glass: A compendium of corrosion characteristics. Volume 2

International Nuclear Information System (INIS)

Cunnane, J.C.

1994-03-01

The objective of this document is to summarize scientific information pertinent to evaluating the extent to which high-level waste borosilicate glass corrosion and the associated radionuclide release processes are understood for the range of environmental conditions to which waste glass may be exposed in service. Alteration processes occurring within the bulk of the glass (e.g., devitrification and radiation-induced changes) are discussed insofar as they affect glass corrosion.This document is organized into three volumes. Volumes I and II represent a tiered set of information intended for somewhat different audiences. Volume I is intended to provide an overview of waste glass corrosion, and Volume 11 is intended to provide additional experimental details on experimental factors that influence waste glass corrosion. Volume III contains a bibliography of glass corrosion studies, including studies that are not cited in Volumes I and II. Volume I is intended for managers, decision makers, and modelers, the combined set of Volumes I, II, and III is intended for scientists and engineers working in the field of high-level waste

High-level waste borosilicate glass: A compendium of corrosion characteristics. Volume 2

Energy Technology Data Exchange (ETDEWEB)

Cunnane, J.C. [comp.; Bates, J.K.; Bradley, C.R. [Argonne National Lab., IL (United States)] [and others

1994-03-01

The objective of this document is to summarize scientific information pertinent to evaluating the extent to which high-level waste borosilicate glass corrosion and the associated radionuclide release processes are understood for the range of environmental conditions to which waste glass may be exposed in service. Alteration processes occurring within the bulk of the glass (e.g., devitrification and radiation-induced changes) are discussed insofar as they affect glass corrosion.This document is organized into three volumes. Volumes I and II represent a tiered set of information intended for somewhat different audiences. Volume I is intended to provide an overview of waste glass corrosion, and Volume 11 is intended to provide additional experimental details on experimental factors that influence waste glass corrosion. Volume III contains a bibliography of glass corrosion studies, including studies that are not cited in Volumes I and II. Volume I is intended for managers, decision makers, and modelers, the combined set of Volumes I, II, and III is intended for scientists and engineers working in the field of high-level waste.

Linguagens documentárias e vocabulários semânticos para a web: elementos conceituais: resenha

Directory of Open Access Journals (Sweden)

Eliana Maria dos Santos Bahia

2012-01-01

ço. Em se tratando do quarto capítulo, o autor aborda Léxico e Linguagens Documentárias, em duas seções: Classificação dos KOS; SKOS, por meio das normas ISO 704:2000 e ISO 1087-Parte1:2000, com vantagens quando à norma ISO 2788:1986 de construção de tesauros. O quinto capítulo (Web 2.0 e Folksonomias, compreende funcionamento das Folksonomias, sua utilidades, vantagens e debilidades e sua comparação aos Tesauros, no qual explica que as folksonomias permitem estudar os termos mais empregados, onde os mesmos evoluem de acordo com as tendências e as comunidades que os empreguem. O capítulo sexto apresenta as Taxonomias, com seus componentes básicos e características, visando a sua construção ligada às linguagens documentarias, voltado ao respectivo processo metodológico. No sétimo capítulo enfoca os Tesauros, apresenta a rede conceitual e sua instrumentalidade, seu uso, vantagens e desvantagens na contribuição de novas normas. Aponta soluções quanto à linguística, à estatística (classificadores cienciométricos, à computação. O autor pondera que a lista de descritores (termos controlados representa os conceitos de um domínio do conhecimento. E que se organiza em estrutura hierárquica com relações semânticas entre si. O oitavo capítulo (Ontologias, o predomínio dos conceitos, Moreiro González ilustra as camadas da web semântica, juntamente com as linguagens, elaboração e os tesauros frente a ontologias baseadas em normas internacionais, passo primordial para a construção de elementos semânticos inteligentes. Para o nono capítulo (Tesauros: progressão conceitual e redes semânticas o autor desenvolve uma discussão sobre os Tesauros de Descritores Verbais e Redes semânticas, salientando que a evolução das redes semânticas resulta nos mapas conceituais na ordenação das linguagens. O décimo capítulo (Topic Maps, mostra a considerável variedade de mapas conceituais, suas considerações, definições, modelos

Linguagens documentárias e vocabulários semânticos para a web: elementos conceituais: resenha

Directory of Open Access Journals (Sweden)

Eliana Maria dos Santos Bahia

2012-08-01

semântica coexistindo harmoniosamente no ciberespaço. Em se tratando do quarto capítulo, o autor aborda Léxico e Linguagens Documentárias, em duas seções: Classificação dos KOS; SKOS, por meio das normas ISO 704:2000 e ISO 1087-Parte1:2000, com vantagens quando à norma ISO 2788:1986 de construção de tesauros. O quinto capítulo (Web 2.0 e Folksonomias, compreende funcionamento das Folksonomias, sua utilidades, vantagens e debilidades e sua comparação aos Tesauros, no qual explica que as folksonomias permitem estudar os termos mais empregados, onde os mesmos evoluem de acordo com as tendências e as comunidades que os empreguem. O capítulo sexto apresenta as Taxonomias, com seus componentes básicos e características, visando a sua construção ligada às linguagens documentarias, voltado ao respectivo processo metodológico. No sétimo capítulo enfoca os Tesauros, apresenta a rede conceitual e sua instrumentalidade, seu uso, vantagens e desvantagens na contribuição de novas normas. Aponta soluções quanto à linguística, à estatística (classificadores cienciométricos, à computação. O autor pondera que a lista de descritores (termos controlados representa os conceitos de um domínio do conhecimento. E que se organiza em estrutura hierárquica com relações semânticas entre si. O oitavo capítulo (Ontologias, o predomínio dos conceitos, Moreiro González ilustra as camadas da web semântica, juntamente com as linguagens, elaboração e os tesauros frente a ontologias baseadas em normas internacionais, passo primordial para a construção de elementos semânticos inteligentes. Para o nono capítulo (Tesauros: progressão conceitual e redes semânticas o autor desenvolve uma discussão sobre os Tesauros de Descritores Verbais e Redes semânticas, salientando que a evolução das redes semânticas resulta nos mapas conceituais na ordenação das linguagens. O décimo capítulo (Topic Maps, mostra a considerável variedade de mapas conceituais

Utilities and offsites design baseline. Outside Battery Limits Facility 6000 tpd SRC-I Demonstration Plant. Volume 1

Energy Technology Data Exchange (ETDEWEB)

None

1984-05-25

As part of the overall Solvent Refined Coal (SRC-1) project baseline being prepared by International Coal Refining Company (ICRC), the RUST Engineering Company is providing necessary input for the Outside Battery Limits (OSBL) Facilities. The project baseline is comprised of: design baseline - technical definition of work; schedule baseline - detailed and management level 1 schedules; and cost baseline - estimates and cost/manpower plan. The design baseline (technical definition) for the OSBL Facilities has been completed and is presented in Volumes I, II, III, IV, V and VI. The OSBL technical definition is based on, and compatible with, the ICRC defined statement of work, design basis memorandum, master project procedures, process and mechanical design criteria, and baseline guidance documents. The design basis memorandum is included in Paragraph 1.3 of Volume I. The baseline design data is presented in 6 volumes. Volume I contains the introduction section and utility systems data through steam and feedwater. Volume II continues with utility systems data through fuel system, and contains the interconnecting systems and utility system integration information. Volume III contains the offsites data through water and waste treatment. Volume IV continues with offsites data, including site development and buildings, and contains raw materials and product handling and storage information. Volume V contains wastewater treatment and solid wastes landfill systems developed by Catalytic, Inc. to supplement the information contained in Volume III. Volume VI contains proprietary information of Resources Conservation Company related to the evaporator/crystallizer system of the wastewater treatment area.

Spent Nuclear Fuel Project technical baseline document. Fiscal year 1995: Volume 1, Baseline description

International Nuclear Information System (INIS)

Womack, J.C.; Cramond, R.; Paedon, R.J.

1995-01-01

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

International Source Book: Nuclear Fuel Cycle Research and Development Vol 1 Volume 1

Energy Technology Data Exchange (ETDEWEB)

Harmon, K. M. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Lakey, L. T. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

1983-07-01

This document starts with an overview that summarizes nuclear power policies and waste management activities for nations with significant commercial nuclear fuel cycle activities either under way or planned. A more detailed program summary is then included for each country or international agency conducting nuclear fuel cycle and waste management research and development. This first volume includes the overview and the program summaries of those countries listed alphabetically from Argentina to Italy.

The Algorithm Theoretical Basis Document for Level 1A Processing

Science.gov (United States)

Jester, Peggy L.; Hancock, David W., III

2012-01-01

The first process of the Geoscience Laser Altimeter System (GLAS) Science Algorithm Software converts the Level 0 data into the Level 1A Data Products. The Level 1A Data Products are the time ordered instrument data converted from counts to engineering units. This document defines the equations that convert the raw instrument data into engineering units. Required scale factors, bias values, and coefficients are defined in this document. Additionally, required quality assurance and browse products are defined in this document.

Education in Neurology Resident Documentation Using Payroll Simulation.

Science.gov (United States)

Liang, John W; Shanker, Vicki L

2017-04-01

Approaches for teaching neurology documentation include didactic lectures, workshops, and face-to-face meetings. Few studies have assessed their effectiveness. To improve the quality of neurology resident documentation through payroll simulation. A documentation checklist was created based on Medicaid and Medicare evaluation and management (E/M) guidelines. In the preintervention phase, neurology follow-up clinic charts were reviewed over a 16-week period by evaluators blinded to the notes' authors. Current E/M level, ideal E/M level, and financial loss were calculated by the evaluators. Ideal E/M level was defined as the highest billable level based on the documented problems, alongside a supporting history and examination. We implemented an educational intervention that consisted of a 1-hour didactic lecture, followed by e-mail feedback "paystubs" every 2 weeks detailing the number of patients seen, income generated, income loss, and areas for improvement. Follow-up charts were assessed in a similar fashion over a 16-week postintervention period. Ten of 11 residents (91%) participated. Of 214 charts that were reviewed preintervention, 114 (53%) had insufficient documentation to support the ideal E/M level, leading to a financial loss of 24% ($5,800). Inadequate documentation was seen in all 3 components: history (47%), examination (27%), and medical decision making (37%). Underdocumentation did not differ across residency years. Postintervention, underdocumentation was reduced to 14% of 273 visits ( P < .001), with a reduction in the financial loss to 6% ($1,880). Improved documentation and increased potential reimbursement was attained following a didactic lecture and a 16-week period in which individual, specific feedback to neurology residents was provided.

Large Scale Document Inversion using a Multi-threaded Computing System.

Science.gov (United States)

Jung, Sungbo; Chang, Dar-Jen; Park, Juw Won

2017-06-01

Current microprocessor architecture is moving towards multi-core/multi-threaded systems. This trend has led to a surge of interest in using multi-threaded computing devices, such as the Graphics Processing Unit (GPU), for general purpose computing. We can utilize the GPU in computation as a massive parallel coprocessor because the GPU consists of multiple cores. The GPU is also an affordable, attractive, and user-programmable commodity. Nowadays a lot of information has been flooded into the digital domain around the world. Huge volume of data, such as digital libraries, social networking services, e-commerce product data, and reviews, etc., is produced or collected every moment with dramatic growth in size. Although the inverted index is a useful data structure that can be used for full text searches or document retrieval, a large number of documents will require a tremendous amount of time to create the index. The performance of document inversion can be improved by multi-thread or multi-core GPU. Our approach is to implement a linear-time, hash-based, single program multiple data (SPMD), document inversion algorithm on the NVIDIA GPU/CUDA programming platform utilizing the huge computational power of the GPU, to develop high performance solutions for document indexing. Our proposed parallel document inversion system shows 2-3 times faster performance than a sequential system on two different test datasets from PubMed abstract and e-commerce product reviews. •Information systems➝Information retrieval • Computing methodologies➝Massively parallel and high-performance simulations.

Preliminary Safety Information Document for the Standard MHTGR. Volume 1, (includes latest Amendments)

Energy Technology Data Exchange (ETDEWEB)

None

1986-01-01

With NRC concurrence, the Licensing Plan for the Standard HTGR describes an application program consistent with 10CFR50, Appendix O to support a US Nuclear Regulatory Commission (NRC) review and design certification of an advanced Standard modular High Temperature Gas-Cooled Reactor (MHTGR) design. Consistent with the NRC's Advanced Reactor Policy, the Plan also outlines a series of preapplication activities which have as an objective the early issuance of an NRC Licensability Statement on the Standard MHTGR conceptual design. This Preliminary Safety Information Document (PSID) has been prepared as one of the submittals to the NRC by the US Department of Energy in support of preapplication activities on the Standard MHTGR. Other submittals to be provided include a Probabilistic Risk Assessment, a Regulatory Technology Development Plan, and an Emergency Planning Bases Report.

Mod-5A wind turbine generator program design report. Volume 3: Final design and system description, book 1

Science.gov (United States)

1984-01-01

The design, development and analysis of the 7.3 MW MOD-5A wind turbine generator is documented. Volume 3, book 1 describes the performance and characteristics of the MOD-5A wind turbine generator in its final configuration. Each subsystem - the rotor, drivetrain, nacelle, tower and foundation is described in detail.

Documents on Disarmament.

Science.gov (United States)

Arms Control and Disarmament Agency, Washington, DC.

This publication, latest in a series of volumes issued annually since 1960, contains primary source documents on arms control and disarmament developments during 1969. The main chronological arrangement is supplemented by both chronological and topical lists of contents. Other reference aids include a subject/author index, and lists of…

Reactor operation environmental information document

Energy Technology Data Exchange (ETDEWEB)

Haselow, J.S.; Price, V.; Stephenson, D.E.; Bledsoe, H.W.; Looney, B.B.

1989-12-01

The Savannah River Site (SRS) produces nuclear materials, primarily plutonium and tritium, to meet the requirements of the Department of Defense. These products have been formed in nuclear reactors that were built during 1950--1955 at the SRS. K, L, and P reactors are three of five reactors that have been used in the past to produce the nuclear materials. All three of these reactors discontinued operation in 1988. Currently, intense efforts are being extended to prepare these three reactors for restart in a manner that protects human health and the environment. To document that restarting the reactors will have minimal impacts to human health and the environment, a three-volume Reactor Operations Environmental Impact Document has been prepared. The document focuses on the impacts of restarting the K, L, and P reactors on both the SRS and surrounding areas. This volume discusses the geology, seismology, and subsurface hydrology. 195 refs., 101 figs., 16 tabs.

Second interim assessment of the Canadian concept for nuclear fuel waste disposal. Volume 1

International Nuclear Information System (INIS)

Wuschke, D.M.; Gillespie, P.A.; Main, D.E.

1985-07-01

The nuclear fuel waste disposal concept chosen for development and assessment in Canada involves the isolation of corrosion-resistant containers of waste in a vault located deep in plutonic rock. As the concept and the assessment tools are developed, periodic assessments are performed to permit evaluation of the methodology and provide feedback to those developing the concept. The ultimate goal of these assessments is to predict what impact the disposal system would have on man and the environment if the concept were implemented. The second assessment was performed in 1984 and is documented in the Second Interim assessment of the Canadian Concept for Nuclear Fuel Waste Disposal Volumes 1 to 4. This volume, entitled Summary, is a condensation of Volumes 2, 3 and 4. It briefly describes the Canadian nuclear fuel waste disposal concept, and the methods and results of the second interim pre-closure and post-closure assessments of that concept. 46 refs

Standard technical specifications: Combustion engineering plants. Volume 3, Revision 1: Bases (Sections 3.4--3.9)

International Nuclear Information System (INIS)

1995-04-01

This report documents the results of the combined effort of the NRC and the industry to produce improved Standard Technical Specifications (STS), Revision 1 for Combustion Engineering Plants. The changes reflected in Revision 1 resulted from the experience gained from license amendment applications to convert to these improved STS or to adopt partial improvements to existing technical specifications. This NUREG is the result of extensive public technical meetings and discussions between the Nuclear Regulatory Commission (NRC) staff and various nuclear power plant licensees, Nuclear Steam Supply System (NSSS) Owners Groups, NSSS vendors, and the Nuclear Energy Institute (NEI). The improved STS were developed based on the criteria in the Final Commission Policy Statement on Technical Specifications Improvements for Nuclear Power Reactors, dated July 22, 1993. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. Volume 1 contains the Specifications for all chapters and sections of the improved STS. Volume 2 contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1--3.3 of the improved STS Volume 3 contains the Bases for Sections 3.4--3.9 of the improved STS

Excess molar volumes and viscosities of (1,1,2,2-tetrabromoethane + 1-alkanols) at T = (293.15 and 303.15) K

International Nuclear Information System (INIS)

Al-Hayan, M.N.M.; Abdul-latif, Abdul-Haq M.

2006-01-01

Density and viscosity measurements for binary mixtures of (1,1,2,2-tetrabromoethane + 1-pentanol, or + 1-hexanol, or + 1-heptanol, or + 1-octanol, or + 1-decanol) at T = (293.15 and 303.15) K, have been conducted at atmospheric pressure. The excess molar volumes V E , have been calculated from the experimental measurements, and the results were fitted to Redlich-Kister equation. The viscosity data were correlated with the model of Grunberg and Nissan, and McAllister four-body model. The excess molar volumes of (1,1,2,2-tetrabromoethane + 1-pentanol, or + 1-haxanol, or + 1-heptanol, or + 1-octanol) had a sigmoidal shape and the values varied from negative to positive with the increase in the molar fraction of 1,1,2,2-tetrabromoethane. The remaining binary mixture of (1,1,2,2-tetrabromoethane + 1-decanol) was positive over the entire composition range. The effects of the 1-alkanol chain length as well as the temperature on the excess molar volume have been studied. The results have been qualitatively used to explain the molecular interaction between the components of these mixtures

IEEE recommended practices for seismic qualification of Class 1E equipment for nuclear power generating stations

International Nuclear Information System (INIS)

Anon.

1975-01-01

The IEEE has developed this document to provide direction for developing programs to seismically qualify Class 1E equipment for nuclear power generating stations. It supplements IEEE Std 323-1974, IEEE Standard for Qualifying Class 1E Equipment for Nuclear Power Generating Stations, which describes the basic requirements for equipment qualification. The Class 1E equipment to be qualified by produres or standards established by this document are of many forms, characteristics, and materials; therefore, the document presents many acceptable methods with the intent of permitting the user to make a judicious selection from among the various options. In making such a selection, the user should choose those that best meet a particular equipment's requirements. Further, in using this document as a specification for the purchase of equipment, the many options should also be recognized and the document invoked accordingly. It is recommended that the need for specific standards for the seismic qualifiction of particular kinds of equipment be evaluated by those responsible for such documents and that consideration be given to the application of particular methods from these documents which are most suitable

Reactor operation environmental information document

Energy Technology Data Exchange (ETDEWEB)

Bauer, L.R.; Hayes, D.W.; Hunter, C.H.; Marter, W.L.; Moyer, R.A.

1989-12-01

This volume is a reactor operation environmental information document for the Savannah River Plant. Topics include meteorology, surface hydrology, transport, environmental impacts, and radiation effects. 48 figs., 56 tabs. (KD)

Broadband Fan Noise Prediction System for Turbofan Engines. Volume 1; Setup_BFaNS User's Manual and Developer's Guide

Science.gov (United States)

Morin, Bruce L.

2010-01-01

Pratt & Whitney has developed a Broadband Fan Noise Prediction System (BFaNS) for turbofan engines. This system computes the noise generated by turbulence impinging on the leading edges of the fan and fan exit guide vane, and noise generated by boundary-layer turbulence passing over the fan trailing edge. BFaNS has been validated on three fan rigs that were tested during the NASA Advanced Subsonic Technology Program (AST). The predicted noise spectra agreed well with measured data. The predicted effects of fan speed, vane count, and vane sweep also agreed well with measurements. The noise prediction system consists of two computer programs: Setup_BFaNS and BFaNS. Setup_BFaNS converts user-specified geometry and flow-field information into a BFaNS input file. From this input file, BFaNS computes the inlet and aft broadband sound power spectra generated by the fan and FEGV. The output file from BFaNS contains the inlet, aft and total sound power spectra from each noise source. This report is the first volume of a three-volume set documenting the Broadband Fan Noise Prediction System: Volume 1: Setup_BFaNS User s Manual and Developer s Guide; Volume 2: BFaNS User's Manual and Developer s Guide; and Volume 3: Validation and Test Cases. The present volume begins with an overview of the Broadband Fan Noise Prediction System, followed by step-by-step instructions for installing and running Setup_BFaNS. It concludes with technical documentation of the Setup_BFaNS computer program.

FY 1996 solid waste integrated life-cycle forecast characteristics summary. Volumes 1 and 2

Energy Technology Data Exchange (ETDEWEB)

Templeton, K.J.

1996-05-23

For the past six years, a waste volume forecast has been collected annually from onsite and offsite generators that currently ship or are planning to ship solid waste to the Westinghouse Hanford Company`s Central Waste Complex (CWC). This document provides a description of the physical waste forms, hazardous waste constituents, and radionuclides of the waste expected to be shipped to the CWC from 1996 through the remaining life cycle of the Hanford Site (assumed to extend to 2070). In previous years, forecast data has been reported for a 30-year time period; however, the life-cycle approach was adopted this year to maintain consistency with FY 1996 Multi-Year Program Plans. This document is a companion report to two previous reports: the more detailed report on waste volumes, WHC-EP-0900, FY1996 Solid Waste Integrated Life-Cycle Forecast Volume Summary and the report on expected containers, WHC-EP-0903, FY1996 Solid Waste Integrated Life-Cycle Forecast Container Summary. All three documents are based on data gathered during the FY 1995 data call and verified as of January, 1996. These documents are intended to be used in conjunction with other solid waste planning documents as references for short and long-term planning of the WHC Solid Waste Disposal Division`s treatment, storage, and disposal activities over the next several decades. This document focuses on two main characteristics: the physical waste forms and hazardous waste constituents of low-level mixed waste (LLMW) and transuranic waste (both non-mixed and mixed) (TRU(M)). The major generators for each waste category and waste characteristic are also discussed. The characteristics of low-level waste (LLW) are described in Appendix A. In addition, information on radionuclides present in the waste is provided in Appendix B. The FY 1996 forecast data indicate that about 100,900 cubic meters of LLMW and TRU(M) waste is expected to be received at the CWC over the remaining life cycle of the site. Based on

FY 1996 solid waste integrated life-cycle forecast characteristics summary. Volumes 1 and 2

International Nuclear Information System (INIS)

Templeton, K.J.

1996-01-01

For the past six years, a waste volume forecast has been collected annually from onsite and offsite generators that currently ship or are planning to ship solid waste to the Westinghouse Hanford Company's Central Waste Complex (CWC). This document provides a description of the physical waste forms, hazardous waste constituents, and radionuclides of the waste expected to be shipped to the CWC from 1996 through the remaining life cycle of the Hanford Site (assumed to extend to 2070). In previous years, forecast data has been reported for a 30-year time period; however, the life-cycle approach was adopted this year to maintain consistency with FY 1996 Multi-Year Program Plans. This document is a companion report to two previous reports: the more detailed report on waste volumes, WHC-EP-0900, FY1996 Solid Waste Integrated Life-Cycle Forecast Volume Summary and the report on expected containers, WHC-EP-0903, FY1996 Solid Waste Integrated Life-Cycle Forecast Container Summary. All three documents are based on data gathered during the FY 1995 data call and verified as of January, 1996. These documents are intended to be used in conjunction with other solid waste planning documents as references for short and long-term planning of the WHC Solid Waste Disposal Division's treatment, storage, and disposal activities over the next several decades. This document focuses on two main characteristics: the physical waste forms and hazardous waste constituents of low-level mixed waste (LLMW) and transuranic waste (both non-mixed and mixed) (TRU(M)). The major generators for each waste category and waste characteristic are also discussed. The characteristics of low-level waste (LLW) are described in Appendix A. In addition, information on radionuclides present in the waste is provided in Appendix B. The FY 1996 forecast data indicate that about 100,900 cubic meters of LLMW and TRU(M) waste is expected to be received at the CWC over the remaining life cycle of the site. Based on

Ultra-sonografia de características lineares e estimativas do volume de rins de cães Ultrasonographic measurement of linear characteristics and renal volumetry in dogs

Directory of Open Access Journals (Sweden)

K.M.O.R. Sampaio

2002-06-01

Full Text Available Obtiveram-se as medidas lineares de rins de cães adultos, clinicamente normais, por meio da ultra-sonografia, e estimou-se o volume dos rins de 35 cães (18 fêmeas e 17 machos sem raça definida e com idade entre dois e seis anos. Os animais foram divididos em três grupos de acordo com o peso corporal (3,1 a 10,0 kg; 10,1 a 20,0 kg e 20,1 a 45,0 kg. Os planos de secção sagital, dorsal e transversal foram utilizados para obtenção das medidas lineares de comprimento (C, largura (L e espessura (E. O volume renal foi calculado a partir das medidas lineares utilizando-se a fórmula para o volume de um elipsóide. Os valores médios encontrados para os três grupos foram, respectivamente: comprimento (4,73; 6,09 e 7,13cm, largura (2,81; 3,44 e 3,95cm, espessura (2,43; 3,00 e 3,58cm e volume (17,98; 33,36 e 53,81cm³. As dimensões dos rins esquerdo e direito e de machos e fêmeas foram equivalentes. Observaram-se correlações positivas entre todas as medidas renais e peso corporal.This work aimed to measure by ultrasonography the length, width and depth and to estimate the volume of kidneys of normal adult dogs. Thirty five dogs (18 females and 17 males of mixed breeds, aging from two to six years, were used. The animals were separated in three groups according to their body weights (3.1 to 10.0 kg; 10.1 to 20.0 kg and 20.1 to 45 kg. Sagittal, dorsal and transverse plans of section were used to obtain measures of length, width and depth. The kidney volume was estimated from these measures. Mean values according to the groups were, respectively: 4.73; 6.09 and 7.13cm for length; 2.81; 3.44 and 3.95cm for width; 2.43; 3.00 and 3.58cm for depth; and the estimated volumes were 17.98; 33.36 and 53.81cm³. The length, width, depth and volume of the left and right kidneys were similar, and no difference between male and female was found for these traits. Body weight of animals was positively correlated with all the kidney traits.

VANDAL user guide. V. 1.1

International Nuclear Information System (INIS)

Unsworth, M.D.

1989-02-01

This document forms Volume 1.1 of the VANDAL User Guide and is intended to provide all the information necessary to define and run a case study. Information is given on the data to be specified, on the structure of the input data files and on how to execute the system. There are three related volumes to this, they are: Volume 1.2 - Input and Execution Appendices; Volume 2.1 - Ouput and Error Messages; and Volume 2.2 - PRA Output Analysis. (author)

Chemical Safety Vulnerability Working Group report. Volume 1

Energy Technology Data Exchange (ETDEWEB)

1994-09-01

The Chemical Safety Vulnerability (CSV) Working Group was established to identify adverse conditions involving hazardous chemicals at DOE facilities that might result in fires or explosions, release of hazardous chemicals to the environment, or exposure of workers or the public to chemicals. A CSV Review was conducted in 148 facilities at 29 sites. Eight generic vulnerabilities were documented related to: abandoned chemicals and chemical residuals; past chemical spills and ground releases; characterization of legacy chemicals and wastes; disposition of legacy chemicals; storage facilities and conditions; condition of facilities and support systems; unanalyzed and unaddressed hazards; and inventory control and tracking. Weaknesses in five programmatic areas were also identified related to: management commitment and planning; chemical safety management programs; aging facilities that continue to operate; nonoperating facilities awaiting deactivation; and resource allocations. Volume 1 contains the Executive summary; Introduction; Summary of vulnerabilities; Management systems weaknesses; Commendable practices; Summary of management response plan; Conclusions; and a Glossary of chemical terms.

Chemical Safety Vulnerability Working Group report. Volume 1

International Nuclear Information System (INIS)

1994-09-01

The Chemical Safety Vulnerability (CSV) Working Group was established to identify adverse conditions involving hazardous chemicals at DOE facilities that might result in fires or explosions, release of hazardous chemicals to the environment, or exposure of workers or the public to chemicals. A CSV Review was conducted in 148 facilities at 29 sites. Eight generic vulnerabilities were documented related to: abandoned chemicals and chemical residuals; past chemical spills and ground releases; characterization of legacy chemicals and wastes; disposition of legacy chemicals; storage facilities and conditions; condition of facilities and support systems; unanalyzed and unaddressed hazards; and inventory control and tracking. Weaknesses in five programmatic areas were also identified related to: management commitment and planning; chemical safety management programs; aging facilities that continue to operate; nonoperating facilities awaiting deactivation; and resource allocations. Volume 1 contains the Executive summary; Introduction; Summary of vulnerabilities; Management systems weaknesses; Commendable practices; Summary of management response plan; Conclusions; and a Glossary of chemical terms

Densidade global de solos medida com anel volumétrico e por cachimbagem de terra fina seca ao ar Bulk density of soil samples measured in the field and through volume measurement of sieved soil

Directory of Open Access Journals (Sweden)

Bernardo Van Raij

1989-01-01

Full Text Available Em laboratórios de rotina de fertilidade do solo, a medida de quantidade de terra para análise é feita em volume, mediante utensílios chamados "cachimbos", que permitem medir volumes de terra. Admite-se que essas medidas reflitam a quantidade de terra existente em volume de solo similar em condições de campo. Essa hipótese foi avaliada neste trabalho, por doze amostras dos horizontes A e B de seis perfis de solos. A densidade em condições de campo foi avaliada por anel volumétrico e, no laboratório, por meio de cachimbos de diversos tamanhos. A cachimbagem revelou-se bastante precisa. Os valores de densidade global calculada variaram de 0,63 a 1,46g/cm³ para medidas de campo e de 0,91 a 1,33g/cm³ para medidas com cachimbos. Portanto, a medida de laboratório subestimou valores altos de densidade e deu resultados mais elevados para valores de campo mais baixos.In soil testing laboratories, soil samples for chemical analysis are usually measured by volume, using appropriate measuring spoons. It is tacitly assumed that such measurements would reflect amounts of soil existing in the same volume under field conditions. This hypothesis was tested, using 12 soil samples of the A and B horizons of six soil profiles. Bulk density in the field was evaluated through a cylindrical metal sampler of 50cm³ and in the laboratory using spoons of different sizes. Measurements of soil volumes by spoons were quite precise. Values of bulk density varied between 0.63 and 1.46g/cm³ for field measurements and between 0.91 and 1.33g/cm³ for laboratory measurements with spoons. Thus, laboratory measurements overestimated lower values of bulk densities and underestimated the higher ones.

Assessment of effectiveness of geologic isolation systems. CIRMIS data system. Volume 1. Initialization, operation, and documentation

International Nuclear Information System (INIS)

Friedrichs, D.R.

1980-01-01

The Assessment of Effectiveness of Geologic Isolation Systems (AEGIS) Program is developing and applying the methodology for assessing the far-field, long-term post-closure safety of deep geologic nuclear waste repositories. AEGIS is being performed by Pacific Northwest Laboratory (PNL) under contract with the Office of Nuclear Waste Isolation (ONWI) for the Department of Energy (DOE). One task within AEGIS is the development of methodology for analysis of the consequences (water pathway) from loss of repository containment as defined by various release scenarios. The various input parameters required in the analysis are compiled in data systems. The data are organized and prepared by various input subroutines for use by the hydrologic and transport codes. The hydrologic models simulate the groundwater flow systems and provide water flow directions, rates, and velocities as inputs to the transport models. Outputs from the transport models are basically graphs of radionuclide concentration in the groundwater plotted against time. After dilution in the receiving surface-water body (e.g., lake, river, bay), these data are the input source terms for the dose models, if dose assessments are required. The dose models calculate radiation dose to individuals and populations. CIRMIS (Comprehensive Information Retrieval and Model Input Sequence) Data System, a storage and retrieval system for model input and output data, including graphical interpretation and display is described. This is the first of four volumes of the description of the CIRMIS Data System

Forecasted electric power demands for the Delmarva Power and Light Company. Volume 1 and Volume 2. Documentation manual

International Nuclear Information System (INIS)

Estomin, S.L.; Beach, J.E.

1990-10-01

The two-volume report presents the results of an econometric forecast of peak load and electric power demands for the Delmarva Power and Light Company (DP ampersand L) through the year 2008. Separate sets of models were estimated for the three jurisdictions served by DP ampersand L: Delaware, Maryland and Virginia. For both Delaware and Maryland, econometric equations were estimated for residential, commercial, industrial, and streetlighting sales. For Virginia, equations were estimated for residential, commercial plus industrial, and streetlighting sales; separate industrial and commercial equations were not estimated for Virginia due to the relatively small size of DP ampersand L's Virginia Industrial load. Wholesale sales were econometrically estimated for the DP ampersand L system as a whole. In addition to the energy sales models, an econometric model of annual (summer) peak demand was estimated for the Company

Proposed Standards for Variable Harmonization Documentation and Referencing: A Case Study Using QuickCharmStats 1.1

Science.gov (United States)

Winters, Kristi; Netscher, Sebastian

2016-01-01

Comparative statistical analyses often require data harmonization, yet the social sciences do not have clear operationalization frameworks that guide and homogenize variable coding decisions across disciplines. When faced with a need to harmonize variables researchers often look for guidance from various international studies that employ output harmonization, such as the Comparative Survey of Election Studies, which offer recoding structures for the same variable (e.g. marital status). More problematically there are no agreed documentation standards or journal requirements for reporting variable harmonization to facilitate a transparent replication process. We propose a conceptual and data-driven digital solution that creates harmonization documentation standards for publication and scholarly citation: QuickCharmStats 1.1. It is free and open-source software that allows for the organizing, documenting and publishing of data harmonization projects. QuickCharmStats starts at the conceptual level and its workflow ends with a variable recording syntax. It is therefore flexible enough to reflect a variety of theoretical justifications for variable harmonization. Using the socio-demographic variable ‘marital status’, we demonstrate how the CharmStats workflow collates metadata while being guided by the scientific standards of transparency and replication. It encourages researchers to publish their harmonization work by providing researchers who complete the peer review process a permanent identifier. Those who contribute original data harmonization work to their discipline can now be credited through citations. Finally, we propose peer-review standards for harmonization documentation, describe a route to online publishing, and provide a referencing format to cite harmonization projects. Although CharmStats products are designed for social scientists our adherence to the scientific method ensures our products can be used by researchers across the sciences. PMID

Large Scale Document Inversion using a Multi-threaded Computing System

Science.gov (United States)

Jung, Sungbo; Chang, Dar-Jen; Park, Juw Won

2018-01-01

Current microprocessor architecture is moving towards multi-core/multi-threaded systems. This trend has led to a surge of interest in using multi-threaded computing devices, such as the Graphics Processing Unit (GPU), for general purpose computing. We can utilize the GPU in computation as a massive parallel coprocessor because the GPU consists of multiple cores. The GPU is also an affordable, attractive, and user-programmable commodity. Nowadays a lot of information has been flooded into the digital domain around the world. Huge volume of data, such as digital libraries, social networking services, e-commerce product data, and reviews, etc., is produced or collected every moment with dramatic growth in size. Although the inverted index is a useful data structure that can be used for full text searches or document retrieval, a large number of documents will require a tremendous amount of time to create the index. The performance of document inversion can be improved by multi-thread or multi-core GPU. Our approach is to implement a linear-time, hash-based, single program multiple data (SPMD), document inversion algorithm on the NVIDIA GPU/CUDA programming platform utilizing the huge computational power of the GPU, to develop high performance solutions for document indexing. Our proposed parallel document inversion system shows 2-3 times faster performance than a sequential system on two different test datasets from PubMed abstract and e-commerce product reviews. CCS Concepts •Information systems➝Information retrieval • Computing methodologies➝Massively parallel and high-performance simulations.

Volume 9 Number 1

African Journals Online (AJOL)

OLUWOLE

Agro-Science Journal of Tropical Agriculture, Food, Environment and Extension. Volume 9 Number 1 ... of persistent dumping of cheap subsidized food imports from developed ... independence of the inefficiency effects in the two estimation ...

Altura da lâmina, tempo e volume de enchimento de um equipamento de irrigação por pavio e determinação da uniformidade de distribuição de água em substratos Water depth, filling time and volume of wick irrigation equipment and determination of water distribution uniformity in substrates

Directory of Open Access Journals (Sweden)

Rhuanito Soranz Ferrarezi

2012-01-01

Full Text Available Os objetivos deste experimento foram realizar a avaliação da altura da lâmina de água, do tempo e volume de enchimento de um equipamento de irrigação por pavio usando calhas autocompensadoras e determinar a uniformidade de distribuição de água (UDA nesse equipamento utilizando substratos orgânicos comerciais (casca de pinus/CP e fibra de coco/FC. Dois módulos experimentais foram montados em delineamento experimental inteiramente casualizado com cinco repetições. Verificou-se grande variação das medidas de altura da lâmina de água (1,6 a 4,0 cm, mesmo com o equipamento nivelado. O tempo médio de enchimento foi de 6h22min para o Módulo 1 com CP e de 3h45min para o Módulo 2 com FC. O volume de enchimento foi variável, observando-se que as calhas das extremidades (n.° 1 e 5 apresentaram os menores volumes no Módulo 1, e as calhas do início (n.° 1 e 2 no Módulo 2. No Módulo 1, a umidade volumétrica (θ variou de 42% a 94%, e no Módulo 2, de 24% a 72%, com pontos isolados de secamento e/ou encharcamento. A altura da lâmina de água, o tempo e o volume de enchimento das calhas foram desuniformes nos dois módulos experimentais e nas cinco calhas autocompensadoras, indicando imperfeições no equipamento. A distribuição de água foi variável nos substratos em razão de suas características físico-hídricas e também da altura da lâmina de água nas calhas, apresentando maior umidade e uniformidade de distribuição de água na casca de pinus do que na fibra de coco.The aims of this study were to evaluate the water depth, filling time and volume in a wick irrigation equipment using auto compensating gutters and to determine the water distribution uniformity (WDU in these equipments filled with organic commercial substrates (pine bark/PB and coconut coir/CC. We assembled two experimental modules in a completely randomized design with five replications. There was variation in water depth measurements (1.6 to 4.0 cm, even

Excess volumes and speeds of sound of mixtures of 1,2-dibromoethane with chlorinated ethanes and ethenes at 303.15 K

International Nuclear Information System (INIS)

Renuka Kumari, S.; Venkateswarlu, P.; Prabhakar, G.

2005-01-01

Excess volumes V E , speeds of sound u and isentropic compressibilities K s at 303.15 K are reported for five binary mixtures containing 1,2-dibromoethane as common component and 1,2-dichloroethane, 1,1,1-trichloroethane, 1,1,2,2-tetrachloroethane, trichloroethene and tetrachlorothene as non-common component. The excess volume data suggests that increase in the number of chlorine atoms on ethane decreases V E , while when on ethene increases the V E . Further, the data suggest that the molecular interactions are stronger in + chlorinated ethanes than in + chlorinated ethenes

Estimating the apparent culm volume for Bambusa oldhamii and Bambusa vulgaris = Estimação do volume aparente de colmos de Bambusa oldhamii e Bambusa vulgaris.

Directory of Open Access Journals (Sweden)

Carlos Roberto Sanquetta

2015-06-01

Full Text Available There is great potential in Brazil for the cultivation of indigenous and introduced species of bamboo. However, there is little scientific research on the biometric aspects of these plants, and this may limit their management and use. The aim of this article therefore, is to present options for estimating the total apparent volume of two species of the genus Bambusa: B. oldhami i and B. vulgaris, planted in an experiment set up in December of 2008 in Pinhais, in the state of Paraná, Brazil (PR. Twenty-four stems were cubed at 50 months using the Smalian method. Diameter at breast height (DAP ranged from 1.8 to 4.5 cm, and height from 3 to 7 m. The options being tested for estimating the apparent volume of the culms were: 1 Schumacher-Hall conventional volume model; 2 fifth-degree polynomial taper model; 3 fractional-power polynomial taper model; and 4 form factor. The options were examined statistically relative to the observed values for the target variable, for each species and for both species as a set. It was found that the four options give precise estimates. There was no statistical difference between the four approaches and the control (observed values by paired t-test. The residuals (estimated x observed values are shown to be homoscedastic with a maximum width of from -30 to 30%. It was concluded that the four methods under test can be used to estimate the target variable under the conditions of the experimental material. The Schumacher-Hall model represents the best compromise between simplicity and accuracy = O Brasil possui grande potencial de cultivo de espécies autóctones e introduzidas de bambu. Contudo, são poucos os trabalhos científicos que versam sobre aspectos biométricos dessas plantas, o que pode representar uma limitação para seu manejo e utilização. Assim, objetivou-se com esse artigo apresentar opções para estimativa do volume total aparente de duas espécies do gênero Bambusa: B. oldhamii e B. vulgaris

Standard technical specifications: Babcock and Wilcox plants. Volume 3, Revision 1: Bases (Sections 3.4--3.9)

International Nuclear Information System (INIS)

1995-04-01

This report documents the results of the combined effort of the NRC and the industry to produce improved Standard Technical Specifications (STS), Revision 1 for Babcock and Wilcox Plants. The changes reflected in Revision 1 resulted from the experience gained from license amendment applications to convert to these improved STS or to adopt partial improvements to existing technical specifications. This NUREG is the result of extensive public technical meetings and discussions between the Nuclear Regulatory Commission (NRC) staff and various nuclear power plant licensees, Nuclear Steam Supply System (NSSS) Owners Groups, NSSS vendors, and the Nuclear Energy Institute (NEI). The improved STS were developed based on the criteria in the Final Commission Policy Statement on Technical Specifications Improvements for Nuclear Power Reactors, dated July 22, 1993. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. Volume 1 contains the Specifications for all chapters and sections of the improved STS. Volume 2 contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1--3.3 of the improved STS. Volume 3 contains the Bases for Sections 3.4--3.9 of the improved STS

Petroleum supply annual 1998: Volume 1

Energy Technology Data Exchange (ETDEWEB)

NONE

1999-06-01

The ``Petroleum Supply Annual`` (PSA) contains information on the supply and disposition of crude oil and petroleum products. The publication reflects data that were collected from the petroleum industry during 1998 through annual and monthly surveys. The PSA is divided into two volumes. This first volume contains three sections: Summary Statistics, Detailed Statistics, and Refinery Statistics; each with final annual data. The second volume contains final statistics for each month of 1998, and replaces data previously published in the PSA. The tables in Volumes 1 and 2 are similarly numbered to facilitate comparison between them. 16 figs., 59 tabs.

Petroleum supply annual, 1997. Volume 1

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-06-01

The Petroleum Supply Annual (PSA) contains information on the supply and disposition of crude oil and petroleum products. The publication reflects data that were collected from the petroleum industry during 1997 through annual and monthly surveys. The PSA is divided into two volumes. This first volume contains three sections: Summary Statistics, Detailed Statistics, and Refinery Statistics; each with final annual data. The second volume contains final statistics for each month of 1997, and replaces data previously published in the Petroleum Supply Monthly (PSM). The tables in Volumes 1 and 2 are similarly numbered to facilitate comparison between them. 16 figs., 48 tabs.

Petroleum supply annual 1992: Volume 1

International Nuclear Information System (INIS)

1993-01-01

The Petroleum Supply Annual (PSA) contains information on the supply and disposition of crude oil and petroleum products. The publication reflects data that were collected from the petroleum industry during 1992 through annual and monthly surveys. The PSA is divided into two volumes. This first volume contains four sections: Summary Statistics, Detailed Statistics, Refinery Capacity and Oxygenate Capacity each with final annual data. The second volume contains final statistics for each month of 1992, and replaces data previously published in the Petroleum Supply Monthly (PSM). The tables in Volumes 1 and 2 are similarly numbered to facilitate comparison between them

Petroleum supply annual 1998: Volume 1

International Nuclear Information System (INIS)

1999-06-01

The ''Petroleum Supply Annual'' (PSA) contains information on the supply and disposition of crude oil and petroleum products. The publication reflects data that were collected from the petroleum industry during 1998 through annual and monthly surveys. The PSA is divided into two volumes. This first volume contains three sections: Summary Statistics, Detailed Statistics, and Refinery Statistics; each with final annual data. The second volume contains final statistics for each month of 1998, and replaces data previously published in the PSA. The tables in Volumes 1 and 2 are similarly numbered to facilitate comparison between them. 16 figs., 59 tabs

Petroleum supply annual, 1997. Volume 1

International Nuclear Information System (INIS)

1998-06-01

The Petroleum Supply Annual (PSA) contains information on the supply and disposition of crude oil and petroleum products. The publication reflects data that were collected from the petroleum industry during 1997 through annual and monthly surveys. The PSA is divided into two volumes. This first volume contains three sections: Summary Statistics, Detailed Statistics, and Refinery Statistics; each with final annual data. The second volume contains final statistics for each month of 1997, and replaces data previously published in the Petroleum Supply Monthly (PSM). The tables in Volumes 1 and 2 are similarly numbered to facilitate comparison between them. 16 figs., 48 tabs

Ajuste do modelo de Schumacher e Hall e aplicação de redes neurais artificiais para estimar volume de árvores de eucalipto Adjustment of the Schumacher and Hall model and application of artificial neural networks to estimate volume of eucalypt trees

Directory of Open Access Journals (Sweden)

Mayra Luiza Marques da Silva

2009-12-01

Full Text Available Objetivou-se, neste trabalho, avaliar o ajuste do modelo volumétrico de Schumacher e Hall por diferentes algoritmos, bem como a aplicação de redes neurais artificiais para estimação do volume de madeira de eucalipto em função do diâmetro a 1,30 m do solo (DAP, da altura total (Ht e do clone. Foram utilizadas 21 cubagens de povoamentos de clones de eucalipto com DAP variando de 4,5 a 28,3 cm e altura total de 6,6 a 33,8 m, num total de 862 árvores. O modelo volumétrico de Schumacher e Hall foi ajustado nas formas linear e não linear, com os seguintes algoritmos: Gauss-Newton, Quasi-Newton, Levenberg-Marquardt, Simplex, Hooke-Jeeves Pattern, Rosenbrock Pattern, Simplex, Hooke-Jeeves e Rosenbrock, utilizado simultaneamente com o método Quasi-Newton e com o princípio da Máxima Verossimilhança. Diferentes arquiteturas e modelos (Multilayer Perceptron MLP e Radial Basis Function RBF de redes neurais artificiais foram testados, sendo selecionadas as redes que melhor representaram os dados. As estimativas dos volumes foram avaliadas por gráficos de volume estimado em função do volume observado e pelo teste estatístico L&O. Assim, conclui-se que o ajuste do modelo de Schumacher e Hall pode ser usado na sua forma linear, com boa representatividade e sem apresentar tendenciosidade; os algoritmos Gauss-Newton, Quasi-Newton e Levenberg-Marquardt mostraram-se eficientes para o ajuste do modelo volumétrico de Schumacher e Hall, e as redes neurais artificiais apresentaram boa adequação ao problema, sendo elas altamente recomendadas para realizar prognose da produção de florestas plantadas.This research aimed at evaluating the adjustment of Schumacher and Hall volumetric model by different algorithms and the application of artificial neural networks to estimate the volume of wood of eucalyptus according to the diameter at breast height (DBH, total height (Ht of the clone. For such, 21 scalings of stands of eucalyptus clones were used with

Volume-Dependent Overestimation of Spontaneous Intracerebral Hematoma Volume by the ABC/2 Formula

International Nuclear Information System (INIS)

Chih-Wei Wang; Chun-Jung Juan; Hsian-He Hsu; Hua-Shan Liu; Cheng-Yu Chen; Chun-Jen Hsueh; Hung-Wen Kao; Guo-Shu Huang; Yi-Jui Liu; Chung-Ping Lo

2009-01-01

Background: Although the ABC/2 formula has been widely used to estimate the volume of intracerebral hematoma (ICH), the formula tends to overestimate hematoma volume. The volume-related imprecision of the ABC/2 formula has not been documented quantitatively. Purpose: To investigate the volume-dependent overestimation of the ABC/2 formula by comparing it with computer-assisted volumetric analysis (CAVA). Material and Methods: Forty patients who had suffered spontaneous ICH and who had undergone non-enhanced brain computed tomography scans were enrolled in this study. The ICH volume was estimated based on the ABC/2 formula and also calculated by CAVA. Based on the ICH volume calculated by the CAVA method, the patients were divided into three groups: group 1 consisted of 17 patients with an ICH volume of less than 20 ml; group 2 comprised 13 patients with an ICH volume of 20 to 40 ml; and group 3 was composed of 10 patients with an ICH volume larger than 40 ml. Results: The mean estimated hematoma volume was 43.6 ml when using the ABC/2 formula, compared with 33.8 ml when using the CAVA method. The mean estimated difference was 1.3 ml, 4.4 ml, and 31.4 ml for groups 1, 2, and 3, respectively, corresponding to an estimation error of 9.9%, 16.7%, and 37.1% by the ABC/2 formula (P<0.05). Conclusion: The ABC/2 formula significantly overestimates the volume of ICH. A positive association between the estimation error and the volume of ICH is demonstrated

Protective Effect of Human Leukocyte Antigen (HLA Allele DRB1*13:02 on Age-Related Brain Gray Matter Volume Reduction in Healthy Women

Directory of Open Access Journals (Sweden)

Lisa M. James

2018-03-01

Full Text Available Background: Reduction of brain volume (brain atrophy during healthy brain aging is well documented and dependent on genetic, lifestyle and environmental factors. Here we investigated the possible dependence of brain gray matter volume reduction in the absence of the Human Leukocyte Antigen (HLA allele DRB1*13:02 which prevents brain atrophy in Gulf War Illness (James et al., 2017. Methods: Seventy-one cognitively healthy women (32–69 years old underwent a structural Magnetic Resonance Imaging (sMRI scan to measure the volumes of total gray matter, cerebrocortical gray matter, and subcortical gray matter. Participants were assigned to two groups, depending on whether they lacked the DRB1*13:02 allele (No DRB1*13:02 group, N = 60 or carried the DRB1*13:02 allele (N = 11. We assessed the change of brain gray matter volume with age in each group by performing a linear regression where the brain volume (adjusted for total intracranial volume was the dependent variable and age was the independent variable. Findings: In the No DRB1*13:02 group, the volumes of total gray matter, cerebrocortical gray matter, and subcortical gray matter were reduced highly significantly. In contrast, none of these volumes showed a statistically significant reduction with age in the DRB1*13:02 group. Interpretation: These findings document the protective effect of DRB1*13:02 on age-dependent reduction of brain gray matter in healthy individuals. Since the role of this allele is to connect to matching epitopes of external antigens for the subsequent production of antibodies and elimination of the offending antigen, we hypothesize that its protective effect may be due to the successful elimination of such antigens to which we are exposed during the lifespan, antigens that otherwise would persist causing gradual brain atrophy. In addition, we consider a possible beneficial role of DRB1*13:02 attributed to its binding to cathepsin S, a known harmful substance in brain

Equações de volume e de taper para quantificar multiprodutos da madeira em Floresta Atlântica Volume and taper equations for wood multiproducts quantification in Floresta Atlantica-Brazil

Directory of Open Access Journals (Sweden)

José Franklin Chichorro

2003-12-01

Full Text Available Este estudo foi conduzido com o objetivo de ajustar uma equação de volume, a partir do modelo logaritmizado de Schumacher & Hall (1933, para estimar o volume comercial, e uma equação de afilamento (taper, a partir do modelo de Demaerschalk (1972, para estimar a quantidade de multiprodutos de madeira de espécies da Floresta Atlântica. Os dados foram coletados na Gleba C da Floresta Nacional do Rio Preto - IBAMA, no município de Conceição da Barra-ES. Foram mensuradas 165 árvores em pé, subdivididas em dez classes de diâmetro, com qualidade de fuste QF1 e pertencentes às espécies com maior VI e, ou, espécies de valor comercial. Essas árvores reuniram 62 espécies e 38 famílias. A equação de volume ajustou-se bem aos dados, com 2 igual a 0,9815 e resíduos normalmente distribuídos. A equação de taper também ajustou-se bem aos dados, com 2 igual a 0,9346 e distribuição gráfica dos resíduos normal. Pelo teste F (Graybill, 1976, constatou-se que houve igualdade entre os diâmetros observados e os diâmetros estimados pela equação de taper. A partir de transformações algébricas da equação de taper, foram estimados a altura para um determinado diâmetro superior d e o volume do tronco ou de parte dele. Em seguida, podem ser estimados o número de toras e o respectivo volume, em função do comprimento da tora, do diâmetro superior d mínimo e do uso desejado, o que permite avaliar a árvore em pé.This study was carried out to estimate a volume equation from a logarithmic model of Schumacher & Hall (1933 for comercial volume determination and a taper equation from the model of Demaerschalk (1972, to estimate wood multiproducts yield in Floresta Atlântica. Data were collected in Gleba C (C Glebe, with 289.5 hectares, owned by Floresta Nacional do Rio Preto (Rio Preto National Forest, under the administration of IBAMA, located in Conceição da Barra - Espírito Santo, Brazil. A total of 165 standing trees were measured

Altura da lâmina, tempo e volume de enchimento de um equipamento de irrigação por pavio e determinação da uniformidade de distribuição de água em substratos

Directory of Open Access Journals (Sweden)

Rhuanito Soranz Ferrarezi

2012-01-01

Full Text Available Os objetivos deste experimento foram realizar a avaliação da altura da lâmina de água, do tempo e volume de enchimento de um equipamento de irrigação por pavio usando calhas autocompensadoras e determinar a uniformidade de distribuição de água (UDA nesse equipamento utilizando substratos orgânicos comerciais (casca de pinus/CP e fibra de coco/FC. Dois módulos experimentais foram montados em delineamento experimental inteiramente casualizado com cinco repetições. Verificou-se grande variação das medidas de altura da lâmina de água (1,6 a 4,0 cm, mesmo com o equipamento nivelado. O tempo médio de enchimento foi de 6h22min para o Módulo 1 com CP e de 3h45min para o Módulo 2 com FC. O volume de enchimento foi variável, observando-se que as calhas das extremidades (n.° 1 e 5 apresentaram os menores volumes no Módulo 1, e as calhas do início (n.° 1 e 2 no Módulo 2. No Módulo 1, a umidade volumétrica (θ variou de 42% a 94%, e no Módulo 2, de 24% a 72%, com pontos isolados de secamento e/ou encharcamento. A altura da lâmina de água, o tempo e o volume de enchimento das calhas foram desuniformes nos dois módulos experimentais e nas cinco calhas autocompensadoras, indicando imperfeições no equipamento. A distribuição de água foi variável nos substratos em razão de suas características físico-hídricas e também da altura da lâmina de água nas calhas, apresentando maior umidade e uniformidade de distribuição de água na casca de pinus do que na fibra de coco.

E-nursing documentation as a tool for quality assurance.

Science.gov (United States)

Rajkovic, Vladislav; Sustersic, Olga; Rajkovic, Uros

2006-01-01

The article presents the results of a project with which we describe the reengineering of nursing documentation. Documentation in nursing is an efficient tool for ensuring quality health care and consequently quality patient treatment along the whole clinical path. We have taken into account the nursing process and patient treatment based on Henderson theoretical model of nursing that consists of 14 basic living activities. The model of new documentation enables tracing, transparency, selectivity, monitoring and analyses. All these factors lead to improvements of a health system as well as to improved safety of patients and members of nursing teams. Thus the documentation was developed for three health care segments: secondary and tertiary level, dispensaries and community health care. The new quality introduced to the documentation process by information and communication technology is presented by a database model and a software prototype for managing documentation.

Enterprise Document Management

Data.gov (United States)

US Agency for International Development — The function of the operation is to provide e-Signature and document management support for Acquisition and Assisitance (A&A) documents including vouchers in...

The Hb E (HBB: c.79G>A), Mean Corpuscular Volume, Mean Corpuscular Hemoglobin Cutoff Points in Double Heterozygous Hb E/- -SEA α-Thalassemia-1 Carriers are Dependent on Hemoglobin Levels.

Science.gov (United States)

Leckngam, Prapapun; Limweeraprajak, Ektong; Kiewkarnkha, Tiemjan; Tatu, Thanusak

2017-01-01

Identifying double heterozygosities in Hb E (HBB: c.79 G>A)/- - SEA (Southeast Asian) (α-thalassemia-1) (α-thal-1) in patients first diagnosed as carrying Hb E is important in thalassemia control. Low Hb E, mean corpuscular volume (MCV) and mean corpuscular hemoglobin (Hb) (MCH) levels have been observed in this double heterozygosity. However, the cutoff points of these parameters have never been systematically established. Here, we analyzed Hb E and red blood cell (RBC) parameters in 372 Hb E patients grouped by Hb levels, by the status of - - SEA and -α 3.7 (α-thal-2; rightward) deletions, to establish the cutoff points. Then, the established cutoff points were evaluated in 184 Hb E patients. It was found that the cutoff points of Hb E, MCV, MCH were significantly dependent on the Hb levels. In the group having Hb levels Hb E, MCV and MCH were 21.2%, 64.9 fL and 21.0 pg, respectively, and were 25.6%, 72.8 fL and 23.9 pg, respectively, in the group having Hb levels 10.0-11.9 g/dL. Finally, in the group having Hb levels ≥12.0 g/dL, the cutoff points of Hb E, MCV and MCH were 27.1%, 76.7 fL and 25.3 pg, respectively. Thus, to screen for the double heterozygous Hb E/- - SEA anomaly in patients initially diagnosed as carrying Hb E, the Hb levels must be taken into account in choosing the suitable cutoff points of these three parameters.

O documentário e a instilação da crença

Directory of Open Access Journals (Sweden)

Laécio Ricardo de Aquino Rodrigues

2015-03-01

Full Text Available O artigo investiga alguns procedimentos empregados pelos cineastas para conferir credibilidade à narrativa documentária e insuflar a crença no espectador, de forma a reiterar o suposto vínculo deste domínio com a realidade, não obstante a proliferação das práticas reflexivas que questionam a escritura fílmica e sua natureza discursiva

Title list of documents made publicly available, March 1-31, 1996

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-05-01

This document is the March 1996 listing of publicly available documents published by the NRC. The documents include: (1) docketed material associated with civilian nuclear power plants and other uses of radioactive material, and (2) nondocketed material received and generated by the NRC in its role as a regulatory agency.

Title list of documents made publicly available, March 1-31, 1996

International Nuclear Information System (INIS)

1996-05-01

This document is the March 1996 listing of publicly available documents published by the NRC. The documents include: (1) docketed material associated with civilian nuclear power plants and other uses of radioactive material, and (2) nondocketed material received and generated by the NRC in its role as a regulatory agency

Improved Optical Document Security Techniques Based on Volume Holography and Lippmann Photography

Science.gov (United States)

Bjelkhagen, Hans I.

Optical variable devices (OVDs), such as holograms, are now common in the field of document security. Up until now mass-produced embossed holograms or other types of mass-produced OVDs are used not only for banknotes but also for personalized documents, such as passports, ID cards, travel documents, driving licenses, credit cards, etc. This means that identical OVDs are used on documents issued to individuals. Today, there is need for a higher degree of security on such documents and this chapter covers new techniques to make improved mass-produced or personalized OVDs.

Volumes de calda e adjuvante no controle de plantas daninhas com glyphosate

OpenAIRE

Bueno,M.R.; Alves,G.S.; Paula,A.D.M.; Cunha,J.P.A.R.

2013-01-01

O sucesso de uma aplicação de herbicida está diretamente relacionado a uma boa deposição da calda no alvo, com o mínimo de perdas para o ambiente. Assim, o presente trabalho objetivou avaliar a deposição e o controle de plantas daninhas promovido pela aplicação de glyphosate em diferentes volumes de calda e com a adição do adjuvante nonil fenol etoxilado. O experimento foi conduzido em delineamento de blocos casualizados com quatro repetições, em esquema fatorial 3x2, sendo três volumes de ca...

Technical support document: Energy efficiency standards for consumer products: Room air conditioners, water heaters, direct heating equipment, mobile home furnaces, kitchen ranges and ovens, pool heaters, fluorescent lamp ballasts and television sets. Volume 2, Fluorescent lamp ballasts, television sets, room air conditioners, and kitchen ranges and ovens

Energy Technology Data Exchange (ETDEWEB)

1993-11-01

This document is divided into ``volumes`` B through E, dealing with individual classes of consumer products. Chapters in each present engineering analysis, base case forecasts, projected national impacts of standards, life-cycle costs and payback periods, impacts on manufacturers, impacts of standards on electric utilities, and environmental effects. Supporting appendices are included.

CNEA's quality system documentation

International Nuclear Information System (INIS)

Mazzini, M.M.; Garonis, O.H.

1998-01-01

Full text: To obtain an effective and coherent documentation system suitable for CNEA's Quality Management Program, we decided to organize the CNEA's quality documentation with : a- Level 1. Quality manual. b- Level 2. Procedures. c-Level 3. Qualities plans. d- Level 4: Instructions. e- Level 5. Records and other documents. The objective of this work is to present a standardization of the documentation of the CNEA's quality system of facilities, laboratories, services, and R and D activities. Considering the diversity of criteria and formats for elaboration the documentation by different departments, and since ultimately each of them generally includes the same quality management policy, we proposed the elaboration of a system in order to improve the documentation, avoiding unnecessary time wasting and costs. This will aloud each sector to focus on their specific documentation. The quality manuals of the atomic centers fulfill the rule 3.6.1 of the Nuclear Regulatory Authority, and the Safety Series 50-C/SG-Q of the International Atomic Energy Agency. They are designed by groups of competent and highly trained people of different departments. The normative procedures are elaborated with the same methodology as the quality manuals. The quality plans which describe the organizational structure of working group and the appropriate documentation, will asses the quality manuals of facilities, laboratories, services, and research and development activities of atomic centers. The responsibilities for approval of the normative documentation are assigned to the management in charge of the administration of economic and human resources in order to fulfill the institutional objectives. Another improvement aimed to eliminate unnecessary invaluable processes is the inclusion of all quality system's normative documentation in the CNEA intranet. (author) [es

NPR hazards review: (Phase 1, Production only appendixes). Volume 2

Energy Technology Data Exchange (ETDEWEB)

Miller, N.R.; Trumble, R.E.

1962-08-15

The NPR Hazards Review is being issued in a series of volumes. Volume 1, which has already been published, was of the nature of an expanded summary. It included the results of hazards analyses with some explanatory material to put the results in context. Volume 2 presents results of reviews made after the preparation of Volume 1. It also contains supporting material and details not included in Volume 1. Volumes 1 and 2 together provide a nearly complete ``Design Hazards Review of the NPR.`` However, certain remaining problems still exist and are to be the subject of a continuing R&D program. These problems and programs are discussed in Appendix H. Neither Volume 1 nor Volume 2 treat operational aspects of reactor hazards in detail. This area of concern will be the primary subject of a third volume of the NPR Hazards Review. This third volume, to be prepared and issued at a later date, may also contain information supplementing Volumes 1 and 2.

Mars power system concept definition study. Volume 2: Appendices

Science.gov (United States)

Littman, Franklin D.

1994-01-01

This report documents the work performed by Rockwell International's Rocketdyne Division on NASA Contract No. NAS3-25808 (Task Order No. 16) entitled 'Mars Power System Definition Study'. This work was performed for NASA's Lewis Research Center (LeRC). The report is divided into two volumes as follows: Volume 1 - Study Results; and Volume 2 - Appendices. The results of the power system characterization studies, operations studies, and technology evaluations are summarized in Volume 1. The appendices include complete, standalone technology development plans for each candidate power system that was investigated.

The Effect of Volume of Transaction On The Intention Towards Tax E-filing

OpenAIRE

Aziz Saliza Abdul; Idris Kamil Md

2017-01-01

Volume of transaction is specifically referring to number of clients or return forms dealing by tax agents/preparers. This variable does play role even though there is less empirical evidence on this matter. This paper is basically to explore the effect of volume of transaction that could possibly influence the acceptance of tax e-filing system as it did in other areas of transaction i.e. court cases. Undoubtedly, it is proved to be significantly influenced the behavioural intention towards t...

Research Studies Index. Authors and Subjects. Volume 1 through Volume 43 (1929-1975).

Science.gov (United States)

Drazan, Joseph, Comp.; Scott, Paula, Comp.

This volume contains author and subject indexes for volumes 1 through 43 (1929-1975) of "Research Studies," a scholarly, multi-disciplinary quarterly published at Washington State University. Each author index entry includes the title, volume, and inclusive pagination of the article. The subject index is a keyword-out-of-context…

26 CFR 301.7513-1 - Reproduction of returns and other documents.

Science.gov (United States)

2010-04-01

... 26 Internal Revenue 18 2010-04-01 2010-04-01 false Reproduction of returns and other documents... the United States § 301.7513-1 Reproduction of returns and other documents. (a) In general. The... make reproductions from such films and photoimpressions. (b) Safeguards—(1) By private contractor. Any...

Fragment E1 labeled with I-123 in the detection of venous thrombosis

International Nuclear Information System (INIS)

Knight, L.C.; Maurer, A.H.; Robbins, P.S.; Malmud, L.S.; Budzynski, A.Z.

1985-01-01

Fragment E1, which has been shown to have specific binding affinity for thrombi in an animal model, was investigated in humans for its safety and ability to bind to venous thrombi. Human Fragment E1 was labeled with I-123 and administered intravenously to patients with proved or suspected deep vein thrombosis. The vascular distribution of radioactivity was documented by obtaining gamma camera images of the patients' legs for 30 minutes following administration of I-123-Fragment E1. All patients (n = 5) with documented venous thrombi had rapid localization of labeled Fragment E1 in the area of thrombus. Patients without evidence of thrombi (n = 5) showed no focal localization, although two of these patients showed diffuse uptake along the length of the veins, due to superficial phlebitis. Analysis of blood samples in four patients indicated that disappearance of Fragment E1 from the circulation was more rapid in individuals with thrombosis (t 1/2 = 20 min) than in individuals without thrombosis (t 1/2 = 90 min), and a radiolabeled species of high molecular weight was found in patients with thrombosis but was absent from patients without thrombosis. These early results suggest that radiolabeled Fragment E1 is a safe and potentially valuable agent for the rapid detection of venous thrombosis

Proceedings of the 7th International Meeting on Nuclear Reactor Thermal-Hydraulics NURETH-7. Volume 1, Sessions 1-5

International Nuclear Information System (INIS)

Block, R.C.; Feiner, F.

1995-09-01

This document, Volume 1, includes papers presented at the 7th International Meeting on Nuclear Reactor Thermal-Hydraulics (NURETH-7) September 10--15, 1995 at Saratoga Springs, N.Y. The following subjects are discussed: Progress in analytical and experimental work on the fundamentals of nuclear thermal-hydraulics, the development of advanced mathematical and numerical methods, and the application of advancements in the field in the development of novel reactor concepts. Also combined issues of thermal-hydraulics and reactor/power-plant safety, core neutronics and/or radiation. Selected papers are indexed separately for inclusion in the Energy Science and Technology Database

Proceedings of the 7th International Meeting on Nuclear Reactor Thermal-Hydraulics NURETH-7. Volume 1, Sessions 1-5

Energy Technology Data Exchange (ETDEWEB)

Block, R.C.; Feiner, F. [comps.] [American Nuclear Society, La Grange Park, IL (United States)

1995-09-01

This document, Volume 1, includes papers presented at the 7th International Meeting on Nuclear Reactor Thermal-Hydraulics (NURETH-7) September 10--15, 1995 at Saratoga Springs, N.Y. The following subjects are discussed: Progress in analytical and experimental work on the fundamentals of nuclear thermal-hydraulics, the development of advanced mathematical and numerical methods, and the application of advancements in the field in the development of novel reactor concepts. Also combined issues of thermal-hydraulics and reactor/power-plant safety, core neutronics and/or radiation. Selected papers are indexed separately for inclusion in the Energy Science and Technology Database.

Resource Conservation and Recovery Act: Part B permit application. Volume 9. Chapter E, Appendix E1-Chapter H, Appendix H3

International Nuclear Information System (INIS)

1995-01-01

Volume nine contains the following appendices: RCRA groundwater protection information; Examples of inspection sheets, logs and instructions for systems/equipment requiring inspection under 20 NMAC 4.1, Subpart V; Material safety data sheets; List of hazardous waste management job titles; and Waste Isolation Pilot Plant RCRA hazardous waste management job description

Fuel Rod Consolidation Project: Phase 2, Final report: Volume 2, Appendices

International Nuclear Information System (INIS)

1987-01-01

This document, Volume 2, provides the appendices to Volume 1 of the Fuel Rod Consolidation Project. It provides information on the following: References; Trade-off Studies; Instrument List; RAM Data; Fabrication Specifications; Software Specifications; and Design Requirements

Regulatory Oversight Program, July 1, 1993--March 3, 1997. Volume 3

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-12-31

On July, 1993, a Regulatory Oversight (RO) organization was established within the US DOE, Oak Ridge Operations (ORO) to provide regulatory oversight of the DOE uranium enrichment facilities leased to the United States Enrichment Corporation (USEC). The purpose of the OR program was to ensure continued plant safety, safeguards and security while the plants were transitioned to regulatory oversight by the Nuclear Regulatory Commission (NRC). Volume 3 contains copies of two reports that document the DOE/ORO regulatory oversight inspection and enforcement history for each gaseous diffusion plant site. Each report provides a formal mechanism by which DOE/ORO could communicate the inspection and enforcement history to NRC. The reports encompass the inspection activities that occurred during July 1, 1993 through March 2, 1997.

INTRODUCTION AND STATIC ELECTRICITY, VOLUME 1.

Science.gov (United States)

KLAUS, DAVID J.; AND OTHERS

THIS VOLUME, PART OF A TWO-VOLUME SET, PROVIDES AUTOINSTRUCTION IN PHYSICS. THE MATERIAL COVERS UNITS ON (1) STATIC ELECTRICITY AND ELECTRICAL CHARGES, (2) COULOMB'S LAW, (3) DISTRIBUTION OF CHARGE AND FLOW OF CURRENT, (4) DIFFERENCE OF POTENTIAL, (5) BATTERIES AND CIRCUITS, (6) RESISTANCE AND RESISTORS, (7) POTENTIAL DIVIDER AND WHEATSTONE…

E-beam direct write versus reticle/stepper technology for ASICS in small volume production

International Nuclear Information System (INIS)

Wheeler, M.J.

1987-01-01

The pros and cons of using e-beam direct writing or reticles plus optical/UV steppers in fast prototyping and the small volume production of ASICs are discussed. The main conclusion is that fast prototyping is best achieved by e-beam direct write whereas small volume production of ASICs is best done via reticles and optical/UV stepping provided that the reticles are made in-house rather than by commercial maskhouses

Technical Assistance in Evaluating Career Education Projects. Final Report. Volume I: Summary Volume.

Science.gov (United States)

Stenner, A. Jackson; And Others

This document contains the first of five volumes reporting the activities and results of a career education evaluation project conducted to accomplish the following two objectives: (1) to improve the quality of evaluations by career education projects funded by the United States Office of Career Education (OCE) through the provision of technical…

Electric and Magnetic Fields (EMF) RAPID Program Engineering Project 8: FINAL REPORT, Evaluation of Field Reduction Technologies, Volume 1 (Report) and Volume 2 (Appendices)

Energy Technology Data Exchange (ETDEWEB)

Commonwealth Associates, Inc.; IIT Research Institute

1997-08-01

This draft report consists of two volumes. Volume 1, the main body, contains an introducto~ sectionj an overview of magnetic fields sectio~ and field reduction technology evaluation section. Magnetic field reduction methods are evalpated for transmission lines, distribution Iines,sulxtations, building wiring applkmd machinery, and transportation systems. The evaluation considers effectiveness, co% and other ftiors. Volume 2 contains five appendices, Append~ A presents magnetic field shielding information. Appendices B and C present design assumptions and magnetic field plots for transmission and distribution lines, respectively. Appendices D and E present cost estimate details for transmission and distribution limes, respectively.

The effect of container volume on seedling production and initial growth of Jatropha curcas L. on the Western ParanaEfeito do volume do recipiente na produção de mudas e no crescimento inicial de Jatropha curcas L. no Oeste Paranaense

Directory of Open Access Journals (Sweden)

Michelle Cristina Ajala

2012-12-01

Full Text Available The effect of container volume on seedling production and initial growth of Jatropha curcas L. on the Western ParanaEste trabalho objetivou comparar a influência do volume de recipientes na produção de mudas e no crescimento, durante o primeiro ano, de pinhão manso no oeste paranaense. A produção de mudas no viveiro utilizou saco plástico de 1.178 cm3 e tubetes de 120 e 180 cm3 preenchidos com substrato comercial. As mensurações quinzenais incluíram os incrementos em altura, diâmetro do coleto e área foliar. Após o plantio foram avaliados os incrementos no número de folhas, de ramificações e a porcentagem de sobrevivência trimestral. Ao final da fase de viveiro, o maior incremento em altura (1,56 cm e em diâmetro do coleto (1,3 mm foi obtido nas mudas de J. curcas conduzidas em saco plástico com volume de 1.178 cm3, enquanto que os valores para mudas em tubetes de 180 cm3 e 120 cm3 resultaram em 1,24 cm e 1,2 mm e 1,48 cm e 1,1 mm, respectivamente. Após o plantio, não foram verificadas diferenças nos incrementos trimestrais em altura, diâmetro de colo, número de folhas, número de ramos (primários e secundários e porcentagem de mortalidade em função do volume dos recipientes utilizados para a formação das mudas. Os incrementos observados no primeiro trimestre após o plantio apresentaram os maiores valores em diâmetro do coleto, número de folhas, e mortalidade. Mudas de J.curcas semeadas no final de agosto, conduzidas em viveiro de setembro a novembro em tubetes de 120 cm3, e plantadas em dezembro em solo PVd da região oeste do Estado do Paraná resultam em crescimento equivalente ao de mudas produzidas em recipientes de maior volume com economia de substrato, espaço de viveiro e esforço no plantio.

Twenty-third water reactor safety information meeting: Volume 1, plenary session, high burnup fuel behavior, thermal hydraulic research. Proceedings

Energy Technology Data Exchange (ETDEWEB)

Monteleone, S. [comp.] [Brookhaven National Lab., Upton, NY (United States)

1996-03-01

This three-volume report contains papers presented at the Twenty- Third Water Reactor Safety Information Meeting held at the Bethesda Marriott Hotel, Bethesda, Maryland, October 23-25, 1995. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included papers presented by researchers from France, Italy, Japan, Norway, Russia, Sweden, and Switzerland. This document, Volume 1, present topics on High Burnup Fuel Behavior, Thermal Hydraulic Research, and Plenary Session topics. Individual papers have been cataloged separately.

Twenty-third water reactor safety information meeting: Volume 1, plenary session, high burnup fuel behavior, thermal hydraulic research. Proceedings

International Nuclear Information System (INIS)

Monteleone, S.

1996-03-01

This three-volume report contains papers presented at the Twenty- Third Water Reactor Safety Information Meeting held at the Bethesda Marriott Hotel, Bethesda, Maryland, October 23-25, 1995. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included papers presented by researchers from France, Italy, Japan, Norway, Russia, Sweden, and Switzerland. This document, Volume 1, present topics on High Burnup Fuel Behavior, Thermal Hydraulic Research, and Plenary Session topics. Individual papers have been cataloged separately

eBgateway : a solution to reduce document exchange expenses

Energy Technology Data Exchange (ETDEWEB)

Demers, D. [ElectroBusiness, Calgary, AB (Canada)

2004-07-01

This paper provides a description of electroBusiness, a document exchange company based in Calgary. Details of the company's exchange methods in servicing multiple companies were presented. A mapping of internal systems and the different formats available for information sharing were outlined. An outdated supply exchange agreement with 10 partners was presented as the basis for a critique of earlier communications technologies and their ineffectiveness and costliness. An industry business solution, including proof-of-concept architecture and security. Advantages of the electroBusiness model included significant cost reductions and effective and up to date secure private community trading data. A list of e-Business utility exchanges was presented, including producers, technology companies as well as suppliers, contractors and distributors. Contact information was given at the end of the presentation. tabs, figs.

Yucca Mountain Project Site Atlas: Volume 1: Draft

International Nuclear Information System (INIS)

1988-10-01

The Nevada Nuclear Waste Storage Investigations (NNWSI) Project Site Atlas is a reference document of field activities which have been, or are being, conducted by the US Department of Energy (DOE) to support investigations of Yucca Mountain as a potential site for an underground repository for high-level radioactive waste. These investigations, as well as future investigations, will yield geologic, geophysical, geochemical, geomechanical, hydrologic, volcanic, seismic, and environmental data necessary to characterize Yucca Mountain and its regional setting. This chapter summarizes the background of the NNWSI Project and the objective, scope, structure, and preparation of the Site Atlas. Chapter 2 describes in more detail the bibliography and map portfolio portions of the Atlas, which are presented in Chapter 4 and Volume 2, respectively. Chapter 3 describes how to use the Atlas. The objective of the Site Atlas is to create a management tool for the DOE Waste Management Project Office (WMPO) that will allow the WMPO to compile and disseminate information regarding the location of NNWSI Project field investigations, and document the permits acquired and the environmental, archaeological, and socioeconomic surveys conducted to support those investigations. The information contained in the Atlas will serve as a historical reference of site investigation field activities. A companion document to the Atlas is the NNWSI Project Surface Based Investigations Plan (SBIP)

Volumes, capacidades pulmonares e força muscular respiratória no pós-operatório de gastroplastia Lung volumes, lung capacities and respiratory muscle strength following gastroplasty

Directory of Open Access Journals (Sweden)

Denise de Moraes Paisani

2005-04-01

Full Text Available INTRODUÇÃO: A gastroplastia tem sido cada vez mais indicada no tratamento de obesos mórbidos, pacientes nos quais podemos identificar alteração pronunciada de volumes e capacidades pulmonares. OBJETIVO: Avaliar o comportamento dos volumes e capacidades pulmonares, força muscular respiratória, padrão respiratório e as possíveis complicações pulmonares pós-operatórias. MÉTODO: Vinte e um pacientes (três homens com média de idade de 39 ± 9,7 anos, média de índice de massa corpórea de 50,4 Kg/m², candidatos à gastroplastia, foram avaliados no pré-operatório, primeiro, terceiro e quinto dias de pós-operatório e submetidos a mensuração de volume corrente, capacidade vital, volume minuto, pressões máximas expiratória e inspiratória, e circunferências abdominal e torácica. Observou-se a ocorrência de complicações pulmonares pós-operatórias e mortalidade. RESULTADOS: No primeiro e terceiro dias de pós-operatório houve queda de 47% e 30,5% na capacidade vital, 18% e 12,5% no volume minuto, 28% e 21% no volume corrente, 47% e 32% no índice diafragmático, 51% e 26% na pressão inspiratória máxima, e 39,5% e 26% na pressão expiratória máxima, respectivamente (p BACKGROUND: Gastroplasty has been increasingly used in the treatment of morbidly obese patients, who typically present pronounced alterations in lung volume and capacity. OBJECTIVE: To evaluate post-gastroplasty lung volume, lung capacity, respiratory muscle strength and respiratory pattern, as well as any postoperative pulmonary complications. METHOD: 21 patients (3 of them men, with an average age of 39 ± 9.7 years and an average body mass index of 50.4 kg/m², all candidates for gastroplasty, were evaluated during the preoperative period and again on the first, third and fifth postoperative days. Tidal volume, vital capacity, minute volume, maximal expiratory pressure and maximal inspiratory pressure, as well as chest and waist circumferences, were

FENDL/MG. Library of multigroup cross sections in GENDF and MATXS format for neutron-photon transport calculations. Version 1.1 of March 1995. Summary documentation

International Nuclear Information System (INIS)

Pashchenko, A.B.; Wienke, H.; Ganesan, S.

1996-01-01

Selected neutron reaction nuclear data evaluations and photon-atomic interaction cross section libraries for elements of interest to the IAEA's program on Fusion Evaluated Nuclear Data Library (FENDL) have been processed into GENDF and MATXS format using the NJOY system by R.E. MacFarlane, in VITAMIN-J group structure with VITAMIN-E weighting spectrum. This document summarizes the resulting multigroup data library FENDL/MG version 1.1. The data are available costfree, upon request from the IAEA Nuclear Data Section, online or on magnetic tape. (author). 7 refs, 1 tab

Class 1E digital systems studies

International Nuclear Information System (INIS)

Hecht, H.; Tai, A.T.; Tso, K.S.

1993-10-01

This document is furnished as part of the effort to develop NRC Class 1E Digital Computer Systems Guidelines which is Task 8 of USAF Rome Laboratories Contract F30602-89-D-0100. The report addresses four major topics, namely, computer programming languages, software design and development, software testing and fault tolerance and fault avoidance. The topics are intended as stepping stones leading to a Draft Regulatory Guide document. As part of this task a small scale survey of software fault avoidance and fault tolerance practices was conducted among vendors of nuclear safety related systems and among agencies that develop software for other applications demanding very high reliability. The findings of the present report are in part based on the survey and in part on review of software literature relating to nuclear and other critical installations, as well as on the authors' experience in these areas

Volume de iogurte light e sensações subjetivas do apetite de homens eutróficos e com excesso de peso Volume of light yogurt and subjective appetite sensations in normal-weight and overweight men

Directory of Open Access Journals (Sweden)

Luciana Neri Nobre

2006-10-01

Full Text Available OBJETIVO: Avaliar, independentemente de outras variáveis, o efeito do volume de iogurte light sobre os parâmetros de ingestão alimentar de homens saudáveis. MÉTODOS: Foi feita incorporação de ar ao iogurte por adição de um produto comercialmente disponível -Emustab® - (6g/300ml com posterior homogeneização em liqüidificador semi-industrial. Utilizaram-se três volumes de iogurte: 300, 450 e 600ml. Trabalhou-se com 20 participantes saudáveis, sendo 10 eutróficos, com índice de massa corporal entre 19 e 24,9kg/m² e 10 com excesso de peso, índice de massa corporal >25kg/m². Cada um deles recebeu um volume de iogurte em três diferentes dias, pela manhã, em jejum de 12 horas. Uma escala de analogia visual foi utilizada, num período de 4 horas e 30 minutos após ingestão de cada volume do iogurte, para avaliar sensações subjetivas de saciedade, fome e desejo por alimentos específicos. RESULTADOS: Os volumes do iogurte light afetaram a saciedade dos dois grupos estudados, sendo que o maior volume exerceu melhor essa ação (pOBJECTIVE: This study aimed to evaluate the effect of light yogurt volume on the food intake of healthy men regardless of other variables. METHODS: Air was added to the yogurt by mixing it with a commercially available product, Emustab®, (6g/300ml and homogenized in a semi-industrial blender. Three volumes of yogurt were used: 300, 450 and 600ml. Twenty healthy volunteers participated in the study, 10 with normal weight, Body Mass Index from 19 to 24.9kg/m² and 10 with excess weight, Body Mass Index >25kg/m². Each one of them was given a yogurt volume in three different days in the morning, after a 12 hour fast. After the intake of each yogurt volume, a visual analog scale was used to assess the subjective sensations of satiety, hunger and desire for specific foods. RESULTS: Light yogurt volumes affected the satiety of both studied groups and the greater volume was more effective (p<0.01. The highest

Energy and Environment : volume 1

OpenAIRE

ANDRE, Michel; SAMARAS, Zissis; JACOB, Bernard

2016-01-01

This book is part of a set of six books called the 'Research for Innovative Transports' set. This collection presents an update of the latest academic and applied research, case studies, best practices and user perspectives on transport carried out in Europe and worldwide. The volumes are made up of a selection of the best papers presented at TRA2014. In this volume 1, recent research works are reported around the triptych : 'transport, energy and environment', which demonstrates that vehicl...

Scale-4 analysis of pressurized water reactor critical configurations: Volume 5, North Anna Unit 1 Cycle 5

International Nuclear Information System (INIS)

Bowman, S.M.; Suto, T.

1996-10-01

ANSI/ANS 8.1 requires that calculational methods for away-from- reactor (AFR) criticality safety analyses be validated against experiment. This report summarizes part of the ongoing effort to benchmark AFR criticality analysis methods using selected critical configurations from commercial PWRs. Codes and data in the SCALE-4 code system were used. This volume documents the SCALE system analysis of one reactor critical configuration for North Anna Unit 1 Cycle 5. The KENO V.a criticality calculations for the North Anna 1 Cycle 5 beginning-of-cycle model yielded a value for k eff of 1. 0040±0.0005

The International Linear Collider - Volume 1: Executive Summary

CERN Document Server

Brau, James E.; Foster, Brian; Fuster, Juan; Harrison, Mike; Paterson, James McEwan; Peskin, Michael; Stanitzki, Marcel; Walker, Nicholas; Yamamoto, Hitoshi

2013-01-01

The International Linear Collider Technical Design Report (TDR) describes in four volumes the physics case and the design of a 500 GeV centre-of-mass energy linear electron-positron collider based on superconducting radio-frequency technology using Niobium cavities as the accelerating structures. The accelerator can be extended to 1 TeV and also run as a Higgs factory at around 250 GeV and on the Z0 pole. A comprehensive value estimate of the accelerator is give, together with associated uncertainties. It is shown that no significant technical issues remain to be solved. Once a site is selected and the necessary site-dependent engineering is carried out, construction can begin immediately. The TDR also gives baseline documentation for two high-performance detectors that can share the ILC luminosity by being moved into and out of the beam line in a "push-pull" configuration. These detectors, ILD and SiD, are described in detail. They form the basis for a world-class experimental programme that promises to incr...

Documentation on the development of the Swiss TIMES Electricity Model (STEM-E)

International Nuclear Information System (INIS)

Kannan, R.; Turton, H.

2011-10-01

This comprehensive report by the Paul Scherrer Institute PSI in Switzerland documents the development of the Swiss TIMES Electricity Model (STEM-E). This is a flexible model which explicitly depicts plausible pathways for the development of the Swiss electricity sector, while dealing with inter-temporal variations in demand and supply. TIMES is quoted as having the capability to portray the entire energy system from resource supply, through fuel processing, representation of infrastructures, conversion to secondary energy carriers, end-use technologies and energy service demands at end-use sectors. The background of the model's development and a reference energy system are described. Also, electricity end-use sectors and generating systems are examined, including hydropower, nuclear power, thermal generation and renewables. Environmental factors and the calibration of the model are discussed, as is the application of the model. The document is completed with an outlook, references and six appendices

Consolidated guidance about materials licenses: Program-specific guidance about portable gauge licenses. Final report; Volume 1

Energy Technology Data Exchange (ETDEWEB)

Vacca, P.C.; Whitten, J.E.; Pelchat, J.M.; Arredondo, S.A.; Matson, E.R.; Lewis, S.H.; Collins, D.J.; Santiago, P.A. [Nuclear Regulatory Commission, Washington, DC (United States). Div. of Industrial and Medical Nuclear Safety; Tingle, W. [Dept. of Environment, Health, and Natural Resources, Raleigh, NC (United States). Div. of Radiation Protection

1997-05-01

As part of its redesign of the materials licensing process, NRC is consolidating and updating numerous guidance documents into a single comprehensive repository as described in NUREG-1539 and draft NUREG-1541. NUREG-1556, Vol. 1, is the first program-specific guidance developed for the new process and will serve as a template for subsequent program-specific guidance. This document is intended for use by applicants, licensees, and NRC staff and will also be available to Agreement States. This document supersedes the guidance previously found in draft Regulatory Guide DG-0008, ``Applications for the Use of Sealed Sources in Portable Gauging Devices,`` and in NMSs Policy and guidance Directive 2-07, ``Standard Review Plan for Applications for Use of Sealed Sources in Portable Gauging Devices.`` This final report takes a more risk-informed, performance-based approach to licensing portable gauges, and reduces the information(amount and level of detail) needed to support an application to use these devices. It incorporates many suggests submitted during the comment period on draft NUREG-1556, Volume 1. When published, this final report should be used in preparing portable gauge license applications. NRC staff will use this final report in reviewing these applications.

Consolidated guidance about materials licenses: Program-specific guidance about portable gauge licenses. Final report; Volume 1

International Nuclear Information System (INIS)

Vacca, P.C.; Whitten, J.E.; Pelchat, J.M.; Arredondo, S.A.; Matson, E.R.; Lewis, S.H.; Collins, D.J.; Santiago, P.A.; Tingle, W.

1997-05-01

As part of its redesign of the materials licensing process, NRC is consolidating and updating numerous guidance documents into a single comprehensive repository as described in NUREG-1539 and draft NUREG-1541. NUREG-1556, Vol. 1, is the first program-specific guidance developed for the new process and will serve as a template for subsequent program-specific guidance. This document is intended for use by applicants, licensees, and NRC staff and will also be available to Agreement States. This document supersedes the guidance previously found in draft Regulatory Guide DG-0008, ''Applications for the Use of Sealed Sources in Portable Gauging Devices,'' and in NMSs Policy and guidance Directive 2-07, ''Standard Review Plan for Applications for Use of Sealed Sources in Portable Gauging Devices.'' This final report takes a more risk-informed, performance-based approach to licensing portable gauges, and reduces the information(amount and level of detail) needed to support an application to use these devices. It incorporates many suggests submitted during the comment period on draft NUREG-1556, Volume 1. When published, this final report should be used in preparing portable gauge license applications. NRC staff will use this final report in reviewing these applications

A noção de estrutura e os registros de informação dos sistemas documentários

Directory of Open Access Journals (Sweden)

Cristina Dotta Ortega

Full Text Available Partindo da constatação de que os princípios e os métodos para construção e gestão dos sistemas documentários são dispersos e carecem de sistematização, este artigo levanta a hipótese de que a noção de estrutura, ao pressupor relações mútuas entre os seus elementos, confere maior organicidade aos sistemas e garante maior qualidade e consistência na recuperação da informação frente às questões dos usuários. Desse modo, objetiva explorar fundamentos, a partir da noção de estrutura, dos registros de informação e dos sistemas documentários. Para tanto, são apresentados conceitos básicos e questões relativas aos sistemas documentários e aos registros de informação. Posteriormente, elenca aportes teóricos sobre a noção de estrutura, tratados por Benveniste, Ferrater Mora, Hjelmslev, Lévi-Strauss, Lopes, Peñalver Simó, Saussure, além de Ducrot, Fávero e Koch, para então tratar das apropriações já realizadas pela Documentação por Paul Otlet, García Gutiérrez e Moreiro González. Conclui-se que a noção de estrutura adotada para tornar explícita uma hipótese de sistematização do real, a partir de um modelo, assegura maior organicidade aos sistemas, bem como confere referência pedagógica ao fazer documentário.

Environmental and other evaluations of alternatives for management of defense transuranic waste at the Idaho National Engineering Laboratory. Volume 1 of 2

International Nuclear Information System (INIS)

1982-04-01

The US Department of Energy (DOE) is responsible for developing and implementing methods for the safe and environmentally acceptable disposal of radioactive wastes. In connection with this responsibility, the DOE is formulating a program for the long-term management of transuranic (TRU) waste buried and stored at the Idaho National Engineering Laboratory (INEL). This report has been prepared to document the results of environmental and other evaluations for three decisions that the DOE is considering: (1) the selection of a general method for the long-term management of the buried TRU waste; (2) the selection of a method for processing the stored waste and for processing the buried waste, if it is retrieved; (3) the selection of a location for the waste-processing facility. This document pertains only to the contact-handled TRU waste buried in pits and trenches and the contact-handled TRU waste held in aboveground storage at the INEL. A decision has previously been made on a method for the long-term management of the stored waste; it will be retrieved and shipped to the Waste Isolation Pilot Plant (WIPP) near Carlsbad, New Mexico. The WIPP is also used in this report as a reference repository for evaluation purposes for the buried waste. This report is contained in two volumes. Volume I is arranged as follows: the summary is an overview of the analyses contained in this document. Section 1 is a statement of the underlying purpose and need to which the report is responding. Section 2 describes the alterntives. Section 3 describes the affected environment at the INEL and the WIPP sites. Section 4 analyzes the environmental effects of each alternative. The appendices in Volume II contain data and discussions supporting the material presented in Volume I

Information architecture. Volume 3: Guidance

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-04-01

The purpose of this document, as presented in Volume 1, The Foundations, is to assist the Department of Energy (DOE) in developing and promulgating information architecture guidance. This guidance is aimed at increasing the development of information architecture as a Departmentwide management best practice. This document describes departmental information architecture principles and minimum design characteristics for systems and infrastructures within the DOE Information Architecture Conceptual Model, and establishes a Departmentwide standards-based architecture program. The publication of this document fulfills the commitment to address guiding principles, promote standard architectural practices, and provide technical guidance. This document guides the transition from the baseline or defacto Departmental architecture through approved information management program plans and budgets to the future vision architecture. This document also represents another major step toward establishing a well-organized, logical foundation for the DOE information architecture.

Modificações do volume e da histologia de focos de endometriose em ratas tratadas com sinvastatina Changes in the volume and histology of focus of endometriosis in rats treated with sinvastatin

Directory of Open Access Journals (Sweden)

João Nogueira Neto

2007-08-01

Full Text Available OBJETIVO: analisar alterações macroscópicas e histológicas que ocorrem com o uso da sinvastatina em endometriose experimental em ratas. MÉTODOS: quarenta ratas da linhagem Wistar foram submetidas à técnica de autotransplante uterino em mesentério. Após três semanas, 24 ratas desenvolveram endometriose experimental grau III e foram divididas em dois grupos: Sinvastatina (dado 20 mg/kg/dia via oral e Controle (dado cloreto de sódio a 0,9% na quantidade de 1 mL/100 g de peso corpóreo via oral, que receberam gavagem durante 14 dias seguido de morte. Os volumes dos implantes foram calculados [4pi (comprimento/2 x (largura/2 x (altura/2/3] nas intervenções cirúrgicas e após a morte dos animais. Os autotransplantes foram retirados, corados com a hematoxilina-eosina e analisados à microscopia de luz. Foram usados o teste de Mann-Whitney para amostras independentes e o teste de Wilcoxon para amostras relacionadas. Para avaliação histológica, foi usado o teste exato de Fisher, adotando-se nível de significância de 5%. RESULTADOS: a diferença entre os volumes médios iniciais dos autotransplantes nos dois grupos foi insignificante (p=1,00, e, entre os volumes médios finais, significante (p=0,04. Houve aumento significativo (p=0,01 entre os volumes médios iniciais e finais do Grupo Controle e redução insignificante no Grupo Sinvastatina (p=0,95. Histologicamente (p=0,64, o Grupo Sinvastatina (n=9 mostrou a parede epitelial moderadamente preservada em sete casos (77,80% e dois casos com camada epitelial bem preservada (22,2%, e o Grupo Controle (n=12 com sete casos (58,30% moderadamente preservados e cinco casos (41,70% bem preservados. CONCLUSÕES: a sinvastatina impediu o crescimento dos focos de endometriose experimental. São promissores os estudos com uso da sinvastatina por período mais prolongado.PURPOSE: to analyze the macroscopic and histological changes that occur with the use of sinvastatin in experimental endometriosis

Insulin resistance is associated with larger thyroid volume in adults with type 1 diabetes independently from presence of thyroid autoimmunity.

Science.gov (United States)

Rogowicz-Frontczak, Anita; Pilacinski, Stanislaw; Chwialkowska, Anna Teresa; Naskret, Dariusz; Zozulinska-Ziolkiewicz, Dorota

2018-04-19

To investigate the effect of insulin resistance (IR) on thyroid function, thyroid autoimmunity (AIT) and thyroid volume in type 1 diabetes (T1DM). 100 consecutive patients with T1DM aged 29 (±6) years with diabetes duration 13 (±6) years were included. Exclusion criteria were: history of thyroid disease, current treatment with L-thyroxin or anti-thyroid drugs. Evaluation of thyroid stimulating hormone (TSH), free thyroid hormones and anti-thyroid antibodies was performed. Thyroid volume was measured by ultrasonography. IR was assessed using the estimated glucose disposal rate (eGDR) formula. In the study group 22% of subjects had insulin resistance defined as eGDR lower or equal to 7.5 mg/kg/min. The prevalence of thyroid autoimmunity (positivity for ATPO or ATg or TRAb) in the study group was 37%. There were no significant differences in the concentration of TSH, FT3, FT4, the prevalence of AIT and hypothyroidism between IR and insulin sensitive (IS) group. Mean (±SD) thyroid volume was 15.6 (±6.2) mL in patients with IR and 11.7 (±4.7) mL in IS subjects (p = .002). Thyroid volume correlated inversely with eGDR (r = -0.35, p < .001). In a multivariate linear regression model the association between thyroid volume and eGDR was independent of sex, age, duration of diabetes, daily insulin dose, BMI, cigarette smoking, TSH value and presence of thyroid autoimmunity (beta: -0.29, p = .012). Insulin resisance is associated with larger thyroid volume in patients with type 1 diabetes independently of sex, body mass index, TSH value and presence of autoimmune thyroid disease.

Constellation Program: Lessons Learned. Volume 1; Executive Summary

Science.gov (United States)

Rhatigan, Jennifer L. (Editor)

2011-01-01

This document (Volume I) provides an executive summary of the lessons learned from the Constellation Program. A companion Volume II provides more detailed analyses for those seeking further insight and information. In this volume, Section 1.0 introduces the approach in preparing and organizing the content to enable rapid assimilation of the lessons. Section 2.0 describes the contextual framework in which the Constellation Program was formulated and functioned that is necessary to understand most of the lessons. Context of a former program may seem irrelevant in the heady days of new program formulation. However, readers should take some time to understand the context. Many of the lessons would be different in a different context, so the reader should reflect on the similarities and differences in his or her current circumstances. Section 3.0 summarizes key findings developed from the significant lessons learned at the program level that appear in Section 4.0. Readers can use the key findings in Section 3.0 to peruse for particular topics, and will find more supporting detail and analyses in Section 4.0 in a topical format. Appendix A contains a white paper describing the Constellation Program formulation that may be of use to readers wanting more context or background information. The reader will no doubt recognize some very similar themes from previous lessons learned, blue-ribbon committee reviews, National Academy reviews, and advisory panel reviews for this and other large-scale human spaceflight programs; including Apollo, Space Shuttle, Shuttle/Mir, and the ISS. This could represent an inability to learn lessons from previous generations; however, it is more likely that similar challenges persist in the Agency structure and approach to program formulation, budget advocacy, and management. Perhaps the greatest value of these Constellation lessons learned can be found in viewing them in context with these previous efforts to guide and advise the Agency and its

76 FR 66311 - Draft Documents To Support Submission of an Electronic Common Technical Document; Availability

Science.gov (United States)

2011-10-26

...] Draft Documents To Support Submission of an Electronic Common Technical Document; Availability AGENCY... making regulatory submissions in electronic format using the electronic Common Technical Document (eCTD....S. regional document type definition, version 3.0) and ``Comprehensive Table of Contents Headings...

National Aeronautics and Space Administration (NASA)/American Society for Engineering Education (ASEE) Summer Faculty Fellowship Program, 1998. Volume 1

Science.gov (United States)

Bannerot, Richard B. (Editor); Sickorez, Donn G. (Editor)

1999-01-01

JSC NASA/ASEE Summer Faculty Fellowship Program was conducted by the University of Houston and JSC, under ASEE. The objectives of the program are to further the professional knowledge of qualified engineering and science members; stimulate an exchange of ideas between participants and NASA; enrich and refresh the research and teaching activities of participants; and contribute to the research objectives of the NASA Centers. Each faculty fellow spent at least 10 weeks at JSC engaged in a research project commensurate with his/her interests and background and worked in collaboration with a NASA/JSC colleague. This document is a compilation of the final reports on the fellows' research projects performed during the summer of 1998. Volume 1, current volume, contains the first reports, and volume 2 contains the remaining reports.

Direct and Indirect Effects of Brain Volume, Socioeconomic Status and Family Stress on Child IQ

Science.gov (United States)

Marcus Jenkins, Jade V; Woolley, Donald P; Hooper, Stephen R; De Bellis, Michael D

2013-01-01

1.1. Background A large literature documents the detrimental effects of socioeconomic disparities on intelligence and neuropsychological development. Researchers typically measure environmental factors such as socioeconomic status (SES), using income, parent's occupation and education. However, SES is more complex, and this complexity may influence neuropsychological outcomes. 1.2. Methods This studyused principal components analysis to reduce 14 SES and 28 family stress indicators into their core dimensions (e.g. community and educational capital, financial resources, marital conflict). Core dimensions were used in path analyses to examine their relationships with parent IQ and cerebral volume (white matter, grey matter and total brain volume), to predict child IQ in a sample of typically developing children. 1.3. Results Parent IQ affected child IQ directly and indirectly through community and educational capital, demonstrating how environmental factors interact with familial factors in neuro-development. There were no intervening effects of cerebral white matter, grey matter, or total brain volume. 1.4. Conclusions Findings may suggest that improving community resources can foster the intellectual development of children. PMID:24533427

Evaluation of potential severe accidents during Low Power and Shutdown Operations at Grand Gulf, Unit 1. Volume 2, Part 1B: Analysis of core damage frequency from internal events for Plant Operational State 5 during a refueling outage, Main report (Section 10)

International Nuclear Information System (INIS)

Whitehead, D.; Darby, J.; Yakle, J.

1994-06-01

This document contains the accident sequence analysis of internally initiated events for Grand Gulf, Unit 1 as it operates in the Low Power and Shutdown Plant Operational State 5 during a refueling outage. The report documents the methodology used during the analysis, describes the results from the application of the methodology, and compares the results with the results from two full power performed on Grand Gulf. This document, Volume 2, Part 1B, presents chapters Section 10 of this report, Human Reliability Analysis

Health physics documentation

International Nuclear Information System (INIS)

Stablein, G.

1980-01-01

When dealing with radioactive material the health physicist receives innumerable papers and documents within the fields of researching, prosecuting, organizing and justifying radiation protection. Some of these papers are requested by the health physicist and some are required by law. The scope, quantity and deposit periods of the health physics documentation at the Karlsruhe Nuclear Research Center are presented and rationalizing methods discussed. The aim of this documentation should be the application of physics to accident prevention, i.e. documentation should protect those concerned and not the health physicist. (H.K.)

High-risk clinical target volume delineation in CT-guided cervical cancer brachytherapy - Impact of information from FIGO stage with or without systematic inclusion of 3D documentation of clinical gynecological examination

Energy Technology Data Exchange (ETDEWEB)

Hegazy, Neamat [Dept. of Radiotherapy, Comprehensive Cancer Centre Vienna, Medical Univ. of Vienna, Vienna (Austria); Dept. of Clinical Oncology, Medical Univ. of Alexandria, Alexandria (Egypt); Poetter Rickard; Kirisits, Christian [Dept. of Radiotherapy, Comprehensive Cancer Centre Vienna, Medical Univ. of Vienna, Vienna (Austria); Christian Doppler Lab. for Medical Radiation Research for Radiation Oncology, Medical Univ. Vienna (Austria); Berger, Daniel; Federico, Mario; Sturdza, Alina; Nesvacil, Nicole [Dept. of Radiotherapy, Comprehensive Cancer Centre Vienna, Medical Univ. of Vienna, Vienna (Austria)], e-mail: nicole.nesvacil@meduniwien.ac.at

2013-10-15

Purpose: The aim of the study was to improve computed tomography (CT)-based high-risk clinical target volume (HR CTV) delineation protocols for cervix cancer patients, in settings without any access to magnetic resonance imaging (MRI) at the time of brachytherapy. Therefore the value of a systematic integration of comprehensive three-dimensional (3D) documentation of repetitive gynecological examination for CT-based HR CTV delineation protocols, in addition to information from FIGO staging, was investigated. In addition to a comparison between reference MRI contours and two different CT-based contouring methods (using complementary information from FIGO staging with or without additional 3D clinical drawings), the use of standardized uterine heights was also investigated. Material and methods: Thirty-five cervix cancer patients with CT- and MR-images and 3D clinical drawings at time of diagnosis and brachytherapy were included. HR CTV{sub stage} was based on CT information and FIGO stage. HR CTV{sub stage} {sub +3Dclin} was contoured on CT using FIGO stage and 3D clinical drawing. Standardized HR CTV heights were: 1/1, 2/3 and 1/2 of uterine height. MRI-based HR CTV was delineated independently. Resulting widths, thicknesses, heights, and volumes of HR CTV{sub stage}, HR CTV{sub stage+3Dclin} and MRI-based HR CTV contours were compared. Results: The overall normalized volume ratios (mean{+-}SD of CT/MRI{sub ref} volume) of HR CTV{sub stage} and HR{sub stage+3Dclin} were 2.6 ({+-}0.6) and 2.1 ({+-}0.4) for 1/1 and 2.3 ({+-}0.5) and 1.8 ({+-}0.4), for 2/3, and 1.9 ({+-}0.5) and 1.5 ({+-}0.3), for 1/2 of uterine height. The mean normalized widths were 1.5{+-}0.2 and 1.2{+-}0.2 for HR CTV{sub stage} and HR CTV{sub stage+3Dclin}, respectively (p < 0.05). The mean normalized heights for HR CTV{sub stage} and HR CTV{sub stage+3Dclin} were both 1.7{+-}0.4 for 1/1 (p < 0.05.), 1.3{+-}0.3 for 2/3 (p < 0.05) and 1.1{+-}0.3 for 1/2 of uterine height. Conclusion: CT-based HR

Controle químico da ferrugem asiática da soja em função de ponta de pulverização e de volume de calda Soybean asian rust control influenced by spray volumes and spray nozzles

Directory of Open Access Journals (Sweden)

João Paulo Arantes Rodrigues da Cunha

2006-10-01

Full Text Available As pontas de pulverização são um dos componentes mais importantes dos pulverizadores hidráulicos para aplicação de agrotóxicos. O presente trabalho teve como objetivo avaliar o controle químico da ferrugem asiática e a deposição da calda fungicida aplicada na cultura da soja, em função de diferentes volumes de aplicação e de tipos de ponta de pulverização. O ensaio foi conduzido no delineamento em blocos ao acaso, com quatro repetições, em esquema bifatorial (4 x 2 + 1: quatro tipos de ponta de pulverização (jato plano padrão, jato plano de pré-orifício, jato plano de indução de ar e jato plano duplo de indução de ar, dois volumes de aplicação (115 e 160L ha-1 e um tratamento adicional, que não recebeu fungicida (testemunha. Realizou-se a semeadura direta da cultivar "Emgopa 313" (ciclo tardio, avaliando-se, após a aplicação do fungicida tebuconazole com as diferentes pontas e volumes, a deposição de calda no dossel da cultura, a severidade da ferrugem e a produtividade. Constatou-se que, apesar de o volume de calda de 160L ha-1 e de a utilização da ponta de jato plano padrão terem proporcionado maior uniformidade de distribuição da calda fungicida nas plantas, não houve influência do tipo de ponta de pulverização e do volume de aplicação no controle da ferrugem e na produtividade da cultura da soja. O fungicida tebuconazole propiciou bom controle da ferrugem, refletindo na produtividade de grãos, que foi, em média, 41% superior à obtida na testemunha.The spray nozzles are one of the most important components of pesticide hydraulic sprayers. This study aimed at evaluating the chemical control of the rust and the deposition of fungicide sprayed on soybean concerning different nozzles, and application volumes. A randomized complete-block design with four replications was used, in a factorial model (4 x 2 + 1: four spray nozzles (standard flat fan, pre-orifice flat fan, air induction flat fan and

No-migration variance petition: Draft. Volume 4, Appendices DIF, GAS, GCR (Volume 1)

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-05-31

The Department of Energy is responsible for the disposition of transuranic (TRU) waste generated by national defense-related activities. Approximately 2.6 million cubic feet of the se waste have been generated and are stored at various facilities across the country. The Waste Isolation Pilot Plant (WIPP), was sited and constructed to meet stringent disposal requirements. In order to permanently dispose of TRU waste, the DOE has elected to petition the US EPA for a variance from the Land Disposal Restrictions of RCRA. This document fulfills the reporting requirements for the petition. This report is volume 4 of the petition which presents details about the transport characteristics across drum filter vents and polymer bags; gas generation reactions and rates during long-term WIPP operation; and geological characterization of the WIPP site.

No-migration variance petition: Draft. Volume 4, Appendices DIF, GAS, GCR (Volume 1)

International Nuclear Information System (INIS)

1995-01-01

The Department of Energy is responsible for the disposition of transuranic (TRU) waste generated by national defense-related activities. Approximately 2.6 million cubic feet of the se waste have been generated and are stored at various facilities across the country. The Waste Isolation Pilot Plant (WIPP), was sited and constructed to meet stringent disposal requirements. In order to permanently dispose of TRU waste, the DOE has elected to petition the US EPA for a variance from the Land Disposal Restrictions of RCRA. This document fulfills the reporting requirements for the petition. This report is volume 4 of the petition which presents details about the transport characteristics across drum filter vents and polymer bags; gas generation reactions and rates during long-term WIPP operation; and geological characterization of the WIPP site

GENII: The Hanford Environmental Radiation Dosimetry Software System: Volume 1, Conceptual representation

Energy Technology Data Exchange (ETDEWEB)

Napier, B.A.; Peloquin, R.A.; Strenge, D.L.; Ramsdell, J.V.

1988-12-01

The Hanford Environmental Dosimetry Upgrade Project was undertaken to incorporate the internal dosimetry models recommended by the International Commission on Radiological Protection (ICRP) in updated versions of the environmental pathway analysis models used at Hanford. The resulting second generation of Hanford environmental dosimetry computer codes is compiled in the Hanford Environmental Dosimetry System (Generation II, or GENII). The purpose of this coupled system of computer codes is to analyze environmental contamination resulting from acute or chronic releases to, or initial contamination of, air, water, or soil. This is accomplished by calculating radiation doses to individuals or populations. GENII is described in three volumes of documentation. The first volume describes the theoretical considerations of the system. The second volume is a Users' Manual, providing code structure, users' instructions, required system configurations, and QA-related topics. The third volume is a Code Maintenance Manual for the user who requires knowledge of code detail. It includes code logic diagrams, global dictionary, worksheets, example hand calculations, and listings of the code and its associated data libraries. 72 refs., 15 figs., 34 tabs.

GENII: The Hanford Environmental Radiation Dosimetry Software System: Volume 1, Conceptual representation

International Nuclear Information System (INIS)

Napier, B.A.; Peloquin, R.A.; Strenge, D.L.; Ramsdell, J.V.

1988-12-01

The Hanford Environmental Dosimetry Upgrade Project was undertaken to incorporate the internal dosimetry models recommended by the International Commission on Radiological Protection (ICRP) in updated versions of the environmental pathway analysis models used at Hanford. The resulting second generation of Hanford environmental dosimetry computer codes is compiled in the Hanford Environmental Dosimetry System (Generation II, or GENII). The purpose of this coupled system of computer codes is to analyze environmental contamination resulting from acute or chronic releases to, or initial contamination of, air, water, or soil. This is accomplished by calculating radiation doses to individuals or populations. GENII is described in three volumes of documentation. The first volume describes the theoretical considerations of the system. The second volume is a Users' Manual, providing code structure, users' instructions, required system configurations, and QA-related topics. The third volume is a Code Maintenance Manual for the user who requires knowledge of code detail. It includes code logic diagrams, global dictionary, worksheets, example hand calculations, and listings of the code and its associated data libraries. 72 refs., 15 figs., 34 tabs

Weapon container catalog. Volumes 1 & 2

Energy Technology Data Exchange (ETDEWEB)

Brown, L.A.; Higuera, M.C.

1998-02-01

The Weapon Container Catalog describes H-gear (shipping and storage containers, bomb hand trucks and the ancillary equipment required for loading) used for weapon programs and for special use containers. When completed, the catalog will contain five volumes. Volume 1 for enduring stockpile programs (B53, B61, B83, W62, W76, W78, W80, W84, W87, and W88) and Volume 2, Special Use Containers, are being released. The catalog is intended as a source of information for weapon program engineers and also provides historical information. The catalog also will be published on the SNL Internal Web and will undergo periodic updates.

FENDL/C-1.0. Charged-particle reaction data library for fusion applications Version 1.0 of November 1991. Summary documentation

International Nuclear Information System (INIS)

Pashchenko, A.B.

1995-01-01

This document describes the FENDL/C-1.0 charged-particle reaction data library which is a sublibrary of FENDL, the evaluated nuclear data library for fusion applications. This file contains evaluated data in ENDF-6 format for the D(d,n), D(d,p), T(d,n), T(t,2n), He-3(d,p) reactions. The processed information, i.e. Maxwellian-averaged reaction rates, and related quantities, calculated from reaction cross-sections, are also included. The data are available from the Nuclear Data Section online via INTERNET by FTP command, or on magnetic tape upon request. (author). 1 tab

Time-motion analysis of clinical nursing documentation during implementation of an electronic operating room management system for ophthalmic surgery.

Science.gov (United States)

Read-Brown, Sarah; Sanders, David S; Brown, Anna S; Yackel, Thomas R; Choi, Dongseok; Tu, Daniel C; Chiang, Michael F

2013-01-01

Efficiency and quality of documentation are critical in surgical settings because operating rooms are a major source of revenue, and because adverse events may have enormous consequences. Electronic health records (EHRs) have potential to impact surgical volume, quality, and documentation time. Ophthalmology is an ideal domain to examine these issues because procedures are high-throughput and demand efficient documentation. This time-motion study examines nursing documentation during implementation of an EHR operating room management system in an ophthalmology department. Key findings are: (1) EHR nursing documentation time was significantly worse during early implementation, but improved to a level near but slightly worse than paper baseline, (2) Mean documentation time varied significantly among nurses during early implementation, and (3) There was no decrease in operating room turnover time or surgical volume after implementation. These findings have important implications for ambulatory surgery departments planning EHR implementation, and for research in system design.

Technical Support Document for Version 3.9.1 of the COMcheck Software

Energy Technology Data Exchange (ETDEWEB)

Bartlett, Rosemarie; Connell, Linda M.; Gowri, Krishnan; Halverson, Mark A.; Lucas, Robert G.; Richman, Eric E.; Schultz, Robert W.; Winiarski, David W.

2012-09-01

COMcheck provides an optional way to demonstrate compliance with commercial and high-rise residential building energy codes. Commercial buildings include all use groups except single family and multifamily not over three stories in height. COMcheck was originally based on ANSI/ASHRAE/IES Standard 90.1-1989 (Standard 90.1-1989) requirements and is intended for use with various codes based on Standard 90.1, including the Codification of ASHRAE/IES Standard 90.1-1989 (90.1-1989 Code) (ASHRAE 1989a, 1993b) and ASHRAE/IESNA Standard 90.1-1999 (Standard 90.1-1999). This includes jurisdictions that have adopted the 90.1-1989 Code, Standard 90.1-1989, Standard 90.1-1999, or their own code based on one of these. We view Standard 90.1-1989 and the 90.1-1989 Code as having equivalent technical content and have used both as source documents in developing COMcheck. This technical support document (TSD) is designed to explain the technical basis for the COMcheck software as originally developed based on the ANSI/ASHRAE/IES Standard 90.1-1989 (Standard 90.1-1989). Documentation for other national model codes and standards and specific state energy codes supported in COMcheck has been added to this report as appendices. These appendices are intended to provide technical documentation for features specific to the supported codes and for any changes made for state-specific codes that differ from the standard features that support compliance with the national model codes and standards. Beginning with COMcheck version 3.8.0, support for 90.1-1989, 90.1-1999, and the 1998 IECC and version 3.9.0 support for 2000 and 2001 IECC are no longer included, but those sections remain in this document for reference purposes.

Results of combustion and emissions testing when co-firing blends of binder-enhanced densified refuse-derived fuel (b-dRDF) pellets and coal in a 440 MW{sub e} cyclone fired combustor. Volume 3: Appendices

Energy Technology Data Exchange (ETDEWEB)

Ohlsson, O.

1994-07-01

This report contains the data resulting from the co-firing of b-dRDF pellets and coal in a 440-MW{sub e} cyclone-fired combustor. These tests were conducted under a Collaborative Research and Development Agreement (CRADA). The CRADA partners included the U.S. Department of Energy (DOE), National Renewable Energy Laboratory (NREL), Argonne National Laboratory (ANL), Otter Tail Power Company, Green Isle Environmental, Inc., XL Recycling Corporation, and Marblehead Lime Company. The report is made up of three volumes. This volume contains other supporting information, along with quality assurance documentation and safety and test plans. With this multi-volume approach, readers can find information at the desired level of detail, depending on individual interest or need.

NRC review of Electric Power Research Institute's Advanced Light Water Reactor Utility Requirements Document - Evolutionary plant designs, Chapters 2--13, Project No. 669

International Nuclear Information System (INIS)

1992-08-01

The staff of the US Nuclear Regulatory Commission has prepared Volume 2 (Parts 1 and 2) of a safety evaluation report (SER), ''NRC Review of Electric Power Research Institute's Advanced Light Water Reactor Utility Requirements Document -- Evolutionary Plant Designs,'' to document the results of its review of the Electric Power Research Institute's ''Advanced Light Water Reactor Utility Requirements Document.'' This SER gives the results of the staff's review of Volume II of the Requirements Document for evolutionary plant designs, which consists of 13 chapters and contains utility design requirements for an evolutionary nuclear power plant (approximately 1300 megawatts-electric)

Efeitos de diferentes volumes correntes e da pressão expiratória final positiva sobre a troca gasosa na fístula broncopleural experimental Effects of different tidal volumes and positive end expiratory pressure on gas exchange in experimental bronchopleural fistula

Directory of Open Access Journals (Sweden)

Maria Gabriela Cavicchia Toneloto

2008-09-01

Full Text Available OBJETIVO: O presente estudo foi desenhado para identificar o efeito da pressão expiratória final positiva (PEEP e o volume corrente pulmonar ideal para ventilar animais com fístula broncopleural produzida cirurgicamente, com o intuito de reduzir a vazão da fístula sem afetar a troca gasosa. MÉTODOS: Avaliação hemodinâmica e respiratória da troca gasosa foi obtida em cinco porcos jovens, saudáveis, da linhagem Large White, ventilados mecanicamente no modo ventilatório volume controlado com FiO2 de 0.4 e relação inspiração:expiração em torno de 1:2, com freqüência respiratória mantida em 22 cpm. A fístula broncopleural foi produzida pela ressecção da língula. Um sistema de drenagem a selo d'água foi instalado e o tórax foi hermeticamente fechado. A troca gasosa e o débito da fístula broncopleural foram medidos com animais ventilados sequencialmente com volumes correntes de 4 ml/kg, 7 ml/kg e 10 ml/Kg alternando zero de pressão expiratória final positiva (ZEEP e PEEP de 10 cmH2O, sempre na mesma ordem. RESULTADOS: Esses dados são atribuídos à ventilação alveolar reduzida e às anormalidades da ventilação/perfusão que foram atenuadas com volumes correntes mais altos. PEEP aumentou o vazamento de ar pela fístula, mesmo com baixos volumes, de 2.0 ± 2,8mL para 31 ± 20,7mL (p= 0,006 e diminuiu a ventilação alveolar em todos os volumes correntes. A ventilação alveolar melhorou com altos volumes correntes, mas aumentou o débito da fístula (4 ml/kg - 2,0 ± 2,8mL e 10 mL/kg - 80,2 ± 43,9mL; p=0,001. Baixos volumes correntes resultaram em hipercapnia (ZEEP - 83,7± 6,9 mmHg e com PEEP 10 -93 ± 10,1mmHg e diminuição significativa da saturação de oxigênio arterial, em torno de 84%. CONCLUSÃO: O volume corrente de 7 ml/kg com ZEEP foi considerado o melhor volume corrente, visto que, apesar da hipercapnia moderada, a saturação de oxigênio arterial é sustentada em torno de 90%. A ventilação alveolar

Upon e-Documents: Evolution or Involution on GED Market

Directory of Open Access Journals (Sweden)

Mircea GEORGESCU

2006-01-01

Full Text Available In many organizations, vital information is trapped within individual desktops and fragmented in server silos across the enterprise. Manual, ad-hoc processes create inefficiencies, confusion and delays as employees waste time searching for important information. Organizations must find safer and easier ways to access, manage and share their content. Document and file management solutions designed to be used across the organization can help achieve these goals and reduce the total cost of managing content throughout the organization. If you decide to use an EDMS, your selection requires a careful, considered balance between your legal requirements and your technological options. The decision to use an EDMS requires significant planning and analysis. Managing documents more effectively, controlling costs associated with documents and document processes, and using resources more efficiently has become and will continue to be increasingly important to businesses and IT organizations.

Information Technology Act 2000 in India - Authentication of E-Documents

Directory of Open Access Journals (Sweden)

R. G. Pawar

2007-06-01

Full Text Available The Information Technology Act 2000 has enacted in India on 9th June 2000. This Act has mentioned provision of authentication of electronic document. It is the need of hour at that time that such provision is needed in the Indian Law system, especially for electronic commerce and electronic governance. Electronic commerce”, which involve the use of alternatives to paper based methods of communication and storage information. To do electronic commerce there should be authentication of particular document. The working of internet is the documents are traveling in terms of bits from one destination to other destination, through various media like – Co-axial cable, fiber optic, satellite etc. While traveling this document there is probability of making changes in that document by any third party is high or some document may get changed due to noise/disturbance in communication media. This Act required to provide legal recognition carried out by means of electronic data interchange and other means of electronic communication.In this paper researchers studied technological aspects of Information Technology Act 2000 like hash function, encryption, decryption, public key, private key etc. and its process. This paper gives details about certifying authority in detail. There should be some mechanism that will take care of document, that what ever the document is received should be the authentic one and it would not get changed in any manner due to any cause.

User information document for WinGridder Version 3.0

International Nuclear Information System (INIS)

Pan, Lehua; Pan, Lehua

2007-01-01

WINGRIDDER V3.0 is a Windows-based software for designing and generating numerical grids for numerical simulators that are based on the 'integral finite difference' or the 'control volume' numerical scheme (e.g., TOUGH2, Pruess et al., 1996). The user can design and generate grid that properly represents the stratigraphic features, inclined faults, and repository. WINGRIDDER V3.0 is an upgrade from WINGRIDDER V2.0. This revision includes testable requirements as listed in the Requirements Document (RD), 10024-RD-3.0-00, Section 2. With new features, WINGRIDDER V3.0 adds the ability to generate a multiple-interactive-continuum (MINC) grid

Preoperational baseline and site characterization report for the Environmental Restoration Disposal Facility. Volume 2, Revision 2

International Nuclear Information System (INIS)

Weekes, D.C.; Lindsey, K.A.; Ford, B.H.; Jaeger, G.K.

1996-12-01

This document is Volume 2 in a two-volume series that comprise the site characterization report, the Preoperational Baseline and Site Characterization Report for the Environmental Restoration Disposal Facility. Volume 1 contains data interpretation and information supporting the conclusions in the main text. This document presents original data in support of Volume 1 of the report. The following types of data are presented: well construction reports; borehole logs; borehole geophysical data; well development and pump installation; survey reports; preoperational baseline chemical data and aquifer test data. Five groundwater monitoring wells, six deep characterization boreholes, and two shallow characterization boreholes were drilled at the Environmental Restoration Disposal Facility (ERDF) site to directly investigate site-specific hydrogeologic conditions

FacetGist: Collective Extraction of Document Facets in Large Technical Corpora.

Science.gov (United States)

Siddiqui, Tarique; Ren, Xiang; Parameswaran, Aditya; Han, Jiawei

2016-10-01

Given the large volume of technical documents available, it is crucial to automatically organize and categorize these documents to be able to understand and extract value from them. Towards this end, we introduce a new research problem called Facet Extraction. Given a collection of technical documents, the goal of Facet Extraction is to automatically label each document with a set of concepts for the key facets ( e.g. , application, technique, evaluation metrics, and dataset) that people may be interested in. Facet Extraction has numerous applications, including document summarization, literature search, patent search and business intelligence. The major challenge in performing Facet Extraction arises from multiple sources: concept extraction, concept to facet matching, and facet disambiguation. To tackle these challenges, we develop FacetGist, a framework for facet extraction. Facet Extraction involves constructing a graph-based heterogeneous network to capture information available across multiple local sentence-level features, as well as global context features. We then formulate a joint optimization problem, and propose an efficient algorithm for graph-based label propagation to estimate the facet of each concept mention. Experimental results on technical corpora from two domains demonstrate that Facet Extraction can lead to an improvement of over 25% in both precision and recall over competing schemes.

Evaluation of potential severe accidents during low power and shutdown operations at Surry, Unit-1: Analysis of core damage frequency from internal events during mid-loop operations. Appendices F-H, Volume 2, Part 4

International Nuclear Information System (INIS)

Chu, T.L.; Musicki, Z.; Kohut, P.; Yang, J.; Bozoki, G.; Hsu, C.J.; Diamond, D.J.; Bley, D.; Johnson, D.; Holmes, B.

1994-06-01

Traditionally, probabilistic risk assessments (PRA) of severe accidents in nuclear power plants have considered initiating events potentially occurring only during full power operation. Some previous screening analyses that were performed for other modes of operation suggested that risks during those modes were small relative to full power operation. However, more recent studies and operational experience have implied that accidents during low power and shutdown could be significant contributors to risk. Two plants, Surry (pressurized water reactor) and Grand Gulf (boiling water reactor), were selected as the plants to be studied. The objectives of the program are to assess the risks of severe accidents initiated during plant operational states other than full power operation and to compare the estimated core damage frequencies, important accident sequences and other qualitative and quantitative results with those accidents initiated during full power operation as assessed in NUREG-1150. The scope of the program includes that of a level-3 PRA. In phase 2, mid-loop operation was selected as the plant configuration to be analyzed based on the results of the phase 1 study. The objective of the phase 2 study is to perform a detailed analysis of the potential accident scenarios that may occur during mid-loop operation, and compare the results with those of NUREG-1150. The scope of the level-1 study includes plant damage state analysis, and uncertainty analysis. Volume 1 summarizes the results of the study. Internal events analysis is documented in Volume 2. It also contains an appendix that documents the part of the phase 1 study that has to do with POSs other than mid-loop operation. Internal fire and internal flood analyses are documented in Volumes 3 and 4. A separate study on seismic analysis, documented in Volume 5, was performed for the NRC by Future Resources Associates, Inc. Volume 6 documents the accident progression, source terms, and consequence analysis

Preoperational baseline and site characterization report for the Environmental Restoration Disposal Facility. Volume 1, Revision 2

International Nuclear Information System (INIS)

Weekes, D.C.; Lindsey, K.A.; Ford, B.H.; Jaeger, G.K.

1996-12-01

This document is the first in a two-volume series that comprise the site characterization report. Volume 1 contains data interpretation and information supporting the conclusions in the text (Appendices A through G). Volume 2 provides raw data. A site located between 200 East and 200 West Areas, in the central portion of the Hanford Site, was selected as the prime location for the ERDF. Modifications to the facility design minimize the footprint and have resulted in a significant reduction in the areal size. This change was initiated in part as a response to recommendations of the Hanford Future Site Uses Working Group to limit waste management activities to an exclusive zone within the squared-off boundary of the 200 Areas. Additionally, the reduction in size of the footprint was initiated to minimize impacts to ecology. The ERDF is designed for disposal of remediation wastes generated during the cleanup of Hanford Site and could be expanded to hold as much as 28 million yd 3 (21.4 million m 3 ) of solid waste

High-level waste storage tank farms/242-A evaporator Standards/Requirements Identification Document (S/RID)