FY 1984 scientific and technical reports, articles, papers and presentations

Science.gov (United States)

Turner, J. E. (Compiler)

1984-01-01

This bibliography lists formal NASA technical reports, papers published in technical journals, and presentations by MSFC personnel. Abstracts are presented for 56 technical memorandum, and 13 technical papers. Six publications, over 260 contractor reports, and more than 300 papers cleared for publication are cited.

Technical and economic assessment of fluidized bed augmented compressed air energy storage system. Volume III. Preconceptual design

Energy Technology Data Exchange (ETDEWEB)

Giramonti, A.J.; Lessard, R.D.; Merrick, D.; Hobson, M.J.

1981-09-01

A technical and economic assessment of fluidized bed combustion augmented compressed air energy storage systems is presented. The results of this assessment effort are presented in three volumes. Volume III - Preconceptual Design contains the system analysis which led to the identification of a preferred component configuration for a fluidized bed combustion augmented compressed air energy storage system, the results of the effort which transformed the preferred configuration into preconceptual power plant design, and an introductory evaluation of the performance of the power plant system during part-load operation and while load following.

Benefit-Cost Analysis of Integrated Paratransit Systems : Volume 6. Technical Appendices.

Science.gov (United States)

1979-09-01

This last volume, includes five technical appendices which document the methodologies used in the benefit-cost analysis. They are the following: Scenario analysis methodology; Impact estimation; Example of impact estimation; Sensitivity analysis; Agg...

Pollutant Assessments Group procedures manual: Volume 2, Technical procedures

Energy Technology Data Exchange (ETDEWEB)

1992-03-01

This is volume 2 of the manuals that describes the technical procedures currently in use by the Pollution Assessments Group. This manual incorporates new developments in hazardous waste assessment technology and administrative policy. Descriptions of the equipment, procedures and operations of such things as radiation detection, soil sampling, radionuclide monitoring, and equipment decontamination are included in this manual. (MB)

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

Index to Nuclear Safety: a technical progress review by chronology, permuted title, and author, Volume 18 (1) through Volume 22 (6)

International Nuclear Information System (INIS)

Cottrell, W.B.; Passiakos, M.

1982-06-01

This index to Nuclear Safety covers articles published in Nuclear Safety, Volume 18, Number 1 (January-February 1977) through Volume 22, Number 6 (November-December 1981). The index is divided into three section: a chronological list of articles (including abstracts), a permuted-title (KWIC) index, and an author index. Nuclear Safety, a bimonthly technical progress review prepared by the Nuclear Safety Information Center, covers all safety aspects of nuclear power reactors and associated facilities. Over 300 technical articles published in Nuclear Safety in the last 5 years are listed in this index

Index to Nuclear Safety: a technical progress review by chronology, permuted title, and author, Volume 18 (1) through Volume 22 (6)

Energy Technology Data Exchange (ETDEWEB)

Cottrell, W.B.; Passiakos, M.

1982-06-01

This index to Nuclear Safety covers articles published in Nuclear Safety, Volume 18, Number 1 (January-February 1977) through Volume 22, Number 6 (November-December 1981). The index is divided into three section: a chronological list of articles (including abstracts), a permuted-title (KWIC) index, and an author index. Nuclear Safety, a bimonthly technical progress review prepared by the Nuclear Safety Information Center, covers all safety aspects of nuclear power reactors and associated facilities. Over 300 technical articles published in Nuclear Safety in the last 5 years are listed in this index.

Isotope Brayton ground demonstration testing and flight qualification. Volume 1. Technical program

Energy Technology Data Exchange (ETDEWEB)

1974-12-09

A program is proposed for the ground demonstration, development, and flight qualification of a radioisotope nuclear heated dynamic power system for use on space missions beginning in the 1980's. This type of electrical power system is based upon and combines two aerospace technologies currently under intense development; namely, the MHW isotope heat source and the closed Brayton cycle gas turbine. This power system represents the next generation of reliable, efficient economic electrical power equipment for space, and will be capable of providing 0.5 to 2.0 kW of electric power to a wide variety of spacecraft for earth orbital and interplanetary missions. The immediate design will be based upon the requirements for the Air Force SURVSATCOM mission. The proposal is presented in three volumes plus an Executive Summary. This volume describes the tasks in the technical program.

FY 2002 Scientific and Technical Reports, Articles, Papers, and Presentations

Science.gov (United States)

Fowler, B. A. (Compiler)

2003-01-01

This Technical Memorandum (TM) presents formal NASA technical reports, papers published in technical journals, and presentations by MSFC personnel in FY 2002. It also includes papers of MSFC contractors. The information in this TM may be of value to the scientific and engineering community in determining what information has been published and what is available.

FY 2005 Scientific and Technical Reports, Articles, Papers, and Presentations

Science.gov (United States)

Narmore, K. A. (Compiler)

2007-01-01

This Technical Memorandum (TM) presents formal NASA technical reports, papers published in technical journals, and presentations by Marshall Space Flight Center (MSFC) personnel in FY 2005. It also includes papers of MSFC contractors. The information in this TM may be of value to the scientific and engineering community in determining what information has been published and what is available.

FY 1985 scientific and technical reports, articles, papers and presentations

Science.gov (United States)

Turner, Joyce E. (Compiler)

1985-01-01

This document presents formal NASA technical reports, papers published in technical journals, and presentations by Marshal Space Flight Center (MSFC) personnel in FY 85. It also includes papers of MSFC contractors. After being announced in STAR, all of the NASA series reports may be obtained from the National Technical Information Service (NTIS), 5285 Port Royal Road, Springfield, Va. 22161.

FY 2004 Scientific and Technical Reports, Articles, Papers, and Presentations

Science.gov (United States)

Fowler, B. A. (Compiler)

2006-01-01

This Technical Memorandum (TM) presents formal NASA technical reports, papers published in technical journals, and presentations by Marshall Space Flight Center (MSFC) personnel FY 2004. It also includes papers of MSFC contractors. After being announced in STAR, all NASA series reports may be obtained from the National Technical Information Service, 5285 Port Royal Road, Springfield, VA 22161. The information in this TM maybe of value to the scientific and engineering community in determining what information has been published and what is available.

FY 2001 Scientific and Technical Reports, Articles, Papers, and Presentations

Science.gov (United States)

Waits, J. E. Turner (Compiler)

2002-01-01

This Technical Memorandum (TM) presents formal NASA technical reports, papers published in technical journals, and presentations by MSFC personnel in FY 2001. It also includes papers of MSFC contractors. After being announced in STAR, all NASA series reports may be obtained from the National Technical Information Service, 5285 Port Royal Road, Springfield, VA 22161. The information in this TM may be of value to the scientific and engineering community in determining what information has been published and what is available.

FY 1986 scientific and technical reports, articles, papers and presentations

Science.gov (United States)

Turner, Joyce E. (Compiler)

1986-01-01

Formal NASA technical reports, papers published in technical journals, and presentations by Marshall Space Flight Center (MSFC) personnel in FY-86 are presented. Also included are papers of MSFC contractors.

FY 1989 scientific and technical reports, articles, papers, and presentations

Science.gov (United States)

Turner, Joyce E. (Compiler)

1989-01-01

A compendium of bibliographic references to papers presented by Marshall Space Flight Center (MSFC) personnel and contractors during FY 1989 is provided. The papers include formal NASA technical reports, memoranda, papers which were published in technical journals, and presentations by MSFC personnel. The formal NASA technical reports and memoranda have abstracts included. Sources for obtaining these documents are also included.

FY 2003 Scientific and Technical Reports, Articles, Papers, and Presentations

Science.gov (United States)

Fowler, B. A. (Compiler)

2004-01-01

This Technical Memorandum (TM) presents formal NASA technical reports, papers published in technical journals, and presentations by Marshall Space Flight Center (MSFC) personnel in FY 2003. It also includes papers of MSFC contractors. After being announced in STAR, all NASA series reports may be obtained from the National Technical Information Service, 5285 Port Royal Road, Spring.eld, VA 22161. The information in this TM may be of value to the scientific and engineering community in determining what information has been published and what is available.

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

Technical presentation: Next Generation Oscilloscopes

CERN Multimedia

PH Department

2011-01-01

  Rohde & Schwarz "Next Generation Oscilloscopes" - Introduction and Presentation Agenda: Wednesday 23 March  -  09:30 to 11:30 (open end) Bldg. 13-2-005 Language: English 09.30 Presentation "Next Generation Oscilloscopes" from Rohde & Schwarz RTO / RTM in theory and practice Gerard Walker 10.15 Technical design details from R&D Dr. Markus Freidhof 10.45 Scope and Probe Roadmap (confidential) Guido Schulze 11.00 Open Discussion Feedback, first impression, wishes, needs and requirements from CERN All 11.30 Expert Talks, Hands on All Mr. Dr. Markus Freidhof, Head of R&D Oscilloscopes, Rohde & Schwarz, Germany; Mr. Guido Schulze, ...

Performance evaluation of the technical capabilities of DOE sites for disposal of mixed low-level waste. Volume 2: Technical basis and discussion of results

International Nuclear Information System (INIS)

Waters, R.D.; Gruebel, M.M.; Hospelhorn, M.B.

1996-03-01

A team of analysts designed and conducted a performance evaluation to estimate the technical capabilities of fifteen Department of Energy sites for disposal of mixed low-level waste (i.e., waste that contains both low-level radioactive materials and hazardous constituents). Volume 1 summarizes the process for selecting the fifteen sites, the methodology used in the evaluation, and the conclusions derived from the evaluation. Volume 2 first describes the screening process used to determine the sites to be considered in the PEs. This volume then provides the technical details of the methodology for conducting the performance evaluations. It also provides a comparison and analysis of the overall results for all sites that were evaluated. Volume 3 contains detailed evaluations of the fifteen sites and discussions of the results for each site

The Acoustical Presentation of Technical Information.

Science.gov (United States)

Barnett, George A.

1992-01-01

Advocates listening to technical information in much the same way as scientists and engineers look at graphics to understand the relationships among variables. Specifies a number of potential benefits of this approach. Demonstrates the presentation of acoustic information with data on the frequency of television viewing from 1950 to 1988. (SR)

Technical support for GEIS: radioactive waste isoltaion in geologic formations. Volume 19. Thermal analyses

International Nuclear Information System (INIS)

1978-04-01

This volume, Y/OWI/TM-36/19, ''Thermal Analyses,'' is one of a 23-volume series, ''Technical Support for GEIS: Radioactive Waste Isolation in Geologic Formations,'' Y/OWI/TM-36, which supplements the ''Contribution to Draft Generic Environmental Impact Statement on Commercial Waste Management: Radioactive Waste Isolation in Geologic Formations,'' Y/OWI/TM-44. The series provides a more complete technical basis for the preconceptual designs, resource requirements, and environmental source terms associated with isolating commercial LWR wastes in underground repositories in salt, granite, shale and basalt. Wastes are considered from three fuel cycles: uranium and plutonium recycling, no recycling of spent fuel and uranium-only recycling. This volume discusses the thermal impacts of the isolated high level and spent-fuel wastes in geologic formations. A detailed account of the methodologies employed is given as well as selected results of the analyses

FY 1998 Scientific and Technical Reports, Articles, Papers, and Presentations

Science.gov (United States)

Waits, J. E. Turner (Compiler)

1999-01-01

This document presents formal NASA technical reports, papers published in technical journals, and presentations by MSFC (Marshall Space Flight Center) personnel in FY98. It also includes papers of MSFC contractors. After being announced in STAR, all of the NASA series reports may be obtained from the National Technical Information Service. The information in this report may be of value to the scientific and engineering community in determining what information has been published and what is available.

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

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

FY 1997 Scientific and Technical Reports, Articles, Papers, and Presentations

Science.gov (United States)

Waits, J. E. Turner (Compiler)

1998-01-01

This document presents formal NASA technical reports, papers published in technical journals, and presentations by MSFC personnel in FY97. The information in this report may be of value to the scientific and engineering community in determining what information has been published and what is available.

FY87 scientific and technical reports, articles, papers, and presentations

Science.gov (United States)

Turner, Joyce E. (Compiler)

1987-01-01

The document presents formal NASA technical reports, papers published in technical journals, and presentations by MSFC personnel in FY87. It also includes papers of MSFC contractors. After being announced in STAR, all of the NASA series reports may be obtained from the National Technical Information Service, 5285 Port Royal Road, Springfield, Va. 22161. The information in this report may be of value to the scientific and engineering community in determining what information has been published and what is available.

FY 1988 scientific and technical reports, articles, papers and presentations

Science.gov (United States)

Turner, Joyce E. (Compiler)

1988-01-01

This document presents formal NASA technical reports, papers published in technical journals, and presentations by MSFC personnel in FY 88. It also includes papers of MSFC contractors. After being announced in STAR, all of the NASA series reports may be obtained from the NationaL Technical Information Service, 5285 Port Royal Road, Springfield, VA 22161. The information in this report may be of value to the scientific and engineering community in determining what information has been published and what is available.

Technical Writing: Past, Present and Future

Science.gov (United States)

Mathes, J. C. (Compiler); Pinelli, T. E. (Compiler)

1981-01-01

The training of technical writers and the objectives of such education are discussed. Special emphasis was placed on the communication between technical personnel and non-technical personnel. The liabilities that affect technical writers were also discussed.

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.

FY 1991 scientific and technical reports, articles, papers, and presentations

Science.gov (United States)

Turner, Joyce E. (Compiler)

1991-01-01

Formal NASA technical reports, papers published in technical journals, and presentations by MSFC personnel in FY 1991 are presented. Papers of MSFC contractors are also included. The information in this report may be of value to the scientific and engineering community in determining what information has been published and what is available.

Fiscal year 1979 scientific and technical reports, articles, papers and presentations

Science.gov (United States)

White, O. L. (Compiler)

1979-01-01

This bibliography lists approximately 590 formal NASA technical reports, papers published in technical journals, presentations by MSFC personnel, and reports of MSFC contractors introduced into the NASA scientific and technical information system in 1979.

Abbreviations [Annex to The Fukushima Daiichi Accident, Technical Volume 5/5

International Nuclear Information System (INIS)

2015-01-01

This annex is a list of abbreviations used in the publication The Fukushima Daiichi Accident, Technical Volume 5/5. The list includes the abbreviations for: • General Safety Requirements; • International Commission on Radiological Protection; • Intensive Contamination Survey Area; • International Experts Meeting; • Ministry of Education, Culture, Sports, Science and Technology; • Ministry of the Environment; • Nuclear Damage Compensation and Decommissioning Facilitation Corporation; • Nuclear Emergency Response Headquarters; • nuclear power plant; • Nuclear Safety Commission; • OECD Nuclear Energy Agency; • Special Decontamination Area; • Specific Safety Requirements; • technical cooperation; • Three Mile Island; • United Nations Scientific Committee on the Effects of Atomic Radiation

FY 1994 scientific and technical reports, articles, papers, and presentations

Science.gov (United States)

Turner, Joyce E. (Compiler)

1994-01-01

This document presents formal NASA technical reports, papers published in technical journals, and presentations by Marshall Space Flight Center personnel in FY94. It also includes papers of MSFC contractors and author indexes. The information in this report may be of value to the scientific and engineering community in determining what information has been published and what is available.

Technical support for GEIS: radioactive waste isolation in geologic formations. Volume 21. Ground water movement and nuclide transport

Energy Technology Data Exchange (ETDEWEB)

None

1978-04-01

This volume, TM-36/21 Ground Water Movement and Nuclide Transport, is one of a 23-volume series, ''Technical Support for GEIS: Radioactive Waste Isolation in Geologic Formations, Y/OWI/TM-36'' which supplements a ''Contribution to Draft Generic Environmental Impact Statement on Commercial Waste Management: Radioactive Waste Isolation in Geologic Formations, Y/OWI/TM-44.'' The series provides a more complete technical basis for the preconceptual designs, resource requirements, and environmental source terms associated with isolating commercial LWR wastes in underground repositories in salt, granite, shale and basalt. Wastes are considered from three fuel cycles: uranium and plutonium recycling of spent fuel and uranium-only recycling. The studies presented in this volume consider the effect of the construction of the repository and the consequent heat generation on the ground water movement. Additionally, the source concentrations and leach rates of selected radionuclides were studied in relation to the estimated ground water inflow rates. Studies were also performed to evaluate the long term migration of radionuclides as affected by the ground water flow. In all these studies, three geologic environments are considered; granite, shale and basalt.

North American Natural Gas Markets: Selected technical studies. Volume 3

Energy Technology Data Exchange (ETDEWEB)

Huntington, H.G.; Schuler, G.E. [eds.

1989-04-01

The Energy Modeling Forum (EMF) was established in 1976 at Stanford University to provide a structural framework within which energy experts, analysts, and policymakers could meet to improve their understanding of critical energy problems. The ninth EMF study, North American Natural Gas Markets, was conducted by a working group comprised of leading natural gas analysts and decision-makers from government, private companies, universities, and research and consulting organizations. The EMF 9 working group met five times from October 1986 through June 1988 to discuss key issues and analyze natural gas markets. This third volume includes technical papers that support many of the conclusions discussed in the EMF 9 summary report (Volume 1) and full working group report (Volume 2). These papers discuss the results from the individual models as well as some nonmodeling analysis related to US natural gas imports and industrial natural gas demand. Individual papers have been processed separately for inclusion in the Energy Science and Technology Database.

High integrity software for nuclear power plants: Candidate guidelines, technical basis and research needs. Executive summary: Volume 1

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 software used in the safety systems of nuclear power plants. The framework for the work consisted of the following software development and assurance activities: requirements specification; design; coding; verification and validation, including 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 range of software life-cycle activities; the assessment of the 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 framework 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; Volume 2 is the main report

Fiscal year 1981 scientific and technical reports, articles, papers, and presentations

Science.gov (United States)

Thacker, S. S. (Compiler)

1981-01-01

This bibliography lists approximately 503 formal NASA technical reports, papers published in technical journals, and presentations by MSFC personnel in FY-1981. It also includes papers of MSFC contractors. Citations announced in the NASA scientific and technical information system are noted.

Technical Reports (Part I). End of Project Report, 1968-1971, Volume III.

Science.gov (United States)

Western Nevada Regional Education Center, Lovelock.

The pamphlets included in this volume are technical reports prepared as outgrowths of the Student Information Systems of the Western Nevada Regional Education Center (WN-REC) funded by a Title III (Elementary and Secondary Education Act) grant. These reports describe methods of interpreting the printouts from the Student Information System;…

FY 1990 scientific and technical reports, articles, papers, and presentations

Science.gov (United States)

Turner, Joyce E. (Compiler)

1990-01-01

Formal NASA technical reports, papers published in technical journals, and presentations by MSFC personnel in FY 90 are presented. Also included are papers of MSFC contractors. After being announced in STAR, all of the NASA series reports may be obtained from NTIS. The information may be of value to the scientific and engineering community in determining what information has been published and what is available.

Third International Mathematics and Science Study 1999 Video Study Technical Report: Volume 2--Science. Technical Report. NCES 2011-049

Science.gov (United States)

Garnier, Helen E.; Lemmens, Meike; Druker, Stephen L.; Roth, Kathleen J.

2011-01-01

This second volume of the Third International Mathematics and Science Study (TIMSS) 1999 Video Study Technical Report focuses on every aspect of the planning, implementation, processing, analysis, and reporting of the science components of the TIMSS 1999 Video Study. The report is intended to serve as a record of the actions and documentation of…

Fiscal year 1993 scientific and technical reports, articles, papers, and presentations

Science.gov (United States)

Turner, Joyce E. (Compiler)

1993-01-01

This document presents formal NASA technical reports, papers published in technical journals, and presentations by MSFC personnel in FY93. It also includes papers of MSFC contractors. After being announced in STAR, all of the NASA series reports may be obtained from the National Technical Information Service, 5285 Port Royal Road, Springfield, VA 22161. The information in this report may be of value to the scientific and engineering community in determining what information has been published and what is available.

The FY 1992 scientific and technical reports, articles, papers, and presentations

Science.gov (United States)

Turner, Joyce E. (Compiler)

1992-01-01

This document presents formal NASA technical reports, papers published in technical journals, and presentations by MSFC personnel in FY92. It also includes papers of MSFC contractors. After being announced in STAR, all of the NASA series reports may be obtained from the National Technical Information Service, 5285 Port Royal Road, Springfield, VA 22161. The information in this report may be of value to the scientific and engineering community in determining what information has been published and what is available.

Technical Reports (Part II). End of Project Report, 1968-1971, Volume IV.

Science.gov (United States)

Western Nevada Regional Education Center, Lovelock.

The pamphlets included in this volume are technical reports prepared as outgrowths of the Student Information System of the Western Nevada Regional Education Center funded by a Title III grant under the Elementary and Secondary Education Act of 1965. These reports demonstrate the use of the stored data; methods of interpreting the printouts from…

Drishti: a volume exploration and presentation tool

Science.gov (United States)

Limaye, Ajay

2012-10-01

Among several rendering techniques for volumetric data, direct volume rendering is a powerful visualization tool for a wide variety of applications. This paper describes the major features of hardware based volume exploration and presentation tool - Drishti. The word, Drishti, stands for vision or insight in Sanskrit, an ancient Indian language. Drishti is a cross-platform open-source volume rendering system that delivers high quality, state of the art renderings. The features in Drishti include, though not limited to, production quality rendering, volume sculpting, multi-resolution zooming, transfer function blending, profile generation, measurement tools, mesh generation, stereo/anaglyph/crosseye renderings. Ultimately, Drishti provides an intuitive and powerful interface for choreographing animations.

Commingled uranium-tailings study. Volume II. Technical report

Energy Technology Data Exchange (ETDEWEB)

None

1982-06-30

Public Law 96-540, Section 213, directs the Secretary of Energy to develop a plan for a cooperative program to provide assistance in the stabilization and management of defense-related uranium mill tailings commingled with other tailings. In developing the plan, the Secretary is further directed to: (1) establish the amount and condition of tailings generated under federal contracts; (2) examine appropriate methodologies for establishing the extent of federal assistance; and (3) consult with the owners and operators of each site. This technical report summarizes US Department of Energy (DOE) and contractor activities in pursuit of items (1), (2), and (3) above. Recommendations regarding policy and a cooperative plan for federal assistance are under separate cover as Volume I.

FY 1999 Scientific and Technical Reports, Articles, Papers, and Presentations

Science.gov (United States)

Waits, J.oyce E.Turner

2000-01-01

This document presents formal NASA technical reports, papers published in technical journals, and presentations by MSFC personnel in FY99. It also includes papers of MSFC contractors. All of the NASA series reports may be obtained from the NASA Center for AeroSpace Information (CASI), 7121 Standard Drive, Hanover, MD 21076-1320 The information in this report may be of value to the scientific and engineering community in determining what information has been published and what is available.

Technical presentation

CERN Multimedia

GS Department

2010-01-01

10 March 2010 DYNEOS 10:00 – 12:00 - Main Building, Room B, 61-1-009 Dyneos AG is active in the fields of photonics, laser and high-precision positioning. Our highly qualified engineer team has more than 30 years of experience in electro-optical solutions sales. The engineers are supported by a technical and administrative team. We are focused on the Swiss market and represent six suppliers (Coherent, PI Physik Instrumente, SIOS, Nanonics Imaging, APE, Ekspla) in order to give a qualified sales and service support to our customers. Our products are dedicated to the research field as well as to industry. In addition to standard catalog products, we offer custom designs to fulfill the specific needs of OEM customers or specific applications.

Compilation of interim technical research memoranda. Volume I

International Nuclear Information System (INIS)

Shanahan, W.R.

1984-04-01

Four interim technical research memoranda are presented that describe the results of numerical simulations designed to investigate the dynamics of energetic plasma beams propagating across magnetic fields

Technical area status report for chemical/physical treatment. Volume 2, Appendices

Energy Technology Data Exchange (ETDEWEB)

Brown, C.H. Jr. [Oak Ridge National Lab., TN (United States); Schwinkendorf, W.E. [BDM Federal, Inc., Arlington, VA (United States)

1993-08-01

These Appendices describe various technologies that may be applicable to the Mixed Waste Treatment Plant (MWTP) Chemical/Physical Treatment System (CPTS). These technologies were identified by the CPTS Technical Support Group (TSG) as potentially applicable to a variety of separation, volume reduction, and decontamination requirements. The purpose was to identify all available and developing technologies, and their characteristics, for subsequent evaluation for specific requirements identified for the CPTS. However, the technologies described herein are not necessarily all inclusive, nor are they necessarily all applicable.

The International Linear Collider Technical Design Report - Volume 2: Physics

CERN Document Server

Barklow, Tim; Fujii, Keisuke; Gao, Yuanning; Hoang, Andre; Kanemura, Shinya; List, Jenny; Logan, Heather E; Nomerotski, Andrei; Perelstein, Maxim; Peskin, Michael E; Pöschl, Roman; Reuter, Jürgen; Riemann, Sabine; Savoy-Navarro, Aurore; Servant, Geraldine; Tait, Tim M P

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...

The International Linear Collider Technical Design Report - Volume 4: Detectors

CERN Document Server

Behnke, Ties; Burrows, Philip N.; Fuster, Juan; Peskin, Michael; Stanitzki, Marcel; Sugimoto, Yasuhiro; Yamada, Sakue; 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...

Spent nuclear fuel project technical databook

Energy Technology Data Exchange (ETDEWEB)

Reilly, M.A.

1998-07-22

The Spent Nuclear Fuel (SNF) project technical databook provides project-approved summary tables of selected parameters and derived physical quantities, with nominal design and safety basis values. It contains the parameters necessary for a complete documentation basis of the SNF Project technical and safety baseline. The databook is presented in two volumes. Volume 1 presents K Basins SNF related information. Volume 2 (not yet available) will present selected sludge and water information, as it relates to the sludge and water removal projects. The values, within this databook, shall be used as the foundation for analyses, modeling, assumptions, or other input to SNF project safety analyses or design. All analysis and modeling using a parameter available in this databook are required to use and cite the appropriate associated value, and document any changes to those values (i.e., analysis assumptions, equipment conditions, etc). Characterization and analysis efforts are ongoing to validate, or update these values.

Spent nuclear fuel project technical databook

International Nuclear Information System (INIS)

Reilly, M.A.

1998-01-01

The Spent Nuclear Fuel (SNF) project technical databook provides project-approved summary tables of selected parameters and derived physical quantities, with nominal design and safety basis values. It contains the parameters necessary for a complete documentation basis of the SNF Project technical and safety baseline. The databook is presented in two volumes. Volume 1 presents K Basins SNF related information. Volume 2 (not yet available) will present selected sludge and water information, as it relates to the sludge and water removal projects. The values, within this databook, shall be used as the foundation for analyses, modeling, assumptions, or other input to SNF project safety analyses or design. All analysis and modeling using a parameter available in this databook are required to use and cite the appropriate associated value, and document any changes to those values (i.e., analysis assumptions, equipment conditions, etc). Characterization and analysis efforts are ongoing to validate, or update these values

The International Linear Collider Technical Design Report - Volume 3.I: Accelerator \\& in the Technical Design Phase

Energy Technology Data Exchange (ETDEWEB)

Adolphsen, Chris [SLAC National Accelerator Lab., Menlo Park, CA (United States); et al.

2013-06-26

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 increase significantly our understanding of the fundamental processes that govern the evolution of the Universe.

Recovery of Navy distillate fuel from reclaimed product. Volume I. Technical discussion

Energy Technology Data Exchange (ETDEWEB)

Brinkman, D.W.; Whisman, M.L.

1984-11-01

In an effort to assist the Navy to better utilize its waste hydrocarbons, NIPER, with support from the US Department of Energy, is conducting research designed to ultimately develop a practical technique for converting Reclaimed Product (RP) into specification Naval Distillate Fuel (F-76). The first phase of the project was focused on reviewing the literature and available information from equipment manufacturers. The literature survey has been carefully culled for methodology applicable to the conversion of RP into diesel fuel suitable for Navy use. Based upon the results of this study, a second phase has been developed and outlined in which experiments will be performed to determine the most practical recycling technologies. It is realized that the final selection of one particular technology may be site-specific due to vast differences in RP volume and available facilities. A final phase, if funded, would involve full-scale testing of one of the recommended techniques at a refueling depot. The Phase I investigations are published in two volumes. Volume 1, Technical Discussion, includes the narrative and Appendices I and II. Appendix III, a detailed Literature Review, includes both a narrative portion and an annotated bibliography containing about 800 referenvces and abstracts. This appendix, because of its volume, has been published separately as Volume 2. 18 figures, 4 tables.

Technical presentation: BGM Cryogenic Engineering Limited

CERN Multimedia

Caroline Laignel - FI Department

2006-01-01

13 - 14 June 2006 TECHNICAL PRESENTATION BGM Cryogenic Engineering Limited 09:00 - 18:00, 60-2-016, Main Building. Presentation on BGM: 11:00 - 12:00, 60-2-016, Main Building. BGM Cryogenic Engineering Limited manufactures assemblies, sub-assemblies and machined components for the cryogenic technology sector. The primary markets served include superconducting magnets used in the healthcare sector (eg MRI body scanners), spectroscopy and NMR equipment for numerous R & D and technology applications, high vacuum applications and particle physics research. BGM has specialist assembly capability including stainless steel and aluminium welding, vacuum testing, electromechanical assembly and metal finishing. BGM offers a ‘one stop shop'facility to satisfy any customer requirement. Through our design partner we can offer a full design and modelling service, including 3D modelling and production of 2D drawings on your own borders. We can conduct heat load and force calculations and advise on the best...

Standard technical specifications combustion engineering plants: 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 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

Technical specifications manual for the MARK-1 pulsed ionizing radiation detection system. Volume 1

Energy Technology Data Exchange (ETDEWEB)

Lawrence, R.S.; Harker, Y.D.; Jones, J.L.; Hoggan, J.M.

1993-03-01

The MARK-1 detection system was developed by the Idaho National Engineering Laboratory for the US Department of Energy Office of Arms Control and Nonproliferation. The completely portable system was designed for the detection and analysis of intense photon emissions from pulsed ionizing radiation sources. This manual presents the technical design specifications for the MARK-1 detection system and was written primarily to assist the support or service technician in the service, calibration, and repair of the system. The manual presents the general detection system theory, the MARK-1 component design specifications, the acquisition and control software, the data processing sequence, and the system calibration procedure. A second manual entitled: Volume 2: Operations Manual for the MARK-1 Pulsed Ionizing Radiation Detection System (USDOE Report WINCO-1108, September 1992) provides a general operational description of the MARK-1 detection system. The Operations Manual was written primarily to assist the field operator in system operations and analysis of the data.

The International Linear Collider Technical Design Report - Volume 2: Physics

Energy Technology Data Exchange (ETDEWEB)

Baer, Howard [Univ. of Oklahoma, Norman, OK (United States); Barklow, Tim [SLAC National Accelerator Lab., Menlo Park, CA (United States); Fujii, Keisuke [National Lab. for High Energy Physics (KEK), Tokai (Japan); Gao, Yuanning [Unlisted; Hoang, Andre [Univ. of Vienna (Austria); Kanemura, Shinya [Univ. of Toyama (Japan); List, Jenny [Deutsches Elektronen-Synchrotron (DESY), Hamburg (Germany); Logan, Heather E. [Carleton Univ., Ottawa, ON (Canada); Nomerotski, Andrei [Univ. of Oxford (United Kingdom); Perelstein, Maxim [Cornell Univ., Ithaca, NY (United States); Peskin, Michael E. [SLAC National Accelerator Lab., Menlo Park, CA (United States); Pöschl, Roman [Univ. Paris-Sud, Orsay (France). Linear Accelerator Lab. (LAL); Reuter, Jürgen [Deutsches Elektronen-Synchrotron (DESY), Hamburg (Germany); Riemann, Sabine [Deutsches Elektronen-Synchrotron (DESY), Hamburg (Germany); Savoy-Navarro, Aurore [CNRS/IN2P3. Univ. Paris (France). Observatoire de Paris. AstroParticule et Cosmologie (APC); Servant, Geraldine [European Organization for Nuclear Research (CERN), Geneva (Switzerland); Tait, Tim P. [Univ. of California, Los Angeles, CA (United States); Yu, Jaehoon [Univ. of Science and Technology of China, Hefei (China)

2013-06-26

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 increase significantly our understanding of the fundamental processes that govern the evolution of the Universe.

The International Linear Collider Technical Design Report - Volume 4: Detectors

Energy Technology Data Exchange (ETDEWEB)

Behnke, Ties [Fermi National Accelerator Lab. (FNAL), Batavia, IL (United States)

2013-06-26

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 increase significantly our understanding of the fundamental processes that govern the evolution of the Universe.

Technical support for GEIS: radioactive waste isolation in geologic formations. Volume 22. Nuclear considerations for repository design

International Nuclear Information System (INIS)

1978-04-01

This volume, Y/OWI/TM-36/22, ''Nuclear Considerations for Repository Design,'' is one of a 23-volume series, ''Technical Support for GEIS: Radioactive Waste Isolation in Geologic Formations,'' Y/OWI/TM-36, which supplements the ''Contribution to Draft Generic Environmental Impact Statement on Commercial Waste Management: Radioactive Waste Isolation in Geologic Formations,'' Y/OWI/TM-44. The series provides a more complete technical basis for the preconceptual designs, resource requirements, and environmental source terms associated with isolating commercial LWR wastes in underground repositories in salt, granite, shale and basalt. Wastes are considered from three fuel cycles: uranium and plutonium recycling, no recycling of spent fuel and uranium-only recycling. Included in this volume are baseline design considerations such as characteristics of canisters, drums, casks, overpacks, and shipping containers; maximum allowable and actual decay-heat levels; and canister radiation levels. Other topics include safeguard and protection considerations; occupational radiation exposure including ALARA programs; shielding of canisters, transporters and forklift trucks; monitoring considerations; mine water treatment; canister integrity; and criticality calculations

Office for Analysis and Evaluation of Operational Data 1996 annual report. Volume 10, Number 3: Technical training

International Nuclear Information System (INIS)

1997-12-01

This annual report of the US Nuclear Regulatory Commission's Office for Analysis and Evaluation of Operational Data (AEOD) describes activities conducted during 1996. The report is published in three parts. NUREG-1272, Vol. 10, No. 1, covers power reactors and presents an overview of the operating experience of the nuclear power industry from the NRC perspective, including comments about trends of some key performance measures. The report also includes the principal findings and issues identified in AEOD studies over the past year and summarizes information from such sources as licensee event reports and reports to the NRC's Operations Center. NUREG-1272, Vol. 10, No. 2, covers nuclear materials and presents a review of the events and concerns during 1996 associated with the use of licensed material in nonreactor applications, such as personnel overexposures and medical misadministrations. Both reports also contain a discussion of the Incident Investigation Team program and summarize both the Incident Investigation Team and Augmented Inspection Team reports. Each volume contains a list of the AEOD reports issued from CY 1980 through 1996. NUREG-1272, Vol. 10, No. 3, covers technical training and presents the activities of the Technical Training Center in support of the NRC's mission in 1996

K Basin spent fuel sludge treatment alternatives study. Volume 2, Technical options

International Nuclear Information System (INIS)

Beary, M.M.; Honekemp, J.R.; Winters, N.

1995-01-01

Approximately 2100 metric tons of irradiated N Reactor fuel are stored in the KE and KW Basins at the Hanford Site, Richland, Washington. Corrosion of the fuel has led to the formation of sludges, both within the storage canisters and on the basin floors. Concern about the degraded condition of the fuel and the potential for leakage from the basins in proximity to the Columbia River has resulted in DOE's commitment in the Tri-Party Agreement (TPA) to Milestone M-34-00-T08 to remove the fuel and sludges by a December 2002 target date. To support the planning for this expedited removal action, the implications of sludge management under various scenarios are examined. This report, Volume 2 of two volumes, describes the technical options for managing the sludges, including schedule and cost impacts, and assesses strategies for establishing a preferred path

Local bone graft harvesting and volumes in posterolateral lumbar fusion: a technical report.

Science.gov (United States)

Carragee, Eugene J; Comer, Garet C; Smith, Micah W

2011-06-01

In lumbar surgery, local bone graft is often harvested and used in posterolateral fusion procedures. The volume of local bone graft available for posterolateral fusion has not been determined in North American patients. Some authors have described this as minimal, but others have suggested the volume was sufficient to be reliably used as a stand-alone bone graft substitute for single-level fusion. To describe the technique used and determine the volume of local bone graft available in a cohort of patients undergoing single-level primary posterolateral fusion by the authors harvesting technique. Technical description and cohort report. Consecutive patients undergoing lumbar posterolateral fusion with or without instrumentation for degenerative processes. Local bone graft volume. Consecutive patients undergoing lumbar posterolateral fusion with or without instrumentation for degenerative processes of were studied. Local bone graft was harvested by a standard method in each patient and the volume measured by a standard procedure. Twenty-five patients were studied, and of these 11 (44%) had a previous decompression. The mean volume of local bone graft harvested was measured to be 25 cc (range, 12-36 cc). Local bone graft was augmented by iliac crest bone in six of 25 patients (24%) if the posterolateral fusion bed was not well packed with local bone alone. There was a trend to greater local bone graft volumes in men and in patients without previous decompression. Large volumes of local bone can be harvested during posterolateral lumbar fusion surgery. Even in patients with previous decompression the volume harvested is similar to that reported harvested from the posterior iliac crest for single-level fusion. Copyright © 2011 Elsevier Inc. All rights reserved.

Fiscal year 1977 scientific and technical reports, articles, papers, and presentations

Science.gov (United States)

White, O. L. (Compiler)

1977-01-01

This bibliography lists 78 NASA technical memoranda, notes, papers, and reports presented by Marshall Space Flight Center personnel in FY 1977. In addition, 525 papers by contractors to that facility are cited along with 129 papers cleared for presentation.

Mixed waste focus area integrated technical baseline report. Phase I, Volume 2: Revision 0

International Nuclear Information System (INIS)

1996-01-01

This document (Volume 2) contains the Appendices A through J for the Mixed Waste Focus Area Integrated Technical Baseline Report Phase I for the Idaho National Engineering Laboratory. Included are: Waste Type Managers' Resumes, detailed information on wastewater, combustible organics, debris, unique waste, and inorganic homogeneous solids and soils, and waste data information. A detailed list of technology deficiencies and site needs identification is also provided

The International Linear Collider Technical Design Report - Volume 3.I: Accelerator R&D in the Technical Design Phase

CERN Document Server

Adolphsen, Chris; Barish, Barry; Buesser, Karsten; Burrows, Philip; Carwardine, John; Clark, Jeffrey; Durand, Hélène Mainaud; Dugan, Gerry; Elsen, Eckhard; Enomoto, Atsushi; Foster, Brian; Fukuda, Shigeki; Gai, Wei; Gastal, Martin; Geng, Rongli; Ginsburg, Camille; Guiducci, Susanna; Harrison, Mike; Hayano, Hitoshi; Kershaw, Keith; Kubo, Kiyoshi; Kuchler, Victor; List, Benno; Liu, Wanming; Michizono, Shinichiro; Nantista, Christopher; Osborne, John; Palmer, Mark; Paterson, James McEwan; Peterson, Thomas; Phinney, Nan; Pierini, Paolo; Ross, Marc; Rubin, David; Seryi, Andrei; Sheppard, John; Solyak, Nikolay; Stapnes, Steinar; Tauchi, Toshiaki; Toge, Nobu; Walker, Nicholas; Yamamoto, Akira; Yokoya, Kaoru

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...

K Basin spent fuel sludge treatment alternatives study. Volume 2, Technical options

Energy Technology Data Exchange (ETDEWEB)

Beary, M.M.; Honekemp, J.R.; Winters, N. [Science Applications International Corp., Richland, WA (United States)

1995-01-01

Approximately 2100 metric tons of irradiated N Reactor fuel are stored in the KE and KW Basins at the Hanford Site, Richland, Washington. Corrosion of the fuel has led to the formation of sludges, both within the storage canisters and on the basin floors. Concern about the degraded condition of the fuel and the potential for leakage from the basins in proximity to the Columbia River has resulted in DOE`s commitment in the Tri-Party Agreement (TPA) to Milestone M-34-00-T08 to remove the fuel and sludges by a December 2002 target date. To support the planning for this expedited removal action, the implications of sludge management under various scenarios are examined. This report, Volume 2 of two volumes, describes the technical options for managing the sludges, including schedule and cost impacts, and assesses strategies for establishing a preferred path.

Technical support for GEIS: radioactive waste isolation in geologic formations. Volume 10. Repository preconceptual design studies: granite

International Nuclear Information System (INIS)

1978-04-01

This volume, Volume 10 ''Repository Preconceptual Design Studies: Granite,'' is one of a 23-volume series, ''Technical Support for GEIS: Radioactive Waste Isolation in Geologic Formations,'' Y/OWI/TM-36, which supplements the ''Contribution to Draft Generic Environmental Impact Statement on Commercial Waste Management: Radioactive Waste Isolation in Geologic Formations,'' Y/OWI/TM-44. The series provides a more complete technical basis for the preconceptual designs, resource requirements, and environmental source terms associated with isolating commercial LWR wastes in underground repositories in salt, granite, shale and basalt. Wastes are considered from three fuel cycles: uranium and plutonium recycling, no recycling of spent fuel and uranium-only recycling. This document describes a preconceptual design for a nuclear waste storage facility in granite. The facility design consists of several chambers excavated deep within a geologic formation together with access shafts and supportive surface structures. The facility design provides for: receiving and unloading waste containers; lowering them down shafts to the mine level; transporting them to the proper storage area, and emplacing them in mined storage rooms. Drawings of the facility design are contained in TM-36/11, ''Drawings for Repository Preconceptual Design Studies: Granite.''

Technical support for GEIS: radioactive waste isolation in geologic formations. Volume 8. Repository preconceptual design studies: salt

International Nuclear Information System (INIS)

1978-04-01

This volume, Volume 8 ''Repository Preconceptual Design Studies: Salt,'' is one of a 23-volume series, ''Technical Support for GEIS: Radioactive Waste Isolation in Geologic Formations,'' Y/OWI/TM-36, which supplements the ''Contribution to Draft Generic Environmental Impact Statement on Commercial Waste Management: Radioactive Waste Isolation in Geologic Formations,'' Y/OWI/TM-44. The series provides a more complete technical basis for the preconceptual designs, resource requirements, and environmental source terms associated with isolating commercial LWR wastes in underground repositories in salt, granite, shale and basalt. Wastes are considered from three fuel cycles: uranium and plutonium recycling, no recycling of spent fuel and uranium-only recycling. This document describes a preconceptual design for a nuclear waste storage facility in salt. The facility design consists of several chambers excavated deep within a geologic formation together with access shafts and supportive surface structures. The facility design provides for: receiving and unloading waste containers; lowering them down shafts to the mine level; transporting them to the proper storage area, and emplacing them in mined storage rooms. Drawings of the facility design are contained in TM-36/9, ''Drawings for Repository Preconceptual Design Studies: Salt.''

FY 1978 scientific and technical reports, articles, papers, and presentations. [bibliography

Science.gov (United States)

White, O. L. (Compiler)

1978-01-01

Abstracts of 73 technical papers published or presented by MSFC personnel in FY-78 are presented. In addition, over 400 papers by contractors to that facility are listed along with the STAR document number for each report. Titles of 208 additional papers already cleared for publication are included.

Technical procedures for water resources: Volume 4, Deaf Smith County site, Texas: Environmental Field Program: Final draft

International Nuclear Information System (INIS)

1987-08-01

This volume contains Technical Procedures pursuant to the water Resources Site Study Plan: including Collection, Preservation, and Shipment of Ground-Water Samples; Inventory Current Water Use and Estimating Projected Water Use; Estimation of Precipitation Depth, Duration, Frequence; Estimation of Probable Maximum Precipitation; Calculation of Floodplains

The International Linear Collider Technical Design Report - Volume 1: Executive Summary

Energy Technology Data Exchange (ETDEWEB)

Behnke, Ties [Deutsches Elektronen-Synchrotron (DESY), Hamburg (Germany); Brau, James E. [Univ. of Oregon, Eugene, OR (United States); Foster, Brian [Deutsches Elektronen-Synchrotron (DESY), Hamburg (Germany); Fuster, Juan [Univ. of Valencia (Spain); Harrison, Mike [Brookhaven National Lab. (BNL), Upton, NY (United States); Paterson, James McEwan [SLAC National Accelerator Lab., Menlo Park, CA (United States); Peskin, Michael [SLAC National Accelerator Lab., Menlo Park, CA (United States); Stanitzki, Marcel [Deutsches Elektronen-Synchrotron (DESY), Hamburg (Germany); Walker, Nicholas [Deutsches Elektronen-Synchrotron (DESY), Hamburg (Germany); Yamamoto, Hitoshi [Tohoku Univ., Sendai (Japan)

2013-06-26

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 increase significantly our understanding of the fundamental processes that govern the evolution of the Universe.

Design and Construction Rules for Mechanical equipments of FBR nuclear islands: RCC-MR. Tome 1, Volume Z: Other technical appendixes

International Nuclear Information System (INIS)

1985-06-01

This book is the 7th of a whole set of 12 which constitute the present edition of the RCC-MR. The technical appendixes of this volume deal with the following characteristics and rules: calculation of screwed assemblies, analysis taking into account creep, welded joint characteristics, elastoplastic analysis of a structure under cyclic loads, elasto-visco-plastic analysis under cyclic loads, calculation rules of revolution shells under external presure and of cylinders under axial compression, design rules of linear supports, calculation rules of convex bottoms under internal pressure [fr

Technical performance characterization of fourier transform profilometry for quantitative waste volume determination under Hanford waste tank conditions - 16281

International Nuclear Information System (INIS)

Monts, David L.; Jang, Ping-Rey; Long, Zhiling; Norton, Olin P.; Gresham, Lawrence L.; Su, Yi; Lindner, Jeffrey S.

2009-01-01

The Hanford Site in western Washington state is currently in the process of an extensive effort to empty and close its radioactive single-shell and double-shell waste storage tanks. Before this can be accomplished, it is necessary to know how much residual material is left in a given waste tank and the chemical makeup of the residue. The Institute for Clean Energy Technology (ICET) at Mississippi State University is currently developing an quantitative in-tank inspection system based on Fourier Transform Profilometry, FTP. FTP is a non-contact, 3-D shape measurement technique. By projecting a fringe pattern onto a target surface and observing its deformation due to surface irregularities from a different view angle, FTP is capable of determining the height (depth) distribution (and hence volume distribution) of the target surface, thus reproducing the profile of the target accurately under a wide variety of conditions. Hence FTP has the potential to be utilized for quantitative determination of residual wastes within Hanford waste tanks. We report the results of a technical feasibility study to document the accuracy and precision of quantitative volume determination using the Fourier transform profilometry technique under simulated Hanford waste tank conditions. We have initiated a technical feasibility assessment of the Fourier transform profilometry (FTP) technique for determining the volume of residual waste in Hanford radioactive waste tanks; preliminary results to date are presented in this paper. We find that we achieve FTP volume determinations with relatively small errors under conditions corresponding to the most challenging within a Hanford waste tank-viewing non-descript targets at a distance of 16.1 m (53 ft) and an angle of 62 deg.. We have determined that we can minimize measurement uncertainty by maximizing the camera-to-projector distance d, using an optical zoom of at least 5x, and ensuring that FTP images are only recorded after instrumental warm

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.

Proceedings: Computer Science and Data Systems Technical Symposium, volume 1

Science.gov (United States)

Larsen, Ronald L.; Wallgren, Kenneth

1985-01-01

Progress reports and technical updates of programs being performed by NASA centers are covered. Presentations in viewgraph form are included for topics in three categories: computer science, data systems and space station applications.

Descriptive analysis of context evaluation instrument for technical oral presentation skills evaluation: A case study in English technical communication course

Science.gov (United States)

Mohamed, Abdullah-Adnan; Asmawi, Adelina; Hamid, Mohd Rashid Ab; Mustafa, Zainol bin

2015-02-01

This paper reports a pilot study of Context Evaluation using a self-developed questionnaire distributed among engineering undergraduates at a university under study. The study aims to validate the self-developed questionnaires used in the Context evaluation, a component in the CIPP Model. The Context evaluation assesses background information for needs, assets, problems and opportunities relevant to beneficiaries of the study in a defined environment. Through the questionnaire, background information for the assessment of needs, assets and problems related to the engineering undergraduates' perceptions on the teaching and learning of technical oral presentation skills was collected and analysed. The questionnaire was developed using 5-points Likert scale to measure the constructs under study. They were distributed to 100 respondents with 79 returned. The respondents consisted of engineering undergraduates studied at various faculties at one technical university in Malaysia. The descriptive analysis of data for each item which makes up the construct for Context evaluation is found to be high. This implied that engineering undergraduates showed high interest in teaching and learning of technical oral presentation skills, thus their needs are met. Also, they agreed that assets and facilities are conducive to their learning. In conclusion, the context evaluation involving needs and assets factors are both considerably important; their needs are met and the assets and facilities do support their technical oral presentation skills learning experience.

Proceedings: Computer Science and Data Systems Technical Symposium, volume 2

Science.gov (United States)

Larsen, Ronald L.; Wallgren, Kenneth

1985-01-01

Progress reports and technical updates of programs being performed by NASA centers are covered. Presentations in viewgraph form, along with abstracts, are included for topics in three catagories: computer science, data systems, and space station applications.

Technical procedures for water resources, Deaf Smith County site, Texas: Volume 1: Environmental Field Program: Final draft

International Nuclear Information System (INIS)

1987-08-01

This volume contains Technical Procedures pursuant to the Water Resources Site Study Plan including, determination of basin topographic characteristics, determination of channel and playa lake characteristics, operation of a stream gaging station, operation of a playa lake stage gaging system, and processing of data from a playa lake stage gaging system

Effectiveness of Powerpoint Presentation On Students’ Cognitive Achievement in Technical Drawing

Directory of Open Access Journals (Sweden)

Amosa Isiaka Gambari

2015-10-01

Full Text Available This paper discusses importance of technology education and evidence of declining performance of junior secondary school students in basic technology subject. Benefits of PowerPoint presentation in classroom instruction as a means to improve classroom teaching in the developing countries are also discussed. The effectiveness of PowerPoint Presentation (PPT for teaching Technical Drawing concepts in Basic Technology was determined using a pretest-posttest, non-equivalent, non-randomized experimental group design. A 2x2x3 factorial design was employed. One hundred JSS 1 students (53 male and 47 female categorized into 29 high, 54 medium and 17 low achievers from two secondary schools in Abuja Metropolis formed the sample. The schools were randomly assigned to experimental and control groups. The experimental group was taught some selected concepts from Technical Drawing using PowerPoint Presentation (PPT while Chalkboard method (CB was used for the control group. A validated Technical Drawing Achievement Test (TDAT comprising a 25-item multiple-choice test was employed for data collection. The reliability coefficient of TDAT was .88 using Kuder-Richardson (KR-20. The hypotheses were tested using ANCOVA and Sidak post-hoc analysis. Results revealed that the students taught with PPT performed better than their counterparts taught with CB. Also, high achievers performed better than medium and low achievers respectfully. The PPT was found also to be gender friendly. Based on the findings, it was recommended that the use of PPT should be encouraged in Nigerian schools.

Technical issues associated with in situ vitrification of the INEL Subsurface Disposal Area

International Nuclear Information System (INIS)

Stoots, C.M.; Bates, S.O.; Callow, R.A.; Campbell, K.A.; Farnsworth, R.K.; Gratson, G.K.; McKellar, M.G.; Nickelson, D.F.; Slater, C.E.

1992-01-01

In situ vitrification (ISV) has been identified as an alternative technology for remediation of the Acid Pit and Transuranic Pits and Trenches (TRU-PTs) that are present at the Idaho National Engineering Laboratory (INEL) Subsurface Disposal Area (SDA). However, a number of technical issues exist that must be resolved before ISV can be considered applicable to these waste sites. To assist in the ISV technology evaluation, an ISV Steering Committee was formed to identify, prioritize, and develop closure roadmaps for technical issues associated with ISV application at the INEL SDA. The activities of the ISV Steering Committee are summarized in three volumes of this report. Volume 1 identifies the systematic approach used to identify and prioritize the ISV technical issues, and briefly discusses the methodology that will be employed to resolve these issues. This document Volume 2 and Volume 3 discusses each technical issue in greater detail and suggest specific closure roadmaps to be used in resolving technical issues associated with ISV at the SDA Acid Pit and TRU-PTs, respectively

The Fukushima Daiichi Accident. Technical Volume 4/5. Radiological Consequences

International Nuclear Information System (INIS)

2015-08-01

This technical volume describes the consequences associated with radioactivity and radiation from the accident at the Fukushima Daiichi nuclear power plant (NPP) for people and the environment. A number of international organizations have already issued reports on the potential health and environmental consequences of the accident, notably the World Health Organization (WHO) and the United Nations Scientific Committee on the Effects of Atomic Radiation (UNSCEAR). The intention of the assessments presented in this volume is to build on their work, using more recent data where available. Quantitative information arising from both personal and environmental monitoring has been provided by the Government of Japan. Section 4.1 provides the best estimates of the magnitude and form of radioactive releases during the accident to the atmosphere and directly into the surrounding sea. It also explains the movement of the discharged radionuclides through air and water and the eventual deposition of the atmospheric activity on land in Japan and other countries worldwide, as well as on the open oceans. The goal is to provide a consolidated repository of information on releases to, and levels of radionuclides in, the environment. Some of this information is used in the analyses in subsequent sections of this volume. Section 4.2 gives an overview of exposures to the main groups of emergency workers at the Fukushima Daiichi NPP, to groups of off-site workers and to members of the public. Where sufficient data are available, average effective dose and thyroid equivalent doses derived from personal measurements are compared with the results of previous assessments for specific locations, population groups and time periods. Section 4.3 summarizes relevant aspects of the system of radiation protection in place at the time of the accident. It includes an overview of the legislation and guidance used to implement the radiation protection framework in Japan. This section also provides a

Technical Meeting on Grading of the Application of Management System Requirements. Presentations

International Nuclear Information System (INIS)

2012-01-01

The objectives of this Technical Meeting are threefold: - to share international experiences and lessons learned, as well as exchange views on best practices and strategies to overcome the difficulties encountered; - to review and discuss the draft technical report on 'Grading the Application of Management System Requirements, to allow the participants to contribute to the improvement of the document and to enrich it with practical examples; and - to strengthen the international networking of specialists in the field. The topics covered during the meeting will include: - Examples and case studies presented by participants from countries with nuclear facilities (mainly focused on NPPs, and, where appropriate, from research reactors, fuel cycle and waste management facilities) on grading the application of management system requirements and lessons learned. - Reviewing and improving the final draft of a technical report on 'Grading the Application of Management System Requirements', which will supersede the previous guidance: Grading of Quality Assurance Requirement: A Manual (Technical Reports Series No. 328)

Volume 2. Probabilistic analysis of HTGR application studies. Supporting data

International Nuclear Information System (INIS)

1980-09-01

Volume II, Probabilistic Analysis of HTGR Application Studies - Supporting Data, gives the detail data, both deterministic and probabilistic, employed in the calculation presented in Volume I. The HTGR plants and the fossil plants considered in the study are listed. GCRA provided the technical experts from which the data were obtained by MAC personnel. The names of the technical experts (interviewee) and the analysts (interviewer) are given for the probabilistic data

IAEA safeguards technical manual

International Nuclear Information System (INIS)

1982-03-01

Part F of the Safeguards Technical Manual is being issued in three volumes. Volume 1 was published in 1977 and revised slightly in 1979. Volume 1 discusses basic probability concepts, statistical inference, models and measurement errors, estimation of measurement variances, and calibration. These topics of general interest in a number of application areas, are presented with examples drawn from nuclear materials safeguards. The final two chapters in Volume 1 deal with problem areas unique to safeguards: calculating the variance of MUF and of D respectively. Volume 2 continues where Volume 1 left off with a presentation of topics of specific interest to Agency safeguards. These topics include inspection planning from a design and effectiveness evaluation viewpoint, on-facility site inspection activities, variables data analysis as applied to inspection data, preparation of inspection reports with respect to statistical aspects of the inspection, and the distribution of inspection samples to more than one analytical laboratory. Volume 3 covers generally the same material as Volumes 1 and 2 but with much greater unity and cohesiveness. Further, the cook-book style of the previous two volumes has been replaced by one that makes use of equations and formulas as opposed to computational steps, and that also provides the bases for the statistical procedures discussed. Hopefully, this will help minimize the frequency of misapplications of the techniques

Standard Technical Specifications, Westinghouse plants

International Nuclear Information System (INIS)

1992-09-01

This NUREG contains improved Standard Technical Specifications (STS) for Westinghouse Plants and documents the positions of the Nuclear Regulatory Commission based on the Westinghouse Owners Group's proposed STS. This document is the result of extensive technical meetings and discussions among the NRC staff, the Nuclear Steam Supply System (NSSS) Owners Groups, the NSSS vendors, and the Nuclear Management and Resources Council (NUMARC). The improved STS were developed based on the criteria in the interim Commission Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, dated February 6, 1987. 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. This document, Volume 3, contains the Bases for Sections 3.4--3.9 of the improved STS

Standard Technical Specifications, Westinghouse Plants

International Nuclear Information System (INIS)

1992-09-01

This NUREG contains improved Standard Technical Specifications (STS) for Westinghouse Plants and documents the positions of the Nuclear Regulatory Commission based on the Westinghouse Owners Group's proposed STS. This document is the result of extensive technical meetings and discussions among the NRC staff, the Nuclear Steam Supply System (NSSS) Owners Groups, the NSSS vendors, and the Nuclear Management and Resources Council (NUMARC). The improved STS were developed based on the criteria in the interim Commission Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, dated February 6, 1987. 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 unproved STS. Volume 3 contains the Bases for Sections 3.4--3.9 of the improved STS which contain information on safety limits, reactivity control systems, power distribution limits, and instrumentation

Standard Technical Specifications, Westinghouse plants

International Nuclear Information System (INIS)

1992-09-01

This NUREG contains improved Standard Technical Specifications (STS) for Westinghouse Plants and documents the positions of the Nuclear Regulatory Commission based on the Westinghouse Owners Group's proposed STS. This document is the result of extensive technical meetings and discussions among the NRC staff, the Nuclear Steam Supply System (NSSS) Owners Groups, the NSSS vendors, and the Nuclear Management and Resources Council (NUMARC). The improved STS were developed based on the criteria in the interim Commission Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, dated February 6, 1987. 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. This document, 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

International Nuclear Model. Volume 3. Program description

International Nuclear Information System (INIS)

Andress, D.

1985-01-01

This is Volume 3 of three volumes of documentation of the International Nuclear Model (INM). This volume presents the Program Description of the International Nuclear Model, which was developed for the Nuclear and Alternate Fuels Division (NAFD), Office of Coal, Nuclear, Electric and Alternate Fuels, Energy Information Administration (EIA), US Department of Energy (DOE). The International Nuclear Model (INM) is a comprehensive model of the commercial nuclear power industry. It simulates economic decisions for reactor deployment and fuel management decision based on an input set of technical economic and scenario parameters. The technical parameters include reactor operating characteristics, fuel cycle timing and mass loss factors, and enrichment tails assays. Economic parameters include fuel cycle costs, financial data, and tax alternatives. INM has a broad range of scenario options covering, for example, process constraints, interregional activities, reprocessing, and fuel management selection. INM reports reactor deployment schedules, electricity generation, and fuel cycle requirements and costs. It also has specialized reports for extended burnup and permanent disposal. Companion volumes to Volume 3 are: Volume 1 - Model Overview, and Volume 2 - Data Base Relationships

The International Linear Collider Technical Design Report - Volume 3.II: Accelerator Baseline Design

CERN Document Server

Adolphsen, Chris; Barish, Barry; Buesser, Karsten; Burrows, Philip; Carwardine, John; Clark, Jeffrey; Durand, Helene Mainaud; Dugan, Gerry; Elsen, Eckhard; Enomoto, Atsushi; Foster, Brian; Fukuda, Shigeki; Gai, Wei; Gastal, Martin; Geng, Rongli; Ginsburg, Camille; Guiducci, Susanna; Harrison, Mike; Hayano, Hitoshi; Kershaw, Keith; Kubo, Kiyoshi; Kuchler, Victor; List, Benno; Liu, Wanming; Michizono, Shinichiro; Nantista, Christopher; Osborne, John; Palmer, Mark; Paterson, James McEwan; Peterson, Thomas; Phinney, Nan; Pierini, Paolo; Ross, Marc; Rubin, David; Seryi, Andrei; Sheppard, John; Solyak, Nikolay; Stapnes, Steinar; Tauchi, Toshiaki; Toge, Nobu; Walker, Nicholas; Yamamoto, Akira; Yokoya, Kaoru

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...

Performance evaluation of the technical capabilities of DOE sites for disposal of mixed low-level waste: Volume 3, Site evaluations

Energy Technology Data Exchange (ETDEWEB)

Waters, R.D.; Gruebel, M.M. [eds.

1996-03-01

A team of analysts designed and conducted a performance evaluation to estimate the technical capabilities of fifteen Department of Energy sites for disposal of mixed low-level waste (i.e., waste that contains both low-level radioactive materials and hazardous constituents). Volume 1 summarizes the process for selecting the fifteen sites, the methodology used in the evaluation, and the conclusions derived from the evaluation. Volume 2 provides details about the site-selection process, the performance-evaluation methodology, and the overall results of the analysis. Volume 3 contains detailed evaluations of the fifteen sites and discussion of the results for each site.

Performance evaluation of the technical capabilities of DOE sites for disposal of mixed low-level waste: Volume 3, Site evaluations

International Nuclear Information System (INIS)

Waters, R.D.; Gruebel, M.M.

1996-03-01

A team of analysts designed and conducted a performance evaluation to estimate the technical capabilities of fifteen Department of Energy sites for disposal of mixed low-level waste (i.e., waste that contains both low-level radioactive materials and hazardous constituents). Volume 1 summarizes the process for selecting the fifteen sites, the methodology used in the evaluation, and the conclusions derived from the evaluation. Volume 2 provides details about the site-selection process, the performance-evaluation methodology, and the overall results of the analysis. Volume 3 contains detailed evaluations of the fifteen sites and discussion of the results for each site

Standard technical specifications combustion engineering plants

International Nuclear Information System (INIS)

1992-09-01

This report documents the results of the combined effort of the NRC and the industry to produce improved Standard Technical Specifications (STS) for Combustion Engineering Plants. The improved STS wee developed based on the criteria in the interim Commission Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, dated February 6, 1987. 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. This document, Volume 1, contains the Specifications for all chapters and sections of the improved STS. Volume 2 contains the Bases for Sections 3.4--3.9 of the improved STS

The second iteration of the Systems Prioritization Method: A systems prioritization and decision-aiding tool for the Waste Isolation Pilot Plant: Volume 2, Summary of technical input and model implementation

Energy Technology Data Exchange (ETDEWEB)

Prindle, N.H.; Mendenhall, F.T.; Trauth, K.; Boak, D.M. [Sandia National Labs., Albuquerque, NM (United States); Beyeler, W. [Science Applications International Corp., Albuquerque, NM (United States); Hora, S. [Hawaii Univ., Hilo, HI (United States); Rudeen, D. [New Mexico Engineering Research Inst., Albuquerque, NM (United States)

1996-05-01

The Systems Prioritization Method (SPM) is a decision-aiding tool developed by Sandia National Laboratories (SNL). SPM provides an analytical basis for supporting programmatic decisions for the Waste Isolation Pilot Plant (WIPP) to meet selected portions of the applicable US EPA long-term performance regulations. The first iteration of SPM (SPM-1), the prototype for SPM< was completed in 1994. It served as a benchmark and a test bed for developing the tools needed for the second iteration of SPM (SPM-2). SPM-2, completed in 1995, is intended for programmatic decision making. This is Volume II of the three-volume final report of the second iteration of the SPM. It describes the technical input and model implementation for SPM-2, and presents the SPM-2 technical baseline and the activities, activity outcomes, outcome probabilities, and the input parameters for SPM-2 analysis.

The second iteration of the Systems Prioritization Method: A systems prioritization and decision-aiding tool for the Waste Isolation Pilot Plant: Volume 2, Summary of technical input and model implementation

International Nuclear Information System (INIS)

Prindle, N.H.; Mendenhall, F.T.; Trauth, K.; Boak, D.M.; Beyeler, W.; Hora, S.; Rudeen, D.

1996-05-01

The Systems Prioritization Method (SPM) is a decision-aiding tool developed by Sandia National Laboratories (SNL). SPM provides an analytical basis for supporting programmatic decisions for the Waste Isolation Pilot Plant (WIPP) to meet selected portions of the applicable US EPA long-term performance regulations. The first iteration of SPM (SPM-1), the prototype for SPM< was completed in 1994. It served as a benchmark and a test bed for developing the tools needed for the second iteration of SPM (SPM-2). SPM-2, completed in 1995, is intended for programmatic decision making. This is Volume II of the three-volume final report of the second iteration of the SPM. It describes the technical input and model implementation for SPM-2, and presents the SPM-2 technical baseline and the activities, activity outcomes, outcome probabilities, and the input parameters for SPM-2 analysis

FAIR - Baseline technical report. Executive summary

International Nuclear Information System (INIS)

Gutbrod, H.H.; Augustin, I.; Eickhoff, H.; Gross, K.D.; Henning, W.F.; Kraemer, D.; Walter, G.

2006-09-01

This document presents the Executive Summary, the first of six volumes comprising the 2006 Baseline Technical Report (BTR) for the international FAIR project (Facility for Antiproton and Ion Research). The BTR provides the technical description, cost, schedule, and assessments of risk for the proposed new facility. The purpose of the BTR is to provide a reliable basis for the construction, commissioning and operation of FAIR. The BTR is one of the central documents requested by the FAIR International Steering Committee (ISC) and its working groups, in order to prepare the legal process and the decisions on the construction and operation of FAIR in an international framework. It provides the technical basis for legal contracts on contributions to be made by, so far, 13 countries within the international FAIR Consortium. The BTR begins with this extended Executive Summary as Volume 1, which is also intended for use as a stand-alone document. The Executive Summary provides brief summaries of the accelerator facilities, the scientific programs and experimental stations, civil construction and safety, and of the workproject structure, costs and schedule. (orig.)

Technical support for GEIS: radioactive waste isolation in geologic formations. Volume 5. Baseline rock properties-granite

International Nuclear Information System (INIS)

1978-04-01

This volume, Y/OWI/TM-36/5, Baseline Rock Properties--Granite, is one of a 23-volume series, ''Technical Support for GEIS: Radioactive Waste Isolation in Geologic Formations, Y/OWI/TM-36'' which supplements a ''Contribution to Draft Generic Environmental Impact Statement on Commercial Waste Management: Radioactive Waste Isolation in Geologic Formations, Y/OWI/TM-44.'' The series provides a more complete technical basis for the preconceptual designs, resource requirements, and environmental source terms associated with isolating commercial LWR wastes in underground repositories in salt, granite, shale and basalt. Wastes are considered from three fuel cycles: uranium and plutonium recycling, no recycling of spent fuel and uranium-only recycling. This report, on the rock properties of typical granites, includes an evaluation of the various test results reported in the literature. Firstly, a literature survey was made in order to obtain a feel for the range of rock properties encountered. Then, granites representative of different geologic ages and from different parts of the United States were selected and studied in further detail. Some of the special characteristics of granite, such as anisotropy, creep and weathering were also investigated. Lastly, intact properties for a typical granite were selected and rock mass properties were derived using appropriate correction factors

The Fukushima Daiichi Accident. Technical Volume 2/5. Safety Assessment

International Nuclear Information System (INIS)

2015-08-01

Technical Volume 1 of this report has described what happened during the accident at the Fukushima Daiichi nuclear power plant (NPP). This volume begins (Section 2.1) with a review of how the design basis of the site for external events was assessed initially and then reassessed over the life of the NPP. The section also describes the physical changes that were made to the units as a result. The remainder of the volume describes the treatment of beyond design basis events in the safety assessment of the site, the accident management provisions, the effectiveness of regulatory programmes, human and organizational factors and the safety culture, and the role of operating experience. Further background information is contained in three annexes included on the CD-ROM of this Technical Volume which describe analytical investigations of the accident along with information on topics such as system performance, defence in depth and severe accident phenomena. Section 2.2 provides an assessment of the systems that failed, resulting in a failure to maintain the fundamental safety functions in Units 1–3, which were in operation at the time of the tsunami and in which the reactor pressure vessels (RPV) and containment vessels failed. The section also describes Units 4-6, which were shut down at the time of the tsunami, and the site’s central spent fuel storage facility. Section 2.3 discusses the probabilistic and deterministic safety assessments of beyond design basis accidents (BDBAs) that had been performed for the plant and the insights from these assessments that had led to changes in the plant’s design. The section pays particular attention to the assessment of extreme natural hazards, such as the one which led to the total loss of AC power supply on the site. The additional loss of DC power supply in Units 1 and 2 played a key role in the progression of the accident because it impeded the diagnosis of plant conditions and made the operators unaware of the status of

Standard Technical Specifications, Combustion Engineering plants

International Nuclear Information System (INIS)

1992-09-01

This NUREG contains improved Standard Technical Specifications (M) for Combustion Engineering (CE) Plants and documents the positions of the Nuclear Regulatory Commission based on the CE Owners Group's proposed STS. This document is the result of extensive technical meetings and discussions among the NRC staff, the Nuclear Steam Supply System (NSSS) Owners Groups, the NSSS vendors, and the Nuclear Management and Resources Council (NUMARC). The improved STS were developed based on the criteria in the interim Commission Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, dated February 6, 1987. 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. 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--3.9 of the improved STS

Standard Technical Specifications, Combustion Engineering plants

International Nuclear Information System (INIS)

1992-09-01

This NUREG contains improved Standard Technical Specifications (STS) for Combustion Engineering (CE) Plants and documents the positions of the Nuclear Regulatory Commission based on the CE Owners Group's proposed STS. This document is the result of extensive technical meetings and discussions among the NRC staff, the Nuclear Steam Supply System (NSSS) Owners Groups, the NSSS vendors, and the Nuclear Management and Resources Council (NUMARC). The improved STS were developed based on the criteria in the interim Commission Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, dated February 6, 1987. 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 SM. Volume 2 contains the 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--3.9 of the improved M

Definition of technology development missions for early Space Station satellite servicing. Volume 2: Technical

Science.gov (United States)

Cable, D. A.; Diewald, C. A.; Hills, T. C.; Parmentier, T. J.; Spencer, R. A.; Stone, G. E.

1984-01-01

Volume 2 contains the Technical Report of the approach and results of the Phase 2 study. The phase 2 servicing study was initiated in June 1983, and is being reported in this document. The scope of the contract was to: (1) define in detail five selected technology development missions (TDM); (2) conduct a design requirement analysis to refine definitions of satellite servicing requirements at the space station; and (3) develop a technology plan that would identify and schedule prerequisite precursor technology development, associated. STS flight experiments and space station experiments needed to provide onorbit validation of the evolving technology.

Percutaneous Image-Guided Cryoablation of Challenging Mediastinal Lesions Using Large-Volume Hydrodissection: Technical Considerations and Outcomes

Energy Technology Data Exchange (ETDEWEB)

Garnon, Julien, E-mail: juliengarnon@gmail.com; Koch, Guillaume, E-mail: Guillaume.koch@gmail.com; Caudrelier, Jean, E-mail: caudjean@yahoo.fr [University Hospital of Strasbourg, Department of Interventional Radiology (France); Ramamurthy, Nitin, E-mail: Nitin-ramamurthy@hotmail.com [Norfolk and Norwich University Hospital, Department of Radiology (United Kingdom); Rao, Pramod, E-mail: pramodrao@me.com [University of Strasbourg, ICube (France); Tsoumakidou, Georgia, E-mail: Georgia.tsoumakidou@chru-strasbourg.fr; Cazzato, Roberto Luigi, E-mail: cazzatorobertoluigi@gmail.com; Gangi, Afshin, E-mail: Afshin.gangi@chru-strasbourg.fr [University Hospital of Strasbourg, Department of Interventional Radiology (France)

2016-11-15

ObjectiveThis study was designed to describe the technique of percutaneous image-guided cryoablation with large-volume hydrodissection for the treatment of challenging mediastinal lesions.MethodsBetween March 2014 and June 2015, three patients (mean age 62.7 years) with four neoplastic anterior mediastinal lesions underwent five cryoablation procedures using large-volume hydrodissection. Procedures were performed under general anaesthesia using CT guidance. Lesion characteristics, hydrodissection and cryoablation data, technical success, complications, and clinical outcomes were assessed using retrospective chart review.ResultsLesions (mean size 2.7 cm; range 2–4.3 cm) were in contact with great vessels (n = 13), trachea (n = 3), and mediastinal nerves (n = 6). Hydrodissection was performed intercostally (n = 4), suprasternally (n = 2), transsternally (n = 1), or via the sternoclavicular joint (n = 1) using 1–3 spinal needles over 13.4 (range 7–26) minutes; 450 ml of dilute contrast was injected (range 300–600 ml) and increased mean lesion-collateral structure distance from 1.9 to 7.7 mm. Vulnerable mediastinal nerves were identified in four of five procedures. Technical success was 100 %, with one immediate complication (recurrent laryngeal nerve injury). Mean follow-up period was 15 months. One lesion demonstrated residual disease on restaging PET-CT and was retreated to achieve complete ablation. At last follow-up, two patients remained disease-free, and one patient developed distant disease after 1 year without local recurrence.ConclusionsCryoablation using large-volume hydrodissection is a feasible technique, enabling safe and effective treatment of challenging mediastinal lesions.

The International Linear Collider Technical Design Report - Volume 3.II: Accelerator Baseline Design

Energy Technology Data Exchange (ETDEWEB)

Adolphsen, Chris [SLAC National Accelerator Lab., Menlo Park, CA (United States); et al.

2013-06-26

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 increase significantly our understanding of the fundamental processes that govern the evolution of the Universe.

Papers presented at the IAEA technical committee meeting on H-mode physics

International Nuclear Information System (INIS)

TCV team

1995-11-01

The two papers contained in this report deal with ohmic H-modes and effect on confinement of edge localized modes in the TCV tokamak. They were presented by the TCV team at the 1995 IAEA technical committee meeting on H-mode physics. figs., tabs., refs

Twenty-fifth water reactor safety information meeting: Proceedings. Volume 2: Human reliability analysis and human performance evaluation; Technical issues related to rulemakings; Risk-informed, performance-based initiatives; High burn-up fuel research

International Nuclear Information System (INIS)

Monteleone, S.

1998-03-01

This three-volume report contains papers presented at the conference. 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, Japan, Norway, and Russia. The titles of the papers and the names of the authors have been updated and may differ from those that appeared in the final program of the meeting. This volume contains the following: (1) human reliability analysis and human performance evaluation; (2) technical issues related to rulemakings; (3) risk-informed, performance-based initiatives; and (4) high burn-up fuel research

Fusion Engineering Device. Volume 1. Mission and program summary

International Nuclear Information System (INIS)

1981-10-01

This volume presents, in summary form, a recommended approach to implementing the Magnetic Fusion Energy Engineering Act of 1980. These recommendations constitute the findings of the FED Technical Management Board (TMB). The TMB and the affiliated technical managers gave particular scrutiny to elucidating the role of FED in fusion development and to defining the device mission

Technical summary of groundwater quality protection program at Savannah River Plant. Volume 1. Site geohydrology, and solid and hazardous wastes

International Nuclear Information System (INIS)

Christensen, E.J.; Gordon, D.E.

1983-12-01

The program for protecting the quality of groundwater underlying the Savannah River Plant (SRP) is described in this technical summary report. The report is divided into two volumes. Volume I contains a discussion of the general site geohydrology and of both active and inactive sites used for disposal of solid and hazardous wastes. Volume II includes a discussion of radioactive waste disposal. Most information contained in these two volumes is current as of December 1983. The groundwater quality protection program has several elements which, taken collectively, are designed to achieve three major goals. These goals are to evaluate the impact on groundwater quality as a result of SRP operations, to restore or protect groundwater quality by taking corrective action as necessary, and to ensure disposal of waste materials in accordance with regulatory guidelines

Performance evaluation of the technical capabilities of DOE sites for disposal of mixed low-level waste. Volume 1: Executive summary

International Nuclear Information System (INIS)

1996-03-01

A team of analysts designed and conducted a performance evaluation (PE) to estimate the technical capabilities of fifteen Department of Energy sites for disposal of mixed low-level waste (i.e., waste that contains both low-level radioactive materials and hazardous constituents). Volume 1 summarizes the process for selecting the fifteen sites, the methodology used in the evaluation, and the conclusions derived from the evaluation. Volume 1 is an executive summary both of the PE methodology and of the results obtained from the PEs. While this volume briefly reviews the scope and method of analyses, its main objective is to emphasize the important insights and conclusions derived from the conduct of the PEs. Volume 2 provides details about the site-selection process, the performance-evaluation methodology, and the overall results of the analysis. Volume 3 contains detailed evaluations of the fifteen sites and discussions of the results for each site

Technical support for GEIS: radioactive waste isolation in geologic formations. Volume 7. Baseline rock properties-basalt

International Nuclear Information System (INIS)

1978-04-01

This volume, Y/OWI/TM-36/7 Baseline Rock Properties--Basalt, is one of a 23-volume series, ''Technical Support for GEIS: Radioactive Waste Isolation in Geologic Formations, Y/OWI/TM-36'' which supplements a ''Contribution to Draft Generic Environmental Impact Statement on Commercial Waste Management: Radioactive Waste Isolation in Geologic Formations, Y/OWI/TM-44.'' The series provides a more complete technical basis for the preconceptual designs, resource requirements, and environmental source terms associated with isolating commercial LWR wastes in underground repositories in salt, granite, shale and basalt. Wastes are considered from three fuel cycles: uranium and plutonium recycling, no recycling of spent fuel and uranium-only recycling. This report contains an evaluation of the results of a literature survey to define the rock mass properties of a generic basalt, which could be considered as a geological medium for storing radioactive waste. The general formation and structure of basaltic rocks is described. This is followed by specific descriptions and rock property data for the Dresser Basalt, the Amchitka Island Basalt, the Nevada Test Site Basalt and the Columbia River Group Basalt. Engineering judgment has been used to derive the rock mass properties of a typical basalt from the relevant intact rock property data and the geological information pertaining to structural defects, such as joints and faults

Technical Meeting on Liquid Metal Reactor Concepts: Core Design and Structural Materials. Presentations

International Nuclear Information System (INIS)

2013-01-01

The objective of the Technical Meeting is to present and discuss innovative liquid metal fast reactor (LMFR) core designs with special focus on the choice, development, testing and qualification of advanced reactor core structural materials

Standard Technical Specifications, Babcock and Wilcox plants

International Nuclear Information System (INIS)

1992-09-01

This NUREG contains improved Standard Technical Specifications (STS) for Babcock and Wilcox (B ampersand W) Plants and documents the positions of the Nuclear Regulatory Commission based on the B ampersand W Owners Group's proposed STS. This document is the result of extensive technical meetings and discussions among the NRC staff, the Nuclear Steam Supply System (NSSS) Owners Groups, the NSSS vendors, and the Nuclear Management and Resources Council (NUMARC). The improved STS were developed based on the criteria in the interim Commission Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, dated February 6, 1987. 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. 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

Abbreviations [Annex to The Fukushima Daiichi Accident, Technical Volume 2/5

International Nuclear Information System (INIS)

2015-01-01

This annex is a list of abbreviations used in the publication The Fukushima Daiichi Accident, Technical Volume 2/5. The list includes the abbreviations for: • Agency for Natural Resources and Energy; • essential service water; • International Nuclear and Radiological Event Scale;• Integrated Regulatory Review Service; • Japan Atomic Energy Agency; • Japan Atomic Energy Commission; • Japan Power Engineering and Inspection Corp; • Japan Nuclear Energy Safety Organization; • low head safety injection; • low level radioactive waste; • Madras Atomic Power Station; • main control room; • Ministry of Economy, Trade and Industry; • Ministry of Education, Culture, Sports, Science and Technology; • Ministry of International Trade and Industry; • Ministry of Foreign Affairs; • Nuclear and Industrial Safety Agency; • Nuclear Power Corporation of India Limited; • nuclear power plant; • Nuclear Safety Commission; • Nuclear Power Engineering Corporation; • Nuclear Safety Technology Centre; • Onahama Port; • pressurized water reactor; • Science and Technology Agency; • Tokyo Electric Power Company

Influence of non-technical policies on choices of waste solidification technologies

International Nuclear Information System (INIS)

Trubatch, S.L.

1987-01-01

This paper describes and discusses non-technical policy considerations which may improperly influence decisions on the solidification of low-level radioactive wastes (''LLW''). These policy considerations are contained principally in several State and Federal statutes which regulate various aspects of LLW disposal. One policy consideration in particular, the unqualified bias in favor of volume reduction, is shown to present a substantial potential for leading to technically suboptimal decisions on the appropriate processes for solidifying LLW. To avoid the unintended skewing of technical decisions by non-technical policy considerations, certain current policies may need to be revised to ensure that the choices of waste treatment, including decisions on solidification, are based primarily on reasonable assurance of adequate protection of public health and safety. This goal may be realized in part by basing any disposal fee structure on more than just LLW volume to include consideration of the waste's activity and its difficulty of confinement

Presentation of the G-24 technical working group on training

International Nuclear Information System (INIS)

Haber, S.

1993-01-01

The Technical Working Group on Training (TWG-T) was created during the Plenary Session of September 1992 in order to inform the Members on ongoing activities in the Nuclear Training field, define redundancies and gaps of the ''Assistance Programs'', and propose efficient ways to progress. Training was recognized as one major activity through which operational safety can be very effectively and quite quickly improved and therefore the Plenary Session unanimously decided to launch a TWG on the subject. The present report is issued one year after the creation of the TWG. It summarizes the major steps of the activities and presents the relevant results. It also contains copies of documents on training infrastructures and requirements, provided by the recipient countries during the course of the work

Quantifying Uncertainty in Soil Volume Estimates

International Nuclear Information System (INIS)

Roos, A.D.; Hays, D.C.; Johnson, R.L.; Durham, L.A.; Winters, M.

2009-01-01

Proper planning and design for remediating contaminated environmental media require an adequate understanding of the types of contaminants and the lateral and vertical extent of contamination. In the case of contaminated soils, this generally takes the form of volume estimates that are prepared as part of a Feasibility Study for Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) sites and/or as part of the remedial design. These estimates are typically single values representing what is believed to be the most likely volume of contaminated soil present at the site. These single-value estimates, however, do not convey the level of confidence associated with the estimates. Unfortunately, the experience has been that pre-remediation soil volume estimates often significantly underestimate the actual volume of contaminated soils that are encountered during the course of remediation. This underestimation has significant implications, both technically (e.g., inappropriate remedial designs) and programmatically (e.g., establishing technically defensible budget and schedule baselines). Argonne National Laboratory (Argonne) has developed a joint Bayesian/geostatistical methodology for estimating contaminated soil volumes based on sampling results, that also provides upper and lower probabilistic bounds on those volumes. This paper evaluates the performance of this method in a retrospective study that compares volume estimates derived using this technique with actual excavated soil volumes for select Formerly Utilized Sites Remedial Action Program (FUSRAP) Maywood properties that have completed remedial action by the U.S. Army Corps of Engineers (USACE) New York District. (authors)

XML: Solution for the integration of nuclear power plant data and technical documents

International Nuclear Information System (INIS)

Gordillo, F.

2000-01-01

Assuring proper operation of the systems that make up a nuclear power plant requires handling a massive amount of technical documents. This technical documentation, consisting mainly of system descriptions, operating and maintenance procedures, safety procedures, etc, presents particular characteristics, mainly: Great volume of information. High contents in figures and graphics. High reliability required. Multiple cross-references among documents. (Author)

Survey of Biomass Gasification, Volume II: Principles of Gasification

Energy Technology Data Exchange (ETDEWEB)

Reed, T.B. (comp.)

1979-07-01

Biomass can be converted by gasification into a clean-burning gaseous fuel that can be used to retrofit existing gas/oil boilers, to power engines, to generate electricity, and as a base for synthesis of methanol, gasoline, ammonia, or methane. This survey describes biomass gasification, associated technologies, and issues in three volumes. Volume I contains the synopsis and executive summary, giving highlights of the findings of the other volumes. In Volume II the technical background necessary for understanding the science, engineering, and commercialization of biomass is presented. In Volume III the present status of gasification processes is described in detail, followed by chapters on economics, gas conditioning, fuel synthesis, the institutional role to be played by the federal government, and recommendations for future research and development.

Twenty-fifth water reactor safety information meeting: Proceedings. Volume 2: Human reliability analysis and human performance evaluation; Technical issues related to rulemakings; Risk-informed, performance-based initiatives; High burn-up fuel research

Energy Technology Data Exchange (ETDEWEB)

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

1998-03-01

This three-volume report contains papers presented at the conference. 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, Japan, Norway, and Russia. The titles of the papers and the names of the authors have been updated and may differ from those that appeared in the final program of the meeting. This volume contains the following: (1) human reliability analysis and human performance evaluation; (2) technical issues related to rulemakings; (3) risk-informed, performance-based initiatives; and (4) high burn-up fuel research. Selected papers have been indexed separately for inclusion in the Energy Science and Technology Database.

Standard Technical Specifications, General Electric Plants, BWR/6

International Nuclear Information System (INIS)

1992-09-01

This NUREG contains improved Standard Technical Specifications (STS) for General Electric Plants, BWR/4, and documents the positions of the Nuclear Regulatory Commission based on the BWR Owners Group's proposed STS. This document is the result of extensive technical meetings and discussions among the NRC staff, the Nuclear Steam Supply System (NSSS) Owners Groups, the NSSS vendors, and the Nuclear Management and Resources Council (NUMARC). The improved STS were developed based on the criteria in the interim Commission Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, dated February 6, 1987. 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

Standard Technical Specifications, General Electric plants, BWR/4

International Nuclear Information System (INIS)

1992-09-01

This NUREG contains improved Standard Technical Specifications (STS) for General Electric Plants, BWR/6, and documents the positions of the Nuclear Regulatory Commission based on the B ampersand W Owners Group's proposed STS. This document is the result of extensive technical meetings and discussions among the NRC staff, the Nuclear Steam Supply System (NSSS) Owners Groups, the NSSS vendors, and the Nuclear Management and Resources Council (NUMARC). The improved STS were developed based on the criteria in the interim Commission Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, dated February 6, 1987. 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. This document Volume 3, contains the Bases for Sections 3.4--3.10 of the improved STS

Standard Technical Specifications, General Electric plants, BWR/6

International Nuclear Information System (INIS)

1992-09-01

This NUREG contains improved Standard Technical Specifications (STS) for General Electric Plants, BWR/6, and documents the positions of the Nuclear Regulatory Commission based on the B ampersand W Owners Group's proposed STS. This document is the result of extensive technical meetings and discussions among the NRC staff, the Nuclear Steam Supply System (NSSS) Owners Groups, the NSSS vendors, and the Nuclear Management and Resources Council (NUMARC). The improved STS were developed based on the criteria in the interim Commission Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, dated February 6, 1987. 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. 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

Standard Technical Specifications, General Electric Plants, BWR/6

International Nuclear Information System (INIS)

1992-09-01

This NUREG contains improved Standard Technical Specifications (STS) for General Electric Plants, BWR/6, and documents the positions of the Nuclear Regulatory Commission based on the B ampersand W Owners Group's proposed STS. This document is the result of extensive technical meetings and discussions among the NRC staff, the Nuclear Steam Supply System (NSSS) Owners Groups, the NSSS vendors, and the Nuclear Management and Resources Council (NUMARC). The improved STS were developed based on the criteria in the interim Commission Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, dated February 6, 1987. 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. This document 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

Standard Technical Specifications, General Electric plants, BWR/4

International Nuclear Information System (INIS)

1992-09-01

This NUREG contains improved Standard Technical Specifications (STS) for General Electric Plants, BWR/6, and documents the positions of the Nuclear Regulatory Commission based on the BWR Owners Group's proposed STS. This document is the result of extensive technical meetings and discussions among the NRC staff, the Nuclear Steam Supply System (NSSS) Owners Groups, the NSSS vendors, and the Nuclear Management and Resources Council (NUMARC). The improved STS were developed based on the criteria in the interim Commission Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, dated February 6, 1987. 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. This document 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

Comprehensive Cooling Water Study. Volume 1. Summary of environmental effects, Savannah River Plant. Annual report

International Nuclear Information System (INIS)

Gladden, J.B.; Lower, M.W.; Mackey, H.E.; Specht, W.L.; Wilde, E.W.

1985-07-01

This volume summarizes the technical content of Volumes II through XI of the annual report. Volume II provides a description of the SRP environment, facilities, and operation, and presents the objectives and design for the CCWS. Volume III presents information on water quality of SRP surface waters. Results of radionuclide and heavy metal transport studies are presented in Volume IV. Volume V contains findings from studies of wetland plant communities. Volume VI presents findings from studies of the lower food chain components of SRP aquatic habitats. The results of fisheries studies are reported in Volume VII. Studies of semi-aquatic vertebrate populations are reported in Volume VIII. Water-fowl utilization of SRP habitats is discussed in Volume IX. The status of endangered species that utilize SRP aquatic habitats is presented in Volume X. The findings from studies of Parr Pond ecosystem are presented in Volume XI

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

Yucca Mountain transportation routes: Preliminary characterization and risk analysis; Volume 2, Figures [and] Volume 3, Technical Appendices

Energy Technology Data Exchange (ETDEWEB)

Souleyrette, R.R. II; Sathisan, S.K.; di Bartolo, R. [Nevada Univ., Las Vegas, NV (United States). Transportation Research Center

1991-05-31

This report presents appendices related to the preliminary assessment and risk analysis for high-level radioactive waste transportation routes to the proposed Yucca Mountain Project repository. Information includes data on population density, traffic volume, ecologically sensitive areas, and accident history.

Technical issues associated with in situ vitrification of the INEL Subsurface Disposal Area

International Nuclear Information System (INIS)

Stoots, C.M.; Bates, S.O.; Callow, R.A.; Campbell, K.A.; Farnsworth, R.K.; Gratson, G.K.; McKellar, M.G.; Nickelson, D.F.; Slater, C.E.

1991-12-01

In situ vitrification (ISV) has been identified as an alternative technology for remediation of the Acid Pit and Transuranic Pits and Trenches (TRU-PTs) that are present at the Idaho National Engineering Laboratory (INEL) Subsurface Disposal Area (SDA). However, a number of technical issues exist that must be resolved before ISV can be considered applicable to these waste sites. To assist in the ISV technology evaluation, an ISV Steering Committee was formed to identify, prioritize, and develop closure roadmaps for technical issues associated with ISV application at the INEL SDA. The activities of the ISV Steering Committee are summarized in three volumes of this report. This document, Volume 1, identifies the systematic approach used to identify and prioritize the ISV technical issues, and briefly discusses the methodology that will be employed to resolve these issues

Technical support for GEIS: radioactive waste isolation in geologic formations. Volume 6. Baseline rock properties-shale

International Nuclear Information System (INIS)

1978-04-01

This volume, Y/OWI/TM36/6 Baseline Rock Properties--Shale, is one of a 23-volume series, ''Technical Support for GEIS: Radioactive Waste Isolation in Geologic Formations, Y/OWI/TM-36'' which supplements a ''Contribution to Draft Generic Environmental Impact Statement on Commercial Waste Management: Radioactive Waste Isolation in Geologic Formations, Y/OWI/TM-44.'' The series provides a more complete technical basis for the preconceptual designs, resource requirements, and environmental source terms associated with isolating commercial LWR wastes in underground repositories in salt, granite, shale and basalt. Wastes are considered from three fuel cycles: uranium and plutonium recycling, no recycling of spent fuel and uranium-only recycling. The report is a result of a literature survey of the rock properties of shales occurring in the United States. Firstly, data were collected from a wide variety of sources in order to obtain a feel for the range of properties encountered. Secondly, some typical shales were selected for detailed review and these are written up as separate chapters in this report. Owing to the wide variability in lithology and properties of shales occurring in the United States, it became necessary to focus the study on consolidated illite shales. Using the specific information already generated, a consistent set of intact properties for a typical, consolidated illite shale was obtained. Correction factors, largely based on geological considerations, were then applied to the intact data in order to yield typical rock mass properties for this type of shale. Lastly, excavation problems in shale formations were reviewed and three tunnel jobs were written up as case histories

Mixed Waste Focus Area integrated technical baseline report, Phase 1: Volume 1

International Nuclear Information System (INIS)

1996-01-01

The Department of Energy (DOE) established the Mixed Waste Characterization, Treatment, and Disposal Focus Area (MWFA) to develop and facilitate implementation of technologies required to meet the Department's commitments for treatment of mixed low-level and transuranic wastes. The mission of the MWFA is to provide acceptable treatment systems, developed in partnership with users and with participation of stakeholders, tribal governments, and regulators, that are capable of treating DOE's mixed waste. These treatment systems include all necessary steps such as characterization, pretreatment, and disposal. To accomplish this mission, a technical baseline is being established that forms the basis for determining which technology development activities will be supported by the MWFA. The technical baseline is the prioritized list of deficiencies, and the resulting technology development activities needed to overcome these deficiencies. This document presents Phase I of the technical baseline development process, which resulted in the prioritized list of deficiencies that the MWFA will address. A summary of the data and the assumptions upon which this work was based is included, as well as information concerning the DOE Office of Environmental Management (EM) mixed waste technology development needs. The next phase in the technical baseline development process, Phase II, will result in the identification of technology development activities that will be conducted through the MWFA to resolve the identified deficiencies

Waste isolation in the U.S., technical programs and public education. Volume 2 - low level waste, volume reduction methodologies and economics. Vol. 2

International Nuclear Information System (INIS)

Post, R.G.

1984-01-01

This volume presents information regarding low-level waste, volume reduction methodologies and economics. Topics include: public education on nuclear waste; economics of low-level waste management systems; operating experience with advanced volume reduction techniques; solidification of waste; operating experience with advanced volume reduction techniques--incineration; regional plans for the disposal of low-level waste; radwaste system modifications at nuclear power plants; operating experience with advanced volume reduction techniques--operations and on-site storage issues; and economic impact of 10CFR61

1993 Pacific Northwest Loads and Resources Study, Technical Appendix: Volume 2, Book 1, Energy.

Energy Technology Data Exchange (ETDEWEB)

United States. Bonneville Power Administration.

1993-12-01

The 1993 Pacific Northwest Loads and Resources Study establishes the Bonneville Power Administration`s (BPA) planning basis for supplying electricity to BPA customers. The Loads and Resources Study is presented in three documents: (1) this technical appendix detailing loads and resources for each major Pacific and Northwest generating utility, (2) a summary of Federal system and Pacific Northwest region loads and resources, and (3) a technical appendix detailing forecasted Pacific Northwest economic trends and loads. This analysis updates the 1992 Pacific Northwest Loads and Resources Study Technical Appendix published in December 1992. This technical appendix provides utility-specific information that BPA uses in its long-range planning. It incorporates the following for each utility (1) Electrical demand firm loads; (2) Generating resources; and (3) Contracts both inside and outside the region. This document should be used in combination with the 1993 Pacific Northwest Loads and Resources Study, published in December 1993, because much of the information in that document is not duplicated here.

Technical support for GEIS: radioactive waste isolation in geologic formations. Volume 16. Repository preconceptual design studies: BPNL waste forms in salt

International Nuclear Information System (INIS)

1978-04-01

This volume, Volume 16, ''Repository Preconceptual Design Studies: BPNL Waste Forms in Salt,'' is one of a 23 volume series, ''Technical Support for GEIS: Radioactive Waste Isolation in Geologic Formations,'' Y/OWI/TM-36, which supplements the ''Contribution to Draft Generic Environmental Impact Statement on Commercial Waste Management: Radioactive Waste Isolation in Geologic Formations,'' Y/OWI/TM-44. The series provide a more complete technical basis for the preconceptual designs, resource requirements, and environmental source terms associated with isolating commercial LWR wastes in underground repositories in salt, granite, shale and basalt. Wastes are considered from three fuel cycles: uranium and plutonium recycling, no recycling of spent fuel and uranium-only recycling. This document describes a preconceptual design for a nuclear waste storage facility in salt. The waste forms assumed to arrive at the repository were supplied by Battelle Pacific Northwest Laboratories (BPNL). The facility design consists of several chambers excavated deep within a geologic formation together with access shafts and supportive surface structures. The facility design provides for: receiving and unloading waste containers; lowering them down shafts to the mine level; transporting them to the proper storage area and emplacing them in mined storage rooms. Drawings of the facility design are contained in TM-36/17, ''Drawings for Repository Preconceptual Design Studies: BPNL Waste Forms in Salt.''

Feasibility of developing a portable driver performance data acquisition system for human factors research: Technical tasks. Volume 1

Energy Technology Data Exchange (ETDEWEB)

Carter, R.J.; Barickman, F.S.; Spelt, P.F.; Schmoyer, R.L.; Kirkpatrick, J.R.

1998-01-01

A two-phase, multi-year research program entitled ``development of a portable driver performance data acquisition system for human factors research`` was recently completed. The primary objective of the project was to develop a portable data acquisition system for crash avoidance research (DASCAR) that will allow drive performance data to be collected using a large variety of vehicle types and that would be capable of being installed on a given vehicle type within a relatively short-time frame. During phase 1 a feasibility study for designing and fabricating DASCAR was conducted. In phase 2 of the research DASCAR was actually developed and validated. This technical memorandum documents the results from the feasibility study. It is subdivided into three volumes. Volume one (this report) addresses the last five items in the phase 1 research and the first issue in the second phase of the project. Volumes two and three present the related appendices, and the design specifications developed for DASCAR respectively. The six tasks were oriented toward: identifying parameters and measures; identifying analysis tools and methods; identifying measurement techniques and state-of-the-art hardware and software; developing design requirements and specifications; determining the cost of one or more copies of the proposed data acquisition system; and designing a development plan and constructing DASCAR. This report also covers: the background to the program; the requirements for the project; micro camera testing; heat load calculations for the DASCAR instrumentation package in automobile trunks; phase 2 of the research; the DASCAR hardware and software delivered to the National Highway Traffic Safety Administration; and crash avoidance problems that can be addressed by DASCAR.

AREVA Technical Days (ATD) session 1: Energy outlook and presentation of the Areva Group; AREVA Technical Days (ATD) session 1: enjeux energetiques et presentation du groupe AREVA

Energy Technology Data Exchange (ETDEWEB)

NONE

2002-07-01

These technical days organized by the Areva Group aims to explain the group activities in a technological and economic point of view, to provide an outlook of worldwide energy trends and challenges and to present each of their businesses in a synthetic manner. This first session deals with energy challenges and nuclear, public acceptance of nuclear power, mining activities, chemistry activities, enrichment activities, fuel assembly, reactors and services activities, nuclear measurements activities, reprocessing and recycling activities, logistics activities and connectors activities. (A.L.B.)

TVA coal-gasification commercial demonstration plant project. Volume 5. Plant based on Koppers-Totzek gasifier. Final report

Energy Technology Data Exchange (ETDEWEB)

1980-11-01

This volume presents a technical description of a coal gasification plant, based on Koppers-Totzek gasifiers, producing a medium Btu fuel gas product. Foster Wheeler carried out a conceptual design and cost estimate of a nominal 20,000 TPSD plant based on TVA design criteria and information supplied by Krupp-Koppers concerning the Koppers-Totzek coal gasification process. Technical description of the design is given in this volume.

Technical summary of Groundwater Quality Protection Program at Savannah River Plant. Volume II. Radioactive waste

International Nuclear Information System (INIS)

Stone, J.A.; Christensen, E.J.

1983-12-01

This report (Volume II) presents representative monitoring data for radioactivity in groundwater at SRP. Four major groups of radioactive waste disposal sites and three minor sites are described. Much of the geohydrological and and other background information given in Volume I is applicable to these sites and is incorporated by reference. Several of the sites that contain mixed chemical and radioactive wastes are discussed in both Volumes I and II. Bulk unirradiated uranium is considered primarily a chemical waste which is addressed in Volume I, but generally not in Volume II

NASA University Research Centers Technical Advances in Aeronautics, Space Sciences and Technology, Earth Systems Sciences, Global Hydrology, and Education. Volumes 2 and 3

Science.gov (United States)

Coleman, Tommy L. (Editor); White, Bettie (Editor); Goodman, Steven (Editor); Sakimoto, P. (Editor); Randolph, Lynwood (Editor); Rickman, Doug (Editor)

1998-01-01

This volume chronicles the proceedings of the 1998 NASA University Research Centers Technical Conference (URC-TC '98), held on February 22-25, 1998, in Huntsville, Alabama. The University Research Centers (URCS) are multidisciplinary research units established by NASA at 11 Historically Black Colleges or Universities (HBCU's) and 3 Other Minority Universities (OMU's) to conduct research work in areas of interest to NASA. The URC Technical Conferences bring together the faculty members and students from the URC's with representatives from other universities, NASA, and the aerospace industry to discuss recent advances in their fields.

Volume reduction techniques for solid radioactive wastes

International Nuclear Information System (INIS)

Clarke, J.H.

1980-01-01

This report gives an account of some of the techniques in current use in the UK for the treatment of solid radioactive wastes to reduce their volume prior to storage or disposal. Reference is also made to current research and development projects. It is based on a report presented at a recent International Atomic Energy Agency Technical Committee when this subject was the main theme. An IAEA Technical Series report covering techniques in use in all parts of the world should be published within the next two years. (author)

Standard technical specifications: Babcock and Wilcox Plants. 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 Babcock ampersand 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

Technical support for GEIS: radioactive waste isolation in geologic formations. Volume 2. Commercial waste forms, packaging and projections for preconceptual repository design studies

International Nuclear Information System (INIS)

1978-04-01

This volume, Y/OWI/TM-36/2, ''Commercial Waste Forms, Packaging and Projections for Preconceptual Repository Design Studies,'' is one of a 23-volume series, ''Technical Support for GEIS: Radioactive Waste Isolation in Geologic Formations,'' Y/OWI/TM-36, which supplements the ''Contribution to Draft Generic Environmental Impact Statement on Commercial Waste Management: Radioactive Waste Isolation in Geologic Formations,'' Y/OWI/TM-44. The series provides a more complete technical basis for the preconceptual designs, resource requirements, and environmental source terms associated with isolating commercial LWR wastes in underground repositories in salt, granite, shale and basalt. Wastes are considered from three fuel cycles: uranium and plutonium recycling, no recycling of spent fuel and uranium-only recycling. This volume contains the data base for waste forms, packages, and projections from the commercial waste defined by the Office of Waste Isolation in ''Nuclear Waste Projections and Source Term Data for FY 1977,'' Y/OWI/TM-34. Also, as an alternative data base for repository design and analysis, waste forms, packages, and projections for commercial waste defined by Battelle Pacific Northwest Laboratory (BPNL) have been included. This data base consists of a reference case for use in the alternative design study and a definition of combustible wastes for use in mine fire and hydrogen generation analyses

Technical procedures for water resources, Deaf Smith County site, Texas: Volume 2: Environmental Field Program: Final draft

International Nuclear Information System (INIS)

1987-08-01

This volume contains the following Technical Procedures pursuant to the Water Resources Site Study Plan operation of a Playa Lake conductivity monitoring station and processing of data from a Playa Lake conductivity monitoring station. This procedure defines steps and methods for the installation, operation, and maintenance of the Playa Lake conductivity monitoring stations. Conductivity measurements will be taken at six playa lakes in the site study area to record changes in total dissolved solids as a function of stage. Playa lake conductivity and stage (volume) measurements will be used, in conjunction with other water quality data collected at the Playa Lake and precipitation stations, to determine the mass of dissolved solids entering and leaving the playas. This baseline information on the pollutant mass balance of the playas will be used to assess potential changes in playa lake water quality and the magnitude of those changes due to site development. The pollutant mass balances will also be used on determining the source of pollutants. 2 refs., 5 figs

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.

Standard Technical Specifications, Babcock and Wilcox plants

International Nuclear Information System (INIS)

1992-09-01

This NUREG contains improved Standard Technical Specifications (STS) for Babcock and Wilcox (B ampersand W) Plants and documents the positions of the Nuclear Regulatory Commission based on the B ampersand W Owners Group's proposed STS. This document is the result of extensive technical meetings and discussions among the NRC staff, the Nuclear Steam Supply System (NSSS) Owners Groups, the NSSS vendors, and the Nuclear Management and Resources Council (NUMARC). The unproved STS were developed based on the, criteria in the interim Commission Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, dated February 6, 1987. The improved STS will be used as the basis for individual nuclear power plant licensees to develop proved plant-specific technical specifications. This report contains three volumes. This document, Volume 1 contains the Specifications for all chapters and sections of the improved STS

Proceedings of the 2010 AFMS Medical Research Symposium. Volume 5. Nursing Track: Abstracts and Presentations

Science.gov (United States)

2011-03-15

Management Education at a Military Hospital .................................................................. 29  Proceedings of the 2010 AFMS... education information is in Appendix C of this volume. Appendices D-L are copies of presentation slides from the plenary sessions.  Volume 2. This volume...women who have menstruation as compared to deployed women who do not have menstruation ? This study is a descriptive co relational research design. The

Technical presentation - KEITHLEY Instruments - CANCELLED

CERN Multimedia

FI Department

2009-01-01

10 March 2009 13:30 – 15:30, Council Chamber, Bldg. 503 Keithley markets highly accurate instruments and data acquisition products, as well as complete system solutions for high-volume production and assembly testing. Keithley Instruments, Inc. designs, develops, manufactures and markets complex electronic instruments and systems geared to the specialized needs of electronics manufacturers for high-performance production testing, process monitoring, product development and research. Products and Services: Digital Multimeters and Data Acquisition Systems Current / Voltage Source and Measure Products Low Current / High Resistance Measurement Products Function/Pulse/Arbitrary/Pattern Generators Low Voltage/Low Resistance Measurement Products RF Spectrum Analyzer / RF Signal Generator / RF Switching Semiconductor Device Characterization Program: Topic 1: Welcome and short overview of new Products SMU 26XXA / ARB Generator 3390 / DMM 3706 / E-Meter 6517B Topic 2a: Te...

Sensors, Volume 4, Thermal Sensors

Science.gov (United States)

Scholz, Jorg; Ricolfi, Teresio

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 describes the construction and applicational aspects of thermal sensors while presenting a rigorous treatment of the underlying physical principles. It provides a unique overview of the various categories of sensors as well as of specific groups, e.g. temperature sensors (resistance thermometers, thermocouples, and radiation thermometers), noise and acoustic thermometers, heat-flow and mass-flow sensors. Specific facettes of applications are presented by specialists from different fields including process control, automotive technology and cryogenics. This volume is an indispensable reference work and text book for both specialists and newcomers, researchers and developers.

Television and Social Behavior; Reports and Papers, Volume V: Television's Effects: Further Explorations.

Science.gov (United States)

Comstock, George A., Ed.; And Others

The studies in this fifth volume of technical reports to the Scientific Advisory Committee on Television and Social Behavior explore the role of mediated aggression and violence on relevant human behaviors in some new and interesting ways. The volume begins with an overview of the studies, presenting a statement of the principal questions asked,…

Continuous modelling study of numerical volumes - Applications to the visualization of anatomical structures

International Nuclear Information System (INIS)

Goret, C.

1990-12-01

Several technics of imaging (IRM, image scanners, tomoscintigraphy, echography) give numerical informations presented by means of a stack of parallel cross-sectional images. Since many years, 3-D mathematical tools have been developed and allow the 3 D images synthesis of surfaces. In first part, we give the technics of numerical volume exploitation and their medical applications to diagnosis and therapy. The second part is about a continuous modelling of the volume with a tensor product of cubic splines. We study the characteristics of this representation and its clinical validation. Finally, we treat of the problem of surface visualization of objects contained in the volume. The results show the interest of this model and allow to propose specifications for 3-D workstation realization [fr

Air Pollution Translations: A Bibliography with Abstracts - Volume 4.

Science.gov (United States)

Environmental Protection Agency, Research Triangle Park, NC. Air Pollution Technical Information Center.

This volume is the fourth in a series of compilations presenting abstracts and indexes of translations of technical air pollution literature. The entries are grouped into 12 subject categories: Emission Sources, Control Methods, Measurement Methods, Air Quality Measurements, Atmospheric Interaction, Basic Science and Technology, Effects--Human…

Air Pollution Translations: A Bibliography with Abstracts - Volume 2.

Science.gov (United States)

National Air Pollution Control Administration (DHEW), Raleigh, NC.

This volume is the second in a series of compilations presenting abstracts and indexes of translations of technical air pollution literature. The 444 entries are grouped into 12 subject categories: General; Emission Sources; Atmospheric Interaction; Measurement Methods; Control Methods; Effects--Human Health; Effects--Plants and Livestock;…

Solar central receiver prototype heliostat CDRL item B. d. Final technical report, Volume 2

Energy Technology Data Exchange (ETDEWEB)

Easton, C. R.

1978-08-01

This is volume II of a two volume report which presents the results of a study to define a low-cost approach to the production, installation, and operation of heliostats for central receiver solar thermal power plants. Performance and cost analyses are presented, and critical R and D areas are identified. Also, computer printed work sheets are included for heliostat investment, maintenance equipment investment, initial spares investment, and first years operations and maintenance for 2,500, 25,000, 250,000, and 1,000,000 units per year production. (WHK)

Reviving Graduate Seminar Series through Non-Technical Presentations

Science.gov (United States)

Madihally, Sundararajan V.

2011-01-01

Most chemical engineering programs that offer M.S. and Ph.D. degrees have a common seminar series for all the graduate students. Many would agree that seminars lack student interest, leading to ineffectiveness. We questioned the possibility of adding value to the seminar series by incorporating non-technical topics that may be more important to…

Technical Meeting on Fast Reactors and Related Fuel Cycle Facilities with Improved Economic Characteristics. Presentations

International Nuclear Information System (INIS)

2013-01-01

The objectives of the meeting were: • To identify the main issues and technical features that affect capital and energy production costs of fast reactors and related fuel cycle facilities; • To present fast reactor concepts and designs with enhanced economic characteristics, as well as innovative technical solutions (components, subsystems, etc.) that have the potential to reduce the capital costs of fast reactors and related fuel cycle facilities; • To present energy models and advanced tools for the cost assessment of innovative fast reactors and associated nuclear fuel cycles; • To discuss the results of studies and ongoing R&D activities that address cost reduction and the future economic competitiveness of fast reactors; • To identify research and technology development needs in the field, also in view of new IAEA initiatives to help and support Member States in improving the economic competitiveness of fast reactors and associated nuclear fuel cycles

Budget estimates, fiscal year 1987. Appropriation: salaries and expenses. Volume 2

International Nuclear Information System (INIS)

1986-02-01

This volume presents the salaries and expenses of the following US NRC programs: nuclear reactor regulation, nuclear material safety and safeguards, inspection and enforcement, nuclear regulatory research, program technical support, and program direction and administration. Special supporting tables are included

Technical support for GEIS: radioactive waste isolation in geologic formations. Volume 2. Commercial waste forms, packaging and projections for preconceptual repository design studies

Energy Technology Data Exchange (ETDEWEB)

1978-04-01

This volume, Y/OWI/TM-36/2, ''Commercial Waste Forms, Packaging and Projections for Preconceptual Repository Design Studies,'' is one of a 23-volume series, ''Technical Support for GEIS: Radioactive Waste Isolation in Geologic Formations,'' Y/OWI/TM-36, which supplements the ''Contribution to Draft Generic Environmental Impact Statement on Commercial Waste Management: Radioactive Waste Isolation in Geologic Formations,'' Y/OWI/TM-44. The series provides a more complete technical basis for the preconceptual designs, resource requirements, and environmental source terms associated with isolating commercial LWR wastes in underground repositories in salt, granite, shale and basalt. Wastes are considered from three fuel cycles: uranium and plutonium recycling, no recycling of spent fuel and uranium-only recycling. This volume contains the data base for waste forms, packages, and projections from the commercial waste defined by the Office of Waste Isolation in ''Nuclear Waste Projections and Source Term Data for FY 1977,'' Y/OWI/TM-34. Also, as an alternative data base for repository design and analysis, waste forms, packages, and projections for commercial waste defined by Battelle Pacific Northwest Laboratory (BPNL) have been included. This data base consists of a reference case for use in the alternative design study and a definition of combustible wastes for use in mine fire and hydrogen generation analyses.

Technical Barriers, Licenses and Tariffs as Means of Limiting Market Access

DEFF Research Database (Denmark)

Schröder, Philipp J.H.; Jørgensen, Jan Guldager

2006-01-01

Technical barriers (standards), import licenses and tariffs may be deployed as means of limiting the market access of foreign firms. The present paper examines these measures in a setting of monopolistic competition. We find that, if protection focuses predominantly on the number of foreign firms...... accessing the domestic market, a technical barrier (an import license) may dominate a tariff (tariff and a tech- nical barrier) in terms of consumer welfare, even when tariff revenues are fully redistributed. However, if protection pays su±cient focus on limiting the total import volume, then tariffs...

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

Technical issues associated with in situ vitrification of the INEL Subsurface Disposal Area

International Nuclear Information System (INIS)

Stoots, C.M.; Bates, S.O.; Callow, R.A.; Campbell, K.A.; Farnsworth, R.K.; Krisman, G.K.; McKellar, M.G.; Nickelson, D.F.; Slater, C.E.

1992-07-01

In situ vitrification (ISV) has been identified as an alternative technology for remediation of the acid pit and transuranic pits and trenches (TRU-PTs) at the Idaho National Engineering Laboratory (INEL) Subsurface Disposal Area (SDA). However, a number of technical issues must be resolved before ISV can be considered applicable to these waste sites. To assist in the ISV technology evaluation, an ISV Steering Committee was formed to identify, prioritize, and develop closure roadmaps for technical issues lated with ISV application at the SDA. The activities of the ISV Steering Committee are summarized in a three-volume report. Volume I identifies the systematic approach used to identify and prioritize the ISV technical issues and briefly discusses the methodology that will be employed to resolve these issues. Volumes 2 and 3 discuss each technical issue in greater detail and suggest specific closure roadmaps to be used in resolving technical issues associated with ISV at the SDA Acid Pit and TRU-PTS, respectively. The three-volume report is a working document that will be updated as necessary to reflect current evaluation strategy for the ISV technology. This is Volume 3

SAPHIRE 8 Volume 2 - Technical Reference

Energy Technology Data Exchange (ETDEWEB)

C. L. Smith; S. T. Wood; W. J. Galyean; J. A. Schroeder; M. B. Sattison

2011-03-01

The Systems Analysis Programs for Hands-on Integrated Reliability Evaluations (SAPHIRE) refers to a set of computer programs that were developed to create and analyze probabilistic risk assessment (PRAs). Herein information is provided on the principles used in the construction and operation of Version 8.0 of the SAPHIRE system. This report summarizes the fundamental mathematical concepts of sets and logic, fault trees, and probability. This volume then describes the algorithms used to construct a fault tree and to obtain the minimal cut sets. It gives the formulas used to obtain the probability of the top event from the minimal cut sets, and the formulas for probabilities that apply for various assumptions concerning reparability and mission time. It defines the measures of basic event importance that SAPHIRE can calculate. This volume gives an overview of uncertainty analysis using simple Monte Carlo sampling or Latin Hypercube sampling, and states the algorithms used by this program to generate random basic event probabilities from various distributions. Also covered are enhance capabilities such as seismic analysis, Workspace algorithms, cut set "recovery," end state manipulation, and use of "compound events."

Feasibility of commercial space manufacturing, production of pharmaceuticals. Volume 2: Technical analysis

Science.gov (United States)

1978-01-01

A technical analysis on the feasibility of commercial manufacturing of pharmaceuticals in space is presented. The method of obtaining pharmaceutical company involvement, laboratory results of the separation of serum proteins by the continuous flow electrophoresis process, the selection and study of candidate products, and their production requirements is described. The candidate products are antihemophilic factor, beta cells, erythropoietin, epidermal growth factor, alpha-1-antitrypsin and interferon. Production mass balances for antihemophelic factor, beta cells, and erythropoietin were compared for space versus ground operation. A conceptual description of a multiproduct processing system for space operation is discussed. Production requirements for epidermal growth factor of alpha-1-antitrypsin and interferon are presented.

Technical Meeting on Impact of Fukushima Event on Current and Future Fast Reactor Designs. Presentations

International Nuclear Information System (INIS)

2012-01-01

The overall purpose of the Technical Meeting was to recognize and analyse the implications of the accident occurred at the Fukushima Dai-ichi Nuclear Power Station on current and future fast neutron systems design and operation. The aim was to provide a global forum for discussing the principal lessons learned from this event, and thus to review safety principles and characteristics of existing and future fast neutron concepts, especially in relation with extreme natural events which potentially may lead to severe accident scenarios. The participants also presented and discussed innovative technical solutions, design features and countermeasures for design extension conditions - including earthquakes, tsunami and other extreme natural hazards - which can enhance the safety level of existing and future fast neutron systems. Furthermore, the meeting gave the opportunity to present advanced methods for the evaluation of the robustness of plants against design extension conditions. Another important goal of this TM was to discuss how to harmonize safety approaches and goals for next generation’s fast reactors. Finally, the meeting was intended to identify areas where further research and development in nuclear safety, technology and engineering in the light of the Fukushima accident are needed. In the frame of the implementation of its Nuclear Safety Action Plan endorsed by all Member States, the IAEA will consider these areas as potential technical topics for new Coordinated Research Projects, to be launched in the near future

Expectation and task for constructing the volume reduction system of removed soils. In search of the technical integrity from the intermediate storage to final disposal

International Nuclear Information System (INIS)

Mori, Hisaki

2016-01-01

The intermediate storage volume of the removed soils and incineration ash in Fukushima is supposed about 22 million cubic meters. Within 30 years after starting the intermediate storage, the final disposal outside Fukushima prefecture to these removed soils and incineration ash is determined by the law. Because these removed soils are the very-very low radio activity, the volume reduction method is most effective to reduce the burden of the final disposal. As the volume reduction technology is the stage of research and development, the possibility of the introduction of the volume reduction technology that has the consistency of the final disposal technology is evaluated from the point of view of cost. Since this business is accompanied by economic and technical risk to implement private companies, this project is considered appropriate to be implemented as a national project. (author)

Flight Technical Error Analysis of the SATS Higher Volume Operations Simulation and Flight Experiments

Science.gov (United States)

Williams, Daniel M.; Consiglio, Maria C.; Murdoch, Jennifer L.; Adams, Catherine H.

2005-01-01

This paper provides an analysis of Flight Technical Error (FTE) from recent SATS experiments, called the Higher Volume Operations (HVO) Simulation and Flight experiments, which NASA conducted to determine pilot acceptability of the HVO concept for normal operating conditions. Reported are FTE results from simulation and flight experiment data indicating the SATS HVO concept is viable and acceptable to low-time instrument rated pilots when compared with today s system (baseline). Described is the comparative FTE analysis of lateral, vertical, and airspeed deviations from the baseline and SATS HVO experimental flight procedures. Based on FTE analysis, all evaluation subjects, low-time instrument-rated pilots, flew the HVO procedures safely and proficiently in comparison to today s system. In all cases, the results of the flight experiment validated the results of the simulation experiment and confirm the utility of the simulation platform for comparative Human in the Loop (HITL) studies of SATS HVO and Baseline operations.

Information base for waste repository design. Volume 5. Decommissioning of underground facilities. Technical report

International Nuclear Information System (INIS)

Giuffre, M.S.; Plum, R.L.; Koplik, C.M.; Talbot, R.

1979-03-01

This report is Volume 5 of a seven volume document on nuclear waste repository design issues. This report discusses the requirements for decommissioning a deep underground facility for the disposal of radioactive waste. The techniques for sealing the mined excavations are presented and an information base on potential backfill materials is provided. Possible requirements for monitoring the site are discussed. The performance requirements for backfill materials are outlined. The advantages and disadvantages of each sealing method are stated

Target volume definition for external beam partial breast radiotherapy: Clinical, pathological and technical studies informing current approaches

International Nuclear Information System (INIS)

Kirby, Anna M.; Coles, Charlotte E.; Yarnold, John R.

2010-01-01

Partial breast irradiation (PBI) is currently under investigation in several phase III trials and, following a recent consensus statement, its use off-study may increase despite ongoing uncertainty regarding optimal target volume definition. We review the clinical, pathological and technical evidence for target volume definition in external beam partial breast irradiation (EB-PBI). The optimal method of tumour bed (TB) delineation requires X-ray CT imaging of implanted excision cavity wall markers. The definition of clinical target volume (CTV) as TB plus concentric 15 mm margins is based on the anatomical distribution of multifocal and multicentric disease around the primary tumour in mastectomy specimens, and the clinical locations of local tumour relapse (LR) after breast conservation surgery. If the majority of LR originate from foci of residual invasive and/or intraduct disease in the vicinity of the TB after complete microscopic resection, CTV margin logically takes account of the position of primary tumour within the surgical resection specimen. The uncertain significance of independent primary tumours as sources of preventable LR, and of wound healing responses in stimulating LR, increases the difficulties in defining optimal CTV. These uncertainties may resolve after long-term follow-up of current PBI trials. By contrast, a commonly used 10 mm clinical to planning target volume (PTV) margin has a stronger evidence base, although departmental set-up errors need to be confirmed locally. A CTV-PTV margin >10 mm may be required in women with larger breasts and/or large seromas, whilst the role of image-guided radiotherapy with or without TB markers in reducing CTV-PTV margins needs to be explored.

Proceedings of the Advanced Turbine Systems Annual Program Review meeting. Volume 1

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-10-01

Goal of the 8-year program is to develop cleaner, more efficient, and less expensive gas turbine systems for utility and industrial electric power generation, cogeneration, and mechanical drive units. The conference is held annually for energy executives, engineers, scientists, and other interested parties industry, academia, and Government. Advanced turbine systems topics discussed during five technical sessions included policy and strategic issues, program element overviews and technical reviews, related activities, university/industry consortium interactions, and supportive projects. Twenty-one papers presented during the technical sessions are contained in this volume; they are processed separately for the data base.

Technical abstracts: Mechanical engineering, 1990

International Nuclear Information System (INIS)

Broesius, J.Y.

1991-01-01

This document is a compilation of the published, unclassified abstracts produced by mechanical engineers at Lawrence Livermore National Laboratory (LLNL) during the calendar year 1990. Many abstracts summarize work completed and published in report form. These are UCRL-JC series documents, which include the full text of articles to be published in journals and of papers to be presented at meetings, and UCID reports, which are informal documents. Not all UCIDs contain abstracts: short summaries were generated when abstracts were not included. Technical Abstracts also provides descriptions of those documents assigned to the UCRL-MI (miscellaneous) category. These are generally viewgraphs or photographs presented at meetings. An author index is provided at the back of this volume for cross referencing

Individual Global Navigation Satellite Systems in the Space Service Volume

Science.gov (United States)

Force, Dale A.

2015-01-01

Besides providing position, navigation, and timing (PNT) to terrestrial users, GPS is currently used to provide for precision orbit determination, precise time synchronization, real-time spacecraft navigation, and three-axis control of Earth orbiting satellites. With additional Global Navigation Satellite Systems (GNSS) coming into service (GLONASS, Beidou, and Galileo), it will be possible to provide these services by using other GNSS constellations. The paper, "GPS in the Space Service Volume," presented at the ION GNSS 19th International Technical Meeting in 2006 (Ref. 1), defined the Space Service Volume, and analyzed the performance of GPS out to 70,000 km. This paper will report a similar analysis of the performance of each of the additional GNSS and compare them with GPS alone. The Space Service Volume, defined as the volume between 3,000 km altitude and geosynchronous altitude, as compared with the Terrestrial Service Volume between the surface and 3,000 km. In the Terrestrial Service Volume, GNSS performance will be similar to performance on the Earth's surface. The GPS system has established signal requirements for the Space Service Volume. A separate paper presented at the conference covers the use of multiple GNSS in the Space Service Volume.

Technical progress safeguards future. Technischer Fortschritt sichert die Zukunft

Energy Technology Data Exchange (ETDEWEB)

1985-01-01

'Technical progress safeguards future', the guiding theme of the 1985 conference of German engineers, calls for discussion. In five lectures representatives of the subdivisions of 'VDI' issued their statements from the viewpoints of their special fields. These lectures were completed by reports on the part of the remaining VDI subdivisions, which are published together with the lectures in this volume. The complex guiding theme is meant to stimulate discussion, which should be conducted also with representatives of other sciences and the public. The volume contains a.o. contributions regarding future prospects, given certain modifications in construction engineering and user behaviour in the sector heating and air-conditioning, regarding the development of new construction techniques to protect the environment, and regarding clean air as an international concern of engineers. For these three contributions separate entries were made. Other presentations relate to: automobile production technology; energy supply as an engineering task; information, invention, innovation as stages of technical progress; progress in materials technology; noise of motor vehicles - current state and future prospects. (orig./HSCH).

Using Model-Based System Engineering to Provide Artifacts for NASA Project Life-Cycle and Technical Reviews Presentation

Science.gov (United States)

Parrott, Edith L.; Weiland, Karen J.

2017-01-01

This is the presentation for the AIAA Space conference in September 2017. It highlights key information from Using Model-Based Systems Engineering to Provide Artifacts for NASA Project Life-cycle and Technical Reviews paper.

14th National Conference on Physics. Abstracts. Volume 2

International Nuclear Information System (INIS)

Calboreanu, Alexandru; Grecu, Dan

2005-01-01

The National Conference on Physics 2005, is dedicated to 'The International Year of Physics' by the scientific community of physicists in Romania. Within the frame of this 'Festival of Physics', The First Symposium on Technical Physics and Physical Engineering' TPPE 2005, was organized as a satellite event at the Polytechnic University of Bucharest. As it is well known, the contributed papers to the National Conference on Physics were structured on chapters, corresponding to 'the sections' of The Romanian Society of Physics, their abstracts being then published in a two volume 'Book of Abstracts'. All the chapters of this book, except the 8th and the 9th, can be found in 'Abstracts Volume I'. According to the topics of the TPPE 2005, these two chapters, namely: 8. Technical Physics and Physical Engineering and 9. Physics and Energy are published separately in the 'Abstracts Volume II', but as it can be seen, the unitary character of the Conference is preserved and developed. The most important topics of this second volume are: optoelectronics; advanced materials and technologies; physics, electronics and electrical engineering; physics and mechanical engineering; physics and chemical engineering; physics, information and computer engineering; physics and industry; physics, biology and medical engineering; renewable energy sources and energy efficiency; nuclear engineering. We present the progress made in physics education concerning: physics teaching in technical education; E-learning and modern methods in physics teaching; physics education in schools and universities, in a special section of the first volume of abstracts. Regarding the essential role of physics in the realizing of a knowledge-based society of the new millennium the strengthening of the relationship between researchers and academics becomes thus the main message of this scientific meeting. (P.S.)

Standard Technical Specifications, General Electric plants, BWR/4

International Nuclear Information System (INIS)

1992-09-01

This NUREG contains improved Standard Technical Specifications (STS) for General Electric Plants, BWR/4, and documents the positions of the Nuclear Regulatory Commission based on the BWR Owners Group's proposed STS. This document is the result of extensive technical meetings and discussions among the NRC staff, the Nuclear Steam Supply System (NSSS) Owners Groups, the NSSS vendors, and the Nuclear Management and Resources Council (NUMARC). The improved STS were developed based on the criteria in the interim Commission Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, dated February 6, 1987. The improved STS will be used as the basis for individual nuclear power specifications. This report contains three volumes. This document, Volume 2, contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1--3.3 of the improved STS

Technical Performance Capability of Fourier Transform Profilometry for Quantitative Waste Volume Determination under Hanford Waste Tank Condition

International Nuclear Information System (INIS)

Monts, D.L.; Jang, P.R.; Long, Z.; Norton, O.P.; Okhuysen, W.P.; Su, Y.; Waggoner, Ch.A.

2009-01-01

The Hanford Site is currently in the process of an extensive effort to empty and close its radioactive single-shell and double-shell waste storage tanks. Before this can be accomplished, it is necessary to know how much residual material is left in a given waste tank and the chemical makeup of the residue. The Institute for Clean Energy Technology (ICET) at Mississippi State University is currently developing a quantitative in-tank inspection system based on Fourier Transform Profilometry (FTP). FTP is a non-contact, 3-D shape measurement technique. By projecting a fringe pattern onto a target surface and observing its deformation due to surface irregularities from a different view angle, FTP is capable of determining the height (depth) distribution (and hence volume distribution) of the target surface, thus reproducing the profile of the target accurately under a wide variety of conditions. Hence FTP has the potential to be utilized for quantitative determination of residual wastes within Hanford waste tanks. We report the results of a technical feasibility study to document the accuracy and precision of quantitative volume determination using the Fourier transform profilometry technique under simulated Hanford waste tank conditions. (authors)

INC93: international nuclear congress. Technical sessions summaries

International Nuclear Information System (INIS)

Boulton, J.

1993-01-01

The conference dealt mainly with safety, environmental and human aspects of nuclear energy, including waste management. This volume consists of summaries of the technical sessions contained in Volumes 2 and 3. The individual papers have also been abstracted separately for INIS, with the summaries abridged

INC93: international nuclear congress. Technical sessions summaries

Energy Technology Data Exchange (ETDEWEB)

Boulton, J

1994-12-31

The conference dealt mainly with safety, environmental and human aspects of nuclear energy, including waste management. This volume consists of summaries of the technical sessions contained in Volumes 2 and 3. The individual papers have also been abstracted separately for INIS, with the summaries abridged.

Fault localization technics in energy and communication cables. Fehlerortungstechnik in Energie- und Nachrichtenkabeln

Energy Technology Data Exchange (ETDEWEB)

Bartz, W G; Wippler, E

1981-01-01

Though fault localization technics in energy and information cables represents a special field within electrical engineering or electrical measurement engineering its significance becomes visible when fault-localization technics is seen with the same eyes as energy supply or information exchange. To maintain supply and exchange disturbance free, e.g. by means of continuous or periodical monitoring or to restore them quickly in case of disturbance is the task of fault localization technics. This new volume shall give a survey on the network structures in energy and communication networks, on the types and frequency of past interruptions and also on procedures to evaluate interruptions statistically. Methods, procedures and measurement techniques of fault-localization technics are presented for usual communication and energy cables as well as for optical communication cables.

Hanford analytical services quality assurance requirements documents. Volume 1: Administrative Requirements

International Nuclear Information System (INIS)

Hyatt, J.E.

1997-01-01

Hanford Analytical Services Quality Assurance Requirements Document (HASQARD) is issued by the Analytical Services, Program of the Waste Management Division, US Department of Energy (US DOE), Richland Operations Office (DOE-RL). The HASQARD establishes quality requirements in response to DOE Order 5700.6C (DOE 1991b). The HASQARD is designed to meet the needs of DOE-RL for maintaining a consistent level of quality for sampling and field and laboratory analytical services provided by contractor and commercial field and laboratory analytical operations. The HASQARD serves as the quality basis for all sampling and field/laboratory analytical services provided to DOE-RL through the Analytical Services Program of the Waste Management Division in support of Hanford Site environmental cleanup efforts. This includes work performed by contractor and commercial laboratories and covers radiological and nonradiological analyses. The HASQARD applies to field sampling, field analysis, and research and development activities that support work conducted under the Hanford Federal Facility Agreement and Consent Order Tri-Party Agreement and regulatory permit applications and applicable permit requirements described in subsections of this volume. The HASQARD applies to work done to support process chemistry analysis (e.g., ongoing site waste treatment and characterization operations) and research and development projects related to Hanford Site environmental cleanup activities. This ensures a uniform quality umbrella to analytical site activities predicated on the concepts contained in the HASQARD. Using HASQARD will ensure data of known quality and technical defensibility of the methods used to obtain that data. The HASQARD is made up of four volumes: Volume 1, Administrative Requirements; Volume 2, Sampling Technical Requirements; Volume 3, Field Analytical Technical Requirements; and Volume 4, Laboratory Technical Requirements. Volume 1 describes the administrative requirements

Technical area status report for low-level mixed waste final waste forms. Volume 1

Energy Technology Data Exchange (ETDEWEB)

Mayberry, J.L.; DeWitt, L.M. [Science Applications International Corp., Idaho Falls, ID (United States); Darnell, R. [EG and G Idaho, Inc., Idaho Falls, ID (United States)] [and others

1993-08-01

The Final Waste Forms (FWF) Technical Area Status Report (TASR) Working Group, the Vitrification Working Group (WG), and the Performance Standards Working Group were established as subgroups to the FWF Technical Support Group (TSG). The FWF TASR WG is comprised of technical representatives from most of the major DOE sites, the Nuclear Regulatory Commission (NRC), the EPA Office of Solid Waste, and the EPA`s Risk Reduction Engineering Laboratory (RREL). The primary activity of the FWF TASR Working Group was to investigate and report on the current status of FWFs for LLNM in this TASR. The FWF TASR Working Group determined the current status of the development of various waste forms described above by reviewing selected articles and technical reports, summarizing data, and establishing an initial set of FWF characteristics to be used in evaluating candidate FWFS; these characteristics are summarized in Section 2. After an initial review of available information, the FWF TASR Working Group chose to study the following groups of final waste forms: hydraulic cement, sulfur polymer cement, glass, ceramic, and organic binders. The organic binders included polyethylene, bitumen, vinyl ester styrene, epoxy, and urea formaldehyde. Section 3 provides a description of each final waste form. Based on the literature review, the gaps and deficiencies in information were summarized, and conclusions and recommendations were established. The information and data presented in this TASR are intended to assist the FWF Production and Assessment TSG in evaluating the Technical Task Plans (TTPs) submitted to DOE EM-50, and thus provide DOE with the necessary information for their FWF decision-making process. This FWF TASR will also assist the DOE and the MWIP in establishing the most acceptable final waste forms for the various LLMW streams stored at DOE facilities.

19th JANNAF Safety and Environmental Protection Subcommittee Meeting. Volume 1

Science.gov (United States)

Cocchiaro, J. E. (Editor); Becker, D. L. (Editor)

2002-01-01

This volume, the first of two volumes, is a compilation of 22 unclassified/unlimited technical papers presented at the 19th Joint Army-Navy-NASA-Air Force (JANNAF) Safety & Environmental Protection Subcommittee Meeting. The meeting was held 18-21 March 2002 at the Sheraton Colorado Springs Hotel, Colorado Springs, Colorado. Topics covered include green energetic materials and life cycle pollution prevention; space launch range safety; propellant/munitions demilitarization, recycling, and reuse: and environmental and occupational health aspects of propellants and energetic materials.

The alteration of gray matter volume in children with mental retardation: the differences between the patients presented with operation deficit predominantly and those presented with language deficit mainly

International Nuclear Information System (INIS)

Yuan Xinyu; Jiang Xuexiang; Jin Chunhua; Zhang Yuanchao; Bai Zhenhua; Yi Xiaoli; Xiao Jiangxi

2012-01-01

Objective: To detect the differences of grey matter volume between the patients with mental retardation (MR) presented clinically as operation deficit (OD) or as language deficit (LD) and the children with typical normal development using optimal VBM. The developmental connections between brain gray matter and language or operation skills were examined. Methods: Magnetic resonance imaging was obtained from 9 children with mental retardation presented as OD predominantly and 11 children with mental retardation presented as LD mainly, as well as the age-matched control group (11 and 14 normal children,respectively) on a 1.5 T scanner. Voxel-based morphometry analysis with an optimization of spatial segmentation and normalization procedures was applied to compare the volume of grey matter between the two groups (OD VS.control; LD VS.control). Statistically, the total and local gray matter volumes were compared between the two groups with t test. Results: The total gray matter volume of OD group was [(1.030 ± 0.078) × 10 6 mm 3 ]. Compared to that of controls [(0.984 ± 0.058) × 10 6 mm 3 ], it was increased significantly (t=-2.6, P<0.05). And the gray matter volume in the posterior cingulated gyrus, left superior prefrontal gyrus, left cuneus, left middle prefrontal gyrus and the body of left caudate nucleus showed significantly increased. Meanwhile, the total gray matter volume of the MR children presented as LD [(1.002 ± 0.068) × 10 6 mm 3 ] showed significantly increased(t=-3.0, P<0.05) compared with that of control group [(0.957 ±0.057) × 10 6 mm 3 ]. The gray matter volume in bilateral thalami, the left inferior temporal gyrus,the left inferior frontal gyrus, and the left cerebellum of the LD group was more than that of normal children. Conclusion: As revealed by VBM, there are differences in alterations of gray matter volume between MR children presented with OD and with LD relative to control. (authors)

Volume and outcome of organ transplantation

NARCIS (Netherlands)

Banta, H.D.; Engel, G.L.; Schersten, T.

1992-01-01

In general, technically demanding medical procedures are associated with better outcomes when they are carried out in institutions and by physicians with higher volumes of practice. This paper examines the evidence for a volume-outcome relationship in the case of organ transplantation. Although few

Routledge French technical dictionary

CERN Document Server

1994-01-01

The French-English volume of this highly acclaimed set consists of some 100,000 keywords in both French and English, drawn from the whole range of modern applied science and technical terminology. Covers over 70 subject areas, from engineering and chemistry to packaging, transportation, data processing and much more.

640-slice DVCT multi-dimensionally and dynamically presents changes in bladder volume and urine flow rate

Science.gov (United States)

Su, Yunshan; Fang, Kewei; Mao, Chongwen; Xiang, Shutian; Wang, Jin; Li, Yingwen

2018-01-01

The present study aimed to explore the application of 640-slice dynamic volume computed tomography (DVCT) to excretory cystography and urethrography. A total of 70 healthy subjects were included in the study. Excretory cystography and urethrography using 640-slice DVCT was conducted to continuously record the motions of the bladder and the proximal female and male urethra. The patients' voiding process was divided into early, early to middle, middle, middle to late, and late voiding phases. The subjects were analyzed using DVCT and conventional CT. The cross-sectional areas of various sections of the male and female urethra were evaluated, and the average urine flow rate was calculated. The 640-slice DVCT technique was used to dynamically observe the urine flow rate and changes in bladder volume at all voiding phases. The urine volume detected by 640-slice DVCT exhibited no significant difference compared with the actual volume, and no significant difference compared with that determined using conventional CT. Furthermore, no significant difference in the volume of the bladder at each phase of the voiding process was detected between 640-slice DVCT and conventional CT. The results indicate that 640-slice DVCT can accurately evaluate the status of the male posterior urethra and female urethra. In conclusion, 640-slice DVCT is able to multi-dimensionally and dynamically present changes in bladder volume and urine flow rate, and could obtain similar results to conventional CT in detecting urine volume, as well as the status of the male posterior urethra and female urethra. PMID:29467853

Modern problems of perfection of elite light athletic sportsmen’s technical skillfulness perfection

Directory of Open Access Journals (Sweden)

A.V. Kolot

2016-04-01

Full Text Available Purpose: perfection of elite sportsmen’s technical skillfulness in competition kinds of light athletic. Material: the data of more than 60 literature sources were systemized. Expert questioning of 36 coaches, having experience of work with elite sportsmen, was carried out; documents of training process planning were analyzed as well as sportsmen’s diaries (n=244. Results: we have presented main principles of sportsmen’s technical skillfulness perfection and elucidated characteristics of technical training methodic. We have determined main priorities of technical training building for light athletes at every stage of many years’ perfection. Dynamic of competition practice volume has been found as well as main requirements to selection of training means of technical orientation. The data of bio-mechanical criteria of sportsmen’s technical skillfulness assessment have been supplemented. Conclusions: effectiveness of sportsmen’s training methodic is determined by realization of previous stages’ technical potential in final competition results. It can be achieved by determination of means of and methods of different orientation rational correlation.

Modern problems of perfection of elite light athletic sportsmen’s technical skillfulness perfection

Directory of Open Access Journals (Sweden)

Kolot A.V.

2016-02-01

Full Text Available Purpose: perfection of elite sportsmen’s technical skillfulness in competition kinds of light athletic. Material: the data of more than 60 literature sources were systemized. Expert questioning of 36 coaches, having experience of work with elite sportsmen, was carried out; documents of training process planning were analyzed as well as sportsmen’s diaries (n=244. Results: we have presented main principles of sportsmen’s technical skillfulness perfection and elucidated characteristics of technical training methodic. We have determined main priorities of technical training building for light athletes at every stage of many years’ perfection. Dynamic of competition practice volume has been found as well as main requirements to selection of training means of technical orientation. The data of bio-mechanical criteria of sportsmen’s technical skillfulness assessment have been supplemented. Conclusions: effectiveness of sportsmen’s training methodic is determined by realization of previous stages’ technical potential in final competition results. It can be achieved by determination of means of and methods of different orientation rational correlation.

Technical reference manual for TIME4. Version 1.0, Volume 1

International Nuclear Information System (INIS)

Wilmot, R.D.; Ringrose, P.S.; Larkin, J.P.A.; Kleissen, F.A.T.

1991-07-01

This document is the Technical Reference Manual for the TIME4 model. TIME4 is the environmental change model developed for use in the probabilistic risk analysis of deep disposal of radioactive waste. The Technical Reference Manual describes the theoretical background to the model. The modelling method is described, followed by a review of related work and a detailed description for each sub-model. (author)

Candlestick Charting and Trading Volume: Evidence from Bursa Malaysia

OpenAIRE

Chin, Chee-Ling; Jais, Mohamad; Balia, Sophee Sulong; Ahmad, Ayoib Che; Abidin, Azlan Zainol

2016-01-01

Technical analysis is deemed to be a futile practice among academicians who propose efficient market hypothesis, typically the weak form market efficiency which strongly protests the application of past prices and trading volume data for prediction of future market movement. As candlestick charting is one of the oldest technical indicators for short term investment, therefore this study examines the predictability of candlestick charting with combination to trading volume for Malaysian stock ...

Tank Farms Technical Safety Requirements. Volume 1 and 2

International Nuclear Information System (INIS)

CASH, R.J.

2000-01-01

The Technical Safety Requirements (TSRs) define the acceptable conditions, safe boundaries, basis thereof, and controls to ensure safe operation during authorized activities, for facilities within the scope of the Tank Waste Remediation System (TWRS) Final Safety Analysis Report (FSAR)

Information management architecture for an integrated computing environment for the Environmental Restoration Program. Environmental Restoration Program, Volume 3, Interim technical architecture

International Nuclear Information System (INIS)

1994-09-01

This third volume of the Information Management Architecture for an Integrated Computing Environment for the Environmental Restoration Program--the Interim Technical Architecture (TA) (referred to throughout the remainder of this document as the ER TA)--represents a key milestone in establishing a coordinated information management environment in which information initiatives can be pursued with the confidence that redundancy and inconsistencies will be held to a minimum. This architecture is intended to be used as a reference by anyone whose responsibilities include the acquisition or development of information technology for use by the ER Program. The interim ER TA provides technical guidance at three levels. At the highest level, the technical architecture provides an overall computing philosophy or direction. At this level, the guidance does not address specific technologies or products but addresses more general concepts, such as the use of open systems, modular architectures, graphical user interfaces, and architecture-based development. At the next level, the technical architecture provides specific information technology recommendations regarding a wide variety of specific technologies. These technologies include computing hardware, operating systems, communications software, database management software, application development software, and personal productivity software, among others. These recommendations range from the adoption of specific industry or Martin Marietta Energy Systems, Inc. (Energy Systems) standards to the specification of individual products. At the third level, the architecture provides guidance regarding implementation strategies for the recommended technologies that can be applied to individual projects and to the ER Program as a whole

Collected software engineering papers, volume 9

Science.gov (United States)

1991-01-01

This document is a collection of selected technical papers produced by participants in the Software Engineering Laboratory (SEL) from November 1990 through October 1991. The purpose of the document is to make available, in one reference, some results of SEL research that originally appeared in a number of different forums. This is the ninth such volume of technical papers produced by the SEL. Although these papers cover several topics related to software engineering, they do not encompass the entire scope of SEL activities and interests. For the convenience of this presentation, the eight papers contained here are grouped into three major categories: (1) software models studies; (2) software measurement studies; and (3) Ada technology studies. The first category presents studies on reuse models, including a software reuse model applied to maintenance and a model for an organization to support software reuse. The second category includes experimental research methods and software measurement techniques. The third category presents object-oriented approaches using Ada and object-oriented features proposed for Ada. The SEL is actively working to understand and improve the software development process at GSFC.

1988 DOE model conference proceedings: Volume 5

Energy Technology Data Exchange (ETDEWEB)

1988-01-01

These Proceedings of the October 3--7, 1988 DOE Model Conference are a compilation of the papers that were presented in the technical or poster sessions at the conference papers and posters not submitted for publication are not included in the Proceedings. The Table of Contents lists the titles of papers as well as the names of the presenters. These individuals are not, in all cases, the primary authors of the papers published. The actual title pages, appearing later with the papers, show the primary author(s) and all co-authors. The papers in all three volumes of the Proceedings appear as they were originally submitted for publication and have not been edited or changed in any way. Topics discussed in Volume 5 include environmental assessments and program strategies, waste treatment technologies, and regulations and compliance studies.

1988 DOE model conference proceedings: Volume 3

International Nuclear Information System (INIS)

1988-01-01

These Proceedings of the October 3 - 7, 1988, DOE Model Conference are a compilation of the papers that were presented in the technical or poster sessions at the conference. Papers and posters not submitted for publication are not included in the Proceedings. The Table of Contents lists the titles of papers as well as the names of the presenters. These individuals are not, in all cases, the primary authors of the papers published. The actual title pages, appearing later with the papers, show the primary author(s) and all co-authors. The papers in all three volumes of the proceedings appear as they were originally submitted for publication and have not been edited or changed in any way. Topics included in Volume 3 include treatment of soils, waste characterization and certification, waste minimization site remediation management plans and programs, and training programs

1988 DOE model conference proceedings: Volume 5

International Nuclear Information System (INIS)

1988-01-01

These Proceedings of the October 3--7, 1988 DOE Model Conference are a compilation of the papers that were presented in the technical or poster sessions at the conference papers and posters not submitted for publication are not included in the Proceedings. The Table of Contents lists the titles of papers as well as the names of the presenters. These individuals are not, in all cases, the primary authors of the papers published. The actual title pages, appearing later with the papers, show the primary author(s) and all co-authors. The papers in all three volumes of the Proceedings appear as they were originally submitted for publication and have not been edited or changed in any way. Topics discussed in Volume 5 include environmental assessments and program strategies, waste treatment technologies, and regulations and compliance studies

IAEA Technical Meeting on Status of IAEA Fast Reactor Knowledge Preservation Initiative. Presentations

International Nuclear Information System (INIS)

2013-01-01

The objectives of the technical meeting were to: • exchange information between the Member States/International Organizations on national and international initiatives addressing knowledge preservation and data retrieval/collection in the field of fast neutron systems; • present and discuss the Member States’/International Organizations’ policies and conditions for releasing to the IAEA both publicly available and confidential information on fast neutron systems; • collect data on fast neutron systems provided by participating Member States/International Organizations and encourage participants to contribute in data collection; • provide recommendations for further IAEA initiatives in the field of fast reactor knowledge preservation

Electric power annual 1994. Volume 2, Operational and financial data

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-11-28

This year, the annual is published in two volumes. Volume I focused on US electric utilities and contained final 1994 data on net generation, fossil fuel consumption, stocks, receipts, and cost. This Volume II presents annual 1994 summary statistics for the electric power industry, including information on both electric utilities and nonutility power producers. Included are preliminary data for electric utility retail sales of electricity, associated revenue, and average revenue per kilowatthour of electricity sold (based on form EIA-861) and for electric utility financial statistics, environmental statistics, power transactions, and demand- side management. Final 1994 data for US nonutility power producers on installed capacity and gross generation, as well as supply and disposition information, are also provided in Volume II. Technical notes and a glossary are included.

Technical guideline technology according to the X-ray regulations

International Nuclear Information System (INIS)

2011-01-01

The guideline covers the required technical knowledge concerning radiation protection and knowledge concerning for the operation of X-ray devices for technical purposes and stray radiation sources requiring licensing, and requirements for the qualification of officially authorized inspectors. The guidelines includes the following chapters: (1) introductory regulations; (2) Volume of the required technical knowledge; (3) Acquirement and certification of the technical knowledge; (4) Actualization of the technical knowledge; (5)Approval of courses and other training measures; (6) Combination of courses and training measures according to the guideline; (7) Requirements for qualification of officially authorized inspectors; (8) Interim regulations.

Teaching Technical Writing - Towards Technical Writing

DEFF Research Database (Denmark)

Kastberg, Peter

2000-01-01

In this paper I will present key aspects of the curriculum for the university degree in technical translation that I have designed for and subsequently implemented at the German Department of the Aarhus School of Business, Denmark. My starting point will be a critical discussion of the norm that ...... of technical writing.......In this paper I will present key aspects of the curriculum for the university degree in technical translation that I have designed for and subsequently implemented at the German Department of the Aarhus School of Business, Denmark. My starting point will be a critical discussion of the norm...... that used to govern what the quality of an LSP text should be as opposed to the standpoint, which I advocate. By way of summing up, I will show how a university curriculum is designed so that - upon graduation - the technical translator could also be methodological quite well suited to take on the challenge...

The SocioEconomic Analysis of Repository Siting (SEARS): Technical documentation: Volume 3, Schematic flowcharts

International Nuclear Information System (INIS)

Kiel, B.; Parpia, B.; Murdock, S.; Hamm, R.; Fannin, D.; Ransom-Nelson, W.; Leistritz, F.L.

1985-05-01

This report presents a summary of results of an assessment of the adaptability, sensitivity, and accuracy of the SEARS model. Specifically, after describing the methods used in the analysis, the report presents a discussion of each aspect of the model evaluation process. The adaptation of the system to three states (Louisiana, Wyoming, and Texas) is described in light of the three key aspects of the model. Volume 3 presents 276 flowcharts for the major functions of the SEARS model

Waste minimization handbook, Volume 1

Energy Technology Data Exchange (ETDEWEB)

Boing, L.E.; Coffey, M.J.

1995-12-01

This technical guide presents various methods used by industry to minimize low-level radioactive waste (LLW) generated during decommissioning and decontamination (D and D) activities. Such activities generate significant amounts of LLW during their operations. Waste minimization refers to any measure, procedure, or technique that reduces the amount of waste generated during a specific operation or project. Preventive waste minimization techniques implemented when a project is initiated can significantly reduce waste. Techniques implemented during decontamination activities reduce the cost of decommissioning. The application of waste minimization techniques is not limited to D and D activities; it is also useful during any phase of a facility`s life cycle. This compendium will be supplemented with a second volume of abstracts of hundreds of papers related to minimizing low-level nuclear waste. This second volume is expected to be released in late 1996.

Waste minimization handbook, Volume 1

International Nuclear Information System (INIS)

Boing, L.E.; Coffey, M.J.

1995-12-01

This technical guide presents various methods used by industry to minimize low-level radioactive waste (LLW) generated during decommissioning and decontamination (D and D) activities. Such activities generate significant amounts of LLW during their operations. Waste minimization refers to any measure, procedure, or technique that reduces the amount of waste generated during a specific operation or project. Preventive waste minimization techniques implemented when a project is initiated can significantly reduce waste. Techniques implemented during decontamination activities reduce the cost of decommissioning. The application of waste minimization techniques is not limited to D and D activities; it is also useful during any phase of a facility's life cycle. This compendium will be supplemented with a second volume of abstracts of hundreds of papers related to minimizing low-level nuclear waste. This second volume is expected to be released in late 1996

AREVA Technical Days (ATD) session 1: Energy outlook and presentation of the Areva Group

International Nuclear Information System (INIS)

2002-01-01

These technical days organized by the Areva Group aims to explain the group activities in a technological and economic point of view, to provide an outlook of worldwide energy trends and challenges and to present each of their businesses in a synthetic manner. This first session deals with energy challenges and nuclear, public acceptance of nuclear power, mining activities, chemistry activities, enrichment activities, fuel assembly, reactors and services activities, nuclear measurements activities, reprocessing and recycling activities, logistics activities and connectors activities. (A.L.B.)

Reader-Centered Technical Writing

Science.gov (United States)

Narayanan, M.

2012-12-01

Technical writing is an essential part of professional communication and in recent years it has shifted from a genre-based approach. Formerly, technical writing primarily focused on generating templates of documents and sometimes it was creating or reproducing traditional forms with minor modifications and updates. Now, technical writing looks at the situations surrounding the need to write. This involves deep thinking about the goals and objectives of the project on hand. Furthermore, one observes that it is very important for any participatory process to have the full support of management. This support needs to be well understood and believed by employees. Professional writing may be very persuasive in some cases. When presented in the appropriate context, technical writing can persuade a company to improve work conditions ensuring employee safety and timely production. However, one must recognize that lot of professional writing still continues to make use of reports and instruction manuals. Normally, technical and professional writing addresses four aspects. Objective: The need for generating a given professionally written technical document and the goals the document is expected to achieve and accomplish. Clientele: The clientele who will utilize the technical document. This may include the people in the organization. This may also include "unintended readers." Customers: The population that may be affected by the content of the technical document generated. This includes the stakeholders who will be influenced. Environment: The background in which the document is created. Also, the nature of the situation that warranted the generation of the document. Swiss Psychologist Jean Piaget's view of Learning focuses on three aspects. The author likes to extend Jean Piaget's ideas to students, who are asked to prepare and submit Reader-Centered Technical Writing reports and exercises. Assimilation: Writers may benefit specifically, by assimilating a new object into

The history of NATO TNF policy: The role of studies, analysis and exercises conference proceedings. Volume 2: Papers and presentations

Energy Technology Data Exchange (ETDEWEB)

Rinne, R.L.

1994-02-01

This conference was organized to study and analyze the role of simulation, analysis, modeling, and exercises in the history of NATO policy. The premise was not that the results of past studies will apply to future policy, but rather that understanding what influenced the decision process -- and how -- would be of value. The structure of the conference was built around discussion panels. The panels were augmented by a series of papers and presentations focusing on particular TNF events, issues, studies, or exercises. The conference proceedings consist of three volumes. Volume 1 contains the conference introduction, agenda, biographical sketches of principal participants, and analytical summary of the presentations and panels. This volume contains a short introduction and the papers and presentations from the conference. Volume 3 contains selected papers by Brig. Gen. Robert C. Richardson III (Ret.). Individual papers in this volume were abstracted and indexed for the database.

4. International reservoir characterization technical conference

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-04-01

This volume contains the Proceedings of the Fourth International Reservoir Characterization Technical Conference held March 2-4, 1997 in Houston, Texas. The theme for the conference was Advances in Reservoir Characterization for Effective Reservoir Management. On March 2, 1997, the DOE Class Workshop kicked off with tutorials by Dr. Steve Begg (BP Exploration) and Dr. Ganesh Thakur (Chevron). Tutorial presentations are not included in these Proceedings but may be available from the authors. The conference consisted of the following topics: data acquisition; reservoir modeling; scaling reservoir properties; and managing uncertainty. Selected papers have been processed separately for inclusion in the Energy Science and Technology database.

Reference book for the nitrogen industry worker in two volumes, volume 1

Science.gov (United States)

1982-05-01

The first volume presents the physical and chemical properties of gaseous and liquid substances used and obtained at the nitrogen industry enterprises. It describes the different methods for producing and purifying production gases (nitrogen-hydrogen mixture, gas synthesis). It examines the physical and chemical properties of the processes of amonia and methanol synthesis, the industrial plans and the principles for automating them. Certain methods are given for technological calculations, characteristics of the catalysts are presented, and the employed equipment is described. It is designed for engineering-technical workers of enterprises of the nitrogen and other sectors of industry, for specialists working in the scientific research and planning institutes, design offices and other organizations, as well as for teachers of higher educational institutions and students specializing in the field of the technology of inorganic products.

1988 DOE model conference proceedings: Volume 4

Energy Technology Data Exchange (ETDEWEB)

1988-01-01

These Proceedings of the October 3-7, 1988, DOE Model Conference are a compilation of the papers that were presented in the technical or poster sessions at the conference. Papers and posters not submitted for publication are not included in the Proceedings. The Table of Contents lists the titles of papers as well as the names of the presenters. These individuals are not, in all cases, the primary authors of the papers published. The actual title pages, appearing later with the papers, show the primary author(s) and all co-authors. The papers in all three volumes of the Proceedings appear as they were originally submitted for publication and have not been edited or changed in any way. Topics discussed in Volume 4 include site characterization and remediation projects, environmental monitoring and modeling; disposal site selection and facility design, risk assessment, safety and health issues, and site remediation technology.

1988 DOE model conference proceedings: Volume 1

International Nuclear Information System (INIS)

1988-01-01

These Proceedings of the October 3-7, 1988, DOE Model Conference are a compilation of the papers that were presented in the technical or poster sessions at the conference. Papers and posters not submitted for publication are not included in the Proceedings. The Table of Contents lists the titles of papers as well as the names of the presenters. These individuals are not, in all cases, the primary authors of the papers published. The actual title pages, appearing later with the papers, show the primary author(s) and all co-authors. The papers in all three volumes of the Proceedings appear as they were originally submitted for publication and have not been edited or changed in any way. Topics included in Volume 1 are Environmental Data Management, Site characterization technology, Wastewater treatment, Waste management in foreign countries, Transuranic waste management, and Groundwater characterization and treatment

1988 DOE model conference proceedings: Volume 4

International Nuclear Information System (INIS)

1988-01-01

These Proceedings of the October 3-7, 1988, DOE Model Conference are a compilation of the papers that were presented in the technical or poster sessions at the conference. Papers and posters not submitted for publication are not included in the Proceedings. The Table of Contents lists the titles of papers as well as the names of the presenters. These individuals are not, in all cases, the primary authors of the papers published. The actual title pages, appearing later with the papers, show the primary author(s) and all co-authors. The papers in all three volumes of the Proceedings appear as they were originally submitted for publication and have not been edited or changed in any way. Topics discussed in Volume 4 include site characterization and remediation projects, environmental monitoring and modeling; disposal site selection and facility design, risk assessment, safety and health issues, and site remediation technology

1988 DOE model conference proceedings: Volume 2

International Nuclear Information System (INIS)

1988-01-01

These Proceedings of the October 3 - 7, 1988, DOE Model Conference are a compilation of the papers that were presented in the technical or poster sessions at the conference. Papers and posters not submitted for publication are not included in the proceedings. The Table of Contents lists the titles of papers as well as the names of the presenters. These individuals are not, in all cases, the primary authors of the papers published. The actual title pages, appearing later with the papers, show the primary author(s) and all co-authors. The papers in all three volumes of the Proceedings appear as they were originally submitted for publication and have not been edited or changed in any way. Volume 2 contains information on environmental restoration at federal facilities, waste disposal technology, quality assurance, contingency planning and emergency response, decontamination and decommissioning, environmental restoration, and public involvement in waste management

1988 DOE model conference proceedings: Volume 1

Energy Technology Data Exchange (ETDEWEB)

1988-01-01

These Proceedings of the October 3-7, 1988, DOE Model Conference are a compilation of the papers that were presented in the technical or poster sessions at the conference. Papers and posters not submitted for publication are not included in the Proceedings. The Table of Contents lists the titles of papers as well as the names of the presenters. These individuals are not, in all cases, the primary authors of the papers published. The actual title pages, appearing later with the papers, show the primary author(s) and all co-authors. The papers in all three volumes of the Proceedings appear as they were originally submitted for publication and have not been edited or changed in any way. Topics included in Volume 1 are Environmental Data Management, Site characterization technology, Wastewater treatment, Waste management in foreign countries, Transuranic waste management, and Groundwater characterization and treatment.

Uranium milling, project M-25. Volume I. summary and text. Final generic environmental impact statement

International Nuclear Information System (INIS)

1980-09-01

The Final Generic Environmental Impact Statement (GEIS) on Uranium Milling focuses primarily upon the matter of mill tailings disposal. It evaluates both the costs and benefits of alternative tailings disposal modes and draws conclusions about criteria which should be incorporated into regulations. Both institutional and technical controls are evaluated. Health impacts considered were both short and long term. Restatement and resolution of all public comments received on the draft (GEIS) are presented. There are three volumes: Volume I is the main text and Volumes II and III are supporting appendices

IPEN Scientific and technical publications 1956-1981

International Nuclear Information System (INIS)

1983-01-01

The Instituto de Pesquisas Energeticas e Nucleares - IPEN (Energy Research Institute) from Sao Paulo, Brazil, was founded in 1956. Since its foundation, the main objectives of IPEN has been to undertake research and development into the peaceful uses of nuclear energy and to train scientific personnel to post-graduate level. The IPEN Scientific and Technical Publication - IPEN/SP, is a system developed at IPEN. Its purpose has been to generate a data base identifying the technical and scientific literature produced by IPEN staff members, published either in the Institute's series or in others brazilian and foreign publications. Documents cited in this jubilee edition include those in which IPEN staff members were authors or co-authors; document published by foreign research visitors while working at IPEN facilities; theses prepared by IPEN staff and reports in which IPEN is a corporate author. The IPEN technical publications reflect the main fields of research persuaded by the Institute, namely nuclear physics radiochemistry, chemical engineering, nuclear metallurgy and engineering and finally medical and industrial applications of radioisotopes. This present volume, published under the new title of IPEN - Scientific and Technical Publications, is a cumulative edition, to celebrate the 25th. anniversary of IPEN. In this jubilee edition, 1345 document published by IPEN staff are cited, following the main subject heading of INIS Subject Categories. (author)

Technical and economic limits to fuel burnup extension. Proceedings of a technical committee meeting

International Nuclear Information System (INIS)

2002-07-01

For many years, the increase of efficiency in the production of nuclear electricity has been an economic challenge in many countries which have developed this kind of energy. The increase of fuel burnup leads to a reduction in the volume of spent fuel discharged to longer fuel cycles in the reactor, which means bigger availability and capacity factors. After having increased the authorized burnup in plants, developing new alloys capable of resisting high burnup, and having accumulated data on fuel evolution with burnup, it has become necessary to establish the limitations which could be imposed by the physical evolution of the fuel, influencing fuel management, neutron properties, reprocessing or, more generally, the management of waste and irradiated fuels. It is also necessary to verify whether the benefits of lower electricity costs would not be offset by an increase in fuel management costs. The main questions are: Are technical and economic limits to the increasing of fuel burnup in parallel? Can we envisage nowadays the hardest limitation in some of these areas? Which are the main points to be solved from the technical point of view? Is this effort worthwhile considering the economy of the cycle? To which extent? For these reasons, the IAEA, following a recommendation by the International Working Group on Fuel Performance and Technology, held a Technical Committee Meeting on Technical and Economic Limits to Fuel Burnup Extension. The purpose of this meeting was to provide an international forum to review the evolution of fuel properties at increased burnup in order to estimate the limitations both from a physical and an economic point of view. The meeting was therefore divided into two parts. The first part, focusing on technical limits, was devoted to the improvement of the fuel element, such as fission gas release (FGR), RIM effect, cladding, etc. and the fabrication, core management, spent fuel and reprocessing. Eighteen related papers were presented which

Book Review: New Perspectives on Technical Editing

Science.gov (United States)

Murphy, A. J. (Ed.); Sterken, Christiaan

2012-08-01

New Perspectives on Technical Editing by Avon J. Murphy (ed.) ISBN : 978-0895033949 (2010) Baywood Publishing Company Inc, Hardcover, 210 pages, 35.5 GBP This book presents a collection of 10 chapters dealing with diverse aspects of technical editing (ie, editorial planning, and analysis and structural changes made to other people's technological documents): research in technical editing, trends and teaching of technical editing, copyediting, and technical journal editing. The role and function of the modern journal and book editor is also dealt with in detail. Each chapter is written by an expert in the field: senior editors, university professors in technical communication, technical writers and linguists. The ever-evolving role of the editor is clearly elucidated in several historical reviews, and in the descriptions of the expectations for the future. A very striking aspect of this book is its extensive collection of bibliographic resources: every chapter lists dozens of very useful references, and the closing chapter, and annotated bibliography, contain many not so well known references, and are most useful. All in all, the book is a treasure trove listing more than 400 references, in addition to numerous webpage URLs embedded in the texts. The book is designed to help the reader to understand current practices and norms in technical editing, and to help to take action in editing as well as in teaching and educating would-be editors. The audience for this book thus includes editors and teachers, but also writers, researchers and students. A deep reading of this book will result in a better understanding of the difference between full technical editing and its much narrower component so well known as copyediting, and will convince any prospective editor that editing should not be undertaken if the people involved do not master the art of precision and accuracy in technical (as well as in human) communication, do not possess the technical know how and computer

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

Cost-volume-profit and net present value analysis of health information systems.

Science.gov (United States)

McLean, R A

1998-08-01

The adoption of any information system should be justified by an economic analysis demonstrating that its projected benefits outweigh its projected costs. Analysis differ, however, on which methods to employ for such a justification. Accountants prefer cost-volume-profit analysis, and economists prefer net present value analysis. The article explains the strengths and weaknesses of each method and shows how they can be used together so that well-informed investments in information systems can be made.

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…

Committee to evaluate Sandia`s risk expertise: Final report. Volume 1: Presentations

Energy Technology Data Exchange (ETDEWEB)

Dudley, E.C.

1998-05-01

On July 1--2, 1997, Sandia National Laboratories hosted the External Committee to Evaluate Sandia`s Risk Expertise. Under the auspices of SIISRS (Sandia`s International Institute for Systematic Risk Studies), Sandia assembled a blue-ribbon panel of experts in the field of risk management to assess their risk programs labs-wide. Panelists were chosen not only for their own expertise, but also for their ability to add balance to the panel as a whole. Presentations were made to the committee on the risk activities at Sandia. In addition, a tour of Sandia`s research and development programs in support of the US Nuclear Regulatory Commission was arranged. The panel attended a poster session featuring eight presentations and demonstrations for selected projects. Overviews and viewgraphs from the presentations are included in Volume 1 of this report. Presentations are related to weapons, nuclear power plants, transportation systems, architectural surety, environmental programs, and information systems.

Incorporating technical analysis in undergraduate curricula

Directory of Open Access Journals (Sweden)

Michael R. Melton

2017-11-01

Full Text Available Purpose – The purpose of this paper is to introduce instruction of technical analysis on the undergraduate level that can coincide with traditional teachings of fundamental analysis. Design/methodology/approach – Through examples using the latest in security analysis technology, this paper illustrates the importance of technical security analysis. Findings – This research illustrates how technical analysis techniques may be used to make more significant investment decisions. Originality/value – Kirkpatrick and Dahlquist define technical analysis as a security analysis discipline for forecasting future direction of prices through the study of past market data primarily price and volume This form of analysis has stood in direct contrast to the fundamental analysis approach whereby actual facts of the company its industry and sector may be ignored. Understanding this contrast, much of academia has chosen to continue to focus its finance curricula on fundamental analysis techniques. As more universities implement trading rooms to reflect that of industry, they must recognize that any large brokerage trading group or financial institution will typically have both a technical analysis and fundamental analysis team. Thus, the need to incorporate technical analysis into undergraduate finance curricula.

National seminar on public information on peaceful uses of nuclear energy - NUCInfo'98. Proceedings. Vol 2. Section B - Scientific and Technical Papers

International Nuclear Information System (INIS)

Dobos, Ion; Comsa, Olivia

1998-01-01

These proceedings published in two volumes contain materials presented at the National Seminar on Public Information on Peaceful uses of Nuclear Energy - NUCInfo'98 - held on 30th September to 2nd October 1998 at Bucharest, Romania. The first volume was dedicated to Public Information. The second volume containing 56 scientific and technical papers is structured in three parts according to the three sessions entitled: B 1 . Sustainable Development - Energy - Environment; B 2 . Nuclear safety, Radioactive Wastes, Radioprotection and Nuclear Safeguards; B 3 . Scientific Research, Technological Development and Applications of the Nuclear Energy in Economic and Social Life. The great majority of the contributions deal with specific public information technical problems and debates on nuclear issues mainly related to radiation monitoring, waste management, air, water and food contamination from accidental radioactive release or from fuel cycle relating activities. Also, several papers discuss the present status of national nuclear program, program management and legal matters in the nuclear field. A number of papers debate the questions related to radiation protection procedures and the safety problems at the Cernavoda NPP based on CANDU type reactors

Viability Assessment of a Repository at Yucca Mountain. Volume 1: Introduction and Site Characteristics

Energy Technology Data Exchange (ETDEWEB)

None

1998-12-01

This first volume contains an introduction to the viability assessment, including the purpose, scope, waste forms, technical challenges, an historical perspective, regulatory framework, management of the repository, technical components, preparations for the license application, and repository milestones after the assessment. The second part of this first volume addresses characteristics of the Yucca Mountain site.

Influence of technical parameters on epicardial fat volume quantification at cardiac CT.

Science.gov (United States)

Bucher, Andreas M; Joseph Schoepf, U; Krazinski, Aleksander W; Silverman, Justin; Spearman, James V; De Cecco, Carlo N; Meinel, Felix G; Vogl, Thomas J; Geyer, Lucas L

2015-06-01

To systematically analyze the influence of technical parameters on quantification of epicardial fat volume (EATV) at cardiac CT. 153 routine cardiac CT data sets were analyzed using three-dimensional pericardial border delineation. Three image series were reconstructed per patient: (a) CTAD: coronary CT angiography (CTA), diastolic phase; (b) CTAS: coronary CTA, systolic phase; (c) CaScD: non-contrast CT, diastolic phase. EATV was calculated using three different upper thresholds (-15HU, -30 HU, -45HU). Repeated measures ANOVA, Spearman's rho, and Bland Altman plots were used. Mean EATV differed between all three image series at a -30HU threshold (CTAD 87.2 ± 38.5 ml, CTAS 90.9 ± 37.7 ml, CaScD 130.7 ± 49.5 ml, PEATV of diastolic and systolic CTA reconstructions did not differ significantly (P=0.225). Mean EATV for contrast enhanced CTA at a -15HU threshold (CTAD15 102.4 ± 43.6 ml, CTAS15 105.3 ± 42.3 ml) could be approximated most closely by non-contrast CT at -45HU threshold (CaScD45 105.3 ± 40.8 ml). The correlation was excellent: CTAS15-CTAD15, rho=0.943; CTAD15-CaScD45, rho=0.905; CTAS15-CaScD45, rho=0.924; each PEATV can differ substantially between contrast enhanced and non-contrast CT studies, which can be reconciled by threshold modification. Heart cycle phase does not significantly influence EATV measurements. Copyright © 2015 Elsevier Ireland Ltd. All rights reserved.

'Nuclex 75'. Preview of the technical fair

International Nuclear Information System (INIS)

Anon.

1975-01-01

The 'Nuclex 75' - fourth international technical fair and specialist meetings for the nuclear industry - takes place from the 7th to the 11th October 1975 in the halls of the Schweizer Mustermesse in Basel. The meeting, which has taken place at three-yearly intervals since 1966, is divided into a technical fair and a congress. 422 exhibitors from 25 countries take part in the 'Nuclex 75'. Several industrial countries are again represented by communal exhibitions. The editorial office of 'Atom and Electricity' gives a few hints on the technical fair to follow which are based on the papers of the exhibitor sent in up to the editor's closing date. A detailed report on the technical fair as well as on important topics of the congress will appear in volume 11/12 1975. (orig./LH) [de

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

KBS Technical report 1-120 (1977-1978). Summaries

International Nuclear Information System (INIS)

1979-05-01

The Swedish nuclear utilities started early in 1977 the KBS (nuclear fuel safety) project to study the high level waste problem and report on how and where a safe final storage could be arranged in Sweden. The docummentation produced by the project during 1977 and 1978 has been collected in a series of technical reports numbered from 1 to 120. The English summaries of the technical reports have been collected in this separate volume, No. 121. (G.B.)

Markets, Availability, Notice, and Technical Performance of Terahertz Systems: Historic Development, Present, and Trends

Science.gov (United States)

Hochrein, Thomas

2015-03-01

Although a lot of work has already been done under the older terms "far infrared" or "sub-millimeter waves", the term "terahertz" stands for a novel technique offering many potential applications. The latter term also represents a new generation of systems with the opportunity for coherent, time-resolved detection. In addition to the well-known technical opportunities, an historical examination of Internet usage, as well as the number of publications and patent applications, confirms ongoing interest in this technique. These activities' annual growth rate is between 9 % and 21 %. The geographical distribution shows the center of terahertz activities. A shift from the scientific to more application-oriented research can be observed. We present a survey among worldwide terahertz suppliers with special focus on the European region and the use of terahertz systems in the field of measurement and analytical applications. This reveals the current state of terahertz systems' commercial and geographical availability as well as their costs, target markets, and technical performance. Component cost distribution using the example of an optical pulsed time-domain terahertz system gives an impression of the prevailing cost structure. The predication regarding prospective market development, decreasing system costs and higher availability shows a convenient situation for potential users and interested customers. The causes are primarily increased competition and larger quantities in the future.

JANNAF 17th Propulsion Systems Hazards Subcommittee Meeting. Volume 1

Science.gov (United States)

Cocchiaro, James E. (Editor); Gannaway, Mary T. (Editor); Rognan, Melanie (Editor)

1998-01-01

Volume 1, the first of two volumes is a compilation of 16 unclassified/unlimited technical papers presented at the 17th meeting of the Joint Army-Navy-NASA-Air Force (JANNAF) Propulsion Systems Hazards Subcommittee (PSHS) held jointly with the 35th Combustion Subcommittee (CS) and Airbreathing Propulsion Subcommittee (APS). The meeting was held on 7 - 11 December 1998 at Raytheon Systems Company and the Marriott Hotel, Tucson, AZ. Topics covered include projectile and shaped charge jet impact vulnerability of munitions; thermal decomposition and cookoff behavior of energetic materials; damage and hot spot initiation mechanisms with energetic materials; detonation phenomena of solid energetic materials; and hazard classification, insensitive munitions, and propulsion systems safety.

HARNESSING BIG DATA VOLUMES

Directory of Open Access Journals (Sweden)

Bogdan DINU

2014-04-01

Full Text Available Big Data can revolutionize humanity. Hidden within the huge amounts and variety of the data we are creating we may find information, facts, social insights and benchmarks that were once virtually impossible to find or were simply inexistent. Large volumes of data allow organizations to tap in real time the full potential of all the internal or external information they possess. Big data calls for quick decisions and innovative ways to assist customers and the society as a whole. Big data platforms and product portfolio will help customers harness to the full the value of big data volumes. This paper deals with technical and technological issues related to handling big data volumes in the Big Data environment.

Altera – Technical update, presented by Sascoholz SA

CERN Multimedia

FI Department

2008-01-01

Thursday 28 August 2008 From 9h00 to 12h00 (welcome at 08h45) in Room B (Main Building 61/1-009) SascoHolz SA cordially invites you to an informative and interesting technical update on the latest Altera FPGA developments. Introducing Altera’s Stratix IV Device Family 40-nm high-performance, high-end FPGAs with 8.5-Gbps transceiver option The Stratix IV FPGA family gives you the highest density, highest system performance, and the lowest power available in an FPGA, enabling innovation without compromise. Speaker Ole Horn, FAE Sascoholz Agenda Altera Stratix IV Device FamilyIntroduction Logic Fabric Architecture DSP Blocks Tri-Matrix Memory PLL and Clock Networks Design Security I/O Connectivity High-Speed Transceiver Low Power Consumption Language: English As a member of the globally active distribution group, Arrow Electronics, SascoHolz SA does more than just following the concepts of classic broadline distributors. In fact, we offer a depth of service throughou...

System analysis of shallow land burial. Volume 2: technical background. Technical report, 26 November 1979-23 January 1981

International Nuclear Information System (INIS)

Lester, D.; Buckley, D.; Donelson, S.; Dura, V.; Hecht, M.

1981-03-01

This is volume two of a three volume set detailing the activities and results of the System Analysis of Shallow Land Burial Project. Activities under four project tasks are described: Task 1 - Identify Potential Radionuclide Release Pathways, Task 2 - Systems Model for Shallow Land Burial of Low-Level Waste, Task 3 - Sensitivity and Optimization Study and Task 4 - Reference Facility Dose Assessment

Magnetic Fusion Energy Program. Volume I. Introduction, technical summaries, list of publications, etc., Appendices A-K. Annual report

International Nuclear Information System (INIS)

Aamodt, R.E.; Byrne, R.N.; Catto, P.J.

1979-12-01

An abstract was prepared for the progress summary on transport theory for open and closed magnetic configurations. Seven abstracts were prepared for included appendices of more detailed work on individual devices. Also included is a list of publications, technical presentations, and DOE program contributions

Standard Technical Specifications, Babcock and Wilcox Plants

International Nuclear Information System (INIS)

1992-09-01

This NUREG contains improved Standard Technical Specifications (STS) for Babcock and Wilcox (B ampersand W) plants and documents the positions of the Nuclear Regulatory Commission (NRC) based on the B ampersand W Owners Group's proposed STS. This document is the result of extensive technical meetings and discussions among the NRC staff, the Nuclear Steam Supply System (NSSS) Owners Groups, the NSSS vendors, and the Nuclear Management and Resources Council. The improved STS were developed based on the criteria in the interim Commission Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, dated February 6, 1987. The improved STS will be used as the basis for developing improved plant-specific technical specifications by individual nuclear power plant licensees. This volume contains sections 3.4--3.9 which cover: Reactor coolant systems, emergency core cooling systems, containment systems, plant systems, electrical power systems, refueling operations

Savannah River Site Approved Site Treatment Plan, 2001 Annual Update (Volumes I and II)

Energy Technology Data Exchange (ETDEWEB)

Lawrence, B.

2001-04-30

The Compliance Plan Volume (Volume I) identifies project activity scheduled milestones for achieving compliance with Land Disposal Restrictions. Information regarding the technical evaluation of treatment options for SRS mixed wastes is contained in the Background Volume (Volume II) and is provided for information.

Management and technical requirements for laboratories in charge of water monitoring

International Nuclear Information System (INIS)

Ottaviani, M.; Bonadonna, L.; Lucentini, L.; Pettine, P.

2008-01-01

This report completes the series of volumes focused on microbiological (Rapporti ISTISAN 07/5) and chemical methods (Rapporti ISTISAN 07/31) for the monitoring of water intended for human consumption according to the Italian Legislative Decree 31/2001 (transposition of European Directive 98/83/EC) and its integrations. The guidelines here presented concern management and technical requirements for laboratories in charge of testing parameters required by the Decree also taking into account the criteria stated by the standard UNI CEI EN ISO/IEC 17025 [it

Technical innovation and industrial change

Energy Technology Data Exchange (ETDEWEB)

Krupp, H

1982-10-01

Technical development is leading by rationalization at economical stagnation to a decrease in the working volume. The economic difficulties are based on the discrepancy between the offer of goods and services as well as the actual demand. The demand of common goods is growing compared to the consumption goods, which will decrease. The therefore necessary structure change requires a high standard of governmental efforts and social consensus.

Draft Technical Position Subtask 1.1: waste package performance after repository closure. Volume 1

International Nuclear Information System (INIS)

Davis, M.S.; Schweitzer, D.G.

1983-08-01

This document provides guidance to the DOE on the issues and information necessary for the NRC to evaluate waste package performance after repository closure. Minimal performance objectives of the waste package are required by proposed 10 CFR 60. This Draft Technical Position describes the various options available to the DOE for compliance and discusses advantages and disadvantages of various choices. Examples are discussed dealing with demonstrability, predictability and reasonable assurance. The types of performance are considered. The document summarizes presently identified high priority issues needed to evaluate waste package performance after repository closure. 20 references, 7 tables

Breckinridge Project, initial effort. Report XI, Volume V. Critical review of the design basis. [Critical review

Energy Technology Data Exchange (ETDEWEB)

None

1982-01-01

Report XI, Technical Audit, is a compendium of research material used during the Initial Effort in making engineering comparisons and decisions. Volumes 4 and 5 of Report XI present those studies which provide a Critical Review of the Design Basis. The Critical Review Report, prepared by Intercontinental Econergy Associates, Inc., summarizes findings from an extensive review of the data base for the H-Coal process design. Volume 4 presents this review and assessment, and includes supporting material; specifically, Design Data Tabulation (Appendix A), Process Flow Sheets (Appendix B), and References (Appendix C). Volume 5 is a continuation of the references of Appendix C. Studies of a proprietary nature are noted and referenced, but are not included in these volumes. They are included in the Limited Access versions of these reports and may be reviewed by properly cleared personnel in the offices of Ashland Synthetic Fuels, Inc.

Combined cycle solar central receiver hybrid power system study. Volume III. Appendices. Final technical report

Energy Technology Data Exchange (ETDEWEB)

None

1979-11-01

A design study for a 100 MW gas turbine/steam turbine combined cycle solar/fossil-fuel hybrid power plant is presented. This volume contains the appendices: (a) preconceptual design data; (b) market potential analysis methodology; (c) parametric analysis methodology; (d) EPGS systems description; (e) commercial-scale solar hybrid power system assessment; and (f) conceptual design data lists. (WHK)

Space and Earth Sciences, Computer Systems, and Scientific Data Analysis Support, Volume 1

Science.gov (United States)

Estes, Ronald H. (Editor)

1993-01-01

This Final Progress Report covers the specific technical activities of Hughes STX Corporation for the last contract triannual period of 1 June through 30 Sep. 1993, in support of assigned task activities at Goddard Space Flight Center (GSFC). It also provides a brief summary of work throughout the contract period of performance on each active task. Technical activity is presented in Volume 1, while financial and level-of-effort data is presented in Volume 2. Technical support was provided to all Division and Laboratories of Goddard's Space Sciences and Earth Sciences Directorates. Types of support include: scientific programming, systems programming, computer management, mission planning, scientific investigation, data analysis, data processing, data base creation and maintenance, instrumentation development, and management services. Mission and instruments supported include: ROSAT, Astro-D, BBXRT, XTE, AXAF, GRO, COBE, WIND, UIT, SMM, STIS, HEIDI, DE, URAP, CRRES, Voyagers, ISEE, San Marco, LAGEOS, TOPEX/Poseidon, Pioneer-Venus, Galileo, Cassini, Nimbus-7/TOMS, Meteor-3/TOMS, FIFE, BOREAS, TRMM, AVHRR, and Landsat. Accomplishments include: development of computing programs for mission science and data analysis, supercomputer applications support, computer network support, computational upgrades for data archival and analysis centers, end-to-end management for mission data flow, scientific modeling and results in the fields of space and Earth physics, planning and design of GSFC VO DAAC and VO IMS, fabrication, assembly, and testing of mission instrumentation, and design of mission operations center.

Standard technical specifications, Westinghouse Plants: Bases (Sections 3.4--3.9). Volume 3, Revision 1

International Nuclear Information System (INIS)

1995-04-01

This NUREG contains the improved Standard Technical Specifications (STS) for Westinghouse plants. Revision 1 incorporates the cumulative changes to Revision 0, which was published in September 1992. 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, specifically the Westinghouse Owners Group (WOG), 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 (58 FR 39132). Licensees are encouraged to upgrade their technical specifications consistent with those criteria and conforming, to the extent practical and consistent with the licensing basis for the facility, to Revision 1 to the improved STS. The Commission continues to place the highest priority on requests for complete conversions to the improved STS. Licensees adopting portions of the improved STS to existing technical specifications should adopt all related requirements, as applicable, to achieve a high degree of standardization and consistency

Standard technical specifications, Westinghouse Plants: Bases (Sections 2.0--3.3). Volume 2, Revision 1

International Nuclear Information System (INIS)

1995-04-01

This NUREG contains the improved Standard Technical Specifications (STS) for Westinghouse plants. Revision 1 incorporates the cumulative changes to Revision 0, which was published in September 1992. 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, specifically the Westinghouse Owners Group (WOG), 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 (58 FR 39132). Licensees are encouraged to upgrade their technical specifications consistent with those criteria and conforming, to the extent practical and consistent with the licensing basis for the facility, to Revision 1 to the improved STS. The Commission continues to place the highest priority on requests for complete conversions to the improved STS. Licensees adopting portions of the improved STS to existing technical specifications should adopt all related requirements, as applicable, to achieve a high degree of standardization and consistency

Final Technical Report - Kotzebue Wind Power Project - Volume II

Energy Technology Data Exchange (ETDEWEB)

Rana Zucchi, Global Energy Concepts, LLC; Brad Reeve, Kotzebue Electric Association; DOE Project Officer - Doug Hooker

2007-10-31

The Kotzebue Wind Power Project is a joint undertaking of the U.S. Department of Energy (DOE); Kotzebue Electric Association (KEA); and the Alaska Energy Authority (AEA). The goal of the project is to develop, construct, and operate a wind power plant interconnected to a small isolated utility grid in an arctic climate in Northwest Alaska. The primary objective of KEA’s wind energy program is to bring more affordable electricity and jobs to remote Alaskan communities. DOE funding has allowed KEA to develop a multi-faceted approach to meet these objectives that includes wind project planning and development, technology transfer, and community outreach. The first wind turbines were installed in the summer of 1997 and the newest turbines were installed in the spring of 2007. The total installed capacity of the KEA wind power project is 1.16 MW with a total of 17 turbines rated between 65 kW and 100 kW. The operation of the wind power plant has resulted in a wind penetration on the utility system in excess of 35% during periods of low loads. This document and referenced attachments are presented as the final technical report for the U.S. Department of Energy (DOE) grant agreement DE-FG36-97GO10199. Interim deliverables previously submitted are also referenced within this document and where reasonable to do so, specific sections are incorporated in the report or attached as appendices.

Productivity and technical efficiency of suckler beef production systems: trends for the period 1990 to 2012.

Science.gov (United States)

Veysset, P; Lherm, M; Roulenc, M; Troquier, C; Bébin, D

2015-12-01

Over the past 23 years (1990 to 2012), French beef cattle farms have expanded in size and increased labour productivity by over 60%, chiefly, though not exclusively, through capital intensification (labour-capital substitution) and simplifying herd feeding practices (more concentrates used). The technical efficiency of beef sector production systems, as measured by the ratio of the volume value (in constant euros) of farm output excluding aids to volume of intermediate consumption, has fallen by nearly 20% while income per worker has held stable thanks to subsidies and the labour productivity gains made. This aggregate technical efficiency of beef cattle systems is positively correlated to feed self-sufficiency, which is in turn negatively correlated to farm and herd size. While volume of farm output per hectare of agricultural area has not changed, forage feed self-sufficiency decreased by 6 percentage points. The continual increase in farm size and labour productivity has come at a cost of lower production-system efficiency - a loss of technical efficiency that 20 years of genetic, technical, technological and knowledge-driven progress has barely managed to offset.

Load research manual. Volume 1. Load research procedures

Energy Technology Data Exchange (ETDEWEB)

Brandenburg, L.; Clarkson, G.; Grund, Jr., C.; Leo, J.; Asbury, J.; Brandon-Brown, F.; Derderian, H.; Mueller, R.; Swaroop, R.

1980-11-01

This three-volume manual presents technical guidelines for electric utility load research. Special attention is given to issues raised by the load data reporting requirements of the Public Utility Regulatory Policies Act of 1978 and to problems faced by smaller utilities that are initiating load research programs. In Volumes 1 and 2, procedures are suggested for determining data requirements for load research, establishing the size and customer composition of a load survey sample, selecting and using equipment to record customer electricity usage, processing data tapes from the recording equipment, and analyzing the data. Statistical techniques used in customer sampling are discussed in detail. The costs of load research also are estimated, and ongoing load research programs at three utilities are described. The manual includes guides to load research literature and glossaries of load research and statistical terms.

JANNAF 18th Propulsion Systems Hazards Subcommittee Meeting. Volume 1

Science.gov (United States)

Cocchiaro, James E. (Editor); Gannaway, Mary T. (Editor)

1999-01-01

This volume, the first of two volumes is a compilation of 18 unclassified/unlimited-distribution technical papers presented at the Joint Army-Navy-NASA-Air Force (JANNAF) 18th Propulsion Systems Hazards Subcommittee (PSHS) meeting held jointly with the 36th Combustion Subcommittee (CS) and 24th Airbreathing Propulsion Subcommittee (APS) meetings. The meeting was held 18-21 October 1999 at NASA Kennedy Space Center and The DoubleTree Oceanfront Hotel, Cocoa Beach, Florida. Topics covered at the PSHS meeting include: shaped charge jet and kinetic energy penetrator impact vulnerability of gun propellants; thermal decomposition and cookoff behavior of energetic materials; violent reaction; detonation phenomena of solid energetic materials subjected to shock and impact stimuli; and hazard classification, insensitive munitions, and propulsion systems safety.

Final Technical Report

Energy Technology Data Exchange (ETDEWEB)

Glasser, Alan H. [Fusion Theory and Computation Inc., Kingston, WA (United States)

2018-02-02

Final technical report on DE-SC0016106. This is the final technical report for a portion of the multi-institutional CEMM project. This report is centered around 3 publications and a seminar presentation, which have been submitted to E-Link.

Endolymphatic Thoracic Duct Stent-Graft Reconstruction for Chylothorax: Approach, Technical Success, Safety, and Short-term Outcomes.

Science.gov (United States)

Srinivasa, Rajiv N; Chick, Jeffrey Forris Beecham; Hage, Anthony N; Gemmete, Joseph J; Murrey, Douglas C; Srinivasa, Ravi N

2018-04-01

To report approach, technical success, safety, and short-term outcomes of thoracic duct stent-graft reconstruction for the treatment of chylothorax. Two patients, 1 (50%) male and 1 (50%) female, with mean age of 38 years (range: 16-59 years) underwent endolymphatic thoracic duct stent-graft reconstruction between September 2016 and July 2017. Patients had radiographic left-sided chylothoraces (n = 2) from idiopathic causes (n = 1) and heart transplantation (n = 1). In both (100%) patients, antegrade lymphatic access was used to opacify the thoracic duct after which retrograde access was used for thoracic duct stent-graft placement. Pelvic lymphangiography technical success, antegrade cisterna chyli cannulation technical success, thoracic duct opacification technical success, retrograde thoracic duct access technical success, thoracic duct stent-graft reconstruction technical success, ethiodized oil volume, contrast volume, estimated blood loss, procedure time, fluoroscopy time, radiation dose, clinical success, complications, deaths, and follow-up were recorded. Pelvic lymphangiography, antegrade cisterna chyli cannulation, thoracic duct opacification, retrograde thoracic duct access, and thoracic duct stent-graft reconstruction were technically successful in both (100%) patients. Mean ethiodized oil volume was 8 mL (range: 5-10 mL). Mean contrast volume was 13 mL (range: 5-20 mL). Mean estimated blood loss was 13 mL (range: 10-15 mL). Mean fluoroscopy time was 50.4 min (range: 31.2-69.7 min). Mean dose area product and reference air kerma were 954.4 μGmy 2 (range: 701-1,208 μGmy 2 ) and 83.5 mGy (range: 59-108 mGy), respectively. Chylothorax resolved in both (100%) patients. There were no minor or major complications directly related to the procedure. Thoracic duct stent-graft reconstruction may be a technically successful and safe alternative to thoracic duct embolization, disruption, and surgical ligation for the treatment of chylothorax

Technical innovation and industrial change

International Nuclear Information System (INIS)

Krupp, H.

1982-01-01

Technical development is leading by rationalization at economical stagnation to a decrease in the working volume. The economical difficulties are based on the discrepancy between the offer of goods and services as well as the actual demand. The demand of common goods is growing compared to the consumption goods, which will decrease. The therefore necessary structure change requires a high standard of governmental efforts and social consensus. (orig.) [de

Handbook of Technical Communication

OpenAIRE

Mehler , Alexander; Romary , Laurent; Gibbon , Dafydd

2012-01-01

International audience; The handbook "Technical Communication" brings together a variety of topics which range from the role of technical media in human communication to the linguistic, multimodal enhancement of present-day technologies. It covers the area of computer-mediated text, voice and multimedia communication as well as of technical documentation. In doing so, the handbook takes professional and private communication into account. Special emphasis is put on technical communication bas...

Assessment and management of ageing of major nuclear power plant components important to safety: In-containment instrumentation and control cables. Volume I

International Nuclear Information System (INIS)

2000-12-01

and technical support organizations dealing with specific plant components addressed in the reports. The component addressed in the present report is the in-containment instrumentation and control (I and C) cables. The report presents, in two volumes, results of a Co-ordinated Research Project (CRP) on the Management of Ageing of In-containment Instrumentation and Control cables. Part I, Volume 1 presents information on current methods for assessing and managing ageing degradation of Instrumentation and Control cables in real NPP environments prepared by the CRP team. An important complement of this information is user perspectives on the application of these methods which are presented in Part II, Volume 1. Volume 2 contains annexes supporting the guidance of Volume 1 with more detailed information and examples provided by individual CRP participants. For a quick overview, readers should see Section 8 of Part I, Volume 1, which describes a systematic ageing management programme for Instrumentation and Control cables utilizing methods presented in the report; Section 9 of Part I, Volume 1, which presents CRP conclusions and recommendations; and Part II providing the application guidance from the user's perspective

Assessment and management of ageing of major nuclear power plant components important to safety: In-containment instrumentation and control cables. Volume II

International Nuclear Information System (INIS)

2000-12-01

and technical support organizations dealing with specific plant components addressed in the reports. The component addressed in the present report is the in-containment instrumentation and control (I and C) cables. The report presents, in two volumes, results of a Co-ordinated Research Project (CRP) on the Management of Ageing of In-containment Instrumentation and Control cables. Part I, Volume 1 presents information on current methods for assessing and managing ageing degradation of Instrumentation and Control cables in real NPP environments prepared by the CRP team. An important complement of this information is user perspectives on the application of these methods which are presented in Part II, Volume 1. Volume 2 contains annexes supporting the guidance of Volume 1 with more detailed information and examples provided by individual CRP participants. For a quick overview, readers should see Section 8 of Part I, Volume 1, which describes a systematic ageing management programme for Instrumentation and Control cables utilizing methods presented in the report; Section 9 of Part I, Volume 1, which presents CRP conclusions and recommendations; and Part II providing the application guidance from the user's perspective

1999 Annual meeting on non-destructive testing. 10. Anniversary of DGZfP in Germany. Volumes 1 and 2. Proceedings

International Nuclear Information System (INIS)

1999-01-01

The two proceedings volumes contain the 92 papers presented at the meeting, dealing with the following key subjects: Ultrasonic testing; industrial radiography and other testing methods using radiation; acoustic emission testing; materials charcaterization; training and certification; standards and other technical codes and regulations. (orig./CB) [de

Abstract of technical and scientific papers for oral and poster presentations

International Nuclear Information System (INIS)

1998-01-01

The National Academy of Science and Technology (NAST) organized the holding of the 4th national social science congress that coincide with the 20th annual scientific meeting on the 'The Philippine social sciences in the life of the nation' as the overall theme. It highlights the significant developments and technical and scientific researches on social, agricultural, mathematical, physical, and engineering, biological and health sciences that contributes to the nation building

46 CFR Appendix B to Subpart C to... - Substance Technical Guidelines, Benzene

Science.gov (United States)

2010-10-01

... 46 Shipping 7 2010-10-01 2010-10-01 false Substance Technical Guidelines, Benzene B Appendix B to... Subpart C to Part 197—Substance Technical Guidelines, Benzene I. Physical and Chemical Data (a) Substance... temperature: 580 °C (1076 °F). (3) Flammable limits in air, % by volume: Lower: 1.3%, Upper: 7.5%. (4...

Technical Training: Technical Training Seminar

CERN Multimedia

2004-01-01

Tuesday 30 March TECHNICAL TRAINING SEMINAR From 9:00 to 12:00 and from 13:00 to 16:00 hrs - Council Chamber, Salle B, Salle des Pas Perdus National Instruments (NI) on Tour 2004 Claudia Jüngel, Evrem Yarkin, Joel Clerc, Hervé Baour / NATIONAL INSTRUMENTS The special event NI on Tour 2004, run in Germany, Austria and Switzerland, will be at CERN on March 30. Technical seminars and free introductory courses will be offered all day long in the Council Chamber, Salle B, and Salle des Pas Perdus (buildings 61 and 503). Technical conferences: 09:00 - 12:00 Data acquisition systems on PCs. Industrial measurement and control techniques. 13:00 - 16:00 Advanced LabVIEW software and PXI instrumentation. Measuring instruments and system components for teststand automation. Introductory courses: 09:00 - 12:00 DIAdem: Data analysis and presentation 13:00 - 16:00 Data acquisition with LabVIEW Language: English and French Free special seminar. Registration is recommended with National Instruments Switzerland (please sp...

Technical Training: Technical Training Seminar

CERN Multimedia

2004-01-01

Tuesday 30 March TECHNICAL TRAINING SEMINAR From 9:00 to 12:00 and from 13:00 to 16:00 hrs - Council Chamber, Salle B, Salle des Pas Perdus National Instruments (NI) on Tour 2004 Claudia Jüngel, Evrem Yarkin, Joel Clerc, Hervé Baour / NATIONAL INSTRUMENTS The special event NI on Tour 2004, run in Germany, Austria and Switzerland, will be at CERN on March 30. Technical seminars and free introductory courses will be offered all day long in the Council Chamber, Salle B, and Salle des Pas Perdus (buildings 61 and 503). Technical conferences: 09:00 - 12:00 Data acquisition systems on PCs. Industrial measurement and control techniques. 13:00 - 16:00 Advanced LabVIEW software and PXI instrumentation. Measuring instruments and system components for teststand automation. Introductory courses: 09:00 - 12:00 DIAdem: Data analysis and presentation 13:00 - 16:00 Data acquisition with LabVIEW Language: English and French Free special seminar. Registration is recommended with National Instruments Swi...

Technical Training: Technical Training Seminar

CERN Multimedia

2004-01-01

TECHNICAL TRAINING Monique Duval tel. 74924 technical.training@cern.ch Monday 9 February 2004 From 10:00 to 12:00 - IT Auditorium - bldg. 31, 3rd floor ANSOFT High-Frequency Seminar David Prestaux, Application Engineer, ANSOFT F-78535 BUC, France This Technical Training seminar will present two Ansoft application products: Ansoft HFSS and Ansoft Designer. Ansoft HFSS makes use of the Finite Element Method (FEM) to calculate field solutions from first principles. It can accurately predict all high-frequency behaviours such as dispersion, mode conversion, and losses due to materials and radiation. Ansoft Designer is a suite of design tools to fully integrate high-frequency, physics-based electromagnetic simulations into a seamless system-level simulation environment. Ansoft Designer uses a simple interface to give complete control over every design task, by a method allowing multiple solvers, Solver on Demand. • Introduction • Overview of the Ansoft Total solution • Ansoft HFSS 9...

ASEAN--USAID Buildings Energy Conservation Project final report. Volume 2, Technology

Energy Technology Data Exchange (ETDEWEB)

Levine, M.D.; Busch, J.F. [eds.

1992-06-01

This volume reports on research in the area of energy conservation technology applied to commercial buildings in the Association of Southeast Asian Nations (ASEAN) region. Unlike Volume I of this series, this volume is a compilation of original technical papers prepared by different authors in the project. In this regard, this volume is much like a technical journal. The papers that follow report on research conducted by both US and ASEAN researchers. The authors representing Indonesia, Malaysia, Philippines, and Thailand, come from a range of positions in the energy arena, including government energy agencies, electric utilities, and universities. As such, they account for a wide range of perspectives on energy problems and the role that technology can play in solving them. This volume is about using energy more intelligently. In some cases, the effort is towards the use of more advanced technologies, such as low-emittance coatings on window glass, thermal energy storage, or cogeneration. In others, the emphasis is towards reclaiming traditional techniques for rendering energy services, but in new contexts such as lighting office buildings with natural light, or cooling buildings of all types with natural ventilation. Used in its broadest sense, the term ``technology`` encompasses all of the topics addressed in this volume. Along with the more customary associations of technology, such as advanced materials and equipment and the analysis of their performance, this volume treats design concepts and techniques, analysis of ``secondary`` impacts from applying technologies (i.e., unintended impacts, or impacts on parties not directly involved in the purchase and use of the technology), and the collection of primary data used for conducting technical analyses.

Engineering Technical Review Planning Briefing

Science.gov (United States)

Gardner, Terrie

2012-01-01

The general topics covered in the engineering technical planning briefing are 1) overviews of NASA, Marshall Space Flight Center (MSFC), and Engineering, 2) the NASA Systems Engineering(SE) Engine and its implementation , 3) the NASA Project Life Cycle, 4) MSFC Technical Management Branch Services in relation to the SE Engine and the Project Life Cycle , 5) Technical Reviews, 6) NASA Human Factor Design Guidance , and 7) the MSFC Human Factors Team. The engineering technical review portion of the presentation is the primary focus of the overall presentation and will address the definition of a design review, execution guidance, the essential stages of a technical review, and the overall review planning life cycle. Examples of a technical review plan content, review approaches, review schedules, and the review process will be provided and discussed. The human factors portion of the presentation will focus on the NASA guidance for human factors. Human factors definition, categories, design guidance, and human factor specialist roles will be addressed. In addition, the NASA Systems Engineering Engine description, definition, and application will be reviewed as background leading into the NASA Project Life Cycle Overview and technical review planning discussion.

Forecasting Resource as a Method of Increasing the Security of Technical Devices

Science.gov (United States)

Cherepanov, Anatoly P.; Lyapustin, Pavel K.

2017-10-01

The article shows a method of increasing the safe operation of technical devices at various stages of the life cycle according to the proposed classification parameters of the resource by applying the model of resource prediction. The model takes into account the presence of defects, the rate of corrosion and corrosion resistance of the material, the volume of technical diagnosis, the degree of risk in case of failure or damage of technical devices. The article shows the application of the model resource of the technical device from the manufacture to the end of its service life.

Reducing surgery of volume for the pulmonary emphysema

International Nuclear Information System (INIS)

Ramirez, Juan Camilo

1997-01-01

The paper includes aspects as selection approaches, functional evaluation, imagenologic evaluation, cardiovascular evaluation, technical aspects and results among other topics related with the reducing surgery of volume of the pulmonary emphysema

SOAC - State-of-the-Art Car Engineering Tests at Department of Transportation High Speed Ground Test Center : Volume 2. Performance Tests.

Science.gov (United States)

1975-01-01

The six-volume report presents the technical methodology, data samples, and results of tests conducted on the SOAC on the Rail Transit Test Track at the High Speed Ground Test Center in Pueblo, Colorado during the period April to July 1973. The Test ...

ALICE: Physics Performance Report, Volume II

International Nuclear Information System (INIS)

Alessandro, B; Antinori, F; Belikov, J A

2006-01-01

ALICE is a general-purpose heavy-ion experiment designed to study the physics of strongly interacting matter and the quark-gluon plasma in nucleus-nucleus collisions at the LHC. It currently involves more than 900 physicists and senior engineers, from both the nuclear and high-energy physics sectors, from over 90 institutions in about 30 countries. The ALICE detector is designed to cope with the highest particle multiplicities above those anticipated for Pb-Pb collisions (dN ch /dy up to 8000) and it will be operational at the start-up of the LHC. In addition to heavy systems, the ALICE Collaboration will study collisions of lower-mass ions, which are a means of varying the energy density, and protons (both pp and pA), which primarily provide reference data for the nucleus-nucleus collisions. In addition, the pp data will allow for a number of genuine pp physics studies. The detailed design of the different detector systems has been laid down in a number of Technical Design Reports issued between mid-1998 and the end of 2004. The experiment is currently under construction and will be ready for data taking with both proton and heavy-ion beams at the start-up of the LHC. Since the comprehensive information on detector and physics performance was last published in the ALICE Technical Proposal in 1996, the detector, as well as simulation, reconstruction and analysis software have undergone significant development. The Physics Performance Report (PPR) provides an updated and comprehensive summary of the performance of the various ALICE subsystems, including updates to the Technical Design Reports, as appropriate. The PPR is divided into two volumes. Volume I, published in 2004 (CERN/LHCC 2003-049, ALICE Collaboration 2004 J. Phys. G: Nucl. Part. Phys. 30 1517-1763), contains in four chapters a short theoretical overview and an extensive reference list concerning the physics topics of interest to ALICE, the experimental conditions at the LHC, a short summary and update

Scientific and technical guidance for the preparation and presentation of a health claim application (Revision 2)

DEFF Research Database (Denmark)

Sjödin, Anders Mikael

2017-01-01

EFSA asked the Panel on Dietetic Products, Nutrition and Allergies (NDA) to update the scientific and technical guidance for the preparation and presentation of an application for authorisation of a health claim published in 2011. Since then, the NDA Panel has gained considerable experience...... developments in this area. This guidance document presents a common format for the organisation of information for the preparation of a well-structured application for authorisation of health claims which fall under Articles 13(5), 14 and 19 of Regulation (EC) No 1924/2006. This guidance outlines...... the information and scientific data which must be included in the application, the hierarchy of different types of data and study designs, and the key issues which should be addressed in the application to substantiate the health claim....

Relationship between non-technical skills and technical performance during cardiopulmonary resuscitation: does stress have an influence?

Science.gov (United States)

Krage, Ralf; Zwaan, Laura; Tjon Soei Len, Lian; Kolenbrander, Mark W; van Groeningen, Dick; Loer, Stephan A; Wagner, Cordula; Schober, Patrick

2017-11-01

Non-technical skills, such as task management, leadership, situational awareness, communication and decision-making refer to cognitive, behavioural and social skills that contribute to safe and efficient team performance. The importance of these skills during cardiopulmonary resuscitation (CPR) is increasingly emphasised. Nonetheless, the relationship between non-technical skills and technical performance is poorly understood. We hypothesise that non-technical skills become increasingly important under stressful conditions when individuals are distracted from their tasks, and investigated the relationship between non-technical and technical skills under control conditions and when external stressors are present. In this simulator-based randomised cross-over study, 30 anaesthesiologists and anaesthesia residents from the VU University Medical Center, Amsterdam, the Netherlands, participated in two different CPR scenarios in random order. In one scenario, external stressors (radio noise and a distractive scripted family member) were added, while the other scenario without stressors served as control condition. Non-technical performance of the team leader and technical performance of the team were measured using the 'Anaesthetists' Non-technical Skill' score and a recently developed technical skills score. Analysis of variance and Pearson correlation coefficients were used for statistical analyses. Non-technical performance declined when external stressors were present (adjusted mean difference 3.9 points, 95% CI 2.4 to 5.5 points). A significant correlation between non-technical and technical performance scores was observed when external stressors were present (r=0.67, 95% CI 0.40 to 0.83, ptechnical performance score (task management, team working, situation awareness, decision-making). During CPR with external stressors, the team's technical performance is related to the non-technical skills of the team leader. This may have important implications for training of

Technical support for GEIS: radioactive waste isolation in geologic formations. Volume 18. Facility construction feasibility and costs by rock type

International Nuclear Information System (INIS)

1978-04-01

The results of a study that compared the general engineering feasibility and unit costs associated with sinking shafts and mining storage rooms in the four rock types (salt, granite, shale, basalt) are presented in this volume. The report includes a discussion of the general effects of rock characteristics on shaft and mine design, the application of these design considerations to the specific designs developed for the Draft GEIS, shaft and mine construction techniques, and the unit cost comparison. The repository designs upon which this comparison was based are presented in other volumes of this series

Reduced waste generation technical work plan

International Nuclear Information System (INIS)

1987-05-01

The United States Department of Energy has established policies for avoiding plutonium losses to the waste streams and minimizing the generation of wastes produced at its nuclear facilities. This policy is evidenced in DOE Order 5820.2, which states ''Technical and administrative controls shall be directed towards reducing the gross volume of TRU waste generated and the amount of radioactivity in such waste.'' To comply with the DOE directive, the Defense Transuranic Waste Program (DTWP) supports and provides funding for specific research and development tasks at the various DOE sites to reduce the generation of waste. This document has been prepared to give an overview of current and past Reduced Waste Generation task activities which are to be based on technical and cost/benefit factors. The document is updated annually, or as needed, to reflect the status of program direction. Reduced Waste Generation (RWG) tasks encompass a wide range of goals which are basically oriented toward (1) avoiding the generation of waste, (2) changing processes or operations to reduce waste, (3) converting TRU waste into LLW by sorting or decontamination, and (4) reducing volumes through operations such as incineration or compaction

Spent nuclear fuel technical baseline description, Fiscal Year 1996: Volume II, supporting data

International Nuclear Information System (INIS)

Womack, J.C.

1995-11-01

The Technical Baseline Description documents the Project-Level functions and requirements, along with associated enabling assumptions, issues, trade studies, interfaces, and products. It is a snapshot in time of the baseline at the beginning of September 1995. It supports the individual subprojects in the development of lower-tier functions, requirements, and specifications in FY 1996. It also supports the need for Hanford site planning to be based on an integrated Hanford site systems engineering technical baseline; and is traceable to that baseline. This document replaces and supercedes WHC-SD-SNF-SD-003

EUV mask defect inspection and defect review strategies for EUV pilot line and high volume manufacturing

Science.gov (United States)

Chan, Y. David; Rastegar, Abbas; Yun, Henry; Putna, E. Steve; Wurm, Stefan

2010-04-01

Reducing mask blank and patterned mask defects is the number one challenge for extreme ultraviolet lithography. If the industry succeeds in reducing mask blank defects at the required rate of 10X every year for the next 2-3 years to meet high volume manufacturing defect requirements, new inspection and review tool capabilities will soon be needed to support this goal. This paper outlines the defect inspection and review tool technical requirements and suggests development plans to achieve pilot line readiness in 2011/12 and high volume manufacturing readiness in 2013. The technical specifications, tooling scenarios, and development plans were produced by a SEMATECH-led technical working group with broad industry participation from material suppliers, tool suppliers, mask houses, integrated device manufacturers, and consortia. The paper summarizes this technical working group's assessment of existing blank and mask inspection/review infrastructure capabilities to support pilot line introduction and outlines infrastructure development requirements and tooling strategies to support high volume manufacturing.

Comprehensive Technical Report of the Inquiry into the Application of Living Systems Theory to 41 U. S. Army Battalions: Executive Summary. Volume 1

Science.gov (United States)

1984-11-01

information such as statutory and executive directives, regulations, and technical manuals is blended with matter/energy (people, equipment, and...which might be initiated in order to counteract these potential pathologies. An organizacion , like an organism, cannot survive when its basic processes...Normative Tables and Performance Indicator Scales presented in the study. The Tables and Scales, much like the specification in a technical ,. manual , permit

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 1, Methodology

Energy Technology Data Exchange (ETDEWEB)

1993-11-01

The Energy Policy and Conservation Act (P.L. 94-163), as amended, establishes energy conservation standards for 12 of the 13 types of consumer products specifically covered by the Act. The legislation requires the Department of Energy (DOE) to consider new or amended standards for these and other types of products at specified times. DOE is currently considering amending standards for seven types of products: water heaters, direct heating equipment, mobile home furnaces, pool heaters, room air conditioners, kitchen ranges and ovens (including microwave ovens), and fluorescent light ballasts and is considering establishing standards for television sets. This Technical Support Document presents the methodology, data, and results from the analysis of the energy and economic impacts of the proposed standards. This volume presents a general description of the analytic approach, including the structure of the major models.

Technical realization of the VISA-2 Project, contract: 2.01/ I phase, Volume No. I

International Nuclear Information System (INIS)

1963-12-01

Cooperation between the Institutes in Vinca and Saclay has started by carrying out the task 'Technical realization of the VISA-2 project' which should enable: obtaining new experimental spaces in the RA reactor with high fast neutron flux for sample irradiation; obtaining experience in reactor continual operation for few months at nominal power of 6.5 MW and increase of RA reactor utilization; solving the problem of activated channels and samples transport, problems of working in hot cells; obtaining irradiated samples for examining radiation effects first in Saclay and later in Vinca. The project is divided in three phases. Phase one covers the reconstruction of the RA reactor fuel channels according to the VISA-2 project demands. The second phase includes the activities related to measuring devices for measuring the temperatures at the incoming and outgoing heavy water in 5 VISA-2 channels, as well as temperature of the samples (55 thermocouples) and testing the channels and capsules after their insertion in the reactor. The third phase includes activities are related to problems of transport of radioactive channels and VISA-2 capsules, problems of cutting as well as packing and transporting of irradiated samples from Vinca to Saclay. This volume includes all the relevant documents for completing the task including contracts, needed preliminary calculations as well as safety analysis [sr

Advanced energy sources and conversion techniques. Proceedings of a seminar. Volume 1. [35 papers

Energy Technology Data Exchange (ETDEWEB)

None

1958-11-01

The Seminar was organized as a series of tutorial presentations and round table discussions on a technical level to implement the following: (a) to identify and explore present and projected needs for energy sources and conversion techniques for military applications; (b) to exchange information on current and planned efforts in these fields; (c) to examine the effect of anticipated scientific and technological advances on these efforts; and (d) to present suggested programs aimed at satisfying the military needs for energy sources and conversion techniques. Volume I contains all of the unclassified papers presented at the Seminar. (W.D.M.)

Low-level radioactive waste in the northeast: disposal volume projections

International Nuclear Information System (INIS)

1982-10-01

The northeastern states, with support of the Coalition of Northeastern Governors (CONEG), are developing compact(s) for the disposal and management of low-level radioactive waste (LLRW) generated in the eleven northeastern states (Connecticut, Delaware, Maine, Maryland, Massachusetts, New Hampshire, New Jersey, New York, Pennsylvania, Rhode Island, and Vermont). The Technical Subcommittee has made a projection of future low-level radioactive waste to the year 2000 based on existing waste volume data and anticipated growth in the Northeast states. Aware of the difficulties involved with any long range projection - unforeseen events can drastically change projections based on current assumptions - the Technical Subcommittee believes that waste volume projections should be reviewed annually as updated information becomes available. The Technical Subcommittee made the following findings based upon a conservative projection methodology: volumes of low-level waste produced annually in the eleven states individually and collectively are expected to grow continually through the year 2000 with the rate of increase varying by state; by the year 2000, the Northeast is projected to generate 58,000 m 3 of low-level waste annually, about 1.9 times the current average; and based on current estimates, 47% of the total projected waste volume in the year 2000 will be produced by nuclear power plants, compared to the current average of 54%. Non-reactor wastes will equal 53% of the total in the year 2000 compared to the current 46%

ABOUT MODERN TECHNICAL GRAPHICS USING IN THE VIRTUAL PROTOTYPING

Directory of Open Access Journals (Sweden)

GHERGHINA George

2008-07-01

Full Text Available The paper presents aspects concerning the using of modern technical graphics elements in the virtual prototyping. The virtual prototyping is a process which uses a virtual prototype in place of physical prototype for the testing and the evaluation of specific features of designed product. The virtual prototype is created by computer such as it could assign the specific features as close as possible to the real conditions which permit its function simulation in the conditions for which is designed. The virtual prototyping permits the replacing of classical design process, although, and the elaboration of graphicalm documentation, which represent an important work volume – with CAD/CAM systems in the increased efficiency conditions.

OEXP exploration studies technical report. Volume 3: Special reports, studies, and indepth systems assessments

International Nuclear Information System (INIS)

Roberts, B.B.; Bland, D.

1988-12-01

The Office of Exploration (OEXP) at NASA has been tasked with defining and recommending alternatives for an early 1990's national decision on a focused program of manned exploration of the Solar System. The Mission analysis and System Engineering (MASE) group, which is managed by the Exploration Studies Office at the Johnson Space Center, is responsible for coordinating the technical studies necessary for accomplishing such a task. This technical report, produced by the MASE, describes the process used to conduct exploration studies and discusses the mission developed in a case study approach. The four case studies developed in FY88 include: (1) a manned expedition to PHOBOS; (2) a manned expedition to MARS; (3) a lunar surface observatory; and a lunar outpost to early Mars evolution. The final outcome of this effort is a set of programmatic and technical conclusions and recommendations for the following year's work

AREVA Technical Days (ATD) session 2: operations of the back-end of the nuclear fuel cycle; AREVA Technical Days (ATD) session 2: les activites du pole Aval du cycle du combustible nucleaire

Energy Technology Data Exchange (ETDEWEB)

NONE

2002-07-01

These technical days organized by the Areva Group aims to explain the group activities in a technological and economic point of view, to provide an outlook of worldwide energy trends and challenges and to present each of their businesses in a synthetic manner. This second session deals with the reprocessing business, back-end financing mechanisms, technology transfer, environmental management, risk management programs, research and development contribution to waste volume reductions, issues and outlook of nuclear wastes, comparison of the open and closed cycles. (A.L.B.)

Technical writing versus technical writing

Science.gov (United States)

Dillingham, J. W.

1981-01-01

Two terms, two job categories, 'technical writer' and 'technical author' are discussed in terms of industrial and business requirements and standards. A distinction between 'technical writing' and technical 'writing' is made. The term 'technical editor' is also considered. Problems inherent in the design of programs to prepare and train students for these jobs are discussed. A closer alliance between industry and academia is suggested as a means of preparing students with competent technical communication skills (especially writing and editing skills) and good technical skills.

Cost/benefit tradeoffs for reducing the energy consumption of the commercial air transportation system. Volume 1: Technical analysis

Science.gov (United States)

Kraus, E. F.

1976-01-01

The effectiveness and associated costs of operational and technical options for reduced fuel consumption by Douglas aircraft in the domestic airline fleet are assessed. Areas explored include alternative procedures for airline and flight operations, advanced and state of the art technology, modification and derivative configurations, new near-term aircraft, turboprop configuration studies, and optimum aircraft geometry. Data for each aircraft studied is presented in tables and graphs.

An Intelligent technical analysis using neural network

Directory of Open Access Journals (Sweden)

Reza Raei

2011-07-01

Full Text Available Technical analysis has been one of the most popular methods for stock market predictions for the past few decades. There have been enormous technical analysis methods to study the behavior of stock market for different kinds of trading markets such as currency, commodity or stock. In this paper, we propose two different methods based on volume adjusted moving average and ease of movement for stock trading. These methods are used with and without generalized regression neural network methods and the results are compared with each other. The preliminary results on historical stock price of 20 firms indicate that there is no meaningful difference between various proposed models of this paper.

Evaluation of dose according to the volume and respiratory range during SBRT in lung cancer

Energy Technology Data Exchange (ETDEWEB)

Lee, Deuk Hee [Dept. of Radiation Oncology, Busan Paik Hospital, Inje University, Busan (Korea, Republic of); Park, Eun Tae; Kim, Jung Hoon; Kang, Se Seik [Dept. of Radiological Science, College of Health Sciences, Catholic University of Pusan, Busan (Korea, Republic of)

2016-09-15

Stereotactic body radiotherapy is effective technic in radiotherapy for low stage lung cancer. But lung cancer is affected by respiratory so accurately concentrate high dose to the target is very difficult. In this study, evaluated the target volume according to how to take the image. And evaluated the dose by photoluminescence glass dosimeter according to how to contour the volume and respiratory range. As a result, evaluated the 4D CT volume was 10.4 cm{sup 3} which was closest value of real size target. And in dose case is internal target volume dose was 10.82, 16.88, 21.90 Gy when prescribed dose was 10, 15, 20 Gy and it was the highest dose. Respiratory gated radiotherapy dose was more higher than internal target volume. But it made little difference by respiratory range. Therefore, when moving cancer treatment, acquiring image by 4D CT, contouring internal target volume and respiratory gated radiotherapy technic would be the best way.

Evaluation of dose according to the volume and respiratory range during SBRT in lung cancer

International Nuclear Information System (INIS)

Lee, Deuk Hee; Park, Eun Tae; Kim, Jung Hoon; Kang, Se Seik

2016-01-01

Stereotactic body radiotherapy is effective technic in radiotherapy for low stage lung cancer. But lung cancer is affected by respiratory so accurately concentrate high dose to the target is very difficult. In this study, evaluated the target volume according to how to take the image. And evaluated the dose by photoluminescence glass dosimeter according to how to contour the volume and respiratory range. As a result, evaluated the 4D CT volume was 10.4 cm 3 which was closest value of real size target. And in dose case is internal target volume dose was 10.82, 16.88, 21.90 Gy when prescribed dose was 10, 15, 20 Gy and it was the highest dose. Respiratory gated radiotherapy dose was more higher than internal target volume. But it made little difference by respiratory range. Therefore, when moving cancer treatment, acquiring image by 4D CT, contouring internal target volume and respiratory gated radiotherapy technic would be the best way

Earth-covered buildings: technical notes

Energy Technology Data Exchange (ETDEWEB)

Moreland, F L; Higgs, F; Shih, J [eds.

1978-01-01

John Cable, Architectural and Engineering Systems Branch, Division of Buildings and Community Systems, Department of Energy, kicked off the conference and spelled out the role of DOE in this area. One of his points was that the technical problems are easier than the institutional problems. A separate abstract was prepared for each of the 18 papers of this volume; all of the abstracts will appear in Energy Research Abstracts (ERA), and 16 were selected for Energy Abstractss for Policy Analysis (EAPA). (DCK)

Towards technical interoperability in telemedicine.

Energy Technology Data Exchange (ETDEWEB)

Craft, Richard Layne, II

2004-05-01

For telemedicine to realize the vision of anywhere, anytime access to care, the question of how to create a fully interoperable technical infrastructure must be addressed. After briefly discussing how 'technical interoperability' compares with other types of interoperability being addressed in the telemedicine community today, this paper describes reasons for pursuing technical interoperability, presents a proposed framework for realizing technical interoperability, identifies key issues that will need to be addressed if technical interoperability is to be achieved, and suggests a course of action that the telemedicine community might follow to accomplish this goal.

Parliamentarian sovereignty and technical development

International Nuclear Information System (INIS)

Dreier, H.; Hofmann, J.

1986-01-01

The title indicates the points of main emphasis of the contributions, and points to the programme embodied in the volume. The question is - given the tremendous and ever increasing amount of secondary problems associated with a heated technology development - whether the 'sovereign' state is at all capable of controlling, piloting and fostering technic-scientific processes. The first part ('sovereignty and parliamentarian legislator state') concentrates on the history of notions and ideas in the concept of the sovereign, modern state, and on the constitutional law in force (Dreier, Frohn); the current efficiency of parliament as an organ of control in the process of legislation is investigated (Schulze-Fielitz). The central concern of part 2 ('environmental law and technical development') are topical questions of environmental law (Hofmann, Luebbe-Wolff). Besides the analysis of dogmatic problems of a special administrative law, the major issue is whether and in how far - given modern large-scale technologies - law can adequately govern technique (Schmidt). By analyzing the relationship between technical development and possibilities for guidance by a parliamentarian constitutional state, the articles deal with a central point of intersection between state and administrative law. (orig./HP) [de

Technical memory 2007

International Nuclear Information System (INIS)

2009-01-01

The technical memory 2007 of the Nuclear Regulatory Authority (ARN) of the Argentine Republic, compiles the papers published in the subject on radiation protection and nuclear safety, and presented in journals, technical reports, congress or meetings of these specialities by personnel of the mentioned institution during 2007. In this edition the documents are presented on: environmental protection; transport of radioactive materials; regulations; research reactors and nuclear power plants; biological radiation effects; therapeutic uses of ionizing radiation and radioprotection of patients; internal dosimetry; physical dosimetry; knowledge management; radioactive waste management [es

Technical support for GEIS: radioactive waste isolation in geologic formations. Volume 20. Thermo-mechanical stress analysis and development of thermal loading guidelines

International Nuclear Information System (INIS)

1978-04-01

This volume is one of a 23-volume series which supplements a Contribution to Draft Generic Environmental Impact Statement on Commercial Waste Management: Radioactive Waste Isolation in Geologic Formations, Y/OWI/TM-44. The series provides a more complete technical basis for the preconceptual designs, resource requirements, and environmental source terms associated with isolating commercial LWR wastes in underground repositories in salt, granite, shale and basalt. Wastes are considered from three fuel cycles: uranium and plutonium recycling, no recycling of spent fuel, and uranium-only recycling. The thermo-mechanical analysis of proposed preconceptual repositories in granite, shale and basalt have been undertaken. The analysis, was conducted on three different levels of scale (i) Very Near Field (canister scale), (ii) Near Field (excavation scale) and (iii) Far Field (regional scale) studies. Three numerical methods were used to undertake the thermo-mechanical calculations; namely, the finite element method for thermal stress analysis, the boundary element method for thermal and thermal stress analysis and the semi-analytical method also for thermal and thermal stresses analysis. From the thermo-mechanical studies with simplifying assumptions on rock mass behavior where applicable, recommendations for areal thermal loadings to assure retrievability of the canisters and long term safety of the repository are given

ARL Summer Student Research Symposium Volume I: Select Presentations

Science.gov (United States)

2017-06-01

papers to an audience of ARL scientists and engineers, including the ARL Director and an ARL Fellows panel. This volume of the Summer Student Symposium...program. As an integral part of their summer study, all students are required to write a paper on their work which summarizes their major activity and its...end product. The program is conducted on two separate competitive levels: undergraduate and graduate. The format of the paper in both levels is the

Analysis of concentrating PV-T systems for the commercial/industrial sector. Volume III. Technical issues and design guidance

Energy Technology Data Exchange (ETDEWEB)

Schwinkendorf, W.E.

1984-09-01

This report provide appropriate guidance for addressing the major technical issues associated with the design and installation of a photovoltaic-thermal (PV-T) system. Nomographs are presented for developing preliminary sizing and costing, and issues associated with specific components and the overall design of the electrical and mechanical system are discussed. SAND82-7157/2 presents a review of current PV-T technology and operating systems and a study of potential PV-T applications. Detailed PV-T system designs for three selected applications and the results of a trade-off study for these applications are presented in SAND82-7157/4. A summary of the major results of this entire study and conclusions concerning PV-T systems and applications is presented in SAND82-7157/1.

Writing a technical note.

Science.gov (United States)

Ng, K H; Peh, W C G

2010-02-01

A technical note is a short article giving a brief description of a specific development, technique or procedure, or it may describe a modification of an existing technique, procedure or device applicable to medicine. The technique, procedure or device described should have practical value and should contribute to clinical diagnosis or management. It could also present a software tool, or an experimental or computational method. Technical notes are variously referred to as technical innovations or technical developments. The main criteria for publication will be the novelty of concepts involved, the validity of the technique and its potential for clinical applications.

TPX: Contractor preliminary design review. Volume 1, Presentation and design description. Final report

International Nuclear Information System (INIS)

Hartman, D.; Naumovich; Walstrom, P.; Clarkson, I.; Schultheiss, J.; Burger, A.

1995-01-01

This first volume of the five volume set begins with a CPDR overview and then details the PF magnet system, manufacturing R ampersand D, Westinghouse R ampersand D, the central solenoid, the PF 5 ring coil, the PF 6/7 ring coil, quality assurance, and the system design description

Draft 1992 Resource Program : Technical Report.

Energy Technology Data Exchange (ETDEWEB)

United States. Bonneville Power Administration.

1992-01-01

The 1992 Resource Program will propose actions to meet future loads placed on the Bonneville Power Administration (BPA). It will also discuss and attempt to resolve resource-related policy issues. The Resource Program assesses resource availability and costs, and analyzes resource requirements and alternative ways of meeting those requirements through both conservation and generation resources. These general resource conclusions are then translated to actions for both conservation and generation. The Resource Program recommends budgets for the Office of Energy Resources for Fiscal Years (FY) 1994 and 1995. BPA's Resource Program bears directly on an important BPA responsibility: the obligation under the Northwest Power Act{sup 3} to meet the power requirements of public and private utility and direct service industrial (DSI) customers according to their contractual agreements. BPA's Draft 1992 Resource Program is contained in four documents: (1) 1992 Resource Program Summary; (2) Technical Report; (3) Technical Assumptions Appendix; and, (4) Conservation Implementation Plan. This volume is the Draft 1992 Resource Program Technical Report, a comprehensive document that provides supporting data and analyses for Resource Program recommendations.

Draft 1992 Resource Program : Technical Report.

Energy Technology Data Exchange (ETDEWEB)

United States. Bonneville Power Administration.

1992-01-01

The 1992 Resource Program will propose actions to meet future loads placed on the Bonneville Power Administration (BPA). It will also discuss and attempt to resolve resource-related policy issues. The Resource Program assesses resource availability and costs, and analyzes resource requirements and alternative ways of meeting those requirements through both conservation and generation resources. These general resource conclusions are then translated to actions for both conservation and generation. The Resource Program recommends budgets for the Office of Energy Resources for Fiscal Years (FY) 1994 and 1995. BPA`s Resource Program bears directly on an important BPA responsibility: the obligation under the Northwest Power Act{sup 3} to meet the power requirements of public and private utility and direct service industrial (DSI) customers according to their contractual agreements. BPA`s Draft 1992 Resource Program is contained in four documents: (1) 1992 Resource Program Summary; (2) Technical Report; (3) Technical Assumptions Appendix; and, (4) Conservation Implementation Plan. This volume is the Draft 1992 Resource Program Technical Report, a comprehensive document that provides supporting data and analyses for Resource Program recommendations.

Complex Liver Resections for Colorectal Metastases: Are They Safe in the Low-Volume, Resource-Poor Caribbean Setting?

Directory of Open Access Journals (Sweden)

Shamir O. Cawich

2015-01-01

Full Text Available Introduction. Although many authorities suggest that major liver resections should only be carried out in high-volume specialized centres, many patients in the Caribbean do not have access to these health care systems. Presentation of a Case. A 50-year-old woman with a solitary colorectal metastasis invading the inferior vena cava underwent an extended left hepatectomy with caval resection and reconstruction. Several technical maneuvers were utilized that were suited to the resource-poor environment. Conclusion. We suggest that good outcomes can still be attained in the resource-poor, low-volume centres once dedicated and appropriately trained teams are available.

Blood, blood compounds and cell cultures irradiation in clinical radiotherapy equipment: studies on ideal volume and dose

International Nuclear Information System (INIS)

Fernandes, Marco Antonio R.; Pereira, Adelino Jose; Novaes, Paulo Eduardo R.S.

1995-01-01

The authors present the technic and equipment used by the Physical Radiologic Service of Radiation Therapy Department of A.C. Camargo Hospital to irradiate blood and blood compounds. The practical routine is illustrated. The results from others Institutions are presented, discussing about the homogeneity of dose of 2000 to 3500 c Gy to all target volume, sufficient to neutralize cells responsible by graft-versus-host disease from blood transfusions. (author). 6 refs., 2 figs., 1 tab

IAEA Technical Meeting on Innovative Heat Exchanger and Steam Generator Designs for Fast Reactors. Presentations

International Nuclear Information System (INIS)

2011-01-01

The fast reactor, which can generate electricity and breed additional fissile material for future fuel stocks, is a resource that will be needed when economic uranium supplies for the thermal reactors diminish. Further, the fast-fission fuel cycle in which material is recycled (a basic requirement to meet sustainability criteria) offers the flexibility needed to contribute decisively towards solving the problem of growing “spent” fuel inventories by greatly reducing the volume, the heat load and the radiotoxic inventory of high-level wastes that must be disposed of in long-term geological repositories. This is a waste management option that will play an increasingly important role in the future, and help to ensure that nuclear energy remains a sustainable long-term option in the world’s overall energy mix. In recognition of the fast reactor’s importance for the sustainability of the nuclear option, currently there is worldwide renewed interest in fast reactor technology development, as indicated, e.g., by the outcome of the Generation IV International Forum (GIF) technology review, which concluded with 3 out of 6 innovative systems to be fast reactors (gas cooled fast reactor, sodium cooled fast reactor, and heavy liquid metal cooled fast reactor), plus a potential fast core for a 4th concept, the super-critical water reactor. Currently, fast reactor construction projects are ongoing in India (PFBR) and Russian Federation (BN-800), whilst in China the first experimental fast reactor (CEFR) is in the commissioning phase. Fast reactor programs are also carried out in Europe (in particular in France), Japan, Republic of Korea and the USA. The most important challenges for fast reactors are in the areas of cost competitiveness with respect to LWRs and other energy sources, enhanced safety, non-proliferation, and public acceptance. With the exception of this latter, these translate into technology development challenges, i.e. the development of advanced reactor

A Curriculum Activities Guide to Water Pollution and Environmental Studies, Volume II - Appendices.

Science.gov (United States)

Hershey, John T., Ed.; And Others

This publication, Volume II of a two volume set of water pollution studies, contains seven appendices which support the studies. Appendix 1, Water Quality Parameters, consolidates the technical aspects of water quality including chemical, biological, computer program, and equipment information. Appendix 2, Implementation, outlines techniques…

Technical Perspective on Using Information Demand Pattern in a Collaborative Recommendation System for Improving E-Mail Communication

Directory of Open Access Journals (Sweden)

Dirk Stamer

2015-04-01

Full Text Available Today e-mail communication information is widely used in organizations to distribute information. The increasing volume of received e-mails hinders an efficient work. It becomes more and more difficult to identify relevant e-mails inside this enormous volume of information. This work presents a solution in a multi-user environment by improving an established e-mail client extension based on information demand pattern with a recommendation system. The contributions of this work are (1 the concept and implementation of the solution for a single-user environment using information demand pattern, (2 the concept and architecture to use the solution in a multi-user environment (3 a detailed technical description about the proposed solutions.

Coal use in the People's Republic of China. Volume 1: Environmental impacts

International Nuclear Information System (INIS)

Bhatti, N.; Tompkins, M.M.; Simbeck, D.R.

1994-11-01

The People's Republic of China (hereafter referred to as China) is the largest producer and consumer of coal in the world. Coal makes up 76% and 74% of China's primary energy consumption and production, respectively. This heavy dependence on coal has come at a high price for China, accounting for a large share of its environmental problems. This report examines the dominance of coal in China's energy balance, its impact on the environment, and the need for technical and financial assistance, specifically for two distinct aspects: the effect of coal use on the environment and the importance of coal to China's economy. The results of the analysis are presented in two volumes. Volume 1 focuses on full fuel cycle coal emissions and the environmental effects of coal consumption. Volume 2 provides a detailed analysis by sector of China's economy and examines the economic impact of constraints on coal use. 51 refs., 19 figs., 15 tabs

Collected software engineering papers, volume 11

Science.gov (United States)

1993-01-01

This document is a collection of selected technical papers produced by participants in the Software Engineering Laboratory (SEL) from November 1992 through November 1993. The purpose of the document is to make available, in one reference, some results of SEL research that originally appeared in a number of different forums. This is the 11th such volume of technical papers produced by the SEL. Although these papers cover several topics related to software engineering, they do not encompass the entire scope of SEL activities and interests. Additional information about the SEL and its research efforts may be obtained from the sources listed in the bibliography at the end of this document.

Collected software engineering papers, volume 12

Science.gov (United States)

1994-01-01

This document is a collection of selected technical papers produced by participants in the Software Engineering Laboratory (SEL) from November 1993 through October 1994. The purpose of the document is to make available, in one reference, some results of SEL research that originally appeared in a number of different forums. This is the 12th such volume of technical papers produced by the SEL. Although these papers cover several topics related to software engineering, they do not encompass the entire scope of SEL activities and interests. Additional information about the SEL and its research efforts may be obtained from the sources listed in the bibliography at the end of this document.

Feasibility study for biomass power plants in Thailand. Volume 2. appendix: Detailed financial analysis results. Export trade information

International Nuclear Information System (INIS)

1997-01-01

This study, conducted by Black and Veatch, was funded by the U.S. Trade and Development Agency. The report presents a technical and commercial analysis for the development of three nearly identical electricity generating facilities (biomass steam power plants) in the towns of Chachgoengsao, Suphan Buri, and Pichit in Thailand. Volume 2 of the study contains the following appendix: Detailed Financial Analysis Results

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.

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.

Manhattan Project Technical Series: The Chemistry of Uranium (I)

International Nuclear Information System (INIS)

Rabinowitch, E. I.; Katz, J. J.

1947-01-01

This constitutes Chapters 11 through 16, inclusive, of the Survey Volume on Uranium Chemistry prepared for the Manhattan Project Technical Series. Chapters are titled: Uranium Oxides, Sulfides, Selenides, and Tellurides; The Non-Volatile Fluorides of Uranium; Uranium Hexafluoride; Uranium-Chlorine Compounds; Bromides, Iodides, and Pseudo-Halides of Uranium; and Oxyhalides of Uranium.

Manhattan Project Technical Series: The Chemistry of Uranium (I)

Energy Technology Data Exchange (ETDEWEB)

Rabinowitch, E. I. [Argonne National Lab. (ANL), Argonne, IL (United States); Katz, J. J. [Argonne National Lab. (ANL), Argonne, IL (United States)

1947-03-10

This constitutes Chapters 11 through 16, inclusive, of the Survey Volume on Uranium Chemistry prepared for the Manhattan Project Technical Series. Chapters are titled: Uranium Oxides, Sulfides, Selenides, and Tellurides; The Non-Volatile Fluorides of Uranium; Uranium Hexafluoride; Uranium-Chlorine Compounds; Bromides, Iodides, and Pseudo-Halides of Uranium; and Oxyhalides of Uranium.

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

Sparse PDF Volumes for Consistent Multi-Resolution Volume Rendering

KAUST Repository

Sicat, Ronell Barrera; Kruger, Jens; Moller, Torsten; Hadwiger, Markus

2014-01-01

This paper presents a new multi-resolution volume representation called sparse pdf volumes, which enables consistent multi-resolution volume rendering based on probability density functions (pdfs) of voxel neighborhoods. These pdfs are defined

Southwest Project: resource/institutional requirements analysis. Volume II. Technical studies

Energy Technology Data Exchange (ETDEWEB)

Ormsby, L. S.; Sawyer, T. G.; Brown, Dr., M. L.; Daviet, II, L. L.; Weber, E. R.; Brown, J. E.; Arlidge, J. W.; Novak, H. R.; Sanesi, Norman; Klaiman, H. C.; Spangenberg, Jr., D. T.; Groves, D. J.; Maddox, J. D.; Hayslip, R. M.; Ijams, G.; Lacy, R. G.; Montgomery, J.; Carito, J. A.; Ballance, J. W.; Bluemle, C. F.; Smith, D. N.; Wehrey, M. C.; Ladd, K. L.; Evans, Dr., S. K.; Guild, D. H.; Brodfeld, B.; Cleveland, J. A.; Hicks, K. L.; Noga, M. W.; Ross, A. M.

1979-12-01

The project provides information which could be used to accelerate the commercialization and market penetration of solar electric generation plants in the southwestern region of the United States. The area of concern includes Arizona, California, Colorado, Nevada, New Mexico, Utah, and sections of Oklahoma and Texas. The project evaluated the potential integration of solar electric generating facilities into the existing electric grids of the region through the year 2000. The technologies included wind energy conversion, solar thermal electric, solar photovoltaic conversion, and hybrid solar electric systems. Each of the technologies considered, except hybrid solar electric, was paired with a compatible energy storage system to improve plant performance and enhance applicability to a utility grid system. The hybrid concept utilizes a conventionally-fueled steam generator as well as a solar steam generator so it is not as dependent upon the availability of solar energy as are the other concepts. Operation of solar electric generating plants in conjunction with existing hydroelectric power facilities was also studied. The participants included 12 electric utility companies and a state power authority in the southwestern US, as well as a major consulting engineering firm. An assessment of the state-of-the-art of solar electric generating plants from an electric utility standpoint; identification of the electric utility industry's technical requirements and considerations for solar electric generating plants; estimation of the capital investment, operation, and maintenance costs for solar electric generating plants; and determination of the capital investment of conventional fossil and nuclear electric generating plants are presented. (MCW)

Broadband Data Converter Technical Presentation at CERN by e2v and ANATEC

CERN Multimedia

FI Department

2008-01-01

12 September 2008 10:00 – 11:45, Room B Main Building. Technical presentation e2v and ANATEC. e2v Grenoble (http://www.e2v.com) designs and manufactures standard and custom low latency and high speed ADCs that are true single core ADCs. Sampling speeds without interleaving range from 500MSPS to beyond 2.2GSPS with resolution ranging from 8 bits to 10bits and input bandwidths exceed 2.5GHz. With built-in interleaving feature some e2v multi-channel ADCs can reach 5GSPS sampling speed per device. e2v is known to offer 8, 10 and 12 bit ADCs with very low latency, exceptional linearity at high input frequency, that is in the 2nd Nyquist zone and beyond for some devices. This seminar will cover the following topics: Overview of existing standard 8bit, 10bit and 12bit ADCs up to 5GSPS. Key aspects of the e2v broadband ADC architecture. Benefits of true single core ADCs without internal interleaving. Choice of several possibilities to drive the ADC inputs, DC coupling at high spe...

Advanced Neutron Source enrichment study. Volume 2: Appendices -- Final report, Revision 12/94

International Nuclear Information System (INIS)

Bari, R.A.; Ludewig, H.; Weeks, J.

1994-01-01

A study has been performed of the impact on performance of using low enriched uranium (20% 235 U) or medium enriched uranium (35% 235 U) as an alternative fuel for the Advanced Neutron Source, which is currently designed to use uranium enriched to 93% 235 U. Higher fuel densities and larger volume cores were evaluated at the lower enrichments in terms of impact on neutron flux, safety, safeguards, technical feasibility, and cost. The feasibility of fabricating uranium silicide fuel at increasing material density was specifically addressed by a panel of international experts on research reactor fuels. The most viable alternative designs for the reactor at lower enrichments were identified and discussed. Several sensitivity analyses were performed to gain an understanding of the performance of the reactor at parametric values of power, fuel density, core volume, and enrichment that were interpolations between the boundary values imposed on the study or extrapolations from known technology. Volume 2 of this report contains 26 appendices containing results, meeting minutes, and fuel panel presentations. There are 26 appendices in this volume

Technical functions : a drawbridge between the intentional and structural nature of technical artefacts

NARCIS (Netherlands)

Vermaas, P.E.; Houkes, W.N.

2006-01-01

In this paper we present an action-theoretic account of artefact using and designing and describe our ICE-theory of function ascriptions to technical artefacts. By means of this account and theory we analyse the thesis of the dual nature of technical artefacts according to which descriptions of

TMX-U [Tandem Mirror Experiment-Upgrade]: Final report, Volume 2

International Nuclear Information System (INIS)

Porter, G.D.

1988-01-01

This paper discusses the plasma control and the physics accomplishments of the Tandem Mirror Experiment-Upgrade. This particular volume discusses fueling, ion heating, Fokker-Planck modeling, plasma stability and technical development. 270 refs

Load research manual. Volume 2. Fundamentals of implementing load research procedures

Energy Technology Data Exchange (ETDEWEB)

Brandenburg, L.; Clarkson, G.; Grund, Jr., C.; Leo, J.; Asbury, J.; Brandon-Brown, F.; Derderian, H.; Mueller, R.; Swaroop, R.

1980-11-01

This three-volume manual presents technical guidelines for electric utility load research. Special attention is given to issues raised by the load data reporting requirements of the Public Utility Regulatory Policies Act of 1978 and to problems faced by smaller utilities that are initiating load research programs. In Volumes 1 and 2, procedures are suggested for determining data requirements for load research, establishing the size and customer composition of a load survey sample, selecting and using equipment to record customer electricity usage, processing data tapes from the recording equipment, and analyzing the data. Statistical techniques used in customer sampling are discussed in detail. The costs of load research also are estimated, and ongoing load research programs at three utilities are described. The manual includes guides to load research literature and glossaries of load research and statistical terms.

Field convergence between technical writers and technical translators

DEFF Research Database (Denmark)

Gnecchi, M.; Maylath, B.; Mousten, Birthe

2011-01-01

As translation of technical documents continues to grow rapidly and translation becomes more automated, the roles of professional communicators and translators appear to be converging. This paper updates preliminary findings first presented at the 2008 International Professional Communication...

Standard technical specifications - Babcock and Wilcox Plants: Bases (Sections 2.0-3.3). Volume 2, Revision 1

International Nuclear Information System (INIS)

1995-04-01

This NUREG contains the improved Standard Technical Specifications (STS) for Babcock and Wilcox (B ampersand W) plants. Revision 1 incorporates the cumulative changes to Revision 0, which was published in September 1992. 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, specifically the B ampersand W Owners Group (BWOG), 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 (58 FR 39132). Licensees are encouraged to upgrade their technical specifications consistent with those criteria and conforming, to the extent practical and consistent with the licensing basis for the facility, to Revision 1 to the improved STS. The Commission continues to place the highest priority on requests for complete conversions to the improved STS. Licensees adopting portions of the improved STS to existing technical specifications should adopt all related requirements, as applicable, to achieve a high degree of standardization and consistency

Optimization of the convection volume in online post-dilution haemodiafiltration : practical and technical issues

NARCIS (Netherlands)

Chapdelaine, Isabelle; de Roij van Zuijdewijn, Camiel L M; Mostovaya, Ira M; Lévesque, Renée; Davenport, Andrew; Blankestijn, P J; Wanner, Christoph; Nubé, Menso J; Grooteman, Muriel P C; Davenport, A; Basile, C; Locatelli, F; Maduell, F; Mitra, S; Ronco, C; Shroff, R; Tattersall, J; Wanner, C

In post-dilution online haemodiafiltration (ol-HDF), a relationship has been demonstrated between the magnitude of the convection volume and survival. However, to achieve high convection volumes (>22 L per session) detailed notion of its determining factors is highly desirable. This manuscript

Probabilistic Structural Analysis Methods for select space propulsion system components (PSAM). Volume 3: Literature surveys and technical reports

Science.gov (United States)

1992-01-01

The technical effort and computer code developed during the first year are summarized. Several formulations for Probabilistic Finite Element Analysis (PFEA) are described with emphasis on the selected formulation. The strategies being implemented in the first-version computer code to perform linear, elastic PFEA is described. The results of a series of select Space Shuttle Main Engine (SSME) component surveys are presented. These results identify the critical components and provide the information necessary for probabilistic structural analysis.

Solid Waste Integrated Forecast Technical (SWIFT) Report FY 2001 to FY 2046 Volume 2

International Nuclear Information System (INIS)

BARCOT, R.A.

2001-01-01

The SWIFT Report provides up-to-date life cycle information about the radioactive solid waste expected to be managed by Hanford's Waste Management (WM) Project from onsite and offsite generators. This report is a mid-year update to the SWIFT 2001.0 report that was published in August 2000. The data contained in this report is the official data for solid waste forecasting until the SWIFT 2002.0 data is published in August 2001. This particular volume provides the following data reports: Annual volume data by waste generator; Summary volume data by location and DOE Office; Annual container type data by volume and count; and Annual physical waste form and waste specification record volume. This report also includes several minor changes from previous versions in an effort to increase the usability of the data and align with current Hanford Site organization changes. The changes include: Minor changes to waste generator names to make them more recognizable; Grouping of the waste generators into DOE Office and location (e.g, Office of River Protection, Fluor Hanford, Bechtel, etc); Addition of WSRd and Container Count sections; and Elimination of the ''functional group'' organization of the data (e.g., Facilities Transition, Spent Nuclear Fuel, etc)

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.

Alternative fuels for vehicles fleet demonstration program. Final report, volume 2: Appendices

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-06-01

The Alternative Fuels for Vehicles Fleet Demonstration Program (AFV-FDP) was a multiyear effort to collect technical data for use in determining the costs and benefits of alternative-fuel vehicles (AFVs) in typical applications in New York State. This report, Volume 2, includes 13 appendices to Volume 1 that expand upon issues raised therein. Volume 1 provides: (1) Information about the purpose and scope of the AFV-FDP; (2) A summary of AFV-FDP findings organized on the basis of vehicle type and fuel type; (3) A short review of the status of AFV technology development, including examples of companies in the State that are active in developing AFVs and AFV components; and (4) A brief overview of the status of AFV deployment in the State. Volume 3 provides expanded reporting of AFV-FDP technical details, including the complete texts of the brochure Garage Guidelines for Alternative Fuels and the technical report Fleet Experience Survey Report, plus an extensive glossary of AFV terminology. The appendices cover a wide range of issues including: emissions regulations in New York State; production and health effects of ozone; vehicle emissions and control systems; emissions from heavy-duty engines; reformulated gasoline; greenhouse gases; production and characteristics of alternative fuels; the Energy Policy Act of 1992; the Clean Fuel Fleet Program; garage design guidelines for alternative fuels; surveys of fleet managers using alternative fuels; taxes on conventional and alternative fuels; and zero-emission vehicle technology.

Forty-Fifth Annual Meeting of the Technical Working Group on Fast Reactors (TWG-FR). Presentations

International Nuclear Information System (INIS)

2012-01-01

The objectives of the meeting were to: • Exchange information on the national programmes on Fast Reactors (FR) and Accelerator Driven Systems (ADS); • Review the progress since the 44 th TWG-FR Annual Meeting, including the status of the actions; • Consider topical technical meeting arrangements for 2012-2013, as well as review FR-related activities included in the IAEA Programme & Budget (P&B) biennium 2012-2013; • Review the IAEA’s concluded, on-going and planned coordinated research projects in the technical fields relevant to the TWG-FR (FRs and ADS), as well as coordination of the TWG-FR’s activities with other organizations and international initiatives (GIF, INPRO, NEA, ESNII, etc.)

CALS Baseline Architecture Analysis of Weapons System. Technical Information: Army, Draft. Volume 8

Science.gov (United States)

1989-09-01

This effort was performed to provide a common framework for analysis and planning of CALS initiatives across the military services, leading eventually to the development of a common DoD-wide architecture for CALS. This study addresses Army technical ...

Centrifuge facilities at Technical University of Denmark

DEFF Research Database (Denmark)

Leth, Caspar Thrane; Krogsbøll, Anette Susanne; Hededal, Ole

2008-01-01

The geotechnical group at the Danish Technical University (DTU) operates a geotechnical beam centrifuge. The centrifuge was build in 1976 and has been upgraded through the years, latest with onboard data and control systems. The centrifuge concept involves an increased gravity field in which...... the physical model is placed and tested. The capabilities of the centrifuge at DTU makes it possible to obtain a scale factor of 75-85 in the tests which equals a soil volume in prototype scale of ø40m and a depth of 36 m. The centrifuge facilities at DTU have through the years been used for testing various...... geotechnical issues, such as suction anchors, tension piles in clay, active earth pressures on sheet piles and group effects for lateral loaded piles. The paper describes physical modelling in general, the centrifuge, present setups and shows samples of obtained results....

Technical progress in planning organization of the Ostravo-Karwina coal basin, ''Mining Projects of Ostravo''

Energy Technology Data Exchange (ETDEWEB)

Karpeta, B; Kolar, J

1979-01-01

Based on the main task of further improvement in labor productivity and improvement in the quality of products, the leading planning organization of the Ostravo-Karwina basin is planning and realizing progressive technological plans based on new equipment. Long-term plans for basin development up to 1990 stipulate a rise in capital investments by 180%, increase in the volume of productivity by 164% with a rise in the number of workers by 142%. Corresponding technical progress in planning is based on an improvement in the system of scientific-technical information, automation and technical equipping of the planning process, improvements in the forms and organizational structure. Organization of specialized research-planning groups to substantiate and to technically-economically evaluate technical progress, and also to develop comprehensive technical assignments is stipulated.

AREVA Technical Days (ATD) session 2: operations of the back-end of the nuclear fuel cycle

International Nuclear Information System (INIS)

2002-01-01

These technical days organized by the Areva Group aims to explain the group activities in a technological and economic point of view, to provide an outlook of worldwide energy trends and challenges and to present each of their businesses in a synthetic manner. This second session deals with the reprocessing business, back-end financing mechanisms, technology transfer, environmental management, risk management programs, research and development contribution to waste volume reductions, issues and outlook of nuclear wastes, comparison of the open and closed cycles. (A.L.B.)

Guidelines for the verification and validation of expert system software and conventional software: Bibliography. Volume 8

International Nuclear Information System (INIS)

Miller, L.A.; Hayes, J.E.; Mirsky, S.M.

1995-03-01

This volume contains all of the technical references found in Volumes 1-7 concerning the development of guidelines for the verification and validation of expert systems, knowledge-based systems, other AI systems, object-oriented systems, and conventional systems

Guidelines for the verification and validation of expert system software and conventional software: Bibliography. Volume 8

Energy Technology Data Exchange (ETDEWEB)

Miller, L.A.; Hayes, J.E.; Mirsky, S.M. [Science Applications International Corp., McLean, VA (United States)

1995-03-01

This volume contains all of the technical references found in Volumes 1-7 concerning the development of guidelines for the verification and validation of expert systems, knowledge-based systems, other AI systems, object-oriented systems, and conventional systems.

Measurement of absolute left ventricular volume by radionuclide angiography: a technical review

International Nuclear Information System (INIS)

Al-Khawaja, I.M.; Lahiri, Avijit; Raftery, E.B.; Medical Research Council, Harrow

1988-01-01

Absolute left ventricular volumes have important clinical implications in the evaluation of cardiac performance. Several invasive and noninvasive techniques have been reported, none of which can be considered ideal for this purpose. Contrast angiography, echocardiography and radionuclide ventriculography are open to criticism. Different radioisotopic approaches are described with emphasis on the importance of accurate separation of left ventricular activity, the selection of background activity, and the correction for photon attenuation by body tissues. Improper use of statistics and validation techniques have obscured the value of these techniques. In the absence of a 'gold standard' there should be a 'radioisotopic' left ventricular volume with established independent characteristics, repeatability and reproducibility by which new approaches can be judged. (author)

Head Start Impact Study. Technical Report

Science.gov (United States)

Puma, Michael; Bell, Stephen; Cook, Ronna; Heid, Camilla; Shapiro, Gary; Broene, Pam; Jenkins, Frank; Fletcher, Philip; Quinn, Liz; Friedman, Janet; Ciarico, Janet; Rohacek, Monica; Adams, Gina; Spier, Elizabeth

2010-01-01

This Technical Report is designed to provide technical detail to support the analysis and findings presented in the "Head Start Impact Study Final Report" (U.S. Department of Health and Human Services, January 2010). Chapter 1 provides an overview of the Head Start Impact Study and its findings. Chapter 2 provides technical information on the…

Influence of technical parameters on epicardial fat volume quantification at cardiac CT

International Nuclear Information System (INIS)

Bucher, Andreas M.; Joseph Schoepf, U.; Krazinski, Aleksander W.; Silverman, Justin; Spearman, James V.; De Cecco, Carlo N.; Meinel, Felix G.; Vogl, Thomas J.; Geyer, Lucas L.

2015-01-01

Highlights: • Upper threshold levels and contrast enhancement influence epicardial fat volumetry. • Cardiac cycle does not significantly influence epicardial fat volumetry. • Adjustments of upper threshold can lead to comparable volumetry results. - Abstract: Objectives: To systematically analyze the influence of technical parameters on quantification of epicardial fat volume (EATV) at cardiac CT. Methods: 153 routine cardiac CT data sets were analyzed using three-dimensional pericardial border delineation. Three image series were reconstructed per patient: (a) CTA D : coronary CT angiography (CTA), diastolic phase; (b) CTA S : coronary CTA, systolic phase; (c) CaSc D : non-contrast CT, diastolic phase. EATV was calculated using three different upper thresholds (−15HU, −30HU, −45HU). Repeated measures ANOVA, Spearman's rho, and Bland Altman plots were used. Results: Mean EATV differed between all three image series at a −30HU threshold (CTA D 87.2 ± 38.5 ml, CTA S 90.9 ± 37.7 ml, CaSc D 130.7 ± 49.5 ml, P < 0.001). EATV of diastolic and systolic CTA reconstructions did not differ significantly (P = 0.225). Mean EATV for contrast enhanced CTA at a −15HU threshold (CTA D15 102.4 ± 43.6 ml, CTA S15 105.3 ± 42.3 ml) could be approximated most closely by non-contrast CT at −45HU threshold (CaSc D45 105.3 ± 40.8 ml). The correlation was excellent: CTA S15 –CTA D15 , rho = 0.943; CTA D15 –CaSc D45 , rho = 0.905; CTA S15 –CaSc D45 , rho = 0.924; each P < 0.001). Bias values from Bland Altman Analysis were: CTA S15 –CTA D15 , 4.9%; CTA D15 –CaSc D45 , −4.3%; CTA S15 –CaSc D45 , 0.6%. Conclusions: Measured EATV can differ substantially between contrast enhanced and non-contrast CT studies, which can be reconciled by threshold modification. Heart cycle phase does not significantly influence EATV measurements

Influence of technical parameters on epicardial fat volume quantification at cardiac CT

Energy Technology Data Exchange (ETDEWEB)

Bucher, Andreas M. [Department of Radiology and Radiological Science, Medical University of South Carolina, Charleston, SC (United States); Department of Diagnostic and Interventional Radiology, Clinic of the Goethe University, Frankfurt (Germany); Joseph Schoepf, U., E-mail: schoepf@musc.edu [Department of Radiology and Radiological Science, Medical University of South Carolina, Charleston, SC (United States); Division of Cardiology, Department of Medicine, Medical University of South Carolina, Charleston, SC (United States); Krazinski, Aleksander W.; Silverman, Justin; Spearman, James V. [Department of Radiology and Radiological Science, Medical University of South Carolina, Charleston, SC (United States); De Cecco, Carlo N. [Department of Radiology and Radiological Science, Medical University of South Carolina, Charleston, SC (United States); Department of Radiological Sciences, Oncology and Pathology, University of Rome “Sapienza” – Polo Pontino, Latina (Italy); Meinel, Felix G. [Department of Radiology and Radiological Science, Medical University of South Carolina, Charleston, SC (United States); Institute for Clinical Radiology, Ludwig-Maximilians-University Hospital, Munich (Germany); Vogl, Thomas J. [Department of Diagnostic and Interventional Radiology, Clinic of the Goethe University, Frankfurt (Germany); Geyer, Lucas L. [Department of Radiology and Radiological Science, Medical University of South Carolina, Charleston, SC (United States); Institute for Clinical Radiology, Ludwig-Maximilians-University Hospital, Munich (Germany)

2015-06-15

Highlights: • Upper threshold levels and contrast enhancement influence epicardial fat volumetry. • Cardiac cycle does not significantly influence epicardial fat volumetry. • Adjustments of upper threshold can lead to comparable volumetry results. - Abstract: Objectives: To systematically analyze the influence of technical parameters on quantification of epicardial fat volume (EATV) at cardiac CT. Methods: 153 routine cardiac CT data sets were analyzed using three-dimensional pericardial border delineation. Three image series were reconstructed per patient: (a) CTA{sub D}: coronary CT angiography (CTA), diastolic phase; (b) CTA{sub S}: coronary CTA, systolic phase; (c) CaSc{sub D}: non-contrast CT, diastolic phase. EATV was calculated using three different upper thresholds (−15HU, −30HU, −45HU). Repeated measures ANOVA, Spearman's rho, and Bland Altman plots were used. Results: Mean EATV differed between all three image series at a −30HU threshold (CTA{sub D} 87.2 ± 38.5 ml, CTA{sub S} 90.9 ± 37.7 ml, CaSc{sub D} 130.7 ± 49.5 ml, P < 0.001). EATV of diastolic and systolic CTA reconstructions did not differ significantly (P = 0.225). Mean EATV for contrast enhanced CTA at a −15HU threshold (CTA{sub D15} 102.4 ± 43.6 ml, CTA{sub S15} 105.3 ± 42.3 ml) could be approximated most closely by non-contrast CT at −45HU threshold (CaSc{sub D45} 105.3 ± 40.8 ml). The correlation was excellent: CTA{sub S15}–CTA{sub D15}, rho = 0.943; CTA{sub D15}–CaSc{sub D45}, rho = 0.905; CTA{sub S15}–CaSc{sub D45}, rho = 0.924; each P < 0.001). Bias values from Bland Altman Analysis were: CTA{sub S15}–CTA{sub D15}, 4.9%; CTA{sub D15}–CaSc{sub D45}, −4.3%; CTA{sub S15}–CaSc{sub D45}, 0.6%. Conclusions: Measured EATV can differ substantially between contrast enhanced and non-contrast CT studies, which can be reconciled by threshold modification. Heart cycle phase does not significantly influence EATV measurements.

Technical support for the EPA cleanup rule on radioactively contaminated sites

Energy Technology Data Exchange (ETDEWEB)

Hull, H.B.; Newman, A.; Wolbarst, A.B. [Environmental Protection Agency, Washington, DC (United States)] [and others

1995-12-31

The U.S. Environmental Protection Agency (EPA) is developing a radiation site cleanup regulation for the protection of the public from radionuclide contamination at sites that are to be cleaned up and released for public use. The regulation will apply to sites under the control of Federal agencies, and to sites licensed by the Nuclear Regulatory Commission (NRC) or NRC Agreement States. The agency is therefore conducting a comprehensive technical analysis aimed at developing information that will be used to support the rule. This presentation describes the regulation and the approach developed to determine how radiological health impacts and volumes of soil requiring remediation vary as functions of the possible cleanup dose or risk level.

Subsurface contamination focus area technical requirements. Volume II

International Nuclear Information System (INIS)

Nickelson, D.; Nonte, J.; Richardson, J.

1996-10-01

This is our vision, a vision that replaces the ad hoc or open-quotes delphiclose quotes method which is to get a group of open-quotes expertsclose quotes together and make decisions based upon opinion. To fulfill our vision for the Subsurface Contaminants Focus Area (SCFA), it is necessary to generate technical requirements or performance measures which are quantitative or measurable. Decisions can be supported if they are based upon requirements or performance measures which can be traced to the origin (documented) and are verifiable, i.e., prove that requirements are satisfied by inspection (show me), demonstration, analysis, monitoring, or test. The data from which these requirements are derived must also reflect the characteristics of individual landfills or plumes so that technologies that meet these requirements will necessarily work at specific sites. Other subjective factors, such as stakeholder concerns, do influence decisions. Using the requirements as a basic approach, the SCFA can depend upon objective criteria to help influence the areas of subjectivity, like the stakeholders. In the past, traceable requirements were not generated, probably because it seemed too difficult to do so. There are risks that the requirements approach will not be accepted because it is new and represents a departure from the historical paradigm

Subsurface contamination focus area technical requirements. Volume II

Energy Technology Data Exchange (ETDEWEB)

Nickelson, D.; Nonte, J.; Richardson, J.

1996-10-01

This is our vision, a vision that replaces the ad hoc or {open_quotes}delphi{close_quotes} method which is to get a group of {open_quotes}experts{close_quotes} together and make decisions based upon opinion. To fulfill our vision for the Subsurface Contaminants Focus Area (SCFA), it is necessary to generate technical requirements or performance measures which are quantitative or measurable. Decisions can be supported if they are based upon requirements or performance measures which can be traced to the origin (documented) and are verifiable, i.e., prove that requirements are satisfied by inspection (show me), demonstration, analysis, monitoring, or test. The data from which these requirements are derived must also reflect the characteristics of individual landfills or plumes so that technologies that meet these requirements will necessarily work at specific sites. Other subjective factors, such as stakeholder concerns, do influence decisions. Using the requirements as a basic approach, the SCFA can depend upon objective criteria to help influence the areas of subjectivity, like the stakeholders. In the past, traceable requirements were not generated, probably because it seemed too difficult to do so. There are risks that the requirements approach will not be accepted because it is new and represents a departure from the historical paradigm.

Viability Assessment of a Repository at Yucca Mountain. Volume 4: License Application Plan and Costs

Energy Technology Data Exchange (ETDEWEB)

None

1998-12-01

defensible LA. Volume 4 is divided into seven sections. Section 2 presents a rationale and summary for the technical work to be done to develop the preclosure and postclosure safety cases that will support the compliance evaluations required for the evaluation of site suitability and for licensing. Section 2 also describes other necessary technical work, including that needed to support design decisions and development of the necessary design information. Section 3 presents a more detailed description of the technical work required to address the issues identified in Section 2. Section 3 also describes activities that will continue after submittal of the site recommendation and the LA. Examples include the drift scale heater test in the Exploratory Studies Facility (Section 3.1.4.3) and long-term waste package corrosion testing (Section 3.2.2.9). Section 4 discusses the statutory and regulatory framework for site recommendation and submittal of an LA, and describes the activities and documentation that must be completed to achieve these milestones, including the development of an EIS. Section 5 describes the numerous activities required to support program milestones, including support for completing the testing program, continuing tests as part of the performance confirmation program, and managing information and records to support regulatory and legal review. Sections 6 and 7 provide cost and schedule information for the activities planned.

Research program for seismic qualification of nuclear plant electrical and mechanical equipment. Task 3. Recommendations for improvement of equipment qualification methodology and criteria. Volume 3

International Nuclear Information System (INIS)

Kana, D.D.; Pomerening, D.J.

1984-08-01

The Research Program for Seismic Qualification of Nuclear Plant Electrical and Mechanical Equipment has spanned a period of three years and resulted in seven technical summary reports, each of which covered in detail the findings of different tasks and subtasks, and have been combined into five NUREG/CR volumes. Volume 3 presents recommendations for improvement of equipment qualification methodology and procedural clarification/modification. The fifth category identifies issues where adequate information does not exist to allow a recommendation to be made

1991 Pacific Northwest Loads and Resources Study, Technical Appendix: Volume 1.

Energy Technology Data Exchange (ETDEWEB)

United States. Bonneville Power Administration.

1992-03-01

This publication provides detailed documentation of the load forecast scenarios and assumptions used in preparing BPA's 1991 Pacific Northwest Loads and Resources Study (the Study). This is one of two technical appendices to the Study; the other appendix details the utility-specific loads and resources used in the Study. The load forecasts and assumption were developed jointly by Bonneville Power Administration (BPA) and Northwest Power Planning Council (Council) staff. This forecast is also used in the Council's 1991 Northwest Conservation and Electric Power Plan (1991 Plan).

Recreational technical diving part 1: an introduction to technical diving methods and activities.

Science.gov (United States)

Mitchell, Simon J; Doolette, David J

2013-06-01

Technical divers use gases other than air and advanced equipment configurations to conduct dives that are deeper and/or longer than typical recreational air dives. The use of oxygen-nitrogen (nitrox) mixes with oxygen fractions higher than air results in longer no-decompression limits for shallow diving, and faster decompression from deeper dives. For depths beyond the air-diving range, technical divers mix helium, a light non-narcotic gas, with nitrogen and oxygen to produce 'trimix'. These blends are tailored to the depth of intended use with a fraction of oxygen calculated to produce an inspired oxygen partial pressure unlikely to cause cerebral oxygen toxicity and a nitrogen fraction calculated to produce a tolerable degree of nitrogen narcosis. A typical deep technical dive will involve the use of trimix at the target depth with changes to gases containing more oxygen and less inert gas during the decompression. Open-circuit scuba may be used to carry and utilise such gases, but this is very wasteful of expensive helium. There is increasing use of closed-circuit 'rebreather' devices. These recycle expired gas and potentially limit gas consumption to a small amount of inert gas to maintain the volume of the breathing circuit during descent and the amount of oxygen metabolised by the diver. This paper reviews the basic approach to planning and execution of dives using these methods to better inform physicians of the physical demands and risks.

Preliminary evaluation of alternative waste form solidification processes. Volume II. Evaluation of the processes

International Nuclear Information System (INIS)

1980-08-01

This Volume II presents engineering feasibility evaluations of the eleven processes for solidification of nuclear high-level liquid wastes (HHLW) described in Volume I of this report. Each evaluation was based in a systematic assessment of the process in respect to six principal evaluation criteria: complexity of process; state of development; safety; process requirements; development work required; and facility requirements. The principal criteria were further subdivided into a total of 22 subcriteria, each of which was assigned a weight. Each process was then assigned a figure of merit, on a scale of 1 to 10, for each of the subcriteria. A total rating was obtained for each process by summing the products of the subcriteria ratings and the subcriteria weights. The evaluations were based on the process descriptions presented in Volume I of this report, supplemented by information obtained from the literature, including publications by the originators of the various processes. Waste form properties were, in general, not evaluated. This document describes the approach which was taken, the developent and application of the rating criteria and subcriteria, and the evaluation results. A series of appendices set forth summary descriptions of the processes and the ratings, together with the complete numerical ratings assigned; two appendices present further technical details on the rating process

Mechanical Engineering Department Technical Review

International Nuclear Information System (INIS)

Carr, R.B.; Denney, R.M.

1981-01-01

The Mechanical Engineering Department Technical Review is published to inform readers of various technical activities within the Department, promote exchange of ideas, and give credit to personnel who are achieving the results. The report is presented in two parts: technical achievements and publication abstracts. The first is divided into seven sections, each of which reports on an engineering division and its specific activities related to nuclear tests, nuclear explosives, weapons, energy systems, engineering sciences, magnetic fusion, and materials fabrication

Technical Education and Economic Growth

Indian Academy of Sciences (India)

First page Back Continue Last page Graphics. Technical Education and Economic Growth. Technical Education and Economic Growth. Review of the Present Status. Expanding no.s and impairment of quality; Faculty shortage; Grim situation at Masters and PhD levels; Regional imbalance; Absence of International flavour ...

SOLID WASTE INTEGRATED FORECAST TECHNICAL (SWIFT) REPORT FY2005 THRU FY2035 VERSION 2005.0 VOLUME 1

Energy Technology Data Exchange (ETDEWEB)

BARCOT, R.A.

2005-04-13

The SWIFT Report provides up-to-date life cycle information about the radioactive solid waste expected to be managed by Hanford's Waste Management (WM) Project from onsite and offsite generators. This report is an annual update to the SWIFT 2004.1 report that was published in August 2004. The SWIFT Report is published in two volumes. SWIFT Volume II provides detailed analyses of the data, graphical representation, comparison to previous years, and waste generator specific information. The data contained in this report are the official data for solid waste forecasting. In this revision, the volume numbers have been switched to reflect the timing of their release. This particular volume provides the following data reports: (1) Summary volume data by DOE Office, company, and location; (2) Annual volume data by waste generator; (3) Annual waste specification record and physical waste form volume; (4) Radionuclide activities and dose-equivalent curies; and (5) Annual container type data by volume and count.

SOLID WASTE INTEGRATED FORECAST TECHNICAL (SWIFT) REPORT FY2005 THRU FY2035 VERSION 2005.0 VOLUME 1

International Nuclear Information System (INIS)

BARCOT, R.A.

2005-01-01

The SWIFT Report provides up-to-date life cycle information about the radioactive solid waste expected to be managed by Hanford's Waste Management (WM) Project from onsite and offsite generators. This report is an annual update to the SWIFT 2004.1 report that was published in August 2004. The SWIFT Report is published in two volumes. SWIFT Volume II provides detailed analyses of the data, graphical representation, comparison to previous years, and waste generator specific information. The data contained in this report are the official data for solid waste forecasting. In this revision, the volume numbers have been switched to reflect the timing of their release. This particular volume provides the following data reports: (1) Summary volume data by DOE Office, company, and location; (2) Annual volume data by waste generator; (3) Annual waste specification record and physical waste form volume; (4) Radionuclide activities and dose-equivalent curies; and (5) Annual container type data by volume and count

Renewable Resources: a national catalog of model projects. Volume 3. Southern Solar Energy Center Region

Energy Technology Data Exchange (ETDEWEB)

None

1980-07-01

This compilation of diverse conservation and renewable energy projects across the United States was prepared through the enthusiastic participation of solar and alternate energy groups from every state and region. Compiled and edited by the Center for Renewable Resources, these projects reflect many levels of innovation and technical expertise. In many cases, a critique analysis is presented of how projects performed and of the institutional conditions associated with their success or failure. Some 2000 projects are included in this compilation; most have worked, some have not. Information about all is presented to aid learning from these experiences. The four volumes in this set are arranged in state sections by geographic region, coinciding with the four Regional Solar Energy Centers. The table of contents is organized by project category so that maximum cross-referencing may be obtained. This volume includes information on the Southern Solar Energy Center Region. (WHK)

Renewable Resources: a national catalog of model projects. Volume 1. Northeast Solar Energy Center Region

Energy Technology Data Exchange (ETDEWEB)

None

1980-07-01

This compilation of diverse conservation and renewable energy projects across the United States was prepared through the enthusiastic participation of solar and alternate energy groups from every state and region. Compiled and edited by the Center for Renewable Resources, these projects reflect many levels of innovation and technical expertise. In many cases, a critique analysis is presented of how projects performed and of the institutional conditions associated with their success or failure. Some 2000 projects are included in this compilation; most have worked, some have not. Information about all is presented to aid learning from these experiences. The four volumes in this set are arranged in state sections by geographic region, coinciding with the four Regional Solar Energy Centers. The table of contents is organized by project category so that maximum cross-referencing may be obtained. This volume includes information on the Northeast Solar Energy Center Region. (WHK).

Renewable Resources: a national catalog of model projects. Volume 4. Western Solar Utilization Network Region

Energy Technology Data Exchange (ETDEWEB)

None

1980-07-01

This compilation of diverse conservation and renewable energy projects across the United States was prepared through the enthusiastic participation of solar and alternate energy groups from every state and region. Compiled and edited by the Center for Renewable Resources, these projects reflect many levels of innovation and technical expertise. In many cases, a critique analysis is presented of how projects performed and of the institutional conditions associated with their success or failure. Some 2000 projects are included in this compilation; most have worked, some have not. Information about all is presented to aid learning from these experiences. The four volumes in this set are arranged in state sections by geographic region, coinciding with the four Regional Solar Energy Centers. The table of contents is organized by project category so that maximum cross-referencing may be obtained. This volume includes information on the Western Solar Utilization Network Region. (WHK)

Research program for seismic qualification of nuclear plant electrical and mechanical equipment. Task 4. Use of fragility in seismic design of nuclear plant equipment. Volume 4

International Nuclear Information System (INIS)

Kana, D.D.; Pomerening, D.J.

1984-08-01

The Research Program for Seismic Qualification of Nuclear Plant Electrical and Mechanical Equipment has spanned a period of three years and resulted in seven technical summary reports, each of which have covered in detail the findings of different tasks and subtasks, and have been combined into five NUREG/CR volumes. Volume 4 presents study of the use of fragility concepts in the design of nuclear plant equipment and compares the results of state-of-the-art proof testing with fragility testing

The story of technical cooperation

International Nuclear Information System (INIS)

Park, Yang Taek

1989-09-01

This book gives descriptions of technical cooperation, which is about why does technology transfer?, process of technology transfer with model, decisive cause and cooperation of technology transfer, cost and effect of technology transfer, historical experience of technology transfer, cases of technology transfer by field such as rubber tire, medicine and computer industry and automobile industry, technology transfer process and present condition of technical cooperation, and strategy for rising of technical cooperation : selection of technology for object of cooperation and development of human resources.

Technical Support and Transfer of Geothrmal Technical Knowledge and Information

Energy Technology Data Exchange (ETDEWEB)

John W. Lund; Toni" Boyd

2007-11-14

The Geo-Heat Center (GHC) staff provided responses to 1442 technical support requests during the contract period (April 1, 2006 to September 30, 2007), which were six quarters under this contract. Our website, consisting of 1900 files, also contributes to our technical assistance activity. Downloaded files were 1,889,323 (3,448 per day) from our website, the total number of users was 1,365,258 (2,491 per day), and the total number of hits were 6,008,500 (10,064 per day). The GHC staff attended 60 workshops, short course and professional meeting and made 29 technical presentations. The staff also prepared and mailed out 2,000 copies of each of five issues of the GHC Quaterly Bulletin which contained 26 articles. We also mailed out approximately 5,000 papers and publications to interested individuals and organizations.

Advanced transportation system studies technical area 3: Alternate propulsion subsystem concepts, volume 2

Science.gov (United States)

Levak, Daniel

1993-01-01

The Alternate Propulsion Subsystem Concepts contract had five tasks defined for the first year. The tasks were: F-1A Restart Study, J-2S Restart Study, Propulsion Database Development, Space Shuttle Main Engine (SSME) Upper Stage Use, and CER's for Liquid Propellant Rocket Engines. The detailed study results, with the data to support the conclusions from various analyses, are being reported as a series of five separate Final Task Reports. Consequently, this volume only reports the required programmatic information concerning Computer Aided Design Documentation, and New Technology Reports. A detailed Executive Summary, covering all the tasks, is also available as Volume 1.

Briefing Products - Tools for Communicating Technical Issues to a Non-Technical Audience

International Nuclear Information System (INIS)

Clark, Harvey; Foster, Kevin T.

2011-01-01

Briefing Products are a new NARAC/IMAAC product line designed to communicate the consequences of a radiological, nuclear, chemical or biological agent incident to non-technical decision makers and key leaders. Each Briefing Product addresses a single decision or issue focused on potential actions that should be considered when responding to a hazard, while avoiding the use of technical or regulatory jargon. Briefing Products do not make protective action recommendations, although they do concretely assist decision-makers with development of their own protective actions by quoting or paraphrasing the published guidance relevant to the decision at hand. Briefing Products are produced in sets tailored to specific types of incident which together depict the key decisions and characteristics of the incident. Each Briefing Product in the set consists of three elements: (1) Primary Effects, (2) Key Points and (3) Presenter Notes. Both the Primary Effects and Key Points are ready for direct presentation, while the Presenter Notes are designed to provide background information to the presenter and are not for direct presentation to the audience. The Briefing Products themselves are alternative presentations of results from the customary standard NARAC/IMAAC technical products. Currently, Briefing Products are available for detonation of both RDDs (Radiological Dispersal Devices) and INDs (Improvised Nuclear Devices). A new set of products tailored to nuclear power plant (NPP) accidents is currently under development. This paper describes the scope, structure and content of the Briefing Product sets. Examples from the two sets of Briefing Products now available are presented.

Turnaround operations analysis for OTV. Volume 2: Detailed technical report

Science.gov (United States)

1988-01-01

The objectives and accomplishments were to adapt and apply the newly created database of Shuttle/Centaur ground operations. Previously defined turnaround operations analyses were to be updated for ground-based OTVs (GBOTVs) and space-based OTVs (SBOTVs), design requirements identified for both OTV and Space Station accommodations hardware, turnaround operations costs estimated, and a technology development plan generated to develop the required capabilities. Technical and programmatic data were provided for NASA pertinent to OTV round and space operations requirements, turnaround operations, task descriptions, timelines and manpower requirements, OTV modular design and booster and Space Station interface requirements. SBOTV accommodations development schedule, cost and turnaround operations requirements, and a technology development plan for ground and space operations and space-based accommodations facilities and support equipment. Significant conclusion are discussed.

The sixth international congress on toxic combustion byproducts. Technical program and abstract book

Energy Technology Data Exchange (ETDEWEB)

NONE

1999-07-01

Topics of this proceedings volume are: technical approaches - waste treatment; general toxicology of combustion byproducts; reaction mechanisms (e.g. formation and decomposition of hydrocarbons and chlorinated hydrocarbons, nitrogen oxides); thermal treatment - reactionas at low temperatures; heterogeneous reactions - heterogeneous systems. (SR)

North American Natural Gas Markets: Selected technical studies

International Nuclear Information System (INIS)

Huntington, H.G.; Schuler, G.E.

1989-04-01

The Energy Modeling Forum (EMF) was established in 1976 at Stanford University to provide a structural framework within which energy experts, analysts, and policymakers could meet to improve their understanding of critical energy problems. The ninth EMF study, North American Natural Gas Markets, was conducted by a working group comprised of leading natural gas analysts and decision-makers from government, private companies, universities, and research and consulting organizations. The EMF 9 working group met five times from October 1986 through June 1988 to discuss key issues and analyze natural gas markets. This third volume includes technical papers that support many of the conclusions discussed in the EMF 9 summary report (Volume 1) and full working group report (Volume 2). These papers discuss the results from the individual models as well as some nonmodeling analysis related to US natural gas imports and industrial natural gas demand. Individual papers have been processed separately for inclusion in the Energy Science and Technology Database

North American Natural Gas Markets: Selected technical studies

Energy Technology Data Exchange (ETDEWEB)

Huntington, H.G.; Schuler, G.E. (eds.)

1989-04-01

The Energy Modeling Forum (EMF) was established in 1976 at Stanford University to provide a structural framework within which energy experts, analysts, and policymakers could meet to improve their understanding of critical energy problems. The ninth EMF study, North American Natural Gas Markets, was conducted by a working group comprised of leading natural gas analysts and decision-makers from government, private companies, universities, and research and consulting organizations. The EMF 9 working group met five times from October 1986 through June 1988 to discuss key issues and analyze natural gas markets. This third volume includes technical papers that support many of the conclusions discussed in the EMF 9 summary report (Volume 1) and full working group report (Volume 2). These papers discuss the results from the individual models as well as some nonmodeling analysis related to US natural gas imports and industrial natural gas demand. Individual papers have been processed separately for inclusion in the Energy Science and Technology Database.

Spent Fuel Test-Climax: technical measurements data management system description and data presentation

International Nuclear Information System (INIS)

Carlson, R.C.

1985-08-01

The Spent Fuel Test-Climax (SFT-C) was located 420 m below surface in the Climax Stock granite on the Nevada Test Site. The test was conducted under the technical direction of the Lawrence Livermore National Laboratory (LLNL) as part of the Nevada Nuclear Waste Storage Investigations (NNWSI) for the US Department of Energy. Eleven canisters of spent nuclear reactor fuel were emplaced, along with six electrical simulators, in April-May 1980. The spent fuel canisters were retrieved and the electrical simulators de-energized in March-April 1983. During the test, just over 1000 MW-hr of thermal energy was deposited in the site, causing temperature changes 100 0 C near the canisters, and about 5 0 in the tunnels. More than 900 channels of geotechnical, seismological, and test status data were recorded on nearly continuous basis for about 3-1/2 years, ending in September 1983. Most geotechnical instrumentation was known to be temperature sensitive, and thus would require temperature compensation before interpretation. Accordingly, a 10-in. reel of digital tape was off-loaded and shipped to Livermore every 4 to 8 weeks, where the data were verified, organized into 45 one-million-word files, and temperature corrected. The purpose of this report is to document the receipt and processing of the data by LLNL Livermore personnel, present facts about the history of the instruments which may be important to the interpretation of the data, present the data themselves in graphical form for each instrument over its operating lifetime, document the forms and locations in which the data will be archived, and offer the data to the geotechnical community for future use in understanding and predicting the effects of the storage of heat-generating waste in hard rocks such as granite

NetView technical research

Science.gov (United States)

1993-01-01

This is the Final Technical Report for the NetView Technical Research task. This report is prepared in accordance with Contract Data Requirements List (CDRL) item A002. NetView assistance was provided and details are presented under the following headings: NetView Management Systems (NMS) project tasks; WBAFB IBM 3090; WPAFB AMDAHL; WPAFB IBM 3084; Hill AFB; McClellan AFB AMDAHL; McClellan AFB IBM 3090; and Warner-Robins AFB.

Paul Scherrer Institute Scientific and Technical Report 2000. Volume VI: Large Research Facilities

International Nuclear Information System (INIS)

Foroughi, Fereydoun; Bercher, Renate; Buechli, Carmen; Zumkeller, Lotty

2001-01-01

The PSI Department Large Research Facilities (GFA) joins the efforts to provide an excellent research environment to Swiss and foreign research groups on the experimental facilities driven by our high intensity proton accelerator complex. Its divisions care for the running, maintenance and enhancement of the accelerator complex, the primary proton beamlines, the targets and the secondary beams as well as the neutron spallation source SINQ. The division for technical support and coordination provides for technical support to the research facility complementary to the basic logistic available from the department for logistics and marketing. Besides running the facilities, the staff of the department is also involved in theoretical and experimental research projects. Some of them address basic scientific questions mainly concerning the properties of micro- or nanostructured materials: experiments as well as large scale computer simulations of molecular dynamics were performed to investigate nonclassical materials properties. Others are related to improvements or extensions of the capabilities of our facilities. We also report on intriguing results from applications of the neutron capture radiography, the prompt gamma activation method and the isotope production facility at SINQ

Paul Scherrer Institute Scientific and Technical Report 2000. Volume VI: Large Research Facilities

Energy Technology Data Exchange (ETDEWEB)

Foroughi, Fereydoun; Bercher, Renate; Buechli, Carmen; Zumkeller, Lotty [eds.

2001-07-01

The PSI Department Large Research Facilities (GFA) joins the efforts to provide an excellent research environment to Swiss and foreign research groups on the experimental facilities driven by our high intensity proton accelerator complex. Its divisions care for the running, maintenance and enhancement of the accelerator complex, the primary proton beamlines, the targets and the secondary beams as well as the neutron spallation source SINQ. The division for technical support and coordination provides for technical support to the research facility complementary to the basic logistic available from the department for logistics and marketing. Besides running the facilities, the staff of the department is also involved in theoretical and experimental research projects. Some of them address basic scientific questions mainly concerning the properties of micro- or nanostructured materials: experiments as well as large scale computer simulations of molecular dynamics were performed to investigate nonclassical materials properties. Others are related to improvements or extensions of the capabilities of our facilities. We also report on intriguing results from applications of the neutron capture radiography, the prompt gamma activation method and the isotope production facility at SINQ.

Renewable Resources: a national catalog of model projects. Volume 2. Mid-American Solar Energy Complex Region

Energy Technology Data Exchange (ETDEWEB)

None

1980-07-01

This compilation of diverse conservation and renewable energy projects across the United States was prepared through the enthusiastic participation of solar and alternate energy groups from every state and region. Compiled and edited by the Center for Renewable Resources, these projects reflect many levels of innovation and technical expertise. In many cases, a critique analysis is presented of how projects performed and of the institutional conditions associated with their success or failure. Some 2000 projects are included in this compilation; most have worked, some have not. Information about all is presented to aid learning from these experiences. The four volumes in this set are arranged in state sections by geographic region, coinciding with the four Regional Solar Energy Centers. The table of contents is organized by project category so that maximum cross-referencing may be obtained. This volume includes information on the Mid-American Solar Energy Complex Region. (WHK)

Fort Stewart integrated resource assessment. Volume 3: Resource assessment

Energy Technology Data Exchange (ETDEWEB)

Sullivan, G.P.; Keller, J.M.; Stucky, D.J.; Wahlstrom, R.R.; Larson, L.L.

1993-10-01

The US Army Forces Command (FORSCOM) has tasked the US Department of Energy (DOE) Federal Energy Management Program (FEMP), supported by the Pacific Northwest Laboratory, to identify, evaluate, and assist in acquiring all cost-effective energy projects at Fort Stewart. This is part of a model program that PNL is designing to support energy-use decisions in the federal sector. This report provides the results of the fossil fuel and electric energy resource opportunity (ERO) assessments performed by PNL at the FORSCOM Fort Stewart facility located approximately 25 miles southwest of Savannah, Georgia. It is a companion report to Volume 1, Executive Summary, and Volume 2, Baseline Detail. The results of the analyses of EROs are presented in 11 common energy end-use categories (e.g., boilers and furnaces, service hot water, and building lighting). A narrative description of each ERO is provided, along with a table detailing information on the installed cost, energy and dollar savings; impacts on operations and maintenance (O&M); and, when applicable, a discussion of energy supply and demand, energy security, and environmental issues. A description of the evaluation methodologies and technical and cost assumptions is also provided for each ERO. Summary tables present the cost-effectiveness of energy end-use equipment before and after the implementation of each ERO. The tables also present the results of the life-cycle cost (LCC) analysis indicating the net present value (NPV) and savings to investment ratio (SIR) of each ERO.

THE USE OF DYNAMIC MODELS OF CAR TRAFFIC VOLUME PROMOTION IN TECHNICAL REGULATION

Directory of Open Access Journals (Sweden)

V. H. Kuznetsov

2007-08-01

Full Text Available Modern lines in the field of transport management are directed on transition from analytical systems of processing of information to the information-operating systems providing support of decision-making in management by transportations. New conditions of managing, on the one hand, and development of the automated systems of gathering and processing of information in transport industry, on the other hand, allows to reach essentially new level of planning the parameters of transport operation with development of new methodology of solution of the given problems. The creation of dynamic model of promotion of traffic volumes is one of the new methods that allows solving a number of operational problems.. In the paper the mathematical description of range of a network and dynamic model is given. The concept of individual transportation is presented, classification of dynamic models depending on the initial information is given. Mathematical study and algorithm of construction of dynamic models enables their applications for solution of wide range of problems on transport.

Greater-than-Class C low-level waste characterization technical review process

Energy Technology Data Exchange (ETDEWEB)

Hutchison, D.; Magleby, M.

1990-01-01

Existing volume projections of greater-than-Class C low-level waste (GTCC LLW) vary significantly. The Department of Energy (DOE) National Low-Level Waste Management Program (NLLWMP) has undertaken activities to develop a best estimate of GTCC LLW volumes and activities for use as the planning basis. Initial information about the generation of GTCC LLW was obtained through a DOE Energy Information Administration survey. That information, combined with information from other related literature, formed the basis of a computer model, which projects potential GTCC LLW. This paper describes uncertainties in existing GTCC LLW characterization and volume projections data and describes the technical review process that is being used to assist in projections of GTCC LLW expected for storage and disposal. 8 refs., 2 tabs.

Greater-than-Class C low-level waste characterization technical review process

International Nuclear Information System (INIS)

Hutchison, D.; Magleby, M.

1990-01-01

Existing volume projections of greater-than-Class C low-level waste (GTCC LLW) vary significantly. The Department of Energy (DOE) National Low-Level Waste Management Program (NLLWMP) has undertaken activities to develop a best estimate of GTCC LLW volumes and activities for use as the planning basis. Initial information about the generation of GTCC LLW was obtained through a DOE Energy Information Administration survey. That information, combined with information from other related literature, formed the basis of a computer model, which projects potential GTCC LLW. This paper describes uncertainties in existing GTCC LLW characterization and volume projections data and describes the technical review process that is being used to assist in projections of GTCC LLW expected for storage and disposal. 8 refs., 2 tabs

Report on the present day situation and technical perspectives of renewable energies; Rapport sur l'etat actuel et les perspectives techniques des energies renouvelables

Energy Technology Data Exchange (ETDEWEB)

Birraux, C; Le Deaut, J Y

2001-11-01

This work, carried out by the parliamentary office for the evaluation of scientific and technological choices on request of the French National Assembly and Senate, takes stock of the present day situation and technical perspectives of development of renewable energy sources and of research needs of the French industry in this domain: 1 - renewable energies: key-technologies for the energy supply of developing countries and for a rational consumption in transportation systems and accommodations of developed countries (energies technically different from fossil or nuclear energies; fundamental energy sources for a developing world; different national goals in Europe depending on the available natural resources and on the political realities; a minor interest in France for the domestic power generation but a major interest for transports, residential and tertiary sectors and export); 2 - priority choices given to the French renewable energy resources: renewable electricity (photovoltaic, wind, biomass), thermal technologies (solar, geothermal, biomass); 3 - future policy: sustain of renewable electricity production with the revival of research, industry and technical cooperation. (J.S.)

The effect of patient position and field configuration on lung volume in the treatment of advanced carcinoma of the breast or lung volumes in breast techniques - a case study

International Nuclear Information System (INIS)

Floyd, J.L.

1989-01-01

The position of the patient together with the configuration of the treatment fields play an important role in the volume of lung irradiated in breast techniques. These factors are even more important when the staging of the disease is advanced. A comparison of lung volumes is made with the patient in three treatment positions, and the effect of beam angling is demonstrated. A method of calculating the approximated lung volume from port films is proposed, together with a comparative analysis of the data obtained. Clinical decisions affecting technical considerations are examined. 6 refs., 5 figs

JANNAF 28th Propellant Development and Characterization Subcommittee and 17th Safety and Environmental Protection Subcommittee Joint Meeting. Volume 1

Science.gov (United States)

Cocchiaro, James E. (Editor); Mulder, Edwin J. (Editor); Gomez-Knight, Sylvia J. (Editor)

1999-01-01

This volume contains 37 unclassified/unlimited-distribution technical papers that were presented at the JANNAF 28th Propellant Development & Characterization Subcommittee (PDCS) and 17th Safety & Environmental Protection Subcommittee (S&EPS) Joint Meeting, held 26-30 April 1999 at the Town & Country Hotel and the Naval Submarine Base, San Diego, California. Volume II contains 29 unclassified/limited-distribution papers that were presented at the 28th PDCS and 17th S&EPS Joint Meeting. Volume III contains a classified paper that was presented at the 28th PDCS Meeting on 27 April 1999. Topics covered in PDCS sessions include: solid propellant rheology; solid propellant surveillance and aging; propellant process engineering; new solid propellant ingredients and formulation development; reduced toxicity liquid propellants; characterization of hypergolic propellants; and solid propellant chemical analysis methods. Topics covered in S&EPS sessions include: space launch range safety; liquid propellant hazards; vapor detection methods for toxic propellant vapors and other hazardous gases; toxicity of propellants, ingredients, and propellant combustion products; personal protective equipment for toxic liquid propellants; and demilitarization/treatment of energetic material wastes.

1980 survey and evaluation of utility conservation, load management, and solar end-use projects. Volume 3: utility load management projects. Final report

Energy Technology Data Exchange (ETDEWEB)

1982-01-01

The results of the 1980 survey of electric utility-sponsored energy conservation, load management, and end-use solar energy conversion projects are described. The work is an expansion of a previous survey and evaluation and has been jointly sponsored by EPRI and DOE through the Oak Ridge National Laboratory. There are three volumes and a summary document. Each volume presents the results of an extensive survey to determine electric utility involvement in customer-side projects related to the particular technology (i.e., conservation, solar, or load management), selected descriptions of utility projects and results, and first-level technical and economic evaluations.

Technical Note: Stored grain volume measurement using a low density point cloud

Science.gov (United States)

The mass of stored grain is often determined from volume measurements by crop insurers, government auditors, and stored grain managers conducting inventories. Recent increases in bin size have accentuated the difficulty of accounting for irregularities and variations in surface conditions in calcula...

Some aspects of the relation between the volume of prostate carcinoma and its interstitial BT volume

International Nuclear Information System (INIS)

Zivanovic, A; Babic, J; Erak, M.; Dabic, K.; Donat, D.; Kuzmanovic, Z.; Savic, D.

1996-01-01

It is a fact that the volume achieved by the interstitial procedure during the brachy treatment of prostate carcinoma is several times smaller than the one we get in, so called, external beam therapy. Furthermore, interstitial brachytherapy offers the possibility to apply large dose into the small volume. However, both dose and volume are at the same time the factors that limit the therapy and the main technical offenders in case of therapy failure. We tried, through a strong individual approach, to compare the volume obtained mathematically and the volume obtained by planning (TPS). By means of clinical examinations and CT scans we conceived a prostate as half of the volume of ellipsoid under one condition only: the magnification of the prostate has to be a symmetrical one. Finally, we applied the following formula: V prostate=(1(2)) ellipsoid=2.09·a/2·e/2·b where a=(1(2)) of sagittal diameter b=prostate height (from apex to base) c=(1(2)) of transversal diameter Each volume obtained in the this way has been taken into account during the application of interstitial needles which in their own way and in accordance to a routine planning, form an active therapeutic interstitial volume. The obtained data showed differences between these two types of volumes. From the statistical point of view, mathematically obtained volume of CV was 16.6% while interstitial volume was 14.9%. T-test was 3.9. On average, mathematical volume is lower and this balance is a desirable one because it means a smaller possibility for potential positive biopsy as a result of a 'rest' tumour. If on the other hand, positive biopsy is a result of the 'rest' tumour and our interpretation has been a contradictory one, precious time with disappointing results will be lost. At the end we achieved: a) double checked control of the embraced volumes, b) stronger fulcrum for the next step: dose-fraction balance

Technical Adequacy of the easyCBM Primary-Level Mathematics Measures (Grades K-2), 2009-2010 Version. Technical Report #1006

Science.gov (United States)

Anderson, Daniel; Lai, Cheng-Fei; Nese, Joseph F. T.; Park, Bitnara Jasmine; Saez, Leilani; Jamgochian, Elisa; Alonzo, Julie; Tindal, Gerald

2010-01-01

In the following technical report, we present evidence of the technical adequacy of the easyCBM[R] math measures in grades K-2. In addition to reliability information, we present criterion-related validity evidence, both concurrent and predictive, and construct validity evidence. The results represent data gathered throughout the 2009/2010 school…

Optimal maintenance work organization and technical education

International Nuclear Information System (INIS)

Toshiro Kitamura

2005-01-01

Under Japanese multi-layered maintenance routines, almost 100% of work is delegated to outside contractors. For taking such form, there are several reasons unique to Japan. U.S. maintenance work organization makes a contrast, reducing the volume of subcontract in these past ten years. On the other hand, France has a trend of increasing the volume of subcontract for cost reduction that is expected in liberalization and privatization. In Japan, since the subcontract went too far, there is a trend that the multi-layered subcontract structure will be relieved. The Japan Atomic Power, Inc., has organized a team that performs a part of maintenance work by employees themselves since three years before. Direct work is effective to greatly supporting the employees' technical ability. It is expected that the quality of subcontract management will be markedly improved from now on. (author)

Problems of technical cooperation

International Nuclear Information System (INIS)

Noramli, M.

1987-01-01

The main principles of the IAEA technical co-operation program, which intends to answer the requirements of the member states as regards technical assistance, are presented. IAEA offers its assistance in the supervision and financial support of the projects, which promise direct and quick profit to the member states. Projects related to the satisfaction of the main demands of humanity, industrial use, energy generation, radiation protection and other fields, which can promote the contribution of nuclear power generation to the course of peace, protection of health and thriving of states, are among them. 35 million dollars (USA) was allocated for the IAEA technical assistance and realization of the co-operation program in 1987

Entrained-flow gasification at elevated pressure: Volume 1: Final technical report, March 1, 1985-April 30,1987

Energy Technology Data Exchange (ETDEWEB)

Hedman, P.O.; Smoot, L.D.; Smith, P.J.; Blackham, A.U.

1987-10-15

The general purpose of this research program was to develop a basic understanding of the physical and chemical processes in entrained coal gasification and to use the results to improve and evaluate an entrained gasification computer model. The first task included the collection and analysis of in-situ gasifier data at elevated pressures with three coal types (North Dakota lignite, Wyoming subbituminous and Illinois bituminous), the design, construction, and testing of new coal/oxygen/steam injectors with a fourth coal type (Utah bituminous), the collection of supporting turbulent fluid dynamic (LDV) data from cold-flow studies, and the investigation of the feasibility of using laser-based (CARS) daignostic instruments to make measurements in coal flames. The second task included improvements to the two-dimensional gasifier submodels, tabulation and evaluation of new coal devolatilization and char oxidation data for predictions, fundamental studies of turbulent particle dispersion, the development of improved numerical methods, and validation of the comprehensive model through comparison of predictions with experimental results. The third task was to transfer technical advances to industry and to METC through technical seminars, production of a detailed data book, code placement, and publication of results. Research results for these three tasks are summarized briefly here and presented in detail in the body of the report and in supporting references. 202 refs., 73 figs., 23 tabs.

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

Mechanistic approach to generalized technical analysis of share prices and stock market indices

Science.gov (United States)

Ausloos, M.; Ivanova, K.

2002-05-01

Classical technical analysis methods of stock evolution are recalled, i.e. the notion of moving averages and momentum indicators. The moving averages lead to define death and gold crosses, resistance and support lines. Momentum indicators lead the price trend, thus give signals before the price trend turns over. The classical technical analysis investment strategy is thereby sketched. Next, we present a generalization of these tricks drawing on physical principles, i.e. taking into account not only the price of a stock but also the volume of transactions. The latter becomes a time dependent generalized mass. The notion of pressure, acceleration and force are deduced. A generalized (kinetic) energy is easily defined. It is understood that the momentum indicators take into account the sign of the fluctuations, while the energy is geared toward the absolute value of the fluctuations. They have different patterns which are checked by searching for the crossing points of their respective moving averages. The case of IBM evolution over 1990-2000 is used for illustrations.

TRIPOLI I: energy-dependent three-dimensional Monte Carlo Program. Volume I. Conception and presentation of the TRIPOLI I System

International Nuclear Information System (INIS)

Katz, S.; Nimal, J.C.

In its present version TRIPOLI/1/ is an energy dependent three-dimensional program which treats the slowing down and diffusion of neutrons for source problems. The version presented here is essentially oriented towards reactor shielding problems. It is written in FORTRAN for IBM (series 360) computer. This volume is devoted to a summary of the essential characteristics of the program as well as to a description of the constants required for the description of the chaining together of the work to be carried out

Critical evaluation of the nonradiological environmental technical specifications. Volume 4. San Onofre Nuclear Generating Station, Unit 1

Energy Technology Data Exchange (ETDEWEB)

Adams, S.M.; Cunningham, P.A.; Gray, D.D.; Kumar, K.D.

1976-08-10

A comprehensive study of the data collected as part of the environmental Technical Specifications program for Unit 1 of the San Onofre Nuclear Generating Station (SONGS 1) was conducted for the Office of Nuclear Regulatory Research of the U.S. Nuclear Regulatory Commission. The program included an analysis of the hydrothermal and ecological monitoring data collected during 1975. The hydrothermal analysis includes a discussion of models used in plume predictions prior to plant operation and an evaluation of the present hydrothermal monitoring program. The ecological evaluation was directed toward reviewing the strengths and weaknesses of the various sampling programs designed to monitor the planktonic, benthic, and nektonic communities inhabiting the inshore coastal area in the vicinity of San Onofre.

Critical evaluation of the nonradiological environmental technical specifications. Volume 4. San Onofre Nuclear Generating Station, Unit 1

International Nuclear Information System (INIS)

Adams, S.M.; Cunningham, P.A.; Gray, D.D.; Kumar, K.D.

1976-01-01

A comprehensive study of the data collected as part of the environmental Technical Specifications program for Unit 1 of the San Onofre Nuclear Generating Station (SONGS 1) was conducted for the Office of Nuclear Regulatory Research of the U.S. Nuclear Regulatory Commission. The program included an analysis of the hydrothermal and ecological monitoring data collected during 1975. The hydrothermal analysis includes a discussion of models used in plume predictions prior to plant operation and an evaluation of the present hydrothermal monitoring program. The ecological evaluation was directed toward reviewing the strengths and weaknesses of the various sampling programs designed to monitor the planktonic, benthic, and nektonic communities inhabiting the inshore coastal area in the vicinity of San Onofre

Minutes of the IFMIF technical meeting

International Nuclear Information System (INIS)

Nakamura, H.; Takeda, M.; Ida, M.; Maebara, S.; Yutani, T.; Sugimoto, M.

2004-03-01

The IFMIF Technical Meeting was held on December 4-5, 2003 at Shiran-kaikan, Kyoto University. The main objectives are 1) to finalize the Comprehensive Design Report (CDR), 2) to discuss IFMIF cost and organization, 3) to review technical status of major systems, transition phase activities and EVEDA plan. This report presents a brief summary of the results of the meeting. Agenda, participants list and presentation materials are attached as Appendix. (author)

Patrick Air Force Base integrated resource assessment. Volume 3, Resource assessment

Energy Technology Data Exchange (ETDEWEB)

Sandusky, W.F.; Parker, S.A.; King, D.A.; Wahlstrom, R.R.; Elliott, D.B.; Shankle, S.A.

1993-12-01

The US Air Force has tasked the Pacific Northwest Laboratory (PNL) in support of the US Department of Energy Federal Energy Management Program to identify, evaluate, and assist in acquiring all cost effective energy projects at Patrick Air Force Base (AFB). This is part of a model program that PNL is designing to support energy-use decisions in the federal sector. This report provides the results of the fossil fuel and electric energy resource opportunity (ERO) assessments performed by PNL at Patrick AFB which is located south of Cocoa Beach, Florida. It is a companion report to Volume 1, Executive Summary, and Volume.2, Baseline Detail. The results of the analyses of EROs are presented in 11 common energy end-use categories. A narrative description of each ERO is provided, including information on the installed cost, energy and dollar savings, impacts on operations and maintenance, and, when applicable, a discussion of energy supply and demand, energy security, and environmental issues. A description of the evaluation methodologies and technical and cost assumptions is also provided for each ERO. Summary tables present the cost-effectiveness of energy end-use equipment before and after the implementation of each ERO and present the results of the life-cycle cost analysis indicating the net present value and value index of each ERO.

Technical specification improvement through safety margin considerations

International Nuclear Information System (INIS)

Howard, R.C.; Jansen, R.L.

1986-01-01

Westinghouse has developed an approach for utilizing safety analysis margin considerations to improve plant operability through technical specification revision. This approach relies on the identification and use of parameter interrelations and sensitivities to identify acceptable operating envelopes. This paper summarizes technical specification activities to date and presents the use of safety margin considerations as another viable method to obtain technical specification improvement

Proceedings of the nineteenth arctic and marine oil spill program (AMOP) technical seminar

International Nuclear Information System (INIS)

1996-01-01

The technical seminar on arctic and marine oil spills introduced issues concerning oil spills at sea, in particular the critical first few hours of an oil spill. State-of-the-art technologies which assist the response team in tracking and predicting the behavior of oil spills, were described. The physical and chemical properties of spilled oil were studied, as well as those of oil spill treating agents, including testing their biological effects. New methods to contain and recover spilled oil were reviewed. Volume 2 presented results from field experiments in which in-situ burning was performed, and demonstrated modelling techniques for the detection, prediction and tracking of oil spills. refs., tabs., figs

Superconducting Machines at the Technical University of Denmark

DEFF Research Database (Denmark)

Jensen, Bogi Bech; Abrahamsen, Asger Bech; Mijatovic, Nenad

2011-01-01

Two high temperature superconducting (HTS) machine prototypes constructed at the Technical University of Denmark are presented. The construction process is presented and the excellent agreement between simulation results and experimental results are presented for one of the prototypes.......Two high temperature superconducting (HTS) machine prototypes constructed at the Technical University of Denmark are presented. The construction process is presented and the excellent agreement between simulation results and experimental results are presented for one of the prototypes....

Proceedings from the technical workshop on near-field performance assessment for high-level waste

International Nuclear Information System (INIS)

Sellin, P.; Apted, M.; Gago, J.

1991-12-01

This report contains the proceedings of 'Technical workshop of near-filed performance assessment for high-level waste' held in Madrid October 15-17, 1990. It includes the invited presentations and summaries of the scientific discussions. The workshop covered several topics: * post-emplacement environment, * benchmarking of computer codes, * glass release, * spent-fuel release, * radionuclide solubility, * near-field transport processes, * coupled processes in the near-field, * integrated assessments, * sensitivity analyses and validation. There was an invited presentation on each topic followed by an extensive discussion. One of the points highlighted in the closing discussion of the workshop was the need for international cooperation in the field of near-field performance assessment. The general opinion was that this was best achieved in smaller groups discussing specific questions. (au) Separate abstracts were prepared for 9 papers in this volume

Regulatory and technical reports (abstract index journal): Annual compilation for 1996, Volume 21, No. 4

Energy Technology Data Exchange (ETDEWEB)

Sheehan, M.A.

1997-04-01

This compilation is the annual cumulation of bibliographic data and abstracts for the formal regulatory and technical reports issued by the U.S. Nuclear Regulatory Commission (NRC) Staff and its contractors.

Regulatory and technical reports (abstract index journal): Annual compilation for 1996, Volume 21, No. 4

International Nuclear Information System (INIS)

Sheehan, M.A.

1997-04-01

This compilation is the annual cumulation of bibliographic data and abstracts for the formal regulatory and technical reports issued by the U.S. Nuclear Regulatory Commission (NRC) Staff and its contractors

Advanced Neutron Source enrichment study -- Volume 1: Main report. Final report, Revision 12/94

International Nuclear Information System (INIS)

Bari, R.A.; Ludewig, H.; Weeks, J.

1994-01-01

A study has been performed of the impact on performance of using low enriched uranium (20% 235 U) or medium enriched uranium (35% 235 U) as an alternative fuel for the Advanced Neutron Source, which is currently designed to use uranium enriched to 93% 235 U. Higher fuel densities and larger volume cores were evaluated at the lower enrichments in terms of impact on neutron flux, safety, safeguards, technical feasibility, and cost. The feasibility of fabricating uranium silicide fuel at increasing material density was specifically addressed by a panel of international experts on research reactor fuels. The most viable alternative designs for the reactor at lower enrichments were identified and discussed. Several sensitivity analyses were performed to gain an understanding of the performance of the reactor at parametric values of power, fuel density, core volume, and enrichment that were interpolations between the boundary values imposed on the study or extrapolations from known technology. Volume 2 of this report contains 26 appendices containing results, meeting minutes, and fuel panel presentations

Alternatives for Jet Engine Control. Volume 1: Modelling and Control Design with Jet Engine Data

Science.gov (United States)

Sain, M. K.

1985-01-01

This document compiles a comprehensive list of publications supported by, or related to, National Aeronautics and Space Administration Grant NSG-3048, entitled "Alternatives for Jet Engine Control". Dr. Kurt Seldner was the original Technical Officer for the grant, at Lewis Research Center. Dr. Bruce Lehtinen was the final Technical Officer. At the University of Notre Dame, Drs. Michael K. Sain and R. Jeffrey Leake were the original Project Directors, with Dr. Sain becoming the final Project Director. Publications cover work over a ten-year period. The Final Report is divided into two parts. Volume i, "Modelling and Control Design with Jet Engine Data", follows in this report. Volume 2, "Modelling and Control Design with Tensors", has been bound separately.

Experimental applications for the MARK-1 and MARK-1A pulsed ionizing radiation detection systems. Volume 3

International Nuclear Information System (INIS)

Harker, Y.D.; Lawrence, R.S.; Yoon, W.Y.; Lones, J.L.

1993-12-01

This report is the third volume in a three volume set describing the MARK series of pulsed ionizing radiation detection systems. This volume describes the MARK-1A detection system, compares it with the MARK-1 system, and describes the experimental testing of the detection systems. Volume 1 of this set presents the technical specifications for the MARK-1 detection system. Volume 2 is an operations manual specifically for the MARK-1 system, but it generally applies to the MARK-1A system as well. These detection systems operate remotely and detect photon radiation from a single or a multiple pulsed source. They contain multiple detector (eight in the MARK-1 and ten in the MARK-1A) for determination of does and incident photon effective energy. The multiple detector arrangement, having different detector sizes and shield thicknesses, provides the capability of determining the effective photon energy of the radiation spectrum. Dose measurements using these units are consistent with TLD measurements. The detection range is from 3 nanorads to 90 microrads per source burst; the response is linear over that range. Three units were built and are ready for field deployment

SPORT AND EXERCISE PHYSIOLOGY TESTING Volume one: Sport Testing Volume two: Exercise and Clinical Testing

Directory of Open Access Journals (Sweden)

Edward M. Winter

2007-03-01

Full Text Available DESCRIPTION The objective of the book is to discuss the theoretical and practical aspects of physiological testing in exercise and sports which is essential to evaluate and monitor developing exercise performance for athletes and public health, and improving quality of life for patients.A board of leading sport and exercise physiologists and scientists are gathered to discuss physiological assessments that have proven validity and reliability, both in sport and health relevant issues. Incidentally, it updates the reader about the current subjects of physiological exertion testing in both research and clinical procedures. Both volumes individually cover the increasing number of available research and review publications, and theoretical explanations are supported by practical examples. A step-by-step and/or checklist method is used in appropriate sections which make the guides more user-friendly than most. PURPOSE The first volume is designed to help readers develop an understanding of the essential concepts of sport specific testing whereas the second volume aims at making the exercise and clinical specific testing comprehensible, dealing with both technical terms and the theories underlying the importance of these tests. AUDIENCE As Guidelines books of the British Association of Sport and Exercise Sciences, it will be of interest to a wide range of students, researchers and practitioners in the sport and exercise disciplines whether they work in the laboratory or in the field. FEATURES The first volume features immediate practical requirements particularly in sport testing. It is composed of five parts with detailed sub-sections in all of them. The topics of the parts are: i general principles, ii methodological issues, iii general procedures, iv sport specific procedures, v special populations.The second volume is also presented in five parts, again with sub-sections in all of them, but considering the requirements in clinical and exercise

Frequency Domain Computer Programs for Prediction and Analysis of Rail Vehicle Dynamics : Volume 1. Technical Report

Science.gov (United States)

1975-12-01

Frequency domain computer programs developed or acquired by TSC for the analysis of rail vehicle dynamics are described in two volumes. Volume I defines the general analytical capabilities required for computer programs applicable to single rail vehi...

Technical aspects of fuel reprocessing

International Nuclear Information System (INIS)

Groenier, W.S.

1982-02-01

The purpose of this paper is to present a brief description of fuel reprocessing and some present developments which show the reliability of nuclear energy as a long-term supply. The following topics are discussed: technical reasons for reprocessing; economic reasons for reprocessing; past experience; justification for advanced reprocessing R and D; technical aspects of current reprocessing development. The present developments are mainly directed at the reprocessing of breeder reactor fuels but there are also many applications to light-water reactor fuel reprocessing. These new developments involve totally remote operation, and maintenance. To demonstrate this advanced reprocessing concept, pilot-scale demonstration facilities are planned with commercial application occurring sometime after the year 2000

In situ leaching of a nuclear rubblized copper ore body. Volume II

International Nuclear Information System (INIS)

1975-06-01

This volume contains detailed descriptions of technical and economical evaluations undertaken for the feasibility study. A summary of these results can be found in Vol. 1 along with the conclusions derived from the feasibility study and the recommendations tendered for future work. The sections of this study are presented in process order, and each section is complete in itself. The form of the presentation, hopefully, is logical and in a manner suitable for design purposes. As a further aid, each section has its own table of contents. The sections presented include method of attack, reference case, description of concept, nuclear rubblization, blasting plan, underground plumbing, fluid circulation, leaching technology, wellhead plant and pipeline, process plant, material and heat balance, hydrology, radioactivity, seismic, economics, sensitivity analysis, guide for environmental studies, exploration, and recommended experimental program. (U.S.)

Technical evaluation of the ATI volume reduction and bitumen solidification topical report

International Nuclear Information System (INIS)

Henscheid, J.W.; Young, T.E.

1985-01-01

This report summarizes EG and G Idaho's review of the Associated Technologies Inorporated (ATI) topical report on a Volume Reduction and Bitumen Solidification System. The review evaluated compliance with pertinent codes, standards and regulations. The initial review was discussed with ATI, and all outstanding issues resolved before this final evaluation was made

A Handbook for Public Playground Safety. Volume II: Technical Guidelines for Equipment and Surfacing.

Science.gov (United States)

Consumer Product Safety Commission, Washington, DC.

This handbook suggests safety guidelines for public playground equipment and describes various surfaces used under the equipment and possible injuries resulting from falls. The handbook is intended for use mainly by manufacturers, installers, school and park officials, and others interested in technical criteria for public playground equipment.…

Report on the present day situation and technical perspectives of renewable energies; Rapport sur l'etat actuel et les perspectives techniques des energies renouvelables

Energy Technology Data Exchange (ETDEWEB)

Birraux, C.; Le Deaut, J.Y.

2001-11-01

This work, carried out by the parliamentary office for the evaluation of scientific and technological choices on request of the French National Assembly and Senate, takes stock of the present day situation and technical perspectives of development of renewable energy sources and of research needs of the French industry in this domain: 1 - renewable energies: key-technologies for the energy supply of developing countries and for a rational consumption in transportation systems and accommodations of developed countries (energies technically different from fossil or nuclear energies; fundamental energy sources for a developing world; different national goals in Europe depending on the available natural resources and on the political realities; a minor interest in France for the domestic power generation but a major interest for transports, residential and tertiary sectors and export); 2 - priority choices given to the French renewable energy resources: renewable electricity (photovoltaic, wind, biomass), thermal technologies (solar, geothermal, biomass); 3 - future policy: sustain of renewable electricity production with the revival of research, industry and technical cooperation. (J.S.)

Technical aspects of positron emission tomography/computed tomography in radiotherapy treatment planning.

Science.gov (United States)

Scripes, Paola G; Yaparpalvi, Ravindra

2012-09-01

The usage of functional data in radiation therapy (RT) treatment planning (RTP) process is currently the focus of significant technical, scientific, and clinical development. Positron emission tomography (PET) using ((18)F) fluorodeoxyglucose is being increasingly used in RT planning in recent years. Fluorodeoxyglucose is the most commonly used radiotracer for diagnosis, staging, recurrent disease detection, and monitoring of tumor response to therapy (Lung Cancer 2012;76:344-349; Lung Cancer 2009;64:301-307; J Nucl Med 2008;49:532-540; J Nucl Med 2007;48:58S-67S). All the efforts to improve both PET and computed tomography (CT) image quality and, consequently, lesion detectability have a common objective to increase the accuracy in functional imaging and thus of coregistration into RT planning systems. In radiotherapy, improvement in target localization permits reduction of tumor margins, consequently reducing volume of normal tissue irradiated. Furthermore, smaller treated target volumes create the possibility of dose escalation, leading to increased chances of tumor cure and control. This article focuses on the technical aspects of PET/CT image acquisition, fusion, usage, and impact on the physics of RTP. The authors review the basic elements of RTP, modern radiation delivery, and the technical parameters of coregistration of PET/CT into RT computerized planning systems. Copyright © 2012 Elsevier Inc. All rights reserved.

Gas Test Loop Functional and Technical Requirements

International Nuclear Information System (INIS)

Glen R. Longhurst; Soli T. Khericha; James L. Jones

2004-01-01

This document defines the technical and functional requirements for a gas test loop (GTL) to be constructed for the purpose of providing a high intensity fast-flux irradiation environment for developers of advanced concept nuclear reactors. This capability is needed to meet fuels and materials testing requirements of the designers of Generation IV (GEN IV) reactors and other programs within the purview of the Advanced Fuel Cycle Initiative (AFCI). Space nuclear power development programs may also benefit by the services the GTL will offer. The overall GTL technical objective is to provide developers with the means for investigating and qualifying fuels and materials needed for advanced reactor concepts. The testing environment includes a fast-flux neutron spectrum of sufficient intensity to perform accelerated irradiation testing. Appropriate irradiation temperature, gaseous environment, test volume, diagnostics, and access and handling features are also needed. This document serves to identify those requirements as well as generic requirements applicable to any system of this kind

Gas Test Loop Functional and Technical Requirements

Energy Technology Data Exchange (ETDEWEB)

Glen R. Longhurst; Soli T. Khericha; James L. Jones

2004-09-01

This document defines the technical and functional requirements for a gas test loop (GTL) to be constructed for the purpose of providing a high intensity fast-flux irradiation environment for developers of advanced concept nuclear reactors. This capability is needed to meet fuels and materials testing requirements of the designers of Generation IV (GEN IV) reactors and other programs within the purview of the Advanced Fuel Cycle Initiative (AFCI). Space nuclear power development programs may also benefit by the services the GTL will offer. The overall GTL technical objective is to provide developers with the means for investigating and qualifying fuels and materials needed for advanced reactor concepts. The testing environment includes a fast-flux neutron spectrum of sufficient intensity to perform accelerated irradiation testing. Appropriate irradiation temperature, gaseous environment, test volume, diagnostics, and access and handling features are also needed. This document serves to identify those requirements as well as generic requirements applicable to any system of this kind.

Study of volume fractions on biphasic stratified regime using gamma ray

Energy Technology Data Exchange (ETDEWEB)

Salgado, William L.; Brandão, Luis E.B., E-mail: william.otero@hotmail.com, E-mail: brandao@ien.gov.br [Instituto de Engenharia Nuclear (IEN/CNEN-RJ), Rio de Janeiro, RJ (Brazil)

2017-07-01

In the oil industries, interconnected pipelines are used to carry large quantities of petroleum and its byproducts. This modal has an advantage because they are more economical, eliminate a need for stocks and, in addition, great safety in operation minimizing a possibility of loss or theft when transported another way. In many cases, especially in the petrochemical industry, the same pipeline is used to carry more than one type of product. They are called poliduct. In the operation of a poliduct there is a sequence of products to be transported and during the exchange of the product, there are still fractions of the previous product and this generates contamination. It is therefore important to identify precisely this region in order to reduce the costs of reprocessing and treatment of discarded products. In this way, this work presents a methodology to evaluate the sensitivity of the gamma densitometry technique in a study of the calculation of volume fractions in biphasic systems, submitted to the stratified flow regime. Using computational simulations using the Monte Carlo Method with the MCNPX code measurement geometry was proposed that presented a higher sensitivity for the calculation of volume fractions. The relevant technical data to perform a simulation of the scintillator detectors were based on information obtained from the gammagraphy technique. The study had a theoretical validation through analytical equations, and the results show that it is possible to identify volume fractions equivalent to 3%. (author)

Backfilling and sealing of tunnels, shafts and boreholes. Volume 2: Appendices

International Nuclear Information System (INIS)

Studer, J.; Ammann, W.; Meier, P.; Mueller, Ch.; Glauser, E.

1984-12-01

The present report is a synthesis of the state of knowledge regarding backfilling and sealing of nuclear waste repositories. It is based on an evaluation of both the general and special publications concerning this problem (articles in scientific journals, research reports, conference papers and textbooks) and represents the state of knowledge up to summer 1984. In addition, it contains an outlook on the continuing work. This will serve to broaden the scientific base and to achieve the technical as well as economical optimization. The report consists of two volumes: Volume 1 Main Part, Volume 2 Appendices. Starting with the functions of backfilling and sealing in the safety concept assessment criteria and from these, taking into consideration the given conditions in the project 'Gewaehr 1985' ('Guarantee'), the requirements for the backfilling and sealing materials are formulated. The properties of several materials under consideration are discussed in the Appendix together with a detailed description of the most important of these materials. The reasons are given for the choice of the proposed materials for the project 'Gewaehr 1985'. Alternative backfilling and sealing concepts for repositories Type B and Type C are presented and reasons are given for the selected variants for the project 'Gewaehr 1985'. Chapter 10 represents a review of the report. This report is intended as a reference work for the corresponding chapters in the NGB reports (cf. /NGB 85-03, 1985/, /NGB 85-06, 1985/). (author)

Study of volume fractions on biphasic stratified regime using gamma ray

International Nuclear Information System (INIS)

Salgado, William L.; Brandão, Luis E.B.

2017-01-01

In the oil industries, interconnected pipelines are used to carry large quantities of petroleum and its byproducts. This modal has an advantage because they are more economical, eliminate a need for stocks and, in addition, great safety in operation minimizing a possibility of loss or theft when transported another way. In many cases, especially in the petrochemical industry, the same pipeline is used to carry more than one type of product. They are called poliduct. In the operation of a poliduct there is a sequence of products to be transported and during the exchange of the product, there are still fractions of the previous product and this generates contamination. It is therefore important to identify precisely this region in order to reduce the costs of reprocessing and treatment of discarded products. In this way, this work presents a methodology to evaluate the sensitivity of the gamma densitometry technique in a study of the calculation of volume fractions in biphasic systems, submitted to the stratified flow regime. Using computational simulations using the Monte Carlo Method with the MCNPX code measurement geometry was proposed that presented a higher sensitivity for the calculation of volume fractions. The relevant technical data to perform a simulation of the scintillator detectors were based on information obtained from the gammagraphy technique. The study had a theoretical validation through analytical equations, and the results show that it is possible to identify volume fractions equivalent to 3%. (author)

Technical Design of Flexible Sustainable Energy Systems

DEFF Research Database (Denmark)

Lund, Henrik

2003-01-01

The paper presents technical designs of potential future flexible energy systems in Denmark, which will be able both to balance production and demand and to secure voltage and frequency requirements on the grid.......The paper presents technical designs of potential future flexible energy systems in Denmark, which will be able both to balance production and demand and to secure voltage and frequency requirements on the grid....

NWTS conceptual reference repository description (CRRD). Volume III. Criteria, bases, special studies, and codes

International Nuclear Information System (INIS)

1981-05-01

This volume documents the criteria, design bases, and special studies and provides the backup for the design presented in Volume II. The criteria presented here were developed by ONWI as a draft version for consideration in this conceptual report. Since these criteria were developed subsequent to preparation of the reports used as a basis for the CRRD, not all of the criteria could be fully considered in preparation of the CRRD. However, they were used as guidelines wherever possible. The criteria for terminal storage of waste are still in development. The chapter on the design bases identifies the important design considerations and provides the justification for their selection. The design bases were developed not so much to give exact values for parameters as to identify the parameters that are significant to the design. They also serve as a common basis for coordinating analysis and design studies unitl the next design phase is completed. Some of the design bases presented here were taken directly from the Stearns-Roger NWTS-R1 Conceptual Design Report. The special studies document technical aspects of the design that are of particular importance or that furnish additional information pertaining to the design

A review and evaluation of the Langley Research Center's Scientific and Technical Information Program: Results of phase 6: The technical report. A survey and analysis

Science.gov (United States)

Mccullough, R. A.; Pinelli, T. E.; Pilley, D. D.; Stohrer, F. F.

1982-01-01

Current practice and usage using selected technical reports; literature relative to the sequential, language, and presentation components of technical reports; and NASA technical report publications standards are discussed. The effctiveness of the technical report as a product for information dissemination is considered.

Technical Memory 2010. Nuclear Regulatory Authority

International Nuclear Information System (INIS)

2010-01-01

The technical memory 2010 of the Nuclear Regulatory Authority of Argentine Republic, compile the papers published in the subject on radiation protection and nuclear safety presented in journals, technical reports, congress or meetings of these subjects by the ARN personnel during 2010. In this edition the documents are presented on: environmental protection; safety transport of radioactive materials; regulations; licensing of medical installations; biological radiation effects; therapeutic uses of ionizing radiation and radioprotection of patients; internal dosimetry; radioactive waste management [es

Technical diagnostics functioning machines and mechanisms

Science.gov (United States)

Kiselev, M. I.; Pronyakin, V. I.; Tulekbaeva, A. K.

2018-02-01

Article discusses the machines and mechanisms technical state monitoring problem. Approaches for estimating mechanical systems current technical state, defects detection and evaluation of mechanical elements degradation levels are considered. The paper analyzes the traditional methods offered in international and national standards, especially vibrodiagnostics. An advanced phase method is presented which is based on registration the kinematic parameters of the mechanism running cycle. The result of coupling the phase method and mathematical modeling is shown, and simulation comparison with the experimental data is presented.

Approaching Technical Issues in Architectural Education

DEFF Research Database (Denmark)

Pugnale, Alberto; Parigi, Dario

2012-01-01

This paper discusses teaching of technical subjects in architecture, presenting two experimental activities, recently organized at Aalborg University - a two week long workshop and a one day long lecture. From the pedagogical point of view, the activities are strategically placed between conventi......This paper discusses teaching of technical subjects in architecture, presenting two experimental activities, recently organized at Aalborg University - a two week long workshop and a one day long lecture. From the pedagogical point of view, the activities are strategically placed between...

Technical Memory 2011. Nuclear Regulatory Authority

International Nuclear Information System (INIS)

2011-01-01

The technical memory 2011 of the Nuclear Regulatory Authority of Argentine Republic, compile the papers published in the subject on radiation protection and nuclear safety presented in journals, technical reports, congress or meetings of these subjects by the ARN personnel during 2011. In this edition the documents are presented on: environmental protection; safety transport of radioactive materials; regulations; licensing of medical installations; biological radiation effects; therapeutic uses of ionizing radiation and radioprotection of patients; internal dosimetry; radioactive waste management [es

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.

Conversations with Technical Writing Teachers: Defining a Problem.

Science.gov (United States)

Selting, Bonita R.

2002-01-01

Considers if teaching technology is problematic for technical writing instructors. Presents ideas of 64 Association of Teachers of Technical Writing (ATTW) members who were queried on their roles as teachers of technical writing in relation to the demands made upon them to also be teachers of technology skills. Concludes with a call for more…

Oxygen from Hydrogen Peroxide. A Safe Molar Volume-Molar Mass Experiment.

Science.gov (United States)

Bedenbaugh, John H.; And Others

1988-01-01

Describes a molar volume-molar mass experiment for use in general chemistry laboratories. Gives background technical information, procedures for the titration of aqueous hydrogen peroxide with standard potassium permanganate and catalytic decomposition of hydrogen peroxide to produce oxygen, and a discussion of the results obtained in three…

Nuclear Energy Center Site Survey, 1975. Part III. Technical considerations

International Nuclear Information System (INIS)

1976-01-01

Studies of the technical feasibility of nuclear energy centers (NECs) and the comparison between NEC technical feasibility and that of nuclear facilities on dispersed sites are reviewed. The conclusions related to technical feasibility of NEC are summarized. Technical feasibility was found to rest mainly on five major issues: heat dissipation, transmission, facility construction, radiological impact, and environmental impact. Although general conclusions can be reached in these five areas, it is recognized that they are interdependent, and detailed site-by-site analysis will be necessary. Some general conclusions on technical feasibility of NECs are presented, then detailed conclusions derived from the technical evaluation of NECs compared to dispersed site facilities are presented. The findings of this study on each of the five major feasibility issues are then discussed in sequence. The study concludes that nuclear energy centers, as defined herein, are technically feasible

Sparse PDF Volumes for Consistent Multi-Resolution Volume Rendering

KAUST Repository

Sicat, Ronell Barrera

2014-12-31

This paper presents a new multi-resolution volume representation called sparse pdf volumes, which enables consistent multi-resolution volume rendering based on probability density functions (pdfs) of voxel neighborhoods. These pdfs are defined in the 4D domain jointly comprising the 3D volume and its 1D intensity range. Crucially, the computation of sparse pdf volumes exploits data coherence in 4D, resulting in a sparse representation with surprisingly low storage requirements. At run time, we dynamically apply transfer functions to the pdfs using simple and fast convolutions. Whereas standard low-pass filtering and down-sampling incur visible differences between resolution levels, the use of pdfs facilitates consistent results independent of the resolution level used. We describe the efficient out-of-core computation of large-scale sparse pdf volumes, using a novel iterative simplification procedure of a mixture of 4D Gaussians. Finally, our data structure is optimized to facilitate interactive multi-resolution volume rendering on GPUs.

Siting, design and cost of shallow land burial facilities in northern New England. Volume 1

International Nuclear Information System (INIS)

1985-05-01

This study investigated the technical feasibility and cost of shallow land burial (SLB) as one low-level radioactive waste disposal option for Maine and the northern New England states of Maine, New Hampshire, and Vermont. The results are presented in five chapters addressing the licensing process for an SLB facility, the siting process, the engineering design, the cost of disposal, and the cost of transportation. Chapter 2 reviews the Federal and State licensing processes and requirements for development of an SLB facility. Included in this discussion are the stages in the life cycle of SLB facility. Chapter 3 provides site selection criteria for Maine and presents a proposed site selection methodology. The site selection criteria are defined and the reasoning behind their selection is explained. Chapter 4 discusses SLB trench and facility designs and costs. To accommodate different waste volume scenarios, differently sized facilities are discussed, representing Maine going-it-alone and a northern New England compact. Designs and costs of scenarios including nuclear power plant decommissioning wastes are also discussed. Cost estimates of licensing, facility construction, operation, closure, and post closure care are presented for the different waste volume scenarios. Chapter 5 presents estimates of what it would cost LLW generators to dispose of their waste in a Maine-only or a northern New England shallow land burial facility. The reliability of the estimates and their sensitivity to changes in waste volume are also discussed. Chapter 6 examines transportation costs

Present state and subjects for hereafter of technical development for decommissioning

International Nuclear Information System (INIS)

Ishikura, Takeshi; Onozawa, Teruo; Saishu, Sadanori

1997-01-01

As to the decommissioning of nuclear power facilities, it was confirmed that there is no technical problem which makes decommissioning impossible in the report of the nuclear power subcommittee of Advisory Committee for Energy. In OECD/NEA, the international joint research for exchanging the information and experience of the decommissioning projects has been carried out. In foreign countries, the decommissioning has been executed practically. As the disassembling techniques for structures, laser cutting, plasma are cutting, arc gouging and gas cutting, arc saw cutting, gas cutting and powder gas cutting, mechanical cutting and molded explosive cutting are described. As the disassembling techniques for concrete structures, diamond wire saw method, mechanical cutting, water jet cutting and the method of using disk cutter and mechanical wedge are described. As to decontamination techniques, decontamination before disassembling, decontamination of large equipment, and decontamination after disassembling by blast, electrolysis and chemical immersion are described. The technology for measuring the radiation before disassembling and the radiation of buildings and disassembled waste is reported. (K.I.)

FOREX trading strategy formation using technical analysis

OpenAIRE

Klimavičius, Domas

2010-01-01

FOREX technical analysis indicators, their characteristics and capabilities are researched in this final master thesis. The main goal of this thesis is to determine if technical analysis indicators can recognise patterns in price movements and if they can predict future price movement. The first part of the thesis presents with FOREX theoretical aspects, its characteristics and participants. In the second part of the thesis FOREX analysis tools are overviewed, focusing on technical analysis. ...

Technical area status report for chemical/physical treatment

International Nuclear Information System (INIS)

Brown, C.H. Jr.; Schwinkendorf, W.E.

1993-08-01

These Appendices describe various technologies that may be applicable to the Mixed Waste Treatment Plant (MWTP) Chemical/Physical Treatment System (CPTS). These technologies were identified by the CPTS Technical Support Group (TSG) as potentially applicable to a variety of separation, volume reduction, and decontamination requirements. The purpose was to identify all available and developing technologies, and their characteristics, for subsequent evaluation for specific requirements identified for the CPTS. However, the technologies described herein are not necessarily all inclusive, nor are they necessarily all applicable

Technical-scientific production of IPEN - 1992

International Nuclear Information System (INIS)

1993-01-01

The technical-scientific production from Nuclear and Energetic Research Institute (IPEN), Brazil, is presented, including 471 references, where 421 papers are from the 1992 year and 50 from the earlier years. The main areas that the IPEN acts are: technical-scientific development of materials; nuclear processes; research reactors; nuclear utilization; nuclear safety and human resources formation. (C.G.C.)

Demonstration, testing, & evaluation of in situ heating of soil. Draft final report, Volume I

Energy Technology Data Exchange (ETDEWEB)

Dev, H.; Enk, J.; Jones, D.; Saboto, W.

1996-02-12

This document is a draft final report (Volume 1) for US DOE contract entitled, {open_quotes}Demonstration Testing and Evaluation of In Situ Soil Heating,{close_quotes} Contract No. DE-AC05-93OR22160, IITRI Project No. C06787. This report is presented in two volumes. Volume I contains the technical report and Volume II contains appendices with background information and data. In this project approximately 300 cu. yd. of clayey soil containing a low concentration plume of volatile organic chemicals was heated in situ by the application of electrical energy. It was shown that as a result of heating the effective permeability of soil to air flow was increased such that in situ soil vapor extraction could be performed. The initial permeability of soil was so low that the soil gas flow rate was immeasurably small even at high vacuum levels. When scaled up, this process can be used for the environmental clean up and restoration of DOE sites contaminated with VOCs and other organic chemicals boiling up to 120{degrees} to 130{degrees}C in the vadose zone. Although it may applied to many types of soil formations, it is particularly attractive for low permeability clayey soil where conventional in situ venting techniques are limited by low air flow.

Technical procedures for land use, Deaf Smith County site, Texas: Environmental Field Program: Final draft

International Nuclear Information System (INIS)

1987-09-01

This volume contains Technical Procedures pursuant to the Land Use Site Study Plan including land use data acquisition, land use/land cover map compilation, verification of land use/land cover map accuracy, and land use/land cover data analysis. 22 refs., 5 figs

Regulatory and technical reports (abstract index journal). Annual compilation for 1984. Volume 9, No. 4

International Nuclear Information System (INIS)

1985-01-01

This compilation consists of bibliographic data and abstracts for the formal regulatory and technical reports issued by the US Nuclear Regulatory Commission (NRC) Staff and its contractors. It is NRC's intention to publish this compilation quarterly and to cumulate it annually

INDOT Technical Training Plan : [Technical Summary

Science.gov (United States)

2012-01-01

A wide range of job classifications, increasing technical : performance expectations, licensing and certification requirements, : budget restrictions and frequent department : reorganization has made technical training of employees : more difficult, ...

Proceedings of the seventh annual gasification and gas stream cleanup systems contractors review meeting: Volume 1

Energy Technology Data Exchange (ETDEWEB)

Ghate, M.R.; Markel, K.E. Jr.; Jarr, L.A.; Bossart, S.J. (eds.)

1987-08-01

On June 16 through 19, 1987, METC sponsored the Seventh Annual Gasification and Gas Stream Cleanup Systems Contractors Review Meeting which was held at the Sheraton Lakeview Conference Center in Morgantown, West Virginia. The primary purpose of the meeting was threefold: to review the technical progress and current status of the gasification and gas stream cleanup projects sponsored by the Department of Energy; to foster technology exchange among participating researchers and other technical communities; to facilitate interactive dialogues which would identify research needs that would make coal-based gasification systems more attractive economically and environmentally. More than 310 representatives of Government, academia, industry, and foreign energy research organizations attended the 4-day meeting. Fifty-three papers and thirty poster displays were presented summarizing recent developments in the gasification and gas stream cleanup programs. Volume I covers information presented at sessions 1 through 4 on systems for the production of Co-products and industrial fuel gas, environmental projects, and components and materials. Individual papers have been processed for the Energy Data Base.

Proceedings of the seventh annual gasification and gas stream cleanup systems contractors review meeting: Volume 2

Energy Technology Data Exchange (ETDEWEB)

Ghate, M.R.; Markel, K.E. Jr.; Jarr, L.A.; Bossart, S.J. (eds.)

1987-08-01

On June 16 through 19, 1987, METC sponsored the Seventh Annual Gasification and Gas Stream Cleanup Systems Contractors Review Meeting which was held at the Sheraton Lakeview Conference Center in Morgantown, West Virginia. The primary purpose of the meeting was threefold: to review the technical progress and current status of the gasification and gas stream cleanup projects sponsored by the Department of Energy; to foster technology exchange among participating researchers and other technical communities; to facilitate interactive dialogues which would identify research needs that would make coal-based gasification systems more attractive economically and environmentally. More than 310 representatives of Government, academia, industry, and foreign energy research organizations attended the 4-day meeting. Fifty-three papers and thirty poster dsplays were presented summarizing recent developments in the gasification and gas stream cleanup programs. Volume II covers papers presented at sessions 5 and 6 on system for the production of synthesis gas, and on system for the production of power. All papers have been processed for inclusion in the Energy Data Base.

Guidelines for selecting codes for ground-water transport modeling of low-level waste burial sites. Volume 2. Special test cases

International Nuclear Information System (INIS)

Simmons, C.S.; Cole, C.R.

1985-08-01

This document was written for the National Low-Level Waste Management Program to provide guidance for managers and site operators who need to select ground-water transport codes for assessing shallow-land burial site performance. The guidance given in this report also serves the needs of applications-oriented users who work under the direction of a manager or site operator. The guidelines are published in two volumes designed to support the needs of users having different technical backgrounds. An executive summary, published separately, gives managers and site operators an overview of the main guideline report. Volume 1, titled ''Guideline Approach,'' consists of Chapters 1 through 5 and a glossary. Chapters 2 through 5 provide the more detailed discussions about the code selection approach. This volume, Volume 2, consists of four appendices reporting on the technical evaluation test cases designed to help verify the accuracy of ground-water transport codes. 20 refs

Technical support and emergency centre

International Nuclear Information System (INIS)

Bohun, L.; Kapisovsk y, M.

1997-01-01

This paper presents technical support and emergency management center which will be on two places: Mochovce NPP Emergency Centre (Technical support center and Support working center) and Reserve Emergency Centre in Levice (Reserve emergency center and Environmental Evaluation Center). The main aims of the emergency management centers are: the management and coordination of all persons and organisations; provision of the all information needed to evaluation of the accident and its mitigation; continuous evaluation of the potential or real radiological consequences; taking measure for an early notification of the governmental bodies and the organizations, warning and protection of the public; and other aims. In the next part the data for technical support and emergency centre are discussed

Technical Memory 2008. Nuclear Regulatory Authority

International Nuclear Information System (INIS)

2011-01-01

The technical memory 2008 of the Nuclear Regulatory Authority of Argentine Republic, compile the papers published in the subject on radiation protection and nuclear safety, and presented in journals, technical reports, congress or meetings of these specialties by personnel of the mentioned institution during 2008. In this edition the documents are presented on: environmental protection; transport of radioactive materials; regulations; research reactors and nuclear power plants; biological radiation effects; therapeutic uses of ionizing radiation and radioprotection of patients; internal dosimetry; physical dosimetry; knowledge management; radioactive waste management. [es

Global Spent Fuel Logistics Systems Study (GSFLS). Volume 3. GSFLS technical and financial analysis. Interim report

International Nuclear Information System (INIS)

1978-01-01

This report is a part of the interim report documentation for the Global Spent Fuel Logistics System (GSFLS) study. The technical and financial considerations underlying a global spent fuel logistics systems have been studied and are reported herein. The Pacific Basin is used as a model throughout this report; however the stated methodology and, in many cases, considerations and conclusions are applicable to other global regions. Spent fuel discharge profiles for Pacific Basin Countries were used to determine the technical systems requirements for alternative concepts. Functional analyses and flows were generated to define both system design requirements and logistics parameters. A technology review was made to ascertain the state-of-the-art of relevant GSFLS technical systems. Modular GSFLS facility designs were developed using the information generated from the functional analysis and technology review. The modular facility designs were used as a basis for siting and cost estimates for various GSFLS alternatives. Various GSFLS concepts were analyzed from a financial and economic perspective in order to provide total concepts costs and ascertain financial and economic sensitivities to key GSFLS variations. Results of the study include quantification of GSFLS facility and hardware requirements; drawings of relevant GSFLS facility designs; system cost estimates; financial reports - including user service charges; and comparative analyses of various GSFLS alternatives

Global Spent Fuel Logistics Systems Study (GSFLS). Volume 3A. GSFLS technical analysis (appendix). Interim report

International Nuclear Information System (INIS)

1978-01-01

This report is a part of the interim report documentation for the Global Spent Fuel Logistics System (GSFLS) study. The technical and financial considerations underlying a global spent fuel logistics systems have been studied and are reported. The Pacific Basin is used as a model throughout this report; however the stated methodology and, in many cases, considerations and conclusions are applicable to other global regions. Spent fuel discharge profiles for Pacific Basin Countries were used to determine the technical systems requirements for alternative concepts. Functional analyses and flows were generated to define both system design requirements and logistics parameters. A technology review was made to ascertain the state-of-the-art of relevant GSFLS technical systems. Modular GSFLS facility designs were developed using the information generated from the functional analysis and technology review. The modular facility designs were used as a basis for siting and cost estimates for various GSFLS alternatives. Various GSFLS concepts were analyzed from a financial and economic perspective in order to provide total concepts costs and ascertain financial and economic sensitivities to key GSFLS variations. Results of the study include quantification of GSFLS facility and hardware requirements; drawings of relevant GSFLS facility designs; system cost estimates; financial reports - including user service charges; and comparative analyses of various GSFLS alternatives

Global Spent Fuel Logistics Systems Study (GSFLS). Volume 3A. GSFLS technical analysis (appendix). Interim report

Energy Technology Data Exchange (ETDEWEB)

Kriger, A.

1978-01-31

This report is a part of the interim report documentation for the Global Spent Fuel Logistics System (GSFLS) study. The technical and financial considerations underlying a global spent fuel logistics systems have been studied and are reported. The Pacific Basin is used as a model throughout this report; however the stated methodology and, in many cases, considerations and conclusions are applicable to other global regions. Spent fuel discharge profiles for Pacific Basin Countries were used to determine the technical systems requirements for alternative concepts. Functional analyses and flows were generated to define both system design requirements and logistics parameters. A technology review was made to ascertain the state-of-the-art of relevant GSFLS technical systems. Modular GSFLS facility designs were developed using the information generated from the functional analysis and technology review. The modular facility designs were used as a basis for siting and cost estimates for various GSFLS alternatives. Various GSFLS concepts were analyzed from a financial and economic perspective in order to provide total concepts costs and ascertain financial and economic sensitivities to key GSFLS variations. Results of the study include quantification of GSFLS facility and hardware requirements; drawings of relevant GSFLS facility designs; system cost estimates; financial reports - including user service charges; and comparative analyses of various GSFLS alternatives.

Robins Air Force Base integrated resource assessment. Volume 3, Resource assessment

Energy Technology Data Exchange (ETDEWEB)

Sullivan, G.P.; Keller, J.M.; Stucky, D.J.; Wahlstrom, R.R.; Larson, L.L.

1993-10-01

The US Air Force Materiel Command (AFMC) has tasked the US Department of Energy (DOE) Federal Energy Management Program (FEMP), supported by the Pacific Northwest Laboratory (PNL), to identify, evaluate, and assist in acquiring all cost-effective energy projects at Robins Air Force Base (AFB). This is part of a model program that PNL is designing to support energy-use decisions in the federal sector. This report provides the results of the fossil fuel and electric energy resource opportunity (ERO) assessments performed by PNL at the AFMC Robins AFB facility located approximately 15 miles south of Macon, Georgia. It is a companion report to Volume 1, Executive Summary, and Volume 2, Baseline Detail. The results of the analyses of EROs are presented in 13 common energy end-use categories (e.g., boilers and furnaces, service hot water, and building lighting). A narrative-description of each ERO is provided, including information on the installed cost, energy and dollar savings; impacts on operation and maintenance (O&M); and, when applicable, a discussion of energy supply and demand, energy security, and environmental issues. A description of the evaluation methodologies and technical and cost assumptions is also provided for each ERO. Summary tables present the cost-effectiveness of energy end-use equipment before and after the implementation of each ERO and present the results of the life-cycle cost (LCC) analysis indicating the net present value (NPV) and savings to investment ratio (SIR) of each ERO.

Implementation of machine learning for high-volume manufacturing metrology challenges (Conference Presentation)

Science.gov (United States)

Timoney, Padraig; Kagalwala, Taher; Reis, Edward; Lazkani, Houssam; Hurley, Jonathan; Liu, Haibo; Kang, Charles; Isbester, Paul; Yellai, Naren; Shifrin, Michael; Etzioni, Yoav

2018-03-01

across 3 products. In the case of product C, it is found that the predicted Rs correlation to the e-test value is significantly improved utilizing spectra acquired at the e-test structure. This paper will explore the considerations required to enable use of machine learning derived metrology output to enable improved process monitoring and control. Further results from the FEOL and BEOL sectors will be presented, together with further discussion on future proliferation of machine learning based metrology solutions in high volume manufacturing.

Technical specifications manual for the MARK-1 pulsed ionizing radiation detection system

International Nuclear Information System (INIS)

Lawrence, R.S.; Harker, Y.D.; Jones, J.L.; Hoggan, J.M.

1993-03-01

The MARK-1 detection system was developed by the Idaho National Engineering Laboratory for the US Department of Energy Office of Arms Control and Nonproliferation. The completely portable system was designed for the detection and analysis of intense photon emissions from pulsed ionizing radiation sources. This manual presents the technical design specifications for the MARK-1 detection system and was written primarily to assist the support or service technician in the service, calibration, and repair of the system. The manual presents the general detection system theory, the MARK-1 component design specifications, the acquisition and control software, the data processing sequence, and the system calibration procedure. A second manual entitled: Volume 2: Operations Manual for the MARK-1 Pulsed Ionizing Radiation Detection System (USDOE Report WINCO-1108, September 1992) provides a general operational description of the MARK-1 detection system. The Operations Manual was written primarily to assist the field operator in system operations and analysis of the data

Technical procedures for implementation of background environmental radioactivity site studies, Deaf Smith County site, Texas: Environmental Field Program: Preliminary draft

International Nuclear Information System (INIS)

1987-09-01

The purpose of this technical procedure is to describe the method for performing field maintenance on low-volume air samplers and the associated topics of personnel and organization, procedure preparation, documentation, and quality assurance. The scope of this procedure includes the maintenance of low-volume air samplers in the field and does not encompass maintenance performed by the manufacturer

Superfund TIO videos: Set B. Community relations, communicating with the media and presenting technical information. Part 9. Audio-Visual

International Nuclear Information System (INIS)

1990-01-01

The videotape is divided into three sections. Section 1 discusses the Superfund Community Relations (CR) Program and its history and objectives. Community Relations requirements as defined by CERCLA for Superfund actions are outlined. Community Relations requirements, the nature of community involvement in CR plans, effective CR techniques, and the roles of the OSC, RPM, and EPA Community Relations Coordinator (CRC) are discussed. Section 2 (1) describes the media's perspective on seeking information; (2) identifies five settings and mechanisms for interacting with the media; (3) offers good media-relations techniques; and (4) lists tips for conducting media interviews. Section 3 outlines techniques for presenting technical information, describes how to be prepared to address typical issues of community concern, and identifies the four key elements in handling tough questions

Basic Quechua. Volume I: Quechua Reader. Volume II: Quechua Grammar and Dictionary.

Science.gov (United States)

Aitken-Soux, Percy G.; Crapo, Richley H.

Volume I, the reader, has 86 lessons consisting of short passages and vocabulary lists. The language and the stories presented were learned and collected at the Indian community and Hacienda of Cayara near Potosi, Bolivia. Translations of the passages are provided in a separate section. The second volume presents the grammar and phonology of the…

Technical memory 1999

International Nuclear Information System (INIS)

2000-01-01

The technical memory 1999 of the Nuclear Regulatory Authority (NRA) of the Argentine Republic, compile the papers published in the subject on radiation protection and nuclear safety, safeguards and physical protection, and presented in congress or meetings of these specialities by personnel of the mentioned institution during 1999

Scientific and technical guidance for the preparation and presentation of an application for authorisation of a health claim (revision 1)

DEFF Research Database (Denmark)

Tetens, Inge

2011-01-01

The scientific and technical guidance of the EFSA Panel on Dietetic Products, Nutrition and Allergies for the preparation and presentation of an application for authorisation of a health claim presents a common format for the organisation of information for the preparation of a well......-structured application for authorisation of health claims which fall under Article 14 (referring to children’s development and health, and to disease risk reduction claims), or 13(5) (which are based on newly developed scientific evidence and/or which include a request for the protection of proprietary data......), or for the modification of an existing authorisation in accordance with Article 19 of Regulation (EC) No 1924/2006 on nutrition and health claims made on foods. This guidance outlines: the information and scientific data which must be included in the application, the hierarchy of different types of data and study designs...

Improvements to Technical Specifications surveillance requirements

International Nuclear Information System (INIS)

Lobel, R.; Tjader, T.R.

1992-12-01

In August 1983 an NRC task group was formed to investigate problems with surveillance testing required by Technical Specifications, and to recommend approaches to effect improvements. NUREG-1024 (''Technical Specifications-Enhancing Safety Impact'') resulted, and it contained recommendations to review the basis for test frequencies; to ensure that the tests promote safety and do not degrade equipment; and to review surveillance tests so that they do not unnecessarily burden personnel. The Technical Specifications Improvement Program (TSIP) was established in December 1984 to provide the framework for rewriting and improving the Technical Specifications. As an element of the TSIP, all Technical Specifications surveillance requirements were comprehensively examined as recommended in NUREG-1024. The results of that effort are presented in this report. The study found that while some testing at power is essential to verify equipment and system operability, safety can be improved, equipment degradation decreased, and unnecessary personnel burden relaxed by reducing the amount of testing at power