Application for approval of the Cold Lake Expansion Project: volume 2: environmental impact assessment: Part 1: biophysical and resource use assessment. Part 2: impact model descriptions

International Nuclear Information System (INIS)

Green, J.; Eccles, R.; Hegmann, G.; Morrison, L.; Salter, R.; van Egmond, T.; Vonk, P.; Ash, G.; Crowther, R.; Dance, T.; Edwards, W.; Veldman, W.

1997-02-01

An environmental assessment of the Cold Lake Expansion Project has been conducted to identify major issues of concern by public and government agencies, to determine means to eliminate or reduce those impacts, and to recommend any further efforts required to obtain missing information or monitor impacts. Volume 2 of the environmental impact assessment is divided into two parts. Part 1 (biophysical and resource use assessment) constitutes the primary environmental impact assessment document for the Cold Lake expansion project. It includes technical support documentation in regard to: (1) an assessment of noise impacts, (2) an assessment of greenhouse gas emissions, (3) a conceptual conservation and reclamation plan, (4) a historical resource impact assessment, and (5) a description of effects of oil spills on fish. Part 2 (impact model description) serves a reference document for part 1. It describes the approach taken in developing and assessing the impact models, discusses proposed methods for mitigation and management of residual impacts, and the recommended monitoring requirements for each of the major resource disciplines. The impact models describe the specific pathways through which impacts will occur as a result of interactions between project-related activities and important environmental components. 476 refs., 58 tabs., 23 figs

Subseabed disposal program annual report, January-December 1979. Volume II. Appendices (principal investigator progress reports). Part 2 of 2

International Nuclear Information System (INIS)

Talbert, D.M.

1981-04-01

Volume II of the sixth annual report describing the progress and evaluating the status of the Subseabed Disposal Program contains the appendices referred to in Volume II, Summary and Status. Because of the length of Volume II, it has been split into two parts for publication purposes. Part 1 contains Appendices A-O; Part 2 contains Appendices P-FF. Separate abstracts have been prepared for each appendix for inclusion in the Energy Data Base

Compilation of reports of the Advisory Committee on Reactor Safeguards, 1957-1984. Volume 1. Project Reviews A-F

International Nuclear Information System (INIS)

1985-04-01

This six-volume compilation contains over 1000 reports prepared by the Advisory Committee on Reactor Safeguards from September 1957 through December 1984. The reports are divided into two groups: Part 1: ACRS Reports on Project Reviews, and Part 2: ACRS Reports on Generic Subjects. Part 1 contains ACRS reports alphabetized by project name and within project name by chronological order. Part 2 categorizes the reports by the most appropriate generic subject area and within subject area by chronological order. This volume contains project reviews arranged alphabetically from A to F

Y-12 Plant remedial action Technology Logic Diagram: Volume 3, Technology evaluation data sheets: Part A, Remedial action

International Nuclear Information System (INIS)

1994-09-01

The Y-12 Plant Remedial Action Technology Logic Diagram (TLD) was developed to provide a decision-support tool that relates environmental restoration (ER) problems at the Y-12 Plant to potential technologies that can remediate these problems. The TLD identifies the research, development, demonstration, testing, and evaluation needed for sufficient development of these technologies to allow for technology transfer and application to remedial action (RA) activities. The TLD consists of three volumes. Volume 1 contains an overview of the TLD, an explanation of the program-specific responsibilities, a review of identified technologies, and the rankings of remedial technologies. Volume 2 contains the logic linkages among environmental management goals, environmental problems and the various technologies that have the potential to solve these problems. Volume 3 contains the TLD data sheets. This report is Part A of Volume 3 and contains the Remedial Action section

Y-12 Plant remedial action Technology Logic Diagram: Volume 3, Technology evaluation data sheets: Part A, Remedial action

Energy Technology Data Exchange (ETDEWEB)

NONE

1994-09-01

The Y-12 Plant Remedial Action Technology Logic Diagram (TLD) was developed to provide a decision-support tool that relates environmental restoration (ER) problems at the Y-12 Plant to potential technologies that can remediate these problems. The TLD identifies the research, development, demonstration, testing, and evaluation needed for sufficient development of these technologies to allow for technology transfer and application to remedial action (RA) activities. The TLD consists of three volumes. Volume 1 contains an overview of the TLD, an explanation of the program-specific responsibilities, a review of identified technologies, and the rankings of remedial technologies. Volume 2 contains the logic linkages among environmental management goals, environmental problems and the various technologies that have the potential to solve these problems. Volume 3 contains the TLD data sheets. This report is Part A of Volume 3 and contains the Remedial Action section.

Oak Ridge National Laboratory Technology Logic Diagram. Volume 3, Technology evaluation data sheets: Part B, Dismantlement, Remedial action

Energy Technology Data Exchange (ETDEWEB)

1993-09-01

The Oak Ridge National Laboratory Technology Logic Diagram (TLD) was developed to provide a decision support tool that relates environmental restoration (ER) and waste management (WM) problems at Oak Ridge National Laboratory (ORNL) to potential technologies that can remediate these problems. The TLD identifies the research, development, demonstration testing, and evaluation needed to develop these technologies to a state that allows technology transfer and application to decontamination and decommissioning (D&D), remedial action (RA), and WM activities. The TLD consists of three fundamentally separate volumes: Vol. 1, Technology Evaluation; Vol. 2, Technology Logic Diagram and Vol. 3, Technology EvaLuation Data Sheets. Part A of Vols. 1 and 2 focuses on RA. Part B of Vols. 1 and 2 focuses on the D&D of contaminated facilities. Part C of Vols. 1 and 2 focuses on WM. Each part of Vol. 1 contains an overview of the TM, an explanation of the problems facing the volume-specific program, a review of identified technologies, and rankings of technologies applicable to the site. Volume 2 (Pts. A. B. and C) contains the logic linkages among EM goals, environmental problems, and the various technologies that have the potential to solve these problems. Volume 3 (Pts. A. B, and C) contains the TLD data sheets. This volume provides the technology evaluation data sheets (TEDS) for ER/WM activities (D&D, RA and WM) that are referenced by a TEDS code number in Vol. 2 of the TLD. Each of these sheets represents a single logic trace across the TLD. These sheets contain more detail than is given for the technologies in Vol. 2.

Radioactive decay properties of CANDU fuel. Volume 1: the natural uranium fuel cycle

International Nuclear Information System (INIS)

Clegg, L.J.; Coady, J.R.

1977-01-01

The two books of Volume 1 comprise the first in a three-volume series of compilations on the radioactive decay propertis of CANDU fuel and deal with the natural uranium fuel cycle. Succeeding volumes will deal with fuel cycles based on plutonium recycle and thorium. In Volume 1 which is divided into three parts, the computer code CANIGEN was used to obtain the mass, activity, decay heat and toxicity of CANDU fuel and its component isotopes. Data are also presented on gamma spectra and neutron emissions. Part 3 contains the data relating to the plutonium product and the high level wastes produced during fuel reprocessing. (author)

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

International Nuclear Information System (INIS)

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

1986-05-01

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

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

Energy Technology Data Exchange (ETDEWEB)

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

1986-05-01

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

Oak Ridge National Laboratory Technology Logic Diagram. Volume 3, Technology evaluation data sheets: Part C, Robotics/automation, Waste management

Energy Technology Data Exchange (ETDEWEB)

1993-09-01

The Oak Ridge National Laboratory Technology Logic Diagram (TLD) was developed to provide a decision support tool that relates environmental restoration (ER) and waste management (WM) problems at Oak Ridge National Laboratory (ORNL) to potential technologies that can remediate these problems. The TLD identifies the research, development, demonstration testing, and evaluation needed to develop these technologies to a state that allows technology transfer and application to decontamination and decommissioning (D&D), remedial action (RA), and WM activities. The TLD consists of three fundamentally separate volumes: Vol. 1, Technology Evaluation; Vol. 2, Technology Logic Diagram and Vol. 3, Technology EvaLuation Data Sheets. Part A of Vols. 1 and 2 focuses on RA. Part B of Vols. 1 and 2 focuses on the D&D of contaminated facilities. Part C of Vols. 1 and 2 focuses on WM. Each part of Vol. 1 contains an overview of the TM, an explanation of the problems facing the volume-specific program, a review of identified technologies, and rankings of technologies applicable to the site. Volume 2 (Pts. A. B. and C) contains the logic linkages among EM goals, environmental problems, and the various technologies that have the potential to solve these problems. Volume 3 (Pts. A. B, and C) contains the TLD data sheets. This volume provides the technology evaluation data sheets (TEDS) for ER/WM activities (D&D, RA and WM) that are referenced by a TEDS code number in Vol. 2 of the TLD. Each of these sheets represents a single logic trace across the TLD. These sheets contain more detail than is given for the technologies in Vol. 2.

Regular Topologies for Gigabit Wide-Area Networks. Volume 1

Science.gov (United States)

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

1994-01-01

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

Nuestras cuentas diarias: Matematicas. Primaria para adultos, Primera parte, Volumens 1 y 2. Edicion Experimental (Our Daily Accounting: Mathematics. Primer for Adults, Part One, Volumes 1 and 2. Experimental Edition).

Science.gov (United States)

Instituto Nacional para la Educacion de los Adultos, Mexico City (Mexico).

These workbooks are part of a Mexican series of instructional materials designed for Spanish speaking adults who are in the process of becoming literate or have recently become literate in their native language. The workbooks, divided in two volumes, are designed to teach skills required in managing ordinary financial transactions and daily tasks…

Oak Ridge National Laboratory Technology Logic Diagram. Volume 2, Technology Logic Diagram: Part B, Remedial Action

Energy Technology Data Exchange (ETDEWEB)

1993-09-01

The Oak Ridge National Laboratory Technology Logic Diagram (TLD) was developed to provide a decision support tool that relates environmental restoration (ER) and waste management (WM) problems at Oak Ridge National Laboratory (ORNL) to potential technologies that can remediate these problems. The TLD identifies the research, development, demonstration, testing, and evaluation needed to develop these technologies to a state that allows technology transfer and application to decontamination and decommissioning (D&D), remedial action (RA), and WM activities. The TLD consists of three fundamentally separate volumes: Vol. 1 (Technology Evaluation), Vol. 2 (Technology Logic Diagram), and Vol. 3 (Technology Evaluation Data Sheets). Part A of Vols. 1. and 2 focuses on D&D. Part B of Vols. 1 and 2 focuses on the RA of contaminated facilities. Part C of Vols. 1 and 2 focuses on WM. Each part of Vol. 1 contains an overview of the TLD, an explanation of the program-specific responsibilities, a review of identified technologies, and the rankings of remedial technologies. Volume 2 (Pts. A, B, and C) contains the logic linkages among EM goals, environmental problems, and the various technologies that have the potential to solve these problems. Volume 3 (Pts. A, B, and C) contains the TLD data sheets. Remedial action is the focus of Vol. 2, Pt. B, which has been divided into the three necessary subelements of the RA: characterization, RA, and robotics and automation. Each of these sections address general ORNL problems, which are then broken down by problem area/constituents and linked to potential remedial technologies. The diagrams also contain summary information about a technology`s status, its science and technology needs, and its implementation needs.

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

International Nuclear Information System (INIS)

1996-06-01

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

Real analysis a comprehensive course in analysis, part 1

CERN Document Server

Simon, Barry

2015-01-01

A Comprehensive Course in Analysis by Poincaré Prize winner Barry Simon is a five-volume set that can serve as a graduate-level analysis textbook with a lot of additional bonus information, including hundreds of problems and numerous notes that extend the text and provide important historical background. Depth and breadth of exposition make this set a valuable reference source for almost all areas of classical analysis. Part 1 is devoted to real analysis. From one point of view, it presents the infinitesimal calculus of the twentieth century with the ultimate integral calculus (measure theory)

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

Energy Technology Data Exchange (ETDEWEB)

None

1996-06-01

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

A Structural Molar Volume Model for Oxide Melts Part III: Fe Oxide-Containing Melts

Science.gov (United States)

Thibodeau, Eric; Gheribi, Aimen E.; Jung, In-Ho

2016-04-01

As part III of this series, the model is extended to iron oxide-containing melts. All available experimental data in the FeO-Fe2O3-Na2O-K2O-MgO-CaO-MnO-Al2O3-SiO2 system were critically evaluated based on the experimental condition. The variations of FeO and Fe2O3 in the melts were taken into account by using FactSage to calculate the Fe2+/Fe3+ distribution. The molar volume model with unary and binary model parameters can be used to predict the molar volume of the molten oxide of the Li2O-Na2O-K2O-MgO-CaO-MnO-PbO-FeO-Fe2O3-Al2O3-SiO2 system in the entire range of compositions, temperatures, and oxygen partial pressures from Fe saturation to 1 atm pressure.

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

Energy Technology Data Exchange (ETDEWEB)

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

1995-04-01

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

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

International Nuclear Information System (INIS)

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

1995-04-01

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

Plasma diagnostics package. Volume 2: Spacelab 2 section. Part B: Thesis projects

Science.gov (United States)

Pickett, Jolene S. (Compiler); Frank, L. A. (Compiler); Kurth, W. S. (Compiler)

1988-01-01

This volume (2), which consists of two parts (A and B), of the Plasma Diagnostics Package (PDP) Final Science Report contains a summary of all of the data reduction and scientific analyses which were performed using PDP data obtained on STS-51F as a part of the Spacelab 2 (SL-2) payload. This work was performed during the period of launch, July 29, 1985, through June 30, 1988. During this period the primary data reduction effort consisted of processing summary plots of the data received by 12 of the 14 instruments located on the PDP and submitting these data to the National Space Science Data Center (NSSDC). Three Master's and three Ph.D. theses were written using PDP instrumentation data. These theses are listed in Volume 2, Part B.

Surplus plutonium disposition draft environmental impact statement. Volume 1, Part A

International Nuclear Information System (INIS)

1998-07-01

On May 22, 1997, DOE published a Notice of Intent (NOI) in the Federal Register (62 Federal Register 28009) announcing its decision to prepare an environmental impact statement (EIS) that would tier from the analysis and decisions reached in connection with the Storage and Disposition of Weapons-Usable Fissile Materials Final Programmatic EIS (Storage and Disposition PEIS). DOE's disposition strategy allows for both the immobilization of surplus plutonium and its use as mixed oxide (MOX) fuel in existing domestic, commercial reactors. The disposition of surplus plutonium would also involve disposal of the immobilized plutonium and MOX fuel (as spent nuclear fuel) in a geologic repository. The Surplus Plutonium Disposition Environmental Impact Statement analyzes alternatives that would use the immobilization approach (for some of the surplus plutonium) and the MOX fuel approach (for some of the surplus plutonium); alternatives that would immobilize all of the surplus plutonium; and the No Action Alternative. The alternatives include three disposition facilities that would be designed so that they could collectively accomplish disposition of up to 50 metric tons (55 tons) of surplus plutonium over their operating lives: (1) the pit disassembly and conversion facility would disassemble pits (a weapons component) and convert the recovered plutonium, as well as plutonium metal from other sources, into plutonium dioxide suitable for disposition; (2) the immobilization facility would include a collocated capability for converting nonpit plutonium materials into plutonium dioxide suitable for immobilization and would be located at either Hanford or SRS. DOE has identified SRS as the preferred site for an immobilization facility; (3) the MOX fuel fabrication facility would fabricate plutonium dioxide into MOX fuel. This volume includes background information; purpose of and need for the proposed action; alternatives for disposition of surplus weapons useable plutonium; and

Trends in laboratory test volumes for Medicare Part B reimbursements, 2000-2010.

Science.gov (United States)

Shahangian, Shahram; Alspach, Todd D; Astles, J Rex; Yesupriya, Ajay; Dettwyler, William K

2014-02-01

Changes in reimbursements for clinical laboratory testing may help us assess the effect of various variables, such as testing recommendations, market forces, changes in testing technology, and changes in clinical or laboratory practices, and provide information that can influence health care and public health policy decisions. To date, however, there has been no report, to our knowledge, of longitudinal trends in national laboratory test use. To evaluate Medicare Part B-reimbursed volumes of selected laboratory tests per 10,000 enrollees from 2000 through 2010. Laboratory test reimbursement volumes per 10,000 enrollees in Medicare Part B were obtained from the Centers for Medicare & Medicaid Services (Baltimore, Maryland). The ratio of the most recent (2010) reimbursed test volume per 10,000 Medicare enrollees, divided by the oldest data (usually 2000) during this decade, called the volume ratio, was used to measure trends in test reimbursement. Laboratory tests with a reimbursement claim frequency of at least 10 per 10,000 Medicare enrollees in 2010 were selected, provided there was more than a 50% change in test reimbursement volume during the 2000-2010 decade. We combined the reimbursed test volumes for the few tests that were listed under more than one code in the Current Procedural Terminology (American Medical Association, Chicago, Illinois). A 2-sided Poisson regression, adjusted for potential overdispersion, was used to determine P values for the trend; trends were considered significant at P reimbursement volumes were electrolytes, digoxin, carbamazepine, phenytoin, and lithium, with volume ratios ranging from 0.27 to 0.64 (P reimbursement volumes were meprobamate, opiates, methadone, phencyclidine, amphetamines, cocaine, and vitamin D, with volume ratios ranging from 83 to 1510 (P reimbursement volumes increased for most of the selected tests, other tests exhibited statistically significant downward trends in annual reimbursement volumes. The observed

OREDA offshore and onshore reliability data volume 1 - topside equipment

CERN Document Server

OREDA

2015-01-01

This handbook presents high quality reliability data for offshore equipment collected during phase VI to IX (project period 2000 – 2009) of the OREDA project. The intention of the handbook is to provide both quantitative and qualitative information as a basis for Performance Forecasting or RAMS (Reliability, Availability, Maintainability and Safety) analyses. Volume 1 is about Topside Equipment. Compared to earlier editions, there are only minor changes in the reliability data presentation. To obtain a reasonable population for presenting reliability data for topside equipment in the 2015 edition, some data from phases VI and VII already issued in the previous 2009 handbook (5th edition) have also been included. The 2015 topside volume is divided into two parts. Part I describes the OREDA project, different data collection phases and the estimation procedures used to generate the data tables presented in Part II of the handbook. Topside data are in general not covering the whole lifetime of equipment, but ...

Nuclear computerized library for assessing reactor reliability (NUCLARR): Data manual: Part 1, Summary description

International Nuclear Information System (INIS)

Gertman, D.I.; Gilbert, B.G.; Gilmore, W.E.; Galyean, W.J.

1988-06-01

This volume of a five-volume series summarizes those data currently resident in the first release of the Nuclear Computerized Library for Assessing Reactor Reliability (NUCLARR) data base. The raw human error probability (HEP) and hardware component failure data (HCFD) contained herein are accompanied by a glossary of terms and the HEP and hardware taxonomies used to structure the data. Instructions are presented on how the user may navigate through the NUCLARR data management system to find anchor values to assist in solving risk-related problems. Volume V: Data Manual will be updated on a periodic basis so that risk analysis without access to a computer may have access to the largest NUCLARR data. This document Part 1 of Volume 5 introduces aspects of the NUCLARR data base management system and prepares the reader for reviewing data in other Parts of Volume 5

International Nuclear Model. Volume 3. Program description. Appendix A-H (Part 1)

International Nuclear Information System (INIS)

Andress, D.

1985-01-01

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 decisions 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. This volume contains appendices A through H including a description of subroutines and the Fortran listing of the program

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

Science.gov (United States)

1999-11-01

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

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

Optimal repairable spare-parts procurement policy under total business volume discount environment

International Nuclear Information System (INIS)

Pascual, Rodrigo; Santelices, Gabriel; Lüer-Villagra, Armin; Vera, Jorge; Cawley, Alejandro Mac

2017-01-01

In asset intensive fields, where components are expensive and high system availability is required, spare parts procurement is often a critical issue. To gain competitiveness and market share is common for vendors to offer Total Business Volume Discounts (TBVD). Accordingly, companies must define the procurement and stocking policy of their spare parts in order to reduce procurement costs and increase asset availability. In response to those needs, this work presents an optimization model that maximizes the availability of the equipment under a TBVD environment, subject to a budget constraint. The model uses a single-echelon structure where parts can be repaired. It determines the optimal number of repairable spare parts to be stocked, giving emphasis on asset availability, procurement costs and service levels as the main decision criteria. A heuristic procedure that achieves high quality solutions in a fast and time-consistent way was implemented to improve the time required to obtain the model solution. Results show that using an optimal procurement policy of spare parts and accounting for TBVD produces better overall results and yields a better availability performance. - Highlights: • We propose a model for procurement of repairable components in single-echelon and business volume discount environments. • We used a mathematical model to develop a competitive heuristic that provides high quality solutions in very short times. • Our model places emphasis on using system availability, procurement costs and service levels as leading decision criteria. • The model can be used as an engine for a multi-criteria Decision Support System.

Inductively coupled plasma emission spectroscopy. Part II: applications and fundamentals. Volume 2

International Nuclear Information System (INIS)

Boumans, P.W.J.M.

1987-01-01

This is the second part of the two-volume treatise by this well-known and respected author. This volume reviews applications of inductively coupled plasma atomic emission spectroscopy (ICP-AES), summarizes fundamental studies, and compares ICP-AES methods with other methods of analysis. The first six chapters are devoted to specific fields of application, including the following: metals and other industrial materials, geology, the environment, agriculture and food, biology and clinical analysis, and organic materials. The chapter on the analysis of organic materials also covers the special instrumental considerations required when organic solvents are introduced into an inductively coupled plasma. A chapter on the direct analysis of solids completes the first part of this volume. Each of the applications chapters begins with a summary of the types of samples that are encountered in that field, and the kinds of problems that an elemental analysis can help to solve. This is followed by a tutorial approach covering applicability, advantages, and limitations of the methods. The coverage is thorough, including sample handling, storage, and preparation, acid, and fusion dissolution, avoiding contamination, methods of preconcentration, the types of interferences that can be expected and ways to reduce them, and the types of ICP plasmas that are used. The second half of the volume covers fundamental studies of ICP-AES: basic processes of aerosol generation, plasma modeling and computer simulation, spectroscopic diagnostics, excitation mechanisms, and discharge characteristics. This section introduces the experimental and modeling methods that have been used to obtain fundamental information about ICPs

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

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-06-01

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

Hanford Site background: Part 1, Soil background for nonradioactive analytes. Revision 1, Volume 2

Energy Technology Data Exchange (ETDEWEB)

1993-04-01

Volume two contains the following appendices: Description of soil sampling sites; sampling narrative; raw data soil background; background data analysis; sitewide background soil sampling plan; and use of soil background data for the detection of contamination at waste management unit on the Hanford Site.

Petroleum supply annual 1994. Volume 1

International Nuclear Information System (INIS)

1995-01-01

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

Plasma diagnostics package. Volume 2: Spacelab 2 section. Part B: Thesis projects. Final science report

International Nuclear Information System (INIS)

Pickett, J.S.; Frank, L.A.; Kurth, W.S.

1988-06-01

This volume (2), which consists of two parts (A and B), of the Plasma Diagnostics Package (PDP) Final Science Report contains a summary of all of the data reduction and scientific analyses which were performed using PDP data obtained on STS-51F as a part of the Spacelab 2 (SL-2) payload. This work was performed during the period of launch, July 29, 1985, through June 30, 1988. During this period the primary data reduction effort consisted of processing summary plots of the data received by 12 of the 14 instruments located on the PDP and submitting these data to the National Space Science Data Center (NSSDC). Three Master's and three Ph.D. theses were written using PDP instrumentation data. These theses are listed in Volume 2, Part B

Y-12 Plant remedial action Technology Logic Diagram: Volume 3, Technology evaluation data sheets: Part B, Characterization; robotics/automation

International Nuclear Information System (INIS)

1994-09-01

The Y-12 Plant Remedial Action Technology Logic Diagram (TLD) was developed to provide a decision-support tool that relates environmental restoration (ER) problems at the Y-12 Plant to potential technologies that can remediate theses problems. The TLD identifies the research, development, demonstration, testing, and evaluation needed for sufficient development of these technologies to allow for technology transfer and application to remedial action (RA) activities. The TLD consists of three volumes. Volume 1 contains an overview of the TLD, an explanation of the program-specific responsibilities, a review of identified technologies, and the rankings of remedial technologies. Volume 2 contains the logic linkages among environmental management goals, environmental problems, and the various technologies that have the potential to solve these problems. Volume 3 contains the TLD data sheets. This report is Part B of Volume 3 and contains the Characterization and Robotics/Automation sections

single photon emission tomography and positron emission tomography - Part 1 (October 2012), Part 2 (October 2010)

International Nuclear Information System (INIS)

Buvat, Irene

2010-10-01

The objective of this lecture is to present the single photon emission computed tomography (SPECT) and the positron emission tomography (PET) imaging techniques. Part 1 Content: 1 - Introduction: anatomic, functional and molecular imaging; 2 - Radiotracers: chemical and physical constraints, gamma photon emitters, positon emitters, radioisotopes production, emitters type and imaging techniques; 3 - Gamma cameras; 4 - Quantification in emission tomography: attenuation, scattering, un-stationary spatial resolution; 5 - Synthesis and conclusion. Part 2 content: 1 - Positon emitters; 2 - Positons detection: Coincidence detection (electronic collimation, PET detectors with gamma cameras, dedicated PET detectors, spectrometry); PET detectors type; time-of-flight PET; 2D PET; 3D PET; 3 - Quantification in emission tomography: detected events, attenuation, scattering, fortuitous coincidences, standardisation; 4 - Common SPECT and PET problems: partial volume effect, movement, tomographic reconstruction, calibration, dead time; 5 - Synthesis and conclusion

Evaluation of potential severe accidents during low power and shutdown operations at Grand Gulf, Unit 1: Analysis of core damage frequency from internal events for Plant Operational State 5 during a refueling outage. Volume 2, Part 3: Internal Events Appendices I and J

Energy Technology Data Exchange (ETDEWEB)

Yakle, J. [Science Applications International Corp., Albuquerque, NM (United States); Darby, J. [Science and Engineering Associates, Inc., Albuquerque, NM (United States); Whitehead, D.; Staple, B. [Sandia National Labs., Albuquerque, NM (United States)

1994-06-01

This report provides supporting documentation for various tasks associated with the performance of the probablistic risk assessment for Plant Operational State 5 during a refueling outage at Grand Gulf, Unit 1 as documented in Volume 2, Part 1 of NUREG/CR-6143.

Evaluation of potential severe accidents during low power and shutdown operations at Grand Gulf, Unit 1: Analysis of core damage frequency from internal events for Plant Operational State 5 during a refueling outage. Volume 2, Part 3: Internal Events Appendices I and J

International Nuclear Information System (INIS)

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

1994-06-01

This report provides supporting documentation for various tasks associated with the performance of the probablistic risk assessment for Plant Operational State 5 during a refueling outage at Grand Gulf, Unit 1 as documented in Volume 2, Part 1 of NUREG/CR-6143

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.

Water Resources Data. Ohio - Water Year 1992. Volume 1. Ohio River Basin excluding project data

Energy Technology Data Exchange (ETDEWEB)

H.L. Shindel; J.H. Klingler; J.P. Mangus; L.E. Trimble

1993-03-01

Water-resources data for the 1992 water year for Ohio consist of records of stage, discharge, and water quality of streams; stage and contents of lakes and reservoirs; and water levels and water quality of ground-water wells. This report, in two volumes, contains records for water discharge at 121 gaging stations, 336 wells, and 72 partial-record sites; and water levels at 312 observation wells. Also included are data from miscellaneous sites. Additional water data were collected at various sites not involved in the systematic data-collection program and are published as miscellaneous measurements and analyses. These data represent that part of the National Water Data System collected by the US Geological Survey and cooperating State and Federal agencies in Ohio. Volume 1 covers the central and southern parts of Ohio, emphasizing the Ohio River Basin. (See Order Number DE95010451 for Volume 2 covering the northern part of Ohio.)

Plasma diagnostics package. Volume 2: Spacelab 2 section, part A

Science.gov (United States)

Pickett, Jolene S. (Compiler); Frank, L. A. (Compiler); Kurth, W. S. (Compiler)

1988-01-01

This volume (2), which consists of two parts (A and B), of the Plasma Diagnostics Package (PDP) Final Science Report contains a summary of all of the data reduction and scientific analyses which were performed using PDP data obtained on STS-51F as a part of the Spacelab 2 (SL-2) payload. This work was performed during the period of launch, July 29, l985, through June 30, l988. During this period the primary data reduction effort consisted of processing summary plots of the data received by 12 of the 14 instruments located on the PDP and submitting these data to the National Space Science Data Center (NSSDC). The scientific analyses during the performance period consisted of follow-up studies of shuttle orbiter environment and orbiter/ionosphere interactions and various plasma particle and wave studies which dealt with data taken when the PDP was on the Remote Manipulator System (RMS) arm and when the PDP was in free flight. Of particular interest during the RMS operations and free flight were the orbiter wake studies and joint studies of beam/plasma interactions with the SL-2 Fast Pulse Electron Generator (FPEG) of the Vehicle Charging and Potential Investigation (VCAP). Internal reports, published papers and presentations which involve PDP/SL-2 data are listed in Sections 3 and 4. A PDP/SL-2 scientific results meeting was held at the University of Iowa on June 10, l986. This meeting was attended by most of the PDP and VCAP investigators and provided a forum for discussing and comparing the various results, particularly with regard to the PDP free flight.

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

International Nuclear Information System (INIS)

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

1994-06-01

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

Market projections of cellulose nanomaterial-enabled products- Part 1: Applications

Science.gov (United States)

Jo Anne Shatkin; Theodore H. Wegner; E.M. (Ted) Bilek; John Cowie

2014-01-01

Nanocellulose provides a new materials platform for the sustainable production of high-performance nano-enabled products in an array of applications. In this paper, potential applications for cellulose nanomaterials are identified as the first step toward estimating market volume. The overall study, presented in two parts, estimates market volume on the basis of...

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

Critical Propulsion Components. Volume 1; Summary, Introduction, and Propulsion Systems Studies

Science.gov (United States)

2005-01-01

Several studies have concluded that a supersonic aircraft, if environmentally acceptable and economically viable, could successfully compete in the 21st century marketplace. However, before industry can commit to what is estimated as a 15 to 20 billion dollar investment, several barrier issues must be resolved. In an effort to address these barrier issues, NASA and Industry teamed to form the High-Speed Research (HSR) program. As part of this program, the Critical Propulsion Components (CPC) element was created and assigned the task of developing those propulsion component technologies necessary to: (1) reduce cruise emissions by a factor of 10 and (2) meet the ever-increasing airport noise restrictions with an economically viable propulsion system. The CPC-identified critical components were ultra-low emission combustors, low-noise/high-performance exhaust nozzles, low-noise fans, and stable/high-performance inlets. Propulsion cycle studies (coordinated with NASA Langley Research Center sponsored airplane studies) were conducted throughout this CPC program to help evaluate candidate components and select the best concepts for the more complex and larger scale research efforts. The propulsion cycle and components ultimately selected were a mixed-flow turbofan (MFTF) engine employing a lean, premixed, prevaporized (LPP) combustor coupled to a two-dimensional mixed compression inlet and a two-dimensional mixer/ejector nozzle. Due to the large amount of material presented in this report, it was prepared in four volumes; Volume 1: Summary, Introduction, and Propulsion System Studies, Volume 2: Combustor, Volume 3: Exhaust Nozzle, and Volume 4: Inlet and Fan/ Inlet Acoustic Team.

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

Energy Technology Data Exchange (ETDEWEB)

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

1962-08-15

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

Nuclear fuel technology - Tank calibration and volume determination for nuclear materials accountancy - Part 2: Data standardization for tank calibration

International Nuclear Information System (INIS)

2007-01-01

Measurements of the volume and height of liquid in a process accountancy tank are often made in order to estimate or verify the tank's calibration or volume measurement equation. The calibration equation relates the response of the tank's measurement system to some independent measure of tank volume. The ultimate purpose of the calibration exercise is to estimate the tank's volume measurement equation (the inverse of the calibration equation), which relates tank volume to measurement system response. In this part of ISO 18213, it is assumed that the primary measurement-system response variable is liquid height and that the primary measure of liquid content is volume. This part of ISO 18213 presents procedures for standardizing a set of calibration data to a fixed set of reference conditions so as to minimize the effect of variations in ambient conditions that occur during the measurement process. The procedures presented herein apply generally to measurements of liquid height and volume obtained for the purpose of calibrating a tank (i.e. calibrating a tank's measurement system). When used in connection with other parts of ISO 18213, these procedures apply specifically to tanks equipped with bubbler probe systems for measuring liquid content. The standardization algorithms presented herein can be profitably applied when only estimates of ambient conditions, such as temperature, are available. However, the most reliable results are obtained when relevant ambient conditions are measured for each measurement of volume and liquid height in a set of calibration data. Information is provided on scope, physical principles, data required, calibration data, dimensional changes in the tank, multiple calibration runs and results on standardized calibration data. Four annexes inform about density of water, buoyancy corrections for mass determination, determination of tank heel volume and statistical method for aligning data from several calibration runs. A bibliography is

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

Science.gov (United States)

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

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

Radiological status of the Saint-Pierre (Cantal) uranium mine and of its environment. Volume 1 + volume 2 + volume 3

International Nuclear Information System (INIS)

2006-01-01

The first volume reports detailed investigations performed by the CRIIRAD (sampling and radiological controls of sediments, and more particularly of waters and aquatic plants) in different areas about the Saint-Pierre uranium mine in France (Cantal department). Measurements were performed by gamma spectrometry. The second part concerns external exposure and the radiological characterization of soils. The third part reports the study of the presence of radon in outdoor and indoor air. For each of these aspects, methodological information is given as well as a great quantity of measurement results

Is a volume of 3.6 mL better than 1.8 mL for inferior alveolar nerve blocks in patients with symptomatic irreversible pulpitis?

Science.gov (United States)

Fowler, Sara; Reader, Al

2013-08-01

The purpose of this retrospective study was to determine the success of the inferior alveolar nerve (IAN) block using either 3.6 mL or 1.8 mL 2% lidocaine with 1:100,000 epinephrine in patients presenting with symptomatic irreversible pulpitis. As part of 7 previously published studies, 319 emergency patients presenting with symptomatic irreversible pulpitis received either a 1.8-mL volume or 3.6-mL volume of 2% lidocaine with 1:100,000 epinephrine in an IAN block. One hundred ninety patients received a 1.8-mL volume, and 129 received a 3.6-mL volume. Endodontic emergency treatment was completed on each subject. Success was defined as the ability to access and instrument the tooth without pain (visual analog scale score of 0) or mild pain (VAS rating ≤54 mm). Success of the 1.8-mL volume was 28%, and for the 3.6-mL volume it was 39%. There was no statistically significant difference between the 2 volumes. In conclusion, for patients presenting with irreversible pulpitis, success was not significantly different between a 3.6-mL volume and a 1.8-mL volume of 2% lidocaine with 1:100,000 epinephrine. The success rates (28%-39%) with either volume were not high enough to ensure complete pulpal anesthesia. Copyright © 2013 American Association of Endodontists. Published by Elsevier Inc. All rights reserved.

Flow rate measurement in a volume

Energy Technology Data Exchange (ETDEWEB)

Galvez, Cristhian

2018-04-17

A system for measuring flow rate within a volume includes one or more transmission devices that transmit one or more signals through fluid contained within the volume. The volume may be bounded, at least in part, by an outer structure and by an object at least partially contained within the outer structure. A transmission device located at a first location of the outer structure transmits a first signal to a second location of the outer structure. A second signal is transmitted through the fluid from the second location to a third location of the outer structure. The flow rate of the fluid within the volume may be determined based, at least in part, on the time of flight of both the first signal and the second signal.

Plasma diagnostics package. Volume 1: OSS-1 section

Science.gov (United States)

Pickett, Jolene S. (Compiler); Frank, L. A. (Compiler); Kurth, W. S. (Compiler)

1988-01-01

This volume (1) of the Plasma Diagnostics Package (PDP) final science report contains a summary of all of the data reduction and scientific analyses which were performed using PDP data obtained on STS-3 as a part of the Office of Space Science first payload (OSS-1). This work was performed during the period of launch, March 22, l982, through June 30, l983. During this period the primary data reduction effort consisted of processing summary plots of the data received by the 14 instruments located on the PDP and submitting these data to the National Space Science Data Center (NSSDC). The scientific analyses during the performance period consisted of general studies which incorporated the results of several of the PDP's instruments, detailed studies which concentrated on data from only one or two of the instruments, and joint studies of beam-plasma interactions with the OSS-1 Fast Pulse Electron Generator (FPEG) of the Vehicle Charging and Potential Investigation (VCAP). Internal reports, published papers and oral presentations which involve PDP/OSS-1 data are listed in Sections 3 and 4. A PDP/OSS-1 scientific results meeting was held at the University of Iowa on April 19-20, 1983. This meeting was attended by most of the PDP and VCAP investigators and provided a forum for discussing and comparing the various results, particularly with regard to the shuttle orbiter environment. One of the most important functional objectives of the PDP on OSS-1 was to characterize the orbiter environment.

MOD-5A wind turbine generator program design report: Volume 1: Executive Summary

Science.gov (United States)

1984-01-01

The design, development and analysis of the 7.3 MW MOD-5A wind turbine generator covering work performed between July 1980 and June 1984 is discussed. The report is divided into four volumes: Volume 1 summarizes the entire MOD-5A program, Volume 2 discusses the conceptual and preliminary design phases, Volume 3 describes the final design of the MOD-5A, and Volume 4 contains the drawings and specifications developed for the final design. Volume 1, the Executive Summary, summarizes all phases of the MOD-5A program. The performance and cost of energy generated by the MOD-5A are presented. Each subsystem - the rotor, drivetrain, nacelle, tower and foundation, power generation, and control and instrumentation subsystems - is described briefly. The early phases of the MOD-5A program, during which the design was analyzed and optimized, and new technologies and materials were developed, are discussed. Manufacturing, quality assurance, and safety plans are presented. The volume concludes with an index of volumes 2 and 3.

NASA Aerospace Flight Battery Program: Wet Life of Nickel-Hydrogen (Ni-H2) Batteries. Volume 1, Part 3

Science.gov (United States)

Jung, David S.; Lee, Leonine S.; Manzo, Michelle A.

2010-01-01

This NASA Aerospace Flight Battery Systems Working Group was chartered within the NASA Engineering and Safety Center (NESC). The Battery Working Group was tasked to complete tasks and to propose proactive work to address battery related, agency-wide issues on an annual basis. In its first year of operation, this proactive program addressed various aspects of the validation and verification of aerospace battery systems for NASA missions. Studies were performed, issues were discussed and in many cases, test programs were executed to generate recommendations and guidelines to reduce risk associated with various aspects of implementing battery technology in the aerospace industry. This document contains Part 3 - Volume I: Wet Life of Nickel-Hydrogen (Ni-H2) Batteries of the program's operations.

Ocean Thermal Energy Converstion (OTEC) test facilities study program. Final report. Volume II. Part B

Energy Technology Data Exchange (ETDEWEB)

None

1977-01-17

Results are presented of an 8-month study to develop alternative non-site-specific OTEC facilities/platform requirements for an integrated OTEC test program which may include land and floating test facilities. Volume II--Appendixes is bound in three parts (A, B, and C) which together comprise a compendium of the most significant detailed data developed during the study. Part B provides an annotated test list and describes component tests and system tests.

A Theory of Intellectual Development: Part 1.

Science.gov (United States)

Confrey, Jere

1994-01-01

Part 1 of a three-part article analyzing radical constructivism (as one interpretation of Piaget) and the socio-cultural perspective (as one interpretation of Vygotsky), including major principles, primary contributions to mathematics education, and potential limitations. Introduces an integration of the two theories through a feminist…

Volume 9 Number 1

African Journals Online (AJOL)

OLUWOLE

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

Purinergic signalling - a possible mechanism for KCNQ1 channel response to cell volume challenges

DEFF Research Database (Denmark)

Bomholtz, Sofia Hammami; Willumsen, Niels J.; Meinild, A.-K.

2013-01-01

AIM: A number of K(+) channels are regulated by small, fast changes in cell volume. The mechanisms underlying cell volume sensitivity are not known, but one possible mechanism could be purinergic signalling. Volume activated ATP release could trigger signalling pathways that subsequently lead...... stimuli. Basal ATP release was approx. three times higher in the KCNQ1 + AQP1 and KCNQ1 injected oocytes compared to the non-injected ones. Exogenously added ATP (0.1 mm) did not have any substantial effect on volume-induced KCNQ1 currents. Nevertheless, apyrase decreased all currents by about 50...

Petroleum supply annual 1998: Volume 1

Energy Technology Data Exchange (ETDEWEB)

NONE

1999-06-01

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

Petroleum supply annual, 1997. Volume 1

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-06-01

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

Petroleum supply annual 1992: Volume 1

International Nuclear Information System (INIS)

1993-01-01

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

Petroleum supply annual 1998: Volume 1

International Nuclear Information System (INIS)

1999-06-01

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

Petroleum supply annual, 1997. Volume 1

International Nuclear Information System (INIS)

1998-06-01

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

Surplus plutonium disposition draft environmental impact statement. Volume 1, Part B

International Nuclear Information System (INIS)

1998-07-01

On May 22, 1997, DOE published a Notice of Intent (NOI) in the Federal Register (62 Federal Register 28009) announcing its decision to prepare an environmental impact statement (EIS) that would tier from the analysis and decisions reached in connection with the Storage and Disposition of Weapons-Usable Fissile Materials Final Programmatic EIS (Storage and Disposition PEIS). DOE's disposition strategy allows for both the immobilization of surplus plutonium and its use as mixed oxide (MOX) fuel in existing domestic, commercial reactors. The disposition of surplus plutonium would also involve disposal of the immobilized plutonium and MOX fuel (as spent nuclear fuel) in a geologic repository. The Surplus Plutonium Disposition Environmental Impact Statement analyzes alternatives that would use the immobilization approach (for some of the surplus plutonium) and the MOX fuel approach (for some of the surplus plutonium); alternatives that would immobilize all of the surplus plutonium; and the No Action Alternative. The alternatives include three disposition facilities that would be designed so that they could collectively accomplish disposition of up to 50 metric tons (55 tons) of surplus plutonium over their operating lives: (1) the pit disassembly and conversion facility would disassemble pits (a weapons component) and convert the recovered plutonium, as well as plutonium metal from other sources, into plutonium dioxide suitable for disposition; (2) the immobilization facility would include a collocated capability for converting nonpit plutonium materials into plutonium dioxide suitable for immobilization and would be located at either Hanford or SRS. DOE has identified SRS as the preferred site for an immobilization facility; (3) the MOX fuel fabrication facility would fabricate plutonium dioxide into MOX fuel. This volume has chapters on environmental consequences; environmental regulations, permits, and consultations; a glossary; list of preparers; distribution list

DISC1 and striatal volume: a potential risk phenotype for mental illness

Directory of Open Access Journals (Sweden)

M. Mallar eChakravarty

2012-06-01

Full Text Available Disrupted-in-schizophrenia 1 was originally discovered in a large Scottish family with abnormally high rates of severe mental illness, including schizophrenia, bipolar disorder, and depression. An accumulating body of evidence from genetic, postmortem, and animal data supports a role for DISC1 in different forms of mental illness. DISC1 may play an important role in determining structure and function of several brain regions. One brain region of particular importance for several mental disorders is the striatum, and DISC1 mutant mice have demonstrated an increase in dopamine (D2 receptors in this structure. However, association between DISC1 functional polymorphisms and striatal structure have not been examined in humans to our knowledge. We, therefore hypothesized that there would be a relationship between human striatal volume and DISC1 genotype, specifically in the Leu607Phe (rs6675281 and Ser704Cys (rs821618 single nucleotide polymorphisms. We tested our hypothesis by automatically identifying the striatum in fifty-four healthy volunteers recruited for this study. We also performed an exploratory analysis of cortical thickness, cortical surface area, and structure volume. Our results demonstrate that Phe allele carriers have larger striatal volume bilaterally (left striatum: p=0.017; right striatum: p=0.016. From the exploratory analyses we found that Phe carriers also had larger right hemisphere volumes and right occipital lobe surface area (p=0.014 compared to LeuLeu homozygotes (p=0.0074. However, these exploratory findings do not survive a conservative correction for multiple comparisons. Our findings demonstrate that a functional DISC1 variant influences striatal volumes. Taken together with animal data that this gene influences D2 receptor levels in striatum, a key risk pathway for mental illnesses such as schizophrenia and bipolar disorder may be conferred via DISC1’s effects on the striatum .

Part 2: Limiting apparent molar volume of organic and inorganic 1:1 electrolytes in (water + ethylammonium nitrate) mixtures at 298 K - Thermodynamic approach using Bahe-Varela pseudo-lattice theory

International Nuclear Information System (INIS)

Bouguerra, Sabbah; Bou Malham, Ibrahim; Letellier, Pierre; Mayaffre, Alain; Turmine, Mireille

2008-01-01

Values of partial molar volumes at infinite dilution of 9 inorganic and 4 organic 1:1 electrolytes have been determined in (water + ethylammonium nitrate) (EAN) binary at 298.15 K throughout the composition scale. Our theoretical analysis shows that the values of partial molar volumes at infinite dilution of a solute in a binary are linked to those of the partial molar volumes of the components of mixed solvent. This applies to mixtures of molecular solvents as well as (water + ionic liquid) media. The use of the 'pseudo-lattice theory' of Bahe recently supplemented Varela can be used for calculations and to obtain information about the interactions between 1:1 electrolytes as solutes at infinite dilution and their concentrated saline environment. We show that the 'pseudo-lattice theory' allows accurate description of the behaviours of symmetrical tetraalkylammoniums bromide between the infinitely dilute state and concentrations higher than 2 mol . L -1

Satellite Power Systems (SPS) concept definition study, exhibit C. Volume 2, part 2: System engineering, cost and programmatics, appendixes

Science.gov (United States)

Hanley, G. M.

1979-01-01

Appendixes for Volume 2 (Part 2) of a seven volume Satellite (SPS) report are presented. The document contains two appendixes. The first is a SPS work breakdown structure dictionary. The second gives SPS cost estimating relationships and contains the cost analyses and a description of cost elements that comprise the SPS program.

Nuclear fuel technology - Tank calibration and volume determination for nuclear materials accountancy - Part 4: Accurate determination of liquid height in accountancy tanks equipped with dip tubes, slow bubbling rate

International Nuclear Information System (INIS)

2008-01-01

ISO 18213 deals with the acquisition, standardization, analysis, and use of calibration to determine liquid volumes in process tanks for the accountancy of nuclear materials. This part of ISO 18213 is complementary to the other parts, ISO 18213-1 (procedural overview), ISO 18213-2 (data standardization), ISO 18213-3 (statistical methods), ISO 18213-5 (fast bubbling rate) and ISO 18213-6 (in-tank determination of liquid density). The procedure presented herein for determining liquid height from measurements of induced pressure applies specifically when a very slow bubbling rate is employed. A similar procedure that is appropriate for a fast bubbling rate is given in ISO 18213-5. Measurements of the volume and height of liquid in a process accountancy tank are often made in order to estimate or verify the tank's calibration or volume measurement equation. The calibration equation relates the response of the tank's measurement system to some independent measure of tank volume. Beginning with an empty tank, calibration data are typically acquired by introducing a series of carefully measured quantities of some calibration liquid into the tank. The quantity of liquid added, the response of the tank's measurement system, and relevant ambient conditions such as temperature are measured for each incremental addition. Several calibration runs are made to obtain data for estimating or verifying a tank's calibration or measurement equation. A procedural overview of the tank calibration and volume measurement process is given in ISO 18213-1. An algorithm for standardizing tank calibration and volume measurement data to minimize the effects of variability in ambient conditions that prevail during the measurement period is given in ISO 18213-2. The procedure presented in this part of ISO 18213 for determining the height of calibration liquid in the tank from a measurement of the pressure it induces in the tank's measurement system is a vital component of that algorithm. In some

Nuclear fuel technology - Tank calibration and volume determination for nuclear materials accountancy - Part 5: Accurate determination of liquid height in accountancy tanks equipped with dip tubes, fast bubbling rate

International Nuclear Information System (INIS)

2008-01-01

ISO 18213 deals with the acquisition, standardization, analysis, and use of calibration to determine liquid volumes in process tanks for the accountancy of nuclear materials. This part of ISO 18213 is complementary to the other parts, ISO 18213-1 (procedural overview), ISO 18213-2 (data standardization), ISO 18213-3 (statistical methods), ISO 18213-5 (fast bubbling rate) and ISO 18213-6 (in-tank determination of liquid density). The procedure presented herein for determining liquid height from measurements of induced pressure applies specifically when a very slow bubbling rate is employed. A similar procedure that is appropriate for a fast bubbling rate is given in ISO 18213-5. Measurements of the volume and height of liquid in a process accountancy tank are often made in order to estimate or verify the tank's calibration or volume measurement equation. The calibration equation relates the response of the tank's measurement system to some independent measure of tank volume. Beginning with an empty tank, calibration data are typically acquired by introducing a series of carefully measured quantities of some calibration liquid into the tank. The quantity of liquid added, the response of the tank's measurement system, and relevant ambient conditions such as temperature are measured for each incremental addition. Several calibration runs are made to obtain data for estimating or verifying a tank's calibration or measurement equation. A procedural overview of the tank calibration and volume measurement process is given in ISO 18213-1. An algorithm for standardizing tank calibration and volume measurement data to minimize the effects of variability in ambient conditions that prevail during the measurement period is given in ISO 18213-2. The procedure presented in this part of ISO 18213 for determining the height of calibration liquid in the tank from a measurement of the pressure it induces in the tank's measurement system is a vital component of that algorithm. In some

Should measurement of maximum urinary flow rate and residual urine volume be a part of a "minimal care" assessment programme in female incontinence?

DEFF Research Database (Denmark)

Sander, Pia; Mouritsen, L; Andersen, J Thorup

2002-01-01

OBJECTIVE: The aim of this study was to evaluate the value of routine measurements of urinary flow rate and residual urine volume as a part of a "minimal care" assessment programme for women with urinary incontinence in detecting clinical significant bladder emptying problems. MATERIAL AND METHODS....... Twenty-six per cent had a maximum flow rate less than 15 ml/s, but only 4% at a voided volume > or =200 ml. Residual urine more than 149 ml was found in 6%. Two women had chronic retention with overflow incontinence. Both had typical symptoms with continuous leakage, stranguria and chronic cystitis...

No-migration variance petition. Appendices A--B: Volume 2, Revision 1

Energy Technology Data Exchange (ETDEWEB)

1990-03-01

Volume II contains Appendix A, emergency plan and Appendix B, waste analysis plan. The Waste Isolation Pilot Plant (WIPP) Emergency plan and Procedures (WP 12-9, Rev. 5, 1989) provides an organized plan of action for dealing with emergencies at the WIPP. A contingency plan is included which is in compliance with 40 CFR Part 265, Subpart D. The waste analysis plan provides a description of the chemical and physical characteristics of the wastes to be emplaced in the WIPP underground facility. A detailed discussion of the WIPP Waste Acceptance Criteria and the rationale for its established units are also included.

PRT Impact Study Pre-PRT Phase : Volume 1. Travel Analysis.

Science.gov (United States)

1976-03-01

Part of a three-volume work, this report describes the analysis performed on travel data collected for the Pre-PRT Impact Study. The data analyzed consist of travel behavior, travel patterns, model utilization and travel costs of various modes of tra...

Weapon container catalog. Volumes 1 & 2

Energy Technology Data Exchange (ETDEWEB)

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

1998-02-01

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

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

International Nuclear Information System (INIS)

1984-11-01

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

The Fukushima Daiichi Accident. Technical Volume 1/5. Description and Context of the Accident. Annexes

International Nuclear Information System (INIS)

2015-08-01

The Fukushima Daiichi Accident consists of a Report by the IAEA Director General and five technical volumes. It is the result of an extensive international collaborative effort involving five working groups with about 180 experts from 42 Member States with and without nuclear power programmes and several international bodies. It provides a description of the accident and its causes, evolution and consequences, based on the evaluation of data and information from a large number of sources available at the time of writing. The Fukushima Daiichi Accident will be of use to national authorities, international organizations, nuclear regulatory bodies, nuclear power plant operating organizations, designers of nuclear facilities and other experts in matters relating to nuclear power, as well as the wider public. The set contains six printed parts and five supplementary CD-ROMs. Contents: Report by the Director General; Technical Volume 1/5, Description and Context of the Accident; Technical Volume 2/5, Safety Assessment; Technical Volume 3/5, Emergency Preparedness and Response; Technical Volume 4/5, Radiological Consequences; Technical Volume 5/5, Post-accident Recovery; Annexes. The Report by the Director General is available separately in Arabic, Chinese, English, French, Russian, Spanish and Japanese

Site Environmental Report for 1999 - Volume 1

Energy Technology Data Exchange (ETDEWEB)

Ruggieri, M

2000-08-12

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

KCNQ1 channels sense small changes in cell volume

DEFF Research Database (Denmark)

Grunnet, Morten; Jespersen, Thomas; MacAulay, Nanna

2003-01-01

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

The irradiation lung volume in tangential fields for the treatment of a breast

International Nuclear Information System (INIS)

Oh, Y. T.; Kim, J. R.; Kang, H. J.; Sohn, J. H.; Kang, S. H.; Chun, M. S.

1997-01-01

Radiation pneumonitis is one of the complications caused by radiation therapy that includes a portion of the lung tissue. The severity of radiation induced pulmonary dysfunction depends on the irradiated lung volume, total dose, dose rate and underlying pulmonary function. The lung volume was measured for 25 patients with breast cancer irradiated with tangential field from Jan. 1995 to Aug. 1996. Parameters that can predict the irradiated lung volume included; (1) the perpendicular distance from the posterior tangential edge to the posterior part of the anterior chest wall at the center of the field (CLD); (2) the maximum perpendicular distance from the posterior tangential field edge to the posterior part of the anterior chest wall (MLD); (3) the greatest perpendicular distance from the posterior tangential edge to the posterior part of anterior chest wall on CT image at the center of the longitudinal field (GPD); (4) the length of the longitudinal field (L). The irradiated lung volume(RV), the entire both lung volume(EV) and the ipsilateral lung volume(IV) were measured using dose volume histogram. The RV is 61-279cc, the RV/EV is 2.9-13.0% and the RV/EN is 4.9-29.6%. The CLD, the MLD and the GPD are 1.9-3.3cm and 1.4-3.1cm respectively. The significant relations between the irradiated lung volume such as RV, RV/EV, RV/IV and parameters such as CLD, MLD, GPD, L, CLD x L, MLD x L and GPD x L are not found with little variances in parameters. The RV/IV of the left breast irradiation is significances. The significant relationship between the irradiated lung volume and predictors is not found with little variation on parameters. The irradiated lung volume in the tangential field is less than 10% of entire lung volume when CLD is less than 3cm. The RV/IV of the left tangential field is larger than that of the right but there was no significant differences in RV/EVs. Symptomatic radiation pneumonitis has not occurred during minimum 6 months follow up. (author)

The GABRB1 gene is associated with thalamus volume and modulates the association between thalamus volume and intelligence.

Science.gov (United States)

Zhu, Bi; Chen, Chuansheng; Xue, Gui; Lei, Xuemei; Li, Jin; Moyzis, Robert K; Dong, Qi; Lin, Chongde

2014-11-15

The GABRB1 gene encodes the beta 1 subunit of the gamma-aminobutyric acid A receptor (GABA A receptor), which is responsible for mediating inhibitory neurotransmission in the thalamus. Potential relationships between the GABRB1 gene, thalamus volume, and intelligence have been suggested by previous clinical studies, but have not been directly examined among nonclinical samples. The current study collected structural MRI, genetic, and behavioral data from 316 healthy Chinese adults (including 187 females and 129 males), and examined associations between GABRB1 variants, thalamus volume, and intelligence (measured by the Wechsler Adult Intelligence Scale Revised). After controlling for intracranial volume, sex, and age, GABRB1 genetic polymorphism at the SNP rs7435958 had the strongest association with thalamus volume (p = 0.002 and 0.00008 for left and right thalamus volumes, respectively), with GG homozygotes having smaller bilateral thalamus volumes than the other genotypes. Furthermore, there were positive correlations between bilateral thalamus volumes and intelligence, especially for GABRB1 rs7435958 GG female homozygotes (r's = 0.31 and 0.29, p intelligence with left and right thalamus volumes, respectively). This study provides the first evidence for the involvement of the GABRB1 gene in the thalamus structure and their interactive effects on intelligence. Future studies of the thalamus-intelligence associations should consider genetic factors as potential moderators. Copyright © 2014 Elsevier Inc. All rights reserved.

Reanalysis of multi-temporal aerial images of Storglaciären, Sweden (1959–99 – Part 1: Determination of length, area, and volume changes

Directory of Open Access Journals (Sweden)

W. Haeberli

2010-09-01

Full Text Available Storglaciären, located in the Kebnekaise massif in northern Sweden, has a long history of glaciological research. Early photo documentations date back to the late 19th century. Measurements of front position variations and distributed mass balance have been carried out since 1910 and 1945/46, respectively. In addition to these in-situ measurements, aerial photographs have been taken at decadal intervals since the beginning of the mass balance monitoring program and were used to produce topographic glacier maps. Inaccuracies in the maps were a challenge to early attempts to derive glacier volume changes and resulted in major differences when compared to the direct glaciological mass balances. In this study, we reanalyzed dia-positives of the original aerial photographs of 1959, -69, -80, -90 and -99 based on consistent photogrammetric processing. From the resulting digital elevation models and orthophotos, changes in length, area, and volume of Storglaciären were computed between the survey years, including an assessment of related errors. Between 1959 and 1999, Storglaciären lost an ice volume of 19×106 m3, which corresponds to a cumulative ice thickness loss of 5.69 m and a mean annual loss of 0.14 m. This ice loss resulted largely from a strong volume loss during the period 1959–80 and was partly compensated during the period 1980–99. As a consequence, the glacier shows a strong retreat in the 1960s, a slowing in the 1970s, and pseudo-stationary conditions in the 1980s and 1990s.

Compilation of reports of the Advisory Committee on Reactor Safeguards, 1957-1984. Volume 4. Generic Subjects A-G

International Nuclear Information System (INIS)

1985-04-01

This six-volume compilation contains over 1000 reports prepared by the Advisory Committee on Reactor Safeguards from September 1957 through December 1984. The reports are divided into two groups: Part 1: ACRS Reports on Project Reviews, and Part 2: ACRS Reports on Generic Subjects. Part 1 contains ACRS reports alphabetized by subject name and within project name by chronological order. Part 2 categorizes the reports by the most appropriate generic subject area and within subject area by chronological order. This volume contains generic reports arranged alphabetically from A to G

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

Energy Technology Data Exchange (ETDEWEB)

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

1993-09-01

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

Mechanisms underlying KCNQ1channel cell volume sensitivity

DEFF Research Database (Denmark)

Hammami, Sofia

Cells are constantly exposed to changes in cell volume during cell metabolism, nutrient uptake, cell proliferation, cell migration and salt and water transport. In order to cope with these perturbations, potassium channels in line with chloride channels have been shown to be likely contributors...... to the process of cell volume adjustments. A great diversity of potassium channels being members of either the 6TM, 4 TM or 2 TM K+ channel gene family have been shown to be strictly regulated by small, fast changes in cell volume. However, the precise mechanism underlying the K+ channel sensitivity to cell...... volume alterations is not yet fully understood. The KCNQ1 channel belonging to the voltage gated KCNQ family is considered a precise sensor of volume changes. The goal of this thesis was to elucidate the mechanism that induces cell volume sensitivity. Until now, a number of investigators have implicitly...

Satellite Power Systems (SPS) concept definition study, exhibit C. Volume 2, part 2: System engineering, cost and programmatics

Science.gov (United States)

Hanley, G. M.

1979-01-01

Volume 2, Part 2, of a seven volume Satellite Power Systems (SPS) report is presented. Part 2 covers cost and programmatics and is divided into four sections. The first section gives illustrations of the SPS reference satellite and rectenna concept, and an overall scenario for SPS space transportation involvement. The second section presents SPS program plans for the implementation of PHASE C/D activities. These plans describe SPS program schedules and networks, critical items of systems evolution/technology development, and the natural resources analysis. The fourth section presents summary comments on the methods and rationale followed in arriving at the results documented. Suggestions are also provided in those areas where further analysis or evaluation will enhance SPS cost and programmatic definitions.

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.

40 CFR Appendix A-1 to Part 60 - Test Methods 1 through 2F

Science.gov (United States)

2010-07-01

... selection procedure described in Section 11.5 of this method. 6.1.1Directional Probe. Any directional probe... facility. Such instructions (for example, establish sampling rates, volumes, or temperatures) are to be... Application 1.1Measured Parameters. The purpose of the method is to provide guidance for the selection of...

Building a New South Africa Volume 1 : Economic Policy | IDRC ...

International Development Research Centre (IDRC) Digital Library (Canada)

Couverture du livre Building a New South Africa Volume 1 : Economic Policy. Editor(s): ... Findings from an IDRC-supported program figure prominently at the annual conference of McGill's Institute for the Study of International Development. ... Special journal issue highlights IDRC-supported findings on women's paid work.

Generating human reliability estimates using expert judgment. Volume 1. Main report

International Nuclear Information System (INIS)

Comer, M.K.; Seaver, D.A.; Stillwell, W.G.; Gaddy, C.D.

1984-11-01

The US Nuclear Regulatory Commission is conducting a research program to determine the practicality, acceptability, and usefulness of several different methods for obtaining human reliability data and estimates that can be used in nuclear power plant probabilistic risk assessment (PRA). One method, investigated as part of this overall research program, uses expert judgment to generate human error probability (HEP) estimates and associated uncertainty bounds. The project described in this document evaluated two techniques for using expert judgment: paired comparisons and direct numerical estimation. Volume 1 of this report provides a brief overview of the background of the project, the procedure for using psychological scaling techniques to generate HEP estimates and conclusions from evaluation of the techniques. Results of the evaluation indicate that techniques using expert judgment should be given strong consideration for use in developing HEP estimates. In addition, HEP estimates for 35 tasks related to boiling water reactors (BMRs) were obtained as part of the evaluation. These HEP estimates are also included in the report

Modulation of Kir4.1 and Kir4.1-Kir5.1 channels by small changes in cell volume

DEFF Research Database (Denmark)

Soe, Rikke; Macaulay, Nanna; Klaerke, Dan Arne

2009-01-01

in Kir4.1 and Kir4.1-Kir5.1 currents upon swelling of the oocytes and a reduction in the current when the oocytes were shrunk. The volume-dependent changes in channel activity were not due to changes in the kinetics of the channels. These findings implicate a putative functional interaction between...... the Kir channels and aquaporins via small, fast cell volume changes in the glial cells....... channels and aquaporins is therefore debated. To test a possible volume-sensitivity of the Kir channels, the Kir4.1 or Kir4.1-Kir5.1 channels were expressed in Xenopus oocytes with or without co-expression of aquaporins and subsequently exposed to cell volume alterations. Our results show an increase...

PATRAM '80. Proceedings. Volume 1

International Nuclear Information System (INIS)

Huebner, H.W.

1980-01-01

Volume 1 contains papers from the following sessions: Plenary Session; Regulations, Licensing and Standards; LMFBR Systems Concepts; Risk/Safety Assessment I; Systems and Package Design; US Institutional Issues; Risk/Safety Assessment II; Leakage, Leak Rate and Seals; Poster Session A; Operations and Systems Experience I; Manufacturing Processes and Materials; and Quality Assurance and Maintenance. Individual papers were processed. (LM)

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

International Nuclear Information System (INIS)

1995-04-01

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

12 CFR Appendix 1 to Part 24 - CD-1-National Bank Community Development (Part 24) Investments

Science.gov (United States)

2010-01-01

... 12 Banks and Banking 1 2010-01-01 2010-01-01 false CD-1-National Bank Community Development (Part 24) Investments 1 Appendix 1 To Part 24 Banks and Banking COMPTROLLER OF THE CURRENCY, DEPARTMENT OF... PUBLIC WELFARE INVESTMENTS Pt. 24, App. 1 Appendix 1 To Part 24—CD-1—National Bank Community Development...

Training of nuclear power facility personnel. Part 1

International Nuclear Information System (INIS)

1989-06-01

The proceedings of the conference entitled ''Training of Nuclear Power Facility Personnel'' and held in Tale, Czechoslovakia, on 24 - 27 April 1989, contain full texts of 58 contributions, 57 of which fall in the INIS subject scope. The aim of the conference was to summarize experience gained during the training and education of Czechoslovak nuclear power plants operating personnel, to put forth new suggestions for increasing the safety and reliability of nuclear power plants, and to establish the needs and new trends in the training and education of nuclear power plants personnel. The topics treated at the conference can be divided into three basic groups as follows: 1. professional qualification of nuclear power plant staff members; 2. development of technical means for the nuclear power plants personnel training; and 3. training of maintenance personnel, the system and organization of this training and education. The proceedings are published in two volumes. Part 1 contains the texts of 25 papers falling in the INIS subject scope. (Z.M.)

The System 80+ Standard Plant design control document. Volume 1

International Nuclear Information System (INIS)

1997-01-01

This Design Control Document (DCD) is a repository of information comprising the System 80+trademark Standard Plant Design. The DCD also provides that design-related information to be incorporated by reference in the design certification rule for the System 80+ Standard Plant Design. Applicants for a combined license pursuant to 10 CFR 52 must ensure that the final Design Certification Rule and the associated Statements of Consideration are used when making all licensing decisions relevant to the System 80+ Standard Plant Design. The Design Control Document contains the DCD introduction, The Certified Design Material (CDM) [i.e., ''Tier 1''] and the Approved Design Material (ADM) [i.e., ''Tier 2''] for the System 80+ Standard Plant Design. The CDM includes the following sections: (1) Introductory material; (2) Certified Design Material for System 80+ systems and structures; (3) Certified Design Material for non-system-based aspects of the System 80+ Certified design; (4) Interface requirements; and (5) Site parameters. The ADM, to the extent applicable for the System 80+ Standard Plant Design, includes: (1) the information required for the final safety analysis report under 20 CFR 50.34; (2) other relevant information required by 10 CFR 52.47; and (3) emergency operations guidelines. This volume covers the DCD introduction and contains sections 1 and parts 1--7 of section 2 of the CDM. Parts 1--7 included the following: (2.1) Design of SSC; (2.2) Reactor; (2.3) RCS and connected systems; (2.4) Engineered Safety Features; (2.5) Instrumentation and Control; (2.6) Electric Power; and (2.7) Auxiliary Systems

Guidance and Control Software Project Data - Volume 1: Planning Documents

Science.gov (United States)

Hayhurst, Kelly J. (Editor)

2008-01-01

The Guidance and Control Software (GCS) project was the last in a series of software reliability studies conducted at Langley Research Center between 1977 and 1994. The technical results of the GCS project were recorded after the experiment was completed. Some of the support documentation produced as part of the experiment, however, is serving an unexpected role far beyond its original project context. Some of the software used as part of the GCS project was developed to conform to the RTCA/DO-178B software standard, "Software Considerations in Airborne Systems and Equipment Certification," used in the civil aviation industry. That standard requires extensive documentation throughout the software development life cycle, including plans, software requirements, design and source code, verification cases and results, and configuration management and quality control data. The project documentation that includes this information is open for public scrutiny without the legal or safety implications associated with comparable data from an avionics manufacturer. This public availability has afforded an opportunity to use the GCS project documents for DO-178B training. This report provides a brief overview of the GCS project, describes the 4-volume set of documents and the role they are playing in training, and includes the planning documents from the GCS project. Volume 1 contains five appendices: A. Plan for Software Aspects of Certification for the Guidance and Control Software Project; B. Software Development Standards for the Guidance and Control Software Project; C. Software Verification Plan for the Guidance and Control Software Project; D. Software Configuration Management Plan for the Guidance and Control Software Project; and E. Software Quality Assurance Activities.

Individual plant examination program: Perspectives on reactor safety and plant performance. Parts 2--5: Final report; Volume 2

International Nuclear Information System (INIS)

1997-12-01

This report provides perspectives gained by reviewing 75 Individual Plant Examination (IPE) submittals pertaining to 108 nuclear power plant units. IPEs are probabilistic analyses that estimate the core damage frequency (CDF) and containment performance for accidents initiated by internal events. The US Nuclear Regulatory Commission (NRC) reviewed the IPE submittals with the objective of gaining perspectives in three major areas: (1) improvements made to individual plants as a result of their IPEs and the collective results of the IPE program, (2) plant-specific design and operational features and modeling assumptions that significantly affect the estimates of CDF and containment performance, and (3) strengths and weaknesses of the models and methods used in the IPEs. These perspectives are gained by assessing the core damage and containment performance results, including overall CDF, accident sequences, dominant contributions to component failure and human error, and containment failure modes. Methods, data, boundary conditions, and assumptions used in the IPEs are considered in understanding the differences and similarities observed among the various types of plants. This report is divided into three volumes containing six parts. Part 1 is a summary report of the key perspectives gained in each of the areas identified above, with a discussion of the NRC's overall conclusions and observations. Part 2 discusses key perspectives regarding the impact of the IPE Program on reactor safety. Part 3 discusses perspectives gained from the IPE results regarding CDF, containment performance, and human actions. Part 4 discusses perspectives regarding the IPE models and methods. Part 5 discusses additional IPE perspectives. Part 6 contains Appendices A, B and C which provide the references of the information from the IPEs, updated PRA results, and public comments on draft NUREG-1560 respectively

Individual plant examination program: Perspectives on reactor safety and plant performance. Parts 2--5: Final report; Volume 2

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-12-01

This report provides perspectives gained by reviewing 75 Individual Plant Examination (IPE) submittals pertaining to 108 nuclear power plant units. IPEs are probabilistic analyses that estimate the core damage frequency (CDF) and containment performance for accidents initiated by internal events. The US Nuclear Regulatory Commission (NRC) reviewed the IPE submittals with the objective of gaining perspectives in three major areas: (1) improvements made to individual plants as a result of their IPEs and the collective results of the IPE program, (2) plant-specific design and operational features and modeling assumptions that significantly affect the estimates of CDF and containment performance, and (3) strengths and weaknesses of the models and methods used in the IPEs. These perspectives are gained by assessing the core damage and containment performance results, including overall CDF, accident sequences, dominant contributions to component failure and human error, and containment failure modes. Methods, data, boundary conditions, and assumptions used in the IPEs are considered in understanding the differences and similarities observed among the various types of plants. This report is divided into three volumes containing six parts. Part 1 is a summary report of the key perspectives gained in each of the areas identified above, with a discussion of the NRC`s overall conclusions and observations. Part 2 discusses key perspectives regarding the impact of the IPE Program on reactor safety. Part 3 discusses perspectives gained from the IPE results regarding CDF, containment performance, and human actions. Part 4 discusses perspectives regarding the IPE models and methods. Part 5 discusses additional IPE perspectives. Part 6 contains Appendices A, B and C which provide the references of the information from the IPEs, updated PRA results, and public comments on draft NUREG-1560 respectively.

Densities, excess molar volumes, and refractive indices of 1,1,2,2-tetrabromoethane and 1-alkanols binary mixtures

International Nuclear Information System (INIS)

Al-Hayan, M.N.M.; Al-Bader, Maher A.M.

2006-01-01

Densities, excess molar volumes, refractive indices, and changes in refractive index on mixing for (1,1,2,2-tetrabromoethane + 1-pentanol, or 1-hexanol, or 1-heptanol, or 1-octanol, or 1-decanol) have been determined at T = 293.15 K and at T = 303.15 K. The excess molar volumes and changes in refractive index have been fitted to Redlich-Kister polynomials. The effect of the chain length of the 1-alkanol on the excess molar volume and the change in the refractive index of its mixtures with 1,1,2,2-tetrabromoethane are discussed. In addition, the refractive indices are compared with calculated values using mixing rules proposed by several authors, and a good agreement is obtained

Densities, excess molar volumes, and refractive indices of 1,1,2,2-tetrachloroethane and 1-alkanols binary mixtures

International Nuclear Information System (INIS)

Al-Hayan, M.N.M.

2006-01-01

Densities, excess molar volumes, refractive indices, and changes in refractive index on mixing for 1,1,2,2-tetrachloroethane + 1-pentanol, or 1-hexanol, or 1-heptanol, or 1-octanol, or 1-decanol have been determined at T = (293.15 and 303.15) K. The excess molar volumes and changes in refractive index have been fitted to Redlich-Kister polynomials. The effect of the chain length of the 1-alkanol on the excess molar volume and the change in the refractive index of its mixtures with 1,1,2,2-tetrachloroethane was discussed. In addition, the refractive indices were compared with calculated values using mixing rules proposed by several authors, and a very good agreement was obtained

Editorial, Volume 5, Issue 1

Directory of Open Access Journals (Sweden)

Kristy L. Archuleta

2014-08-01

Full Text Available Welcome to Volume 5, Issue 1 of the Journal of Financial Therapy! In this issue, four scholarly papers are presented along with two profiles and a book review. These four papers address very important issues, such as mental health therapists’ competency in working with financial issues, financial stress of college students, parental messages about money, and financial advice media.

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

Energy Technology Data Exchange (ETDEWEB)

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

1980-07-01

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

LSENS: A General Chemical Kinetics and Sensitivity Analysis Code for homogeneous gas-phase reactions. Part 1: Theory and numerical solution procedures

Science.gov (United States)

Radhakrishnan, Krishnan

1994-01-01

LSENS, the Lewis General Chemical Kinetics and Sensitivity Analysis Code, has been developed for solving complex, homogeneous, gas-phase chemical kinetics problems and contains sensitivity analysis for a variety of problems, including nonisothermal situations. This report is part 1 of a series of three reference publications that describe LENS, provide a detailed guide to its usage, and present many example problems. Part 1 derives the governing equations and describes the numerical solution procedures for the types of problems that can be solved. The accuracy and efficiency of LSENS are examined by means of various test problems, and comparisons with other methods and codes are presented. LSENS is a flexible, convenient, accurate, and efficient solver for chemical reaction problems such as static system; steady, one-dimensional, inviscid flow; reaction behind incident shock wave, including boundary layer correction; and perfectly stirred (highly backmixed) reactor. In addition, the chemical equilibrium state can be computed for the following assigned states: temperature and pressure, enthalpy and pressure, temperature and volume, and internal energy and volume. For static problems the code computes the sensitivity coefficients of the dependent variables and their temporal derivatives with respect to the initial values of the dependent variables and/or the three rate coefficient parameters of the chemical reactions.

Bibliography on Cold Regions Science and Technology. Volume 51, Part 1.

Science.gov (United States)

1997-12-01

interaction, Ice heat flux, Drift, Ice forecasting, Ice models, Computer- ized simulation 51-1008 Renovation techniques of ski areas. |Les tech...project was to determine the perfor- mance of the ground-coupled heat pump HVAC systems installed as part of the building renovation to Building 2189 at...power sup- ply for automatic recording systems. [Compor- tamiento de acumuladores como fuente de energia electrica para la alimentation de sistemas

Parts, materials, and processes experience summary, volume 2. [design, engineering, and quality control

Science.gov (United States)

1973-01-01

This summary provides the general engineering community with the accumulated experience from ALERT reports issued by NASA and the Government-Industry. Data Exchange Program, and related experience gained by Government and industry. It provides expanded information on selected topics by relating the problem area (failure) to the cause, the investigation and findings, the suggestions for avoidance (inspections, screening tests, proper part applications, requirements for manufacturer's plant facilities, etc.), and failure analysis procedures. Diodes, integrated circuits, and transistors are covered in this volume.

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

International Nuclear Information System (INIS)

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

1994-06-01

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

Papers, Volume 1 1962-1985

DEFF Research Database (Denmark)

Thoft-Christensen, Palle

In this Volume 1 of “Papers”, 20 papers published from 1962 to 1985 are presented. The papers are reproduced by using scanning techniques and retyping of equations. During this work, small modifications and corrections have been made. Unfortunately, new errors may have been introduced. This is my...

A Local Net Volume Equation for Iowa

Science.gov (United States)

Jerold T. Hahn

1976-01-01

As a part of the 1974 Forest Survey of Iowa, the Station''s Forst Resources Evaluatioin Research Staff developed a merchantable tree volume equation and tables of coefficients for Iowa. They were developed for both board-foot (International ?-inch rule) and cubic foot volumes, for several species and species groups of growing-stock trees. The equation and...

Characterization of Mixtures. Part 2: QSPR Models for Prediction of Excess Molar Volume and Liquid Density Using Neural Networks.

Science.gov (United States)

Ajmani, Subhash; Rogers, Stephen C; Barley, Mark H; Burgess, Andrew N; Livingstone, David J

2010-09-17

In our earlier work, we have demonstrated that it is possible to characterize binary mixtures using single component descriptors by applying various mixing rules. We also showed that these methods were successful in building predictive QSPR models to study various mixture properties of interest. Here in, we developed a QSPR model of an excess thermodynamic property of binary mixtures i.e. excess molar volume (V(E) ). In the present study, we use a set of mixture descriptors which we earlier designed to specifically account for intermolecular interactions between the components of a mixture and applied successfully to the prediction of infinite-dilution activity coefficients using neural networks (part 1 of this series). We obtain a significant QSPR model for the prediction of excess molar volume (V(E) ) using consensus neural networks and five mixture descriptors. We find that hydrogen bond and thermodynamic descriptors are the most important in determining excess molar volume (V(E) ), which is in line with the theory of intermolecular forces governing excess mixture properties. The results also suggest that the mixture descriptors utilized herein may be sufficient to model a wide variety of properties of binary and possibly even more complex mixtures. Copyright © 2010 WILEY-VCH Verlag GmbH & Co. KGaA, Weinheim.

Electric power annual 1997. Volume 1

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-07-01

The Electric Power Annual presents a summary of electric power industry statistics at national, regional, and State levels. The objective of the publication is to provide industry decisionmakers, government policy-makers, analysts, and the general public with data that may be used in understanding US electricity markets. The Electric Power Annual is prepared by the Electric Power Division; Office of Coal, Nuclear, Electric and Alternate Fuels; Energy Information Administration (EIA); US Department of Energy. Volume 1 -- with a focus on US electric utilities -- contains final 1997 data on net generation and fossil fuel consumption, stocks, receipts, and cost; preliminary 1997 data on generating unit capability, and retail sales of electricity, associated revenue, and the average revenue per kilowatthour of electricity sold (based on a monthly sample: Form EIA-826, ``Monthly Electric Utility Sales and Revenue Report with State Distributions``). Additionally, information on net generation from renewable energy sources and on the associated generating capability is included in Volume 1 of the EPA.

Nuclear Computerized Library for Assessing Reactor Reliability (NUCLARR): Part 1, Overview of NUCLARR data retrieval: User's guide

International Nuclear Information System (INIS)

Gilmore, W.E.; Gentillon, C.D.; Gertman, D.I.; Beers, G.H.; Galyean, W.J.; Gilbert, B.G.

1988-06-01

The Nuclear Computerized Library for Assessing Reactor Reliability (NUCLARR) is an automated data base management system for processing and storing human error probability and hardware component failure data. The NUCLARR system software resides on an IBM (or compatible) personal micro-computer. NUCLARR can be used by the end user to furnish data inputs for both human and hardware reliability analysis in support of a variety of risk assessment activities. The NUCLARR system is documented in a five-volume series of reports. Volume IV of this series is the User's Guide for operating the NUCLARR software and is presented in three parts. This document, Part 1: Overview of NUCLARR Data Retrieval provides an introductory overview to the system's capabilities and procedures for data retrieval. The methods and criteria for selection of data sources and entering them into the NUCLARR system are also described in this document

An overview of artificial intelligence and robotics. Volume 1: Artificial intelligence. Part A: The core ingredients

Science.gov (United States)

Gevarter, W. B.

1983-01-01

Artificial Intelligence (AI) is an emerging technology that has recently attracted considerable attention. Many applications are now under development. The goal of Artificial Intelligence is focused on developing computational approaches to intelligent behavior. This goal is so broad - covering virtually all aspects of human cognitive activity - that substantial confusion has arisen as to the actual nature of AI, its current status and its future capability. This volume, the first in a series of NBS/NASA reports on the subject, attempts to address these concerns. Thus, this report endeavors to clarify what AI is, the foundations on which it rests, the techniques utilized, applications, the participants and, finally, AI's state-of-the-art and future trends. It is anticipated that this report will prove useful to government and private engineering and research managers, potential users, and others who will be affected by this field as it unfolds.

NASA Aerospace Flight Battery Program: Wet Life of Nickel-Hydrogen (Ni-H2) Batteries. Volume 2, Part 3; Appendices

Science.gov (United States)

Jung, David S,; Lee, Leonine S.; Manzo, Michelle A.

2010-01-01

This NASA Aerospace Flight Battery Systems Working Group was chartered within the NASA Engineering and Safety Center (NESC). The Battery Working Group was tasked to complete tasks and to propose proactive work to address battery related, agency-wide issues on an annual basis. In its first year of operation, this proactive program addressed various aspects of the validation and verification of aerospace battery systems for NASA missions. Studies were performed, issues were discussed and in many cases, test programs were executed to generate recommendations and guidelines to reduce risk associated with various aspects of implementing battery technology in the aerospace industry. This document contains Part 3 - Volume II Appendices to Part 3 - Volume I.

Directory of certificates of compliance for radioactive materials packages. Volume 1, Revision 17: Report of NRC approved packages

International Nuclear Information System (INIS)

1994-10-01

This directory contains a Report of NRC Approved Packages (Volume 1), Certificates of Compliance (Volume 2), and a Report of NRC Approved Quality Assurance Programs for Radioactive Materials Packages (Volume 3). The purpose of this directory is to make available a convenient source of information on Quality Assurance Programs and Packagings which have been approved by the US Nuclear Regulatory Commission. Shipments of radioactive material utilizing these packagings must be in accordance with the provisions of 49 CFR section 173.471 and 10 CFR Part 71, as applicable. In satisfying the requirements of Section 71.12, it is the responsibility of the licensees to insure themselves that they have a copy of the current approval and conduct their transportation activities in accordance with an NRC approved quality assurance program

ILC Reference Design Report Volume 1 - Executive Summary

CERN Document Server

Brau, James; Walker, Nicholas; Aarons, Gerald; Abe, Toshinori; Abernathy, Jason; Ablikim, Medina; Abramowicz, Halina; Adey, David; Adloff, Catherine; Adolphsen, Chris; Afanaciev, Konstantin; Agapov, Ilya; Ahn, Jung-Keun; Aihara, Hiroaki; Akemoto, Mitsuo; del Carmen Alabau, Maria; Albert, Justin; Albrecht, Hartwig; Albrecht, Michael; Alesini, David; Alexander, Gideon; Alexander, Jim; Allison, Wade; Amann, John; Amirikas, Ramila; An, Qi; Anami, Shozo; Ananthanarayan, B.; Anderson, Terry; Andricek, Ladislav; Anduze, Marc; Anerella, Michael; Anfimov, Nikolai; Angal-Kalinin, Deepa; Antipov, Sergei; Antoine, Claire; Aoki, Mayumi; Aoza, Atsushi; Aplin, Steve; Appleby, Rob; Arai, Yasuo; Araki, Sakae; Arkan, Tug; Arnold, Ned; Arnold, Ray; Arnowitt, Richard; Artru, Xavier; Arya, Kunal; Aryshev, Alexander; Asakawa, Eri; Asiri, Fred; Asner, David; Atac, Muzaffer; Atoian, Grigor; Attié, David; Augustin, Jean-Eudes; Augustine, David B.; Ayres, Bradley; Aziz, Tariq; Baars, Derek; Badaud, Frederique; Baddams, Nigel; Bagger, Jonathan; Bai, Sha; Bailey, David; Bailey, Ian R.; Baker, David; Balalykin, Nikolai I.; Balbuena, Juan Pablo; Baldy, Jean-Luc; Ball, Markus; Ball, Maurice; Ballestrero, Alessandro; Ballin, Jamie; Baltay, Charles; Bambade, Philip; Ban, Syuichi; Band, Henry; Bane, Karl; Banerjee, Bakul; Barbanotti, Serena; Barbareschi, Daniele; Barbaro-Galtieri, Angela; Barber, Desmond P.; Barbi, Mauricio; Bardin, Dmitri Y.; Barish, Barry; Barklow, Timothy L.; Barlow, Roger; Barnes, Virgil E.; Barone, Maura; Bartels, Christoph; Bartsch, Valeria; Basu, Rahul; Battaglia, Marco; Batygin, Yuri; Baudot, Jerome; Baur, Ulrich; Elwyn Baynham, D.; Beard, Carl; Bebek, Chris; Bechtle, Philip; Becker, Ulrich J.; Bedeschi, Franco; Bedjidian, Marc; Behera, Prafulla; Behnke, Ties; Bellantoni, Leo; Bellerive, Alain; Bellomo, Paul; Bentson, Lynn D.; Benyamna, Mustapha; Bergauer, Thomas; Berger, Edmond; Bergholz, Matthias; Beri, Suman; Berndt, Martin; Bernreuther, Werner; Bertolini, Alessandro; Besancon, Marc; Besson, Auguste; Beteille, Andre; Bettoni, Simona; Beyer, Michael; Bhandari, R.K.; Bharadwaj, Vinod; Bhatnagar, Vipin; Bhattacharya, Satyaki; Bhattacharyya, Gautam; Bhattacherjee, Biplob; Bhuyan, Ruchika; Bi, Xiao-Jun; Biagini, Marica; Bialowons, Wilhelm; Biebel, Otmar; Bieler, Thomas; Bierwagen, John; Birch, Alison; Bisset, Mike; Biswal, S.S.; Blackmore, Victoria; Blair, Grahame; Blanchard, Guillaume; Blazey, Gerald; Blue, Andrew; Blümlein, Johannes; Boffo, Christian; Bohn, Courtlandt; Boiko, V.I.; Boisvert, Veronique; Bondarchuk, Eduard N.; Boni, Roberto; Bonvicini, Giovanni; Boogert, Stewart; Boonekamp, Maarten; Boorman, Gary; Borras, Kerstin; Bortoletto, Daniela; Bosco, Alessio; Bosio, Carlo; Bosland, Pierre; Bosotti, Angelo; Boudry, Vincent; Boumediene, Djamel-Eddine; Bouquet, Bernard; Bourov, Serguei; Bowden, Gordon; Bower, Gary; Boyarski, Adam; Bozovic-Jelisavcic, Ivanka; Bozzi, Concezio; Brachmann, Axel; Bradshaw, Tom W.; Brandt, Andrew; Brasser, Hans Peter; Brau, Benjamin; Breidenbach, Martin; Bricker, Steve; Brient, Jean-Claude; Brock, Ian; Brodsky, Stanley; Brooksby, Craig; Broome, Timothy A.; Brown, David; Brown, David; Brownell, James H.; Bruchon, Mélanie; Brueck, Heiner; Brummitt, Amanda J.; Brun, Nicole; Buchholz, Peter; Budagov, Yulian A.; Bulgheroni, Antonio; Bulyak, Eugene; Bungau, Adriana; Bürger, Jochen; Burke, Dan; Burkhart, Craig; Burrows, Philip; Burt, Graeme; Burton, David; Büsser, Karsten; Butler, John; Butterworth, Jonathan; Buzulutskov, Alexei; Cabruja, Enric; Caccia, Massimo; Cai, Yunhai; Calcaterra, Alessandro; Caliier, Stephane; Camporesi, Tiziano; Cao, Jun-Jie; Cao, J.S.; Capatina, Ofelia; Cappellini, Chiara; Carcagno, Ruben; Carena, Marcela; Carloganu, Cristina; Carosi, Roberto; Stephen Carr, F.; Carrion, Francisco; Carter, Harry F.; Carter, John; Carwardine, John; Cassel, Richard; Cassell, Ronald; Cavallari, Giorgio; Cavallo, Emanuela; Cembranos, Jose A.R.; Chakraborty, Dhiman; Chandez, Frederic; Charles, Matthew; Chase, Brian; Chattopadhyay, Subhasis; Chauveau, Jacques; Chefdeville, Maximilien; Chehab, Robert; Chel, Stéphane; Chelkov, Georgy; Chen, Chiping; Chen, He Sheng; Chen, Huai Bi; Chen, Jia Er; Chen, Sen Yu; Chen, Shaomin; Chen, Shenjian; Chen, Xun; Chen, Yuan Bo; Cheng, Jian; Chevallier, M.; Chi, Yun Long; Chickering, William; Cho, Gi-Chol; Cho, Moo-Hyun; Choi, Jin-Hyuk; Choi, Jong Bum; Choi, Seong Youl; Choi, Young-Il; Choudhary, Brajesh; Choudhury, Debajyoti; Rai Choudhury, S.; Christian, David; Christian, Glenn; Christophe, Grojean; Chung, Jin-Hyuk; Church, Mike; Ciborowski, Jacek; Cihangir, Selcuk; Ciovati, Gianluigi; Clarke, Christine; Clarke, Don G.; Clarke, James A.; Clements, Elizabeth; Coca, Cornelia; Coe, Paul; Cogan, John; Colas, Paul; Collard, Caroline; Colledani, Claude; Combaret, Christophe; Comerma, Albert; Compton, Chris; Constance, Ben; Conway, John; Cook, Ed; Cooke, Peter; Cooper, William; Corcoran, Sean; Cornat, Rémi; Corner, Laura; Cortina Gil, Eduardo; Clay Corvin, W.; Cotta Ramusino, Angelo; Cowan, Ray; Crawford, Curtis; Cremaldi, Lucien M; Crittenden, James A.; Cussans, David; Cvach, Jaroslav; da Silva, Wilfrid; Dabiri Khah, Hamid; Dabrowski, Anne; Dabrowski, Wladyslaw; Dadoun, Olivier; Dai, Jian Ping; Dainton, John; Daly, Colin; Damerell, Chris; Danilov, Mikhail; Daniluk, Witold; Daram, Sarojini; Datta, Anindya; Dauncey, Paul; David, Jacques; Davier, Michel; Davies, Ken P.; Dawson, Sally; De Boer, Wim; De Curtis, Stefania; De Groot, Nicolo; de la Taille, Christophe; de Lira, Antonio; De Roeck, Albert; de Sangro, Riccardo; De Santis,Stefano; Deacon, Laurence; Deandrea, Aldo; Dehmelt, Klaus; Delagnes, Eric; Delahaye, Jean-Pierre; Delebecque, Pierre; Delerue, Nicholas; Delferriere, Olivier; Demarteau, Marcel; Deng, Zhi; Denisov, Yu.N.; Densham, Christopher J.; Desch, Klaus; Deshpande, Nilendra; Devanz, Guillaume; Devetak, Erik; Dexter, Amos; Di benedetto, Vito; Diéguez, Angel; Diener, Ralf; Dinh, Nguyen Dinh; Dixit, Madhu; Dixit, Sudhir; Djouadi, Abdelhak; Dolezal, Zdenek; Dollan, Ralph; Dong, Dong; Dong, Hai Yi; Dorfan, Jonathan; Dorokhov, Andrei; Doucas, George; Downing, Robert; Doyle, Eric; Doziere, Guy; Drago, Alessandro; Dragt, Alex; Drake, Gary; Drásal, Zbynek; Dreiner, Herbert; Drell, Persis; Driouichi, Chafik; Drozhdin, Alexandr; Drugakov, Vladimir; Du, Shuxian; Dugan, Gerald; Duginov, Viktor; Dulinski, Wojciech; Dulucq, Frederic; Dutta, Sukanta; Dwivedi, Jishnu; Dychkant, Alexandre; Dzahini, Daniel; Eckerlin, Guenter; Edwards, Helen; Ehrenfeld, Wolfgang; Ehrlichman, Michael; Ehrlichmann, Heiko; Eigen, Gerald; Elagin, Andrey; Elementi, Luciano; Eliasson, Peder; Ellis, John; Ellwood, George; Elsen, Eckhard; Emery, Louis; Enami, Kazuhiro; Endo, Kuninori; Enomoto, Atsushi; Eozénou, Fabien; Erbacher, Robin; Erickson, Roger; Oleg Eyser, K.; Fadeyev, Vitaliy; Fang, Shou Xian; Fant, Karen; Fasso, Alberto; Faucci Giannelli, Michele; Fehlberg, John; Feld, Lutz; Feng, Jonathan L.; Ferguson, John; Fernandez-Garcia, Marcos; Luis Fernandez-Hernando, J.; Fiala, Pavel; Fieguth, Ted; Finch, Alexander; Finocchiaro, Giuseppe; Fischer, Peter; Fisher, Peter; Eugene Fisk, H.; Fitton, Mike D.; Fleck, Ivor; Fleischer, Manfred; Fleury, Julien; Flood, Kevin; Foley, Mike; Ford, Richard; Fortin, Dominique; Foster, Brian; Fourches, Nicolas; Francis, Kurt; Frey, Ariane; Frey, Raymond; Friedsam, Horst; Frisch, Josef; Frishman, Anatoli; Fuerst, Joel; Fujii, Keisuke; Fujimoto, Junpei; Fukuda, Masafumi; Fukuda, Shigeki; Funahashi, Yoshisato; Funk, Warren; Furletova, Julia; Furukawa, Kazuro; Furuta, Fumio; Fusayasu, Takahiro; Fuster, Juan; Gadow, Karsten; Gaede, Frank; Gaglione, Renaud; Gai, Wei; Gajewski, Jan; Galik, Richard; Galkin, Alexei; Galkin, Valery; Gallin-Martel, Laurent; Gannaway, Fred; Gao, Jian She; Gao, Jie; Gao, Yuanning; Garbincius, Peter; Garcia-Tabares, Luis; Garren, Lynn; Garrido, Luís; Garutti, Erika; Garvey, Terry; Garwin, Edward; Gascón, David; Gastal, Martin; Gatto, Corrado; Gatto, Raoul; Gay, Pascal; Ge, Lixin; Ge, Ming Qi; Ge, Rui; Geiser, Achim; Gellrich, Andreas; Genat, Jean-Francois; Geng, Zhe Qiao; Gentile, Simonetta; Gerbick, Scot; Gerig, Rod; Ghosh, Dilip Kumar; Ghosh, Kirtiman; Gibbons, Lawrence; Giganon, Arnaud; Gillespie, Allan; Gillman, Tony; Ginzburg, Ilya; Giomataris, Ioannis; Giunta, Michele; Gladkikh, Peter; Gluza, Janusz; Godbole, Rohini; Godfrey, Stephen; Goldhaber, Gerson; Goldstein, Joel; Gollin, George D.; Gonzalez-Sanchez, Francisco Javier; Goodrick, Maurice; Gornushkin, Yuri; Gostkin, Mikhail; Gottschalk, Erik; Goudket, Philippe; Gough Eschrich, Ivo; Gournaris, Filimon; Graciani, Ricardo; Graf, Norman; Grah, Christian; Grancagnolo, Francesco; Grandjean, Damien; Grannis, Paul; Grassellino, Anna; Graugés, Eugeni; Gray, Stephen; Green, Michael; Greenhalgh, Justin; Greenshaw, Timothy; Grefe, Christian; Gregor, Ingrid-Maria; Grenier, Gerald; Grimes, Mark; Grimm, Terry; Gris, Philippe; Grivaz, Jean-Francois; Groll, Marius; Gronberg, Jeffrey; Grondin, Denis; Groom, Donald; Gross, Eilam; Grunewald, Martin; Grupen, Claus; Grzelak, Grzegorz; Gu, Jun; Gu, Yun-Ting; Guchait, Monoranjan; Guiducci, Susanna; Guler, Ali Murat; Guler, Hayg; Gulmez, Erhan; Gunion, John; Guo, Zhi Yu; Gurtu, Atul; Ha, Huy Bang; Haas, Tobias; Haase, Andy; Haba, Naoyuki; Haber, Howard; Haensel, Stephan; Hagge, Lars; Hagura, Hiroyuki; Hajdu, Csaba; Haller, Gunther; Haller, Johannes; Hallermann, Lea; Halyo, Valerie; Hamaguchi, Koichi; Hammond, Larry; Han, Liang; Han, Tao; Hand, Louis; Handu, Virender K.; Hano, Hitoshi; Hansen, Christian; Hansen, Jørn Dines; Hansen, Jorgen Beck; Hara, Kazufumi; Harder, Kristian; Hartin, Anthony; Hartung, Walter; Hast, Carsten; Hauptman, John; Hauschild, Michael; Hauviller, Claude; Havranek, Miroslav; Hawkes, Chris; Hawkings, Richard; Hayano, Hitoshi; Hazumi, Masashi; He, An; He, Hong Jian; Hearty, Christopher; Heath, Helen; Hebbeker, Thomas; Hedberg, Vincent; Hedin, David; Heifets, Samuel; Heinemeyer, Sven; Heini, Sebastien; Helebrant, Christian; Helms, Richard; Heltsley, Brian; Henrot-Versille, Sophie; Henschel, Hans; Hensel, Carsten; Hermel, Richard; Herms, Atilà; Herten, Gregor; Hesselbach, Stefan; Heuer, Rolf-Dieter; Heusch, Clemens A.; Hewett, Joanne; Higashi, Norio; Higashi, Takatoshi; Higashi, Yasuo; Higo, Toshiyasu; Hildreth, Michael D.; Hiller, Karlheinz; Hillert, Sonja; Hillier, Stephen James; Himel, Thomas; Himmi, Abdelkader; Hinchliffe, Ian; Hioki, Zenro; Hirano, Koichiro; Hirose, Tachishige; Hisamatsu, Hiromi; Hisano, Junji; Hlaing, Chit Thu; Hock, Kai Meng; Hoeferkamp, Martin; Hohlfeld, Mark; Honda, Yousuke; Hong, Juho; Hong, Tae Min; Honma, Hiroyuki; Horii, Yasuyuki; Horvath, Dezso; Hosoyama, Kenji; Hostachy, Jean-Yves; Hou, Mi; Hou, Wei-Shu; Howell, David; Hronek, Maxine; Hsiung, Yee B.; Hu, Bo; Hu, Tao; Huang, Jung-Yun; Huang, Tong Ming; Huang, Wen Hui; Huedem, Emil; Huggard, Peter; Hugonie, Cyril; Hu-Guo, Christine; Huitu, Katri; Hwang, Youngseok; Idzik, Marek; Ignatenko, Alexandr; Ignatov, Fedor; Ikeda, Hirokazu; Ikematsu, Katsumasa; Ilicheva, Tatiana; Imbault, Didier; Imhof, Andreas; Incagli, Marco; Ingbir, Ronen; Inoue, Hitoshi; Inoue, Youichi; Introzzi, Gianluca; Ioakeimidi, Katerina; Ishihara, Satoshi; Ishikawa, Akimasa; Ishikawa, Tadashi; Issakov, Vladimir; Ito, Kazutoshi; Ivanov, V.V.; Ivanov, Valentin; Ivanyushenkov, Yury; Iwasaki, Masako; Iwashita, Yoshihisa; Jackson, David; Jackson, Frank; Jacobsen, Bob; Jaganathan, Ramaswamy; Jamison, Steven; Janssen, Matthias Enno; Jaramillo-Echeverria, Richard; Jaros, John; Jauffret, Clement; Jawale, Suresh B.; Jeans, Daniel; Jedziniak, Ron; Jeffery, Ben; Jehanno, Didier; Jenner, Leo J.; Jensen, Chris; Jensen, David R.; Jiang, Hairong; Jiang, Xiao Ming; Jimbo, Masato; Jin, Shan; Keith Jobe, R.; Johnson, Anthony; Johnson, Erik; Johnson, Matt; Johnston, Michael; Joireman, Paul; Jokic, Stevan; Jones, James; Jones, Roger M.; Jongewaard, Erik; Jönsson, Leif; Joshi, Gopal; Joshi, Satish C.; Jung, Jin-Young; Junk, Thomas; Juste, Aurelio; Kado, Marumi; Kadyk, John; Käfer, Daniela; Kako, Eiji; Kalavase, Puneeth; Kalinin, Alexander; Kalinowski, Jan; Kamitani, Takuya; Kamiya, Yoshio; Kamiya, Yukihide; Kamoshita, Jun-ichi; Kananov, Sergey; Kanaya, Kazuyuki; Kanazawa, Ken-ichi; Kanemura, Shinya; Kang, Heung-Sik; Kang, Wen; Kanjial, D.; Kapusta, Frédéric; Karataev, Pavel; Karchin, Paul E.; Karlen, Dean; Karyotakis, Yannis; Kashikhin, Vladimir; Kashiwagi, Shigeru; Kasley, Paul; Katagiri, Hiroaki; Kato, Takashi; Kato, Yukihiro; Katzy, Judith; Kaukher, Alexander; Kaur, Manjit; Kawagoe, Kiyotomo; Kawamura, Hiroyuki; Kazakov, Sergei; Kekelidze, V.D.; Keller, Lewis; Kelley, Michael; Kelly, Marc; Kelly, Michael; Kennedy, Kurt; Kephart, Robert; Keung, Justin; Khainovski, Oleg; Khan, Sameen Ahmed; Khare, Prashant; Khovansky, Nikolai; Kiesling, Christian; Kikuchi, Mitsuo; Kilian, Wolfgang; Killenberg, Martin; Kim, Donghee; Kim, Eun San; Kim, Eun-Joo; Kim, Guinyun; Kim, Hongjoo; Kim, Hyoungsuk; Kim, Hyun-Chui; Kim, Jonghoon; Kim, Kwang-Je; Kim, Kyung Sook; Kim, Peter; Kim, Seunghwan; Kim, Shin-Hong; Kim, Sun Kee; Kim, Tae Jeong; Kim, Youngim; Kim, Young-Kee; Kimmitt, Maurice; Kirby, Robert; Kircher, François; Kisielewska, Danuta; Kittel, Olaf; Klanner, Robert; Klebaner, Arkadiy L.; Kleinwort, Claus; Klimkovich, Tatsiana; Klinkby, Esben; Kluth, Stefan; Knecht, Marc; Kneisel, Peter; Ko, In Soo; Ko, Kwok; Kobayashi, Makoto; Kobayashi, Nobuko; Kobel, Michael; Koch, Manuel; Kodys, Peter; Koetz, Uli; Kohrs, Robert; Kojima, Yuuji; Kolanoski, Hermann; Kolodziej, Karol; Kolomensky, Yury G.; Komamiya, Sachio; Kong, Xiang Cheng; Konigsberg, Jacobo; Korbel, Volker; Koscielniak, Shane; Kostromin, Sergey; Kowalewski, Robert; Kraml, Sabine; Krammer, Manfred; Krasnykh, Anatoly; Krautscheid, Thorsten; Krawczyk, Maria; James Krebs, H.; Krempetz, Kurt; Kribs, Graham; Krishnagopal, Srinivas; Kriske, Richard; Kronfeld, Andreas; Kroseberg, Jürgen; Kruchonak, Uladzimir; Kruecker, Dirk; Krüger, Hans; Krumpa, Nicholas A.; Krumshtein, Zinovii; Kuang, Yu Ping; Kubo, Kiyoshi; Kuchler, Vic; Kudoh, Noboru; Kulis, Szymon; Kumada, Masayuki; Kumar, Abhay; Kume, Tatsuya; Kundu, Anirban; Kurevlev, German; Kurihara, Yoshimasa; Kuriki, Masao; Kuroda, Shigeru; Kuroiwa, Hirotoshi; Kurokawa, Shin-ichi; Kusano, Tomonori; Kush, Pradeep K.; Kutschke, Robert; Kuznetsova, Ekaterina; Kvasnicka, Peter; Kwon, Youngjoon; Labarga, Luis; Lacasta, Carlos; Lackey, Sharon; Lackowski, Thomas W.; Lafaye, Remi; Lafferty, George; Lagorio, Eric; Laktineh, Imad; Lal, Shankar; Laloum, Maurice; Lam, Briant; Lancaster, Mark; Lander, Richard; Lange, Wolfgang; Langenfeld, Ulrich; Langeveld, Willem; Larbalestier, David; Larsen, Ray; Lastovicka, Tomas; Lastovicka-Medin, Gordana; Latina, Andrea; Latour, Emmanuel; Laurent, Lisa; Le, Ba Nam; Le, Duc Ninh; Le Diberder, Francois; Dû, Patrick Le; Lebbolo, Hervé; Lebrun, Paul; Lecoq, Jacques; Lee, Sung-Won; Lehner, Frank; Leibfritz, Jerry; Lenkszus, Frank; Lesiak, Tadeusz; Levy, Aharon; Lewandowski, Jim; Leyh, Greg; Li, Cheng; Li, Chong Sheng; Li, Chun Hua; Li, Da Zhang; Li, Gang; Li, Jin; Li, Shao Peng; Li, Wei Ming; Li, Weiguo; Li, Xiao Ping; Li, Xue-Qian; Li, Yuanjing; Li, Yulan; Li, Zenghai; Li, Zhong Quan; Liang, Jian Tao; Liao, Yi; Lilje, Lutz; Guilherme Lima, J.; Lintern, Andrew J.; Lipton, Ronald; List, Benno; List, Jenny; Liu, Chun; Liu, Jian Fei; Liu, Ke Xin; Liu, Li Qiang; Liu, Shao Zhen; Liu, Sheng Guang; Liu, Shubin; Liu, Wanming; Liu, Wei Bin; Liu, Ya Ping; Liu, Yu Dong; Lockyer, Nigel; Logan, Heather E.; Logatchev, Pavel V.; Lohmann, Wolfgang; Lohse, Thomas; Lola, Smaragda; Lopez-Virto, Amparo; Loveridge, Peter; Lozano, Manuel; Lu, Cai-Dian; Lu, Changguo; Lu, Gong-Lu; Lu, Wen Hui; Lubatti, Henry; Lucotte, Arnaud; Lundberg, Björn; Lundin, Tracy; Luo, Mingxing; Luong, Michel; Luth, Vera; Lutz, Benjamin; Lutz, Pierre; Lux, Thorsten; Luzniak, Pawel; Lyapin, Alexey; Lykken, Joseph; Lynch, Clare; Ma, Li; Ma, Lili; Ma, Qiang; Ma, Wen-Gan; Macfarlane, David; Maciel, Arthur; MacLeod, Allan; MacNair, David; Mader, Wolfgang; Magill, Stephen; Magnan, Anne-Marie; Maiheu, Bino; Maity, Manas; Majchrzak, Millicent; Majumder, Gobinda; Makarov, Roman; Makowski, Dariusz; Malaescu, Bogdan; Mallik, C.; Mallik, Usha; Malton, Stephen; Malyshev, Oleg B.; Malysheva, Larisa I.; Mammosser, John; Mamta; Mamuzic, Judita; Manen, Samuel; Manghisoni, Massimo; Manly, Steven; Marcellini, Fabio; Marcisovsky, Michal; Markiewicz, Thomas W.; Marks, Steve; Marone, Andrew; Marti, Felix; Martin, Jean-Pierre; Martin, Victoria; Martin-Chassard, Gisèle; Martinez, Manel; Martinez-Rivero, Celso; Martsch, Dennis; Martyn, Hans-Ulrich; Maruyama, Takashi; Masuzawa, Mika; Mathez, Hervé; Matsuda, Takeshi; Matsumoto, Hiroshi; Matsumoto, Shuji; Matsumoto, Toshihiro; Matsunaga, Hiroyuki; Mättig, Peter; Mattison, Thomas; Mavromanolakis, Georgios; Mawatari, Kentarou; Mazzacane, Anna; McBride, Patricia; McCormick, Douglas; McCormick, Jeremy; McDonald, Kirk T.; McGee, Mike; McIntosh, Peter; McKee, Bobby; McPherson, Robert A.; Meidlinger, Mandi; Meier, Karlheinz; Mele, Barbara; Meller, Bob; Melzer-Pellmann, Isabell-Alissandra; Mendez, Hector; Mercer, Adam; Merkin, Mikhail; Meshkov, I.N.; Messner, Robert; Metcalfe, Jessica; Meyer, Chris; Meyer, Hendrik; Meyer, Joachim; Meyer, Niels; Meyners, Norbert; Michelato, Paolo; Michizono, Shinichiro; Mihalcea, Daniel; Mihara, Satoshi; Mihara, Takanori; Mikami, Yoshinari; Mikhailichenko, Alexander A.; Milardi, Catia; Miller, David J.; Miller, Owen; Miller, Roger J.; Milstene, Caroline; Mimashi, Toshihiro; Minashvili, Irakli; Miquel, Ramon; Mishra, Shekhar; Mitaroff, Winfried; Mitchell, Chad; Miura, Takako; Miyamoto, Akiya; Miyata, Hitoshi; Mjörnmark, Ulf; Mnich, Joachim; Moenig, Klaus; Moffeit, Kenneth; Mokhov, Nikolai; Molloy, Stephen; Monaco, Laura; Monasterio, Paul R.; Montanari, Alessandro; Moon, Sung Ik; Moortgat-Pick, Gudrid A.; Mora de Freitas, Paulo; Morel, Federic; Moretti, Stefano; Morgunov, Vasily; Mori, Toshinori; Morin, Laurent; Morisseau, François; Morita, Yoshiyuki; Morita, Youhei; Morita, Yuichi; Morozov, Nikolai; Morozumi, Yuichi; Morse, William; Moser, Hans-Guenther; Moultaka, Gilbert; Mtingwa, Sekazi; Mudrinic, Mihajlo; Mueller, Alex; Mueller, Wolfgang; Muennich, Astrid; Muhlleitner, Milada Margarete; Mukherjee, Bhaskar; Mukhopadhyaya, Biswarup; Müller, Thomas; Munro, Morrison; Murayama, Hitoshi; Muto, Toshiya; Myneni, Ganapati Rao; Nabhiraj, P.Y.; Nagaitsev, Sergei; Nagamine, Tadashi; Nagano, Ai; Naito, Takashi; Nakai, Hirotaka; Nakajima, Hiromitsu; Nakamura, Isamu; Nakamura, Tomoya; Nakanishi, Tsutomu; Nakao, Katsumi; Nakao, Noriaki; Nakayoshi, Kazuo; Nam, Sang; Namito, Yoshihito; Namkung, Won; Nantista, Chris; Napoly, Olivier; Narain, Meenakshi; Naroska, Beate; Nauenberg, Uriel; Nayyar, Ruchika; Neal, Homer; Nelson, Charles; Nelson, Janice; Nelson, Timothy; Nemecek, Stanislav; Neubauer, Michael; Neuffer, David; Newman, Myriam Q.; Nezhevenko, Oleg; Ng, Cho-Kuen; Nguyen, Anh Ky; Nguyen, Minh; Van Nguyen Thi,Hong; Niebuhr, Carsten; Niehoff, Jim; Niezurawski, Piotr; Nishitani, Tomohiro; Nitoh, Osamu; Noguchi, Shuichi; Nomerotski, Andrei; Noonan, John; Norbeck, Edward; Nosochkov, Yuri; Notz, Dieter; Nowak, Grazyna; Nowak, Hannelies; Noy, Matthew; Nozaki, Mitsuaki; Nyffeler, Andreas; Nygren, David; Oddone, Piermaria; O'Dell, Joseph; Oh, Jong-Seok; Oh, Sun Kun; Ohkuma, Kazumasa; Ohlerich, Martin; Ohmi, Kazuhito; Ohnishi, Yukiyoshi; Ohsawa, Satoshi; Ohuchi, Norihito; Oide, Katsunobu; Okada, Nobuchika; Okamura, Takahiro; Okugi, Toshiyuki; Okumi, Shoji; Okumura, Ken-ichi; Olchevski, Alexander; Oliver, William; Olivier, Bob; Olsen, James; Olsen, Jeff; Olsen, Stephen; Olshevsky, A.G.; Olsson, Jan; Omori, Tsunehiko; Onel, Yasar; Onengut, Gulsen; Ono, Hiroaki; Onoprienko, Dmitry; Oreglia, Mark; Oren, Will; Orimoto, Toyoko J.; Oriunno, Marco; Orlandea, Marius Ciprian; Oroku, Masahiro; Orr, Lynne H.; Orr, Robert S.; Oshea, Val; Oskarsson, Anders; Osland, Per; Ossetski, Dmitri; Österman, Lennart; Ostiguy, Francois; Otono, Hidetoshi; Ottewell, Brian; Ouyang, Qun; Padamsee, Hasan; Padilla, Cristobal; Pagani, Carlo; Palmer, Mark A.; Pam, Wei Min; Pande, Manjiri; Pande, Rajni; Pandit, V.S.; Pandita, P.N.; Pandurovic, Mila; Pankov, Alexander; Panzeri, Nicola; Papandreou, Zisis; Paparella, Rocco; Para, Adam; Park, Hwanbae; Parker, Brett; Parkes, Chris; Parma, Vittorio; Parsa, Zohreh; Parsons, Justin; Partridge, Richard; Pasquinelli, Ralph; Pásztor, Gabriella; Paterson, Ewan; Patrick, Jim; Patteri, Piero; Ritchie Patterson, J.; Pauletta, Giovanni; Paver, Nello; Pavlicek, Vince; Pawlik, Bogdan; Payet, Jacques; Pchalek, Norbert; Pedersen, John; Pei, Guo Xi; Pei, Shi Lun; Pelka, Jerzy; Pellegrini, Giulio; Pellett, David; Peng, G.X.; Penn, Gregory; Penzo, Aldo; Perry, Colin; Peskin, Michael; Peters, Franz; Petersen, Troels Christian; Peterson, Daniel; Peterson, Thomas; Petterson, Maureen; Pfeffer, Howard; Pfund, Phil; Phelps, Alan; Van Phi, Quang; Phillips, Jonathan; Phinney, Nan; Piccolo, Marcello; Piemontese, Livio; Pierini, Paolo; Thomas Piggott, W.; Pike, Gary; Pillet, Nicolas; Jayawardena, Talini Pinto; Piot, Phillippe; Pitts, Kevin; Pivi, Mauro; Plate, Dave; Pleier, Marc-Andre; Poblaguev, Andrei; Poehler, Michael; Poelker, Matthew; Poffenberger, Paul; Pogorelsky, Igor; Poirier, Freddy; Poling, Ronald; Poole, Mike; Popescu, Sorina; Popielarski, John; Pöschl, Roman; Postranecky, Martin; Potukochi, Prakash N.; Prast, Julie; Prat, Serge; Preger, Miro; Prepost, Richard; Price, Michael; Proch, Dieter; Puntambekar, Avinash; Qin, Qing; Qu, Hua Min; Quadt, Arnulf; Quesnel, Jean-Pierre; Radeka, Veljko; Rahmat, Rahmat; Rai, Santosh Kumar; Raimondi, Pantaleo; Ramberg, Erik; Ranjan, Kirti; Rao, Sista V.L.S.; Raspereza, Alexei; Ratti, Alessandro; Ratti, Lodovico; Raubenheimer, Tor; Raux, Ludovic; Ravindran, V.; Raychaudhuri, Sreerup; Re, Valerio; Rease, Bill; Reece, Charles E.; Regler, Meinhard; Rehlich, Kay; Reichel, Ina; Reichold, Armin; Reid, John; Reid, Ron; Reidy, James; Reinhard, Marcel; Renz, Uwe; Repond, Jose; Resta-Lopez, Javier; Reuen, Lars; Ribnik, Jacob; Rice, Tyler; Richard, François; Riemann, Sabine; Riemann, Tord; Riles, Keith; Riley, Daniel; Rimbault, Cécile; Rindani, Saurabh; Rinolfi, Louis; Risigo, Fabio; Riu, Imma; Rizhikov, Dmitri; Rizzo, Thomas; Rochford, James H.; Rodriguez, Ponciano; Roeben, Martin; Rolandi, Gigi; Roodman, Aaron; Rosenberg, Eli; Roser, Robert; Ross, Marc; Rossel, François; Rossmanith, Robert; Roth, Stefan; Rougé, André; Rowe, Allan; Roy, Amit; Roy, Sendhunil B.; Roy, Sourov; Royer, Laurent; Royole-Degieux, Perrine; Royon, Christophe; Ruan, Manqi; Rubin, David; Ruehl, Ingo; Jimeno, Alberto Ruiz; Ruland, Robert; Rusnak, Brian; Ryu, Sun-Young; Sabbi, Gian Luca; Sadeh, Iftach; Sadygov, Ziraddin Y; Saeki, Takayuki; Sagan, David; Sahni, Vinod C.; Saini, Arun; Saito, Kenji; Saito, Kiwamu; Sajot, Gerard; Sakanaka, Shogo; Sakaue, Kazuyuki; Salata, Zen; Salih, Sabah; Salvatore, Fabrizio; Samson, Joergen; Sanami, Toshiya; Levi Sanchez, Allister; Sands, William; Santic, John; Sanuki, Tomoyuki; Sapronov, Andrey; Sarkar, Utpal; Sasao, Noboru; Satoh, Kotaro; Sauli, Fabio; Saunders, Claude; Saveliev, Valeri; Savoy-Navarro, Aurore; Sawyer, Lee; Saxton, Laura; Schäfer, Oliver; Schälicke, Andreas; Schade, Peter; Schaetzel, Sebastien; Scheitrum, Glenn; Schibler, Emilie; Schindler, Rafe; Schlösser, Markus; Schlueter, Ross D.; Schmid, Peter; Schmidt, Ringo Sebastian; Schneekloth, Uwe; Schreiber, Heinz Juergen; Schreiber, Siegfried; Schroeder, Henning; Peter Schüler, K.; Schulte, Daniel; Schultz-Coulon, Hans-Christian; Schumacher, Markus; Schumann, Steffen; Schumm, Bruce A.; Schwienhorst, Reinhard; Schwierz, Rainer; Scott, Duncan J.; Scuri, Fabrizio; Sefkow, Felix; Sefri, Rachid; Seguin-Moreau, Nathalie; Seidel, Sally; Seidman, David; Sekmen, Sezen; Seletskiy, Sergei; Senaha, Eibun; Senanayake, Rohan; Sendai, Hiroshi; Sertore, Daniele; Seryi, Andrei; Settles, Ronald; Sever, Ramazan; Shales, Nicholas; Shao, Ming; Shelkov, G.A.; Shepard, Ken; Shepherd-Themistocleous, Claire; Sheppard, John C.; Shi, Cai Tu; Shidara, Tetsuo; Shim, Yeo-Jeong; Shimizu, Hirotaka; Shimizu, Yasuhiro; Shimizu, Yuuki; Shimogawa, Tetsushi; Shin, Seunghwan; Shioden, Masaomi; Shipsey, Ian; Shirkov, Grigori; Shishido, Toshio; Shivpuri, Ram K.; Shrivastava, Purushottam; Shulga, Sergey; Shumeiko, Nikolai; Shuvalov, Sergey; Si, Zongguo; Siddiqui, Azher Majid; Siegrist, James; Simon, Claire; Simrock, Stefan; Sinev, Nikolai; Singh, Bhartendu K.; Singh, Jasbir; Singh, Pitamber; Singh, R.K.; Singh, S.K.; Singini, Monito; Sinha, Anil K.; Sinha, Nita; Sinha, Rahul; Sinram, Klaus; Sissakian, A.N.; Skachkov, N.B.; Skrinsky, Alexander; Slater, Mark; Slominski, Wojciech; Smiljanic, Ivan; Smith, A J Stewart; Smith, Alex; Smith, Brian J.; Smith, Jeff; Smith, Jonathan; Smith, Steve; Smith, Susan; Smith, Tonee; Neville Snodgrass, W.; Sobloher, Blanka; Sohn, Young-Uk; Solidum, Ruelson; Solyak, Nikolai; Son, Dongchul; Sonmez, Nasuf; Sopczak, Andre; Soskov, V.; Spencer, Cherrill M.; Spentzouris, Panagiotis; Speziali, Valeria; Spira, Michael; Sprehn, Daryl; Sridhar, K.; Srivastava, Asutosh; St. Lorant, Steve; Stahl, Achim; Stanek, Richard P.; Stanitzki, Marcel; Stanley, Jacob; Stefanov, Konstantin; Stein, Werner; Steiner, Herbert; Stenlund, Evert; Stern, Amir; Sternberg, Matt; Stockinger, Dominik; Stockton, Mark; Stoeck, Holger; Strachan, John; Strakhovenko, V.; Strauss, Michael; Striganov, Sergei I.; Strologas, John; Strom, David; Strube, Jan; Stupakov, Gennady; Su, Dong; Sudo, Yuji; Suehara, Taikan; Suehiro, Toru; Suetsugu, Yusuke; Sugahara, Ryuhei; Sugimoto, Yasuhiro; Sugiyama, Akira; Suh, Jun Suhk; Sukovic, Goran; Sun, Hong; Sun, Stephen; Sun, Werner; Sun, Yi; Sun, Yipeng; Suszycki, Leszek; Sutcliffe, Peter; Suthar, Rameshwar L.; Suwada, Tsuyoshi; Suzuki, Atsuto; Suzuki, Chihiro; Suzuki, Shiro; Suzuki, Takashi; Swent, Richard; Swientek, Krzysztof; Swinson, Christina; Syresin, Evgeny; Szleper, Michal; Tadday, Alexander; Takahashi, Rika; Takahashi, Tohru; Takano, Mikio; Takasaki, Fumihiko; Takeda, Seishi; Takenaka, Tateru; Takeshita, Tohru; Takubo, Yosuke; Tanaka, Masami; Tang, Chuan Xiang; Taniguchi, Takashi; Tantawi, Sami; Tapprogge, Stefan; Tartaglia, Michael A.; Tassielli, Giovanni Francesco; Tauchi, Toshiaki; Tavian, Laurent; Tawara, Hiroko; Taylor, Geoffrey; Telnov, Alexandre V.; Telnov, Valery; Tenenbaum, Peter; Teodorescu, Eliza; Terashima, Akio; Terracciano, Giuseppina; Terunuma, Nobuhiro; Teubner, Thomas; Teuscher, Richard; Theilacker, Jay; Thomson, Mark; Tice, Jeff; Tigner, Maury; Timmermans, Jan; Titov, Maxim; Toge, Nobukazu; Tokareva, N.A.; Tollefson, Kirsten; Tomasek, Lukas; Tomovic, Savo; Tompkins, John; Tonutti, Manfred; Topkar, Anita; Toprek, Dragan; Toral, Fernando; Torrence, Eric; Traversi, Gianluca; Trimpl, Marcel; Mani Tripathi, S.; Trischuk, William; Trodden, Mark; Trubnikov, G.V.; Tschirhart, Robert; Tskhadadze, Edisher; Tsuchiya, Kiyosumi; Tsukamoto, Toshifumi; Tsunemi, Akira; Tucker, Robin; Turchetta, Renato; Tyndel, Mike; Uekusa, Nobuhiro; Ueno, Kenji; Umemori, Kensei; Ummenhofer, Martin; Underwood, David; Uozumi, Satoru; Urakawa, Junji; Urban, Jeremy; Uriot, Didier; Urner, David; Ushakov, Andrei; Usher, Tracy; Uzunyan, Sergey; Vachon, Brigitte; Valerio, Linda; Valin, Isabelle; Valishev, Alex; Vamra, Raghava; Van der Graaf, Harry; Van Kooten, Rick; Van Zandbergen, Gary; Vanel, Jean-Charles; Variola, Alessandro; Varner, Gary; Velasco, Mayda; Velte, Ulrich; Velthuis, Jaap; Vempati, Sundir K.; Venturini, Marco; Vescovi, Christophe; Videau, Henri; Vila, Ivan; Vincent, Pascal; Virey, Jean-Marc; Visentin, Bernard; Viti, Michele; Vo, Thanh Cuong; Vogel, Adrian; Vogt, Harald; von Toerne, Eckhard; Vorozhtsov, S.B.; Vos, Marcel; Votava, Margaret; Vrba, Vaclav; Wackeroth, Doreen; Wagner, Albrecht; Wagner, Carlos E.M.; Wagner, Stephen; Wake, Masayoshi; Walczak, Roman; Walkowiak, Wolfgang; Wallon, Samuel; Walsh, Roberval; Walston, Sean; Waltenberger, Wolfgang; Walz, Dieter; Wang, Chao En; Wang, Chun Hong; Wang, Dou; Wang, Faya; Wang, Guang Wei; Wang, Haitao; Wang, Jiang; Wang, Jiu Qing; Wang, Juwen; Wang, Lanfa; Wang, Lei; Wang, Min-Zu; Wang, Qing; Wang, Shu Hong; Wang, Xiaolian; Wang, Xue-Lei; Wang, Yi Fang; Wang, Zheng; Wanzenberg, Rainer; Ward, Bennie; Ward, David; Warmbein, Barbara; Warner, David W.; Warren, Matthew; Washio, Masakazu; Watanabe, Isamu; Watanabe, Ken; Watanabe, Takashi; Watanabe, Yuichi; Watson, Nigel; Wattimena, Nanda; Wayne, Mitchell; Weber, Marc; Weerts, Harry; Weiglein, Georg; Weiland, Thomas; Weinzierl, Stefan; Weise, Hans; Weisend, John; Wendt, Manfred; Wendt, Oliver; Wenzel, Hans; Wenzel, William A.; Wermes, Norbert; Werthenbach, Ulrich; Wesseln, Steve; Wester, William; White, Andy; White, Glen R.; Wichmann, Katarzyna; Wienemann, Peter; Wierba, Wojciech; Wilksen, Tim; Willis, William; Wilson, Graham W.; Wilson, John A.; Wilson, Robert; Wing, Matthew; Winter, Marc; Wirth, Brian D.; Wolbers, Stephen A.; Wolff, Dan; Wolski, Andrzej; Woodley, Mark D.; Woods, Michael; Woodward, Michael L.; Woolliscroft, Timothy; Worm, Steven; Wormser, Guy; Wright, Dennis; Wright, Douglas; Wu, Andy; Wu, Tao; Wu, Yue Liang; Xella, Stefania; Xia, Guoxing; Xia, Lei; Xiao, Aimin; Xiao, Liling; Xie, Jia Lin; Xing, Zhi-Zhong; Xiong, Lian You; Xu, Gang; Xu, Qing Jing; Yajnik, Urjit A.; Yakimenko, Vitaly; Yamada, Ryuji; Yamaguchi, Hiroshi; Yamamoto, Akira; Yamamoto, Hitoshi; Yamamoto, Masahiro; Yamamoto, Naoto; Yamamoto, Richard; Yamamoto, Yasuchika; Yamanaka, Takashi; Yamaoka, Hiroshi; Yamashita, Satoru; Yamazaki, Hideki; Yan, Wenbiao; Yang, Hai-Jun; Yang, Jin Min; Yang, Jongmann; Yang, Zhenwei; Yano, Yoshiharu; Yazgan, Efe; Yeh, G.P.; Yilmaz, Hakan; Yock, Philip; Yoda, Hakutaro; Yoh, John; Yokoya, Kaoru; Yokoyama, Hirokazu; York, Richard C.; Yoshida, Mitsuhiro; Yoshida, Takuo; Yoshioka, Tamaki; Young, Andrew; Yu, Cheng Hui; Yu, Jaehoon; Yu, Xian Ming; Yuan, Changzheng; Yue, Chong-Xing; Yue, Jun Hui; Zacek, Josef; Zagorodnov, Igor; Zalesak, Jaroslav; Zalikhanov, Boris; Zarnecki, Aleksander Filip; Zawiejski, Leszek; Zeitnitz, Christian; Zeller, Michael; Zerwas, Dirk; Zerwas, Peter; Zeyrek, Mehmet; Zhai, Ji Yuan; Zhang, Bao Cheng; Zhang, Bin; Zhang, Chuang; Zhang, He; Zhang, Jiawen; Zhang, Jing; Zhang, Jing Ru; Zhang, Jinlong; Zhang, Liang; Zhang, X.; Zhang, Yuan; Zhang, Zhige; Zhang, Zhiqing; Zhang, Ziping; Zhao, Haiwen; Zhao, Ji Jiu; Zhao, Jing Xia; Zhao, Ming Hua; Zhao, Sheng Chu; Zhao, Tianchi; Zhao, Tong Xian; Zhao, Zhen Tang; Zhao, Zhengguo; Zhou, De Min; Zhou, Feng; Zhou, Shun; Zhu, Shou Hua; Zhu, Xiong Wei; Zhukov, Valery; Zimmermann, Frank; Ziolkowski, Michael; Zisman, Michael S.; Zomer, Fabian; Zong, Zhang Guo; Zorba, Osman; Zutshi, Vishnu

2007-01-01

The International Linear Collider (ILC) is a 200-500 GeV center-of-mass high-luminosity linear electron-positron collider, based on 1.3 GHz superconducting radio-frequency (SCRF) accelerating cavities. The ILC has a total footprint of about 31 km and is designed for a peak luminosity of 2x10^34 cm^-2s^-1. This report is the Executive Summary (Volume I) of the four volume Reference Design Report. It gives an overview of the physics at the ILC, the accelerator design and value estimate, the detector concepts, and the next steps towards project realization.

Characterization of radioactive waste forms. Volume 1

International Nuclear Information System (INIS)

Brodersen, K.; Nilsson, K.

1989-01-01

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

An overview of artificial intelligence and robotics. Volume 1: Artificial intelligence. Part B: Applications

Science.gov (United States)

Gevarter, W. B.

1983-01-01

Artificial Intelligence (AI) is an emerging technology that has recently attracted considerable attention. Many applications are now under development. This report, Part B of a three part report on AI, presents overviews of the key application areas: Expert Systems, Computer Vision, Natural Language Processing, Speech Interfaces, and Problem Solving and Planning. The basic approaches to such systems, the state-of-the-art, existing systems and future trends and expectations are covered.

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

International Nuclear Information System (INIS)

1995-04-01

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

WIPP Compliance Certification Application calculations parameters. Part 1: Parameter development

International Nuclear Information System (INIS)

Howarth, S.M.

1997-01-01

The Waste Isolation Pilot Plant (WIPP) in southeast New Mexico has been studied as a transuranic waste repository for the past 23 years. During this time, an extensive site characterization, design, construction, and experimental program was completed, which provided in-depth understanding of the dominant processes that are most likely to influence the containment of radionuclides for 10,000 years. Nearly 1,500 parameters were developed using information gathered from this program; the parameters were input to numerical models for WIPP Compliance Certification Application (CCA) Performance Assessment (PA) calculations. The CCA probabilistic codes frequently require input values that define a statistical distribution for each parameter. Developing parameter distributions begins with the assignment of an appropriate distribution type, which is dependent on the type, magnitude, and volume of data or information available. The development of the parameter distribution values may require interpretation or statistical analysis of raw data, combining raw data with literature values, scaling of lab or field data to fit code grid mesh sizes, or other transformation. Parameter development and documentation of the development process were very complicated, especially for those parameters based on empirical data; they required the integration of information from Sandia National Laboratories (SNL) code sponsors, parameter task leaders (PTLs), performance assessment analysts (PAAs), and experimental principal investigators (PIs). This paper, Part 1 of two parts, contains a discussion of the parameter development process, roles and responsibilities, and lessons learned. Part 2 will discuss parameter documentation, traceability and retrievability, and lessons learned from related audits and reviews

NJP VOLUME 40 No 1B

African Journals Online (AJOL)

Prof Ezechukwu

2012-07-13

10.4314/njp.v40i1,9. Abstract Objective: Although the calibre of the airway is kept patent by multifactorial control system, there is evidence that ..... Lewinshohn HC, Capel LH, Smart. J. Changes in forced expiratory volumes throughout ...

Nordic study on reactor waste. Technical part 1 and 2

International Nuclear Information System (INIS)

1981-08-01

An important part of the Nordic studies on system- and safety analysis of the management of low and medium level radioactive waste from nuclear power plants, is the safety analysis of a Reference System. This reference system was established within the study and is described in this Technical Part 1. The reference system covers waste management Schemes that are potential possibilities in either one of the four participating Nordic countries. The reference system is based on: a power reactor system consisting of 6 BWR's of 500 MWe each, operated simultaneously over the same 30 year period, and deep bed granular ion exchange resin wastes from the Reactor Water Clean-Up System (RWCS and powdered ion exchange resin from the Spent Fuel Pool Cleanup System (SFPCS)). Both waste types are supposed to be solidified by mixing with cement and bitumen. Two basic types of containers are considered. Standard 200 liter steel drums and specially made cubicreinforced concrete moulds with a net volume of 1 m 3 . The Nordic study assumes temporary storage of the solidified waste for a maximum of 50 years before the waste is transferred to the disposal site. Transportation of the waste from the storage facilitiy to the disposal site will be by road or sea. Three different disposal facilities are considered: Shallow land burial, near surface concrete bunker, and rock cavern with about 30 m granite cover. (EG)

Characterization of Class A low-level radioactive waste 1986--1990. Volume 3: Main report -- Part B

Energy Technology Data Exchange (ETDEWEB)

Dehmel, J.C.; Loomis, D.; Mauro, J. [S. Cohen & Associates, Inc., McLean, VA (United States); Kaplan, M. [Eastern Research Group, Inc., Lexington, MA (United States)

1994-01-01

Under contract to the US Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, the firms of S. Cohen & Associates, Inc. (SC&A) and Eastern Research Group (ERG) have compiled a report that describes the physical, chemical, and radiological properties of Class-A low-level radioactive waste. The report also presents information characterizing various methods and facilities used to treat and dispose non-radioactive waste. A database management program was developed for use in accessing, sorting, analyzing, and displaying the electronic data provided by EG&G. The program was used to present and aggregate data characterizing the radiological, physical, and chemical properties of the waste from descriptions contained in shipping manifests. The data thus retrieved are summarized in tables, histograms, and cumulative distribution curves presenting radionuclide concentration distributions in Class-A waste as a function of waste streams, by category of waste generators, and regions of the United States. The report also provides information characterizing methods and facilities used to treat and dispose non-radioactive waste, including industrial, municipal, and hazardous waste regulated under Subparts C and D of the Resource Conservation and Recovery Act (RCRA). The information includes a list of disposal options, the geographical locations of the processing and disposal facilities, and a description of the characteristics of such processing and disposal facilities. Volume 1 contains the Executive Summary, Volume 2 presents the Class-A waste database, Volume 3 presents the information characterizing non-radioactive waste management practices and facilities, and Volumes 4 to 7 contain Appendices A to P with supporting information.

Pancreas volume and fat fraction in children with Type 1 diabetes.

Science.gov (United States)

Regnell, S E; Peterson, P; Trinh, L; Broberg, P; Leander, P; Lernmark, Å; Månsson, S; Elding Larsson, H

2016-10-01

People with Type 1 diabetes have smaller pancreases than healthy individuals. Several diseases causing pancreatic atrophy are associated with pancreatic steatosis, but pancreatic fat in Type 1 diabetes has not been measured. This cross-sectional study aimed to compare pancreas size and fat fraction in children with Type 1 diabetes and controls. The volume and fat fraction of the pancreases of 22 children with Type 1 diabetes and 29 controls were determined using magnetic resonance imaging. Pancreas volume was 27% smaller in children with diabetes (median 34.9 cm(3) ) than in controls (47.8 cm(3) ; P Pancreas volume correlated positively with age in controls (P = 0.033), but not in children with diabetes (P = 0.649). Pancreas volume did not correlate with diabetes duration, but it did correlate positively with units of insulin/kg body weight/day (P = 0.048). A linear model of pancreas volume as influenced by age, body surface area and insulin units/kg body weight/day found that insulin dosage correlated with pancreas volume after controlling for both age and body surface area (P = 0.009). Pancreatic fat fraction was not significantly different between the two groups (1.34% vs. 1.57%; P = 0.891). Our findings do not indicate that pancreatic atrophy in Type 1 diabetes is associated with an increased pancreatic fat fraction, unlike some other diseases featuring reduced pancreatic volume. We speculate that our results may support the hypotheses that much of pancreatic atrophy in Type 1 diabetes occurs before the clinical onset of the disease and that exogenous insulin administration decelerates pancreatic atrophy after diabetes onset. © 2016 Diabetes UK.

Acid Pit Stabilization Project (Volume 1 - Cold Testing) and (Volume 2 - Hot Testing)

International Nuclear Information System (INIS)

Loomis, G. G.; Zdinak, A. P.; Ewanic, M. A.; Jessmore, J. J.

1998-01-01

During the summer and fall of Fiscal Year 1997, a Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) Treatability Study was performed at the Idaho National Engineering and Environmental Laboratory. The study involved subsurface stabilization of a mixed waste contaminated soil site called the Acid Pit. This study represents the culmination of a successful technology development effort that spanned Fiscal Years 1994-1996. Research and development of the in situ grout stabilization technique was conducted. Hardware and implementation techniques are currently documented in a patent pending with the United States Patent and Trademark Office. The stabilization technique involved using jet grouting of an innovative grouting material to form a monolith out of the contamination zone. The monolith simultaneously provides a barrier to further contaminant migration and closes voids in the soil structure against further subsidence. This is accomplished by chemical incorporation of contaminants into less soluble species and achieving a general reduction in hydraulic conductivity within the monolith. The grout used for this study was TECT-HG, a relatively dense iron oxide-based cementitious grout. The treatability study involved cold testing followed by in situ stabilization of the Acid Pit. Volume 1 of this report discusses cold testing, performed as part of a ''Management Readiness Assessment'' in preparation for going hot. Volume 2 discusses the results of the hot Acid Pit Stabilization phase of this project. Drilling equipment was specifically rigged to reduce the spread of contamination, and all grouting was performed under a concrete block containing void space to absorb any grout returns. Data evaluation included examination of implementability of the grouting process and an evaluation of the contaminant spread during grouting. Following curing of the stabilized pit, cores were obtained and evaluated for toxicity characteristic leach ing

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

International Nuclear Information System (INIS)

Bowman, S.M.; Suto, T.

1996-10-01

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

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

KAUST Repository

Matson, Samira M.

2012-08-01

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

Experimental determination of the drywell volume: 1/5 scale pressure suppression test

International Nuclear Information System (INIS)

Pitts, J.H.

1977-01-01

The BWR Mk 1 1/5 scale drywell volume, including space in all ports up to the first flange, was experimentally determined to be 10.01 m 3 with an uncertainty of +- 0.03 m 3 . The method of measurement used a 0.040879 m 3 calibrated volume that was initially filled with helium to 36.5 MPa. The calibrated volume was then connected to the drywell and the pressures equalized. The volumes of the vent pipes, instrumentation ports, and either the steam inlet or nitrogen inlet were subtracted from the measured drywell volume to obtain the net active drywell volume. The net active drywell volume is 9.87 m 3 for air tests and 9.85 m 3 for steam tests

Harmonic analysis a comprehensive course in analysis, part 3

CERN Document Server

Simon, Barry

2015-01-01

A Comprehensive Course in Analysis by Poincaré Prize winner Barry Simon is a five-volume set that can serve as a graduate-level analysis textbook with a lot of additional bonus information, including hundreds of problems and numerous notes that extend the text and provide important historical background. Depth and breadth of exposition make this set a valuable reference source for almost all areas of classical analysis. Part 3 returns to the themes of Part 1 by discussing pointwise limits (going beyond the usual focus on the Hardy-Littlewood maximal function by including ergodic theorems and m

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

International Nuclear Information System (INIS)

McFadden, J.G.

1998-01-01

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

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

International Nuclear Information System (INIS)

1995-01-01

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

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

International Nuclear Information System (INIS)

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

1996-12-01

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

Brain tumor locating in 3D MR volume using symmetry

Science.gov (United States)

Dvorak, Pavel; Bartusek, Karel

2014-03-01

This work deals with the automatic determination of a brain tumor location in 3D magnetic resonance volumes. The aim of this work is not the precise segmentation of the tumor and its parts but only the detection of its location. This work is the first step in the tumor segmentation process, an important topic in neuro-image processing. The algorithm expects 3D magnetic resonance volumes of brain containing a tumor. The detection is based on locating the area that breaks the left-right symmetry of the brain. This is done by multi-resolution comparing of corresponding regions in left and right hemisphere. The output of the computation is the probabilistic map of the tumor location. The created algorithm was tested on 80 volumes from publicly available BRATS databases containing 3D brain volumes afflicted by a brain tumor. These pathological structures had various sizes and shapes and were located in various parts of the brain. The locating performance of the algorithm was 85% for T1-weighted volumes, 91% for T1-weighted contrast enhanced volumes, 96% for FLAIR and T2-wieghted volumes and 95% for their combinations.

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

International Nuclear Information System (INIS)

1996-06-01

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

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

International Nuclear Information System (INIS)

1995-04-01

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

Power plant site evaluation - Douglas Point site. Volume 1, part 2. Final report

International Nuclear Information System (INIS)

1977-11-01

This is part of a series of reports containing an evaluation of the proposed Douglas Point nuclear generating station site located on the Potomac River in Maryland 30 miles south of Washington, DC. This report contains sections on cooling tower air emissions, noise impacts, transmission line effects, radiation from normal releases, site features affecting radiological accidents, and meteorology

Oak Ridge Reservation environmental report for 1992. Volume 1: Narrative

Energy Technology Data Exchange (ETDEWEB)

Koncinski, W.S. [ed.

1993-09-01

The two volumes of this report present data and supporting narratives regarding the impact of the US Department of Energy`s (DOE`s) Oak Ridge Reservation (ORR) on its environs and the public during 1992. This Volume (Volume 1) includes all narrative descriptions, summaries, and conclusions and is intended to be a ``stand-alone`` report for the reader who does not want to review in detail all of the 1992 data for the ORR. Volume 2 includes the detailed data in formats that ensure all the environmental data are represented. Narratives are not included in Vol. 2.

Site Environmental Report for 2008, Volume 1

Energy Technology Data Exchange (ETDEWEB)

Lackner, Regina; Baskin, David; Fox, Robert; Jelinski, John; Pauer, Ron; Thorson, Patrick; Wahl, Linnea; Xu, Suying

2009-09-21

The Site Environmental Report for 2008 is an integrated report on the environmental programs at Lawrence Berkeley National Laboratory and satisfies the requirements of DOE order 231.1A, Environment, Safety, and Health Reporting. Volume II contains individual data results from surveillance and monitoring activities

Executive Summary: Parts on Demand Project (CATT Phase II) - Volume 1 of 2

National Research Council Canada - National Science Library

Gates, Robert

1996-01-01

.... The GAO has profiled DoD challenges in: maintaining an aging aircraft fleet, reducing response time and cost of providing the spare parts, implementing commercial inventory management practices, reinventing buying and contracting practices...

A guide to GALAXY 5 part 1

International Nuclear Information System (INIS)

Price, J.A.

1975-11-01

GALAXY 6 Part 1 is a program, written in Fortran IV language, to compute spectrum-weighted, group-averaged nuclear cross-sections and group-to-group transfer cross-sections from the evaluated microscopic cross-section data contained in the UKAEA Nuclear Data Library. A description is given of the input and output schemes and operating procedures for the IBM 370/168, together with the structure and functioning of the program and other relevant topics. (author)

2016 Billion-Ton Report: Environmental Sustainability Effects of Select Scenarios from Volume 1 (Volume 2)

Energy Technology Data Exchange (ETDEWEB)

Efroymson, R. A. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Langholtz, M. H. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Johnson, K. E. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Stokes, B. J. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

2017-01-13

On behalf of all the authors and contributors, it is a great privilege to present the 2016 Billion-Ton Report (BT16), volume 2: Environmental Sustainability Effects of Select Scenarios from volume 1. This report represents the culmination of several years of collaborative effort among national laboratories, government agencies, academic institutions, and industry. BT16 was developed to support the U.S. Department of Energy’s efforts towards national goals of energy security and associated quality of life.

Bibliography on Cold Regions Science and Technology. Volume 34, Part 1 and Part 2

Science.gov (United States)

1980-12-01

34-3302 Automatically controlled t :.,’nrmation system for the Arctic (ALISA). [Avtom: li/irovannaia ledovo- informatsionnaia sistema dlia...This is a companion issue to Vol. 34, Pt 1 The latter contains the full bibliographic citations referred to in the author and subject indexes included...Rüsten. A., et al. [1980. p.l 1-21. eng) 34-2409 Companion on the non-slip quality among three different types on langlauf ski-plates

Fluctuations of trading volume in a stock market

Science.gov (United States)

Hong, Byoung Hee; Lee, Kyoung Eun; Hwang, Jun Kyung; Lee, Jae Woo

2009-03-01

We consider the probability distribution function of the trading volume and the volume changes in the Korean stock market. The probability distribution function of the trading volume shows double peaks and follows a power law, P(V/)∼( at the tail part of the distribution with α=4.15(4) for the KOSPI (Korea composite Stock Price Index) and α=4.22(2) for the KOSDAQ (Korea Securities Dealers Automated Quotations), where V is the trading volume and is the monthly average value of the trading volume. The second peaks originate from the increasing trends of the average volume. The probability distribution function of the volume changes also follows a power law, P(Vr)∼Vr-β, where Vr=V(t)-V(t-T) and T is a time lag. The exponents β depend on the time lag T. We observe that the exponents β for the KOSDAQ are larger than those for the KOSPI.

Structural studies of MFE-1: the 1.9 A crystal structure of the dehydrogenase part of rat peroxisomal MFE-1.

Science.gov (United States)

Taskinen, Jukka P; Kiema, Tiila R; Hiltunen, J Kalervo; Wierenga, Rik K

2006-01-27

The 1.9 A structure of the C-terminal dehydrogenase part of the rat peroxisomal monomeric multifunctional enzyme type 1 (MFE-1) has been determined. In this construct (residues 260-722 and referred to as MFE1-DH) the N-terminal hydratase part of MFE-1 has been deleted. The structure of MFE1-DH shows that it consists of an N-terminal helix, followed by a Rossmann-fold domain (domain C), followed by two tightly associated helical domains (domains D and E), which have similar topology. The structure of MFE1-DH is compared with the two known homologous structures: human mitochondrial 3-hydroxyacyl-CoA dehydrogenase (HAD; sequence identity is 33%) (which is dimeric and monofunctional) and with the dimeric multifunctional alpha-chain (alphaFOM; sequence identity is 28%) of the bacterial fatty acid beta-oxidation alpha2beta2-multienzyme complex. Like MFE-1, alphaFOM has an N-terminal hydratase part and a C-terminal dehydrogenase part, and the structure comparisons show that the N-terminal helix of MFE1-DH corresponds to the alphaFOM linker helix, located between its hydratase and dehydrogenase part. It is also shown that this helix corresponds to the C-terminal helix-10 of the hydratase/isomerase superfamily, suggesting that functionally it belongs to the N-terminal hydratase part of MFE-1.

Trans-Caspian gas pipeline feasibility study. Volume 1

International Nuclear Information System (INIS)

1999-01-01

This study, conducted by Enron Engineering and Construction Company, was funded by the US Trade and Development Agency. The study provides detailed information concerning natural gas demand in Turkey and Southern Europe. The purpose of the study is to estimate the rate at which new gas can be absorbed in the Turkish market and be re-exported to the markets in Europe, as well as to forecast Turkish natural gas demand for the period up to 2020. The study also evaluates gas demand and pricing for the market in the 2002--2005 time frame. This is Volume 1 of a 3-volume report, and is divided into the following sections: (1) Task A: Gas Sales; (2) Task B: Initial Economic Screening; (3) Task D: Project Cost Analysis

DNFSB Recommendation 94-1 Hanford Site Integrated Stabilization Management Plan. Volume 2

International Nuclear Information System (INIS)

Gerber, E.W.

1995-10-01

The Hanford Site Integrated Stabilization Management Plan (SISMP) was developed in support of the US Department of Energy's (DOE) Defense Nuclear Facilities Safety Board (DNFSB) Recommendation 94-1 Integrated Program Plan (IPP). Volume 1 of the SISMP identifies the technical scope and costs associated with Hanford Site plans to resolve concerns identified in DNFSB Recommendation 94-1. Volume 2 of the SISMP provides the Resource Loaded Integrated Schedules for Spent Nuclear Fuel Project and Plutonium Finishing Plant activities identified in Volume 1 of the SISMP. Appendix A provides the schedules and progress curves related to spent nuclear fuel management. Appendix B provides the schedules and progress curves related to plutonium-bearing material management. Appendix C provides programmatic logic diagrams that were referenced in Volume 1 of the SISMP

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.

Soil contamination. part 1. changes in the humidity of non saturated soils after reject in a limited space. part 2. movements of radioactive ions in non saturated soils after reject in a limited space

International Nuclear Information System (INIS)

Rancon, D.

1969-01-01

An important feature in radiological safety studies of sites is the knowledge of water movements in the unsaturated layer surmounting aquifer; this zone of aerated soil can be effective as a protection against aquifer contamination. Utilizing a neutron-moisture meter, a method was developed permitting to build graphically the hydric states of soil and the moistened volume evolution with time in the particular case of a limited feeding surface. It is also possible to measure moisture gradients, drying kinetics, the retention capacity of soil and the gravific water content achieved by a given water head. The initial hydric state has an effect only upon the infiltration rate and neither upon the moistened front position nor upon the volume of moistened soil; consequently, the storable water amount in soil can be calculated. When water feeding has been stopped, the volume of moistened soil increases to an equilibrium state restricted by the moistened front and all the other water movements occur exclusively inside this volume. Consequently in case of radioactive waste disposal, the ionic pollution will be confined inside a measurable volume, the moistened front being the maximum limits of this volume. Part 2. Following up the report on water movements in non-saturated s o i l s after reject on a limited space - CEA R 3635 (1) - the radioactive ions movements in these soils are studied in using an anion and a cation of reference: iodine 131 and strontium 85. The experimental method is founded on the simultaneous measurements of moisture and radioactivity fronts by means of a neutrons moisture meter and an specially conceived radioactivity probe. It has so been possible to measure: the relative velocities of moisture and radioactivity fronts; the contaminated soil volume inside the moistened oil volume; the concentration gradients; the contamination changes upon watering; the effect of chemical composition of water upon this ions movements and the effect of soil moisture

Remote sensing for global change, climate change and atmosphere and ocean forecasting. Volume 1

International Nuclear Information System (INIS)

1992-01-01

This volume is separated in three sessions. First part is on remote sensing for global change (with global modelling, land cover change on global scale, ocean colour studies of marine biosphere, biological and hydrological interactions and large scale experiments). Second part is on remote sensing for climate change (with earth radiation and clouds, sea ice, global climate research programme). Third part is on remote sensing for atmosphere and ocean forecasting (with temperatures and humidity, winds, data assimilation, cloud imagery, sea surface temperature, ocean waves and topography). (A.B.). refs., figs., tabs

Lung volumes during sustained microgravity on Spacelab SLS-1

Science.gov (United States)

Elliott, Ann R.; Prisk, Gordon Kim; Guy, Harold J. B.; West, John B.

1994-01-01

Gravity is known to influence the topographical gradients of pulmonary ventilation, perfusion, and pleural pressures. The effect of sustained microgravity on lung volumes has not previously been investigated. Pulmonary function tests were performed by four subjects before, during, and after 9 days of microgravity exposure. Ground measurements were made in standing and supine postures. Tests were performed using a bag-in-box and flowmeter system and a respiratory mass spectrometer. Measurements of tidal volume (V(sub T)), expiratory reserve volume (ERV), inspiratory and expiratory vital capacities (IVC, EVC), functional residual capacity (FRC), and residual volume (RV) were made. During microgravity, V(sub T) decreased by 15%. IVC and EVC were slightly reduced during the first 24 hrs of microgravity and returned to 1 g standing values within 72 hrs after the onset of microgravity. FRC was reduced by 15% and ERV decreased by 10-20%. RV was significantly reduced by 18%. The reductions in FRC, ERV, and V(sub T) during microgravity are probably due to the cranial shift of the diaphragm and an increase in intrathoracic blood volume.

Site Environmental Report for 2002, Volume 1

Energy Technology Data Exchange (ETDEWEB)

Pauer, Ron

2003-07-01

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

Excess molar volumes and partial molar volumes for (propionitrile + an alkanol) at T = 298.15 K and p = 0.1 MPa

International Nuclear Information System (INIS)

Deenadayalu, N.; Bhujrajh, P.

2006-01-01

The excess molar volumes and the partial molar volumes for (propionitrile + an alkanol) at T = 298.15 K and at atmospheric pressure are reported. The hydrogen bonding between the OH133;NC groups are discussed in terms of the chain length of the alkanol. The alkanols studied are (methanol, ethanol, 1-propanol, 2-propanol, 1-butanol, and 1-pentanol). The excess molar volume data was fitted to the Redlich-Kister equation The partial molar volumes were calculated from the Redlich-Kister coefficients

The Energy Information Administration`s assessment of reformulated gasoline. Volume 1

Energy Technology Data Exchange (ETDEWEB)

NONE

1994-09-28

This report is divided into two volumes. The first volume contains EIA`s findings and analyses on reformulated gasoline as it affects the petroleum industry. The data contained herein should assist members of the Congress, Federal, State and local governments, analysts, researchers, the media and academia to understand the RFG program and the current status of implementation. This second volume contains 10 appendices that include letter from Congressman Dingell, survey results, survey forms, and historical summary data. A glossary and a list of acronyms and abbreviations are printed in Volumes 1 and 2.

Index to Nuclear Safety: a technical progress review by chrology, permuted title, and author, Volume 11(1) through Volume 20(6)

Energy Technology Data Exchange (ETDEWEB)

Cottrell, W B; Passiakos, M

1980-06-01

This index to Nuclear Safety, a bimonthly technical progress review, covers articles published in Nuclear Safety, Volume II, No. 1 (January-February 1970), through Volume 20, No. 6 (November-December 1979). It is divided into three sections: a chronological list of articles (including abstracts) followed by a permuted-title (KWIC) index and an author index. Nuclear Safety, a bimonthly technical progress review prepared by the Nuclear Safety Information Center (NSIC), covers all safety aspects of nuclear power reactors and associated facilities. Over 600 technical articles published in Nuclear Safety in the last ten years are listed in this index.

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

Energy Technology Data Exchange (ETDEWEB)

McFadden, J.G.

1998-09-04

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

Introduction to Part 3

DEFF Research Database (Denmark)

Petersen, Nils Holger

2015-01-01

A brief contextualising discussion of Western Music History and its relations to Theological Aesthetical Thought since Carolingian Times as an introduction to 3 music articles in Part 3 of the volume.......A brief contextualising discussion of Western Music History and its relations to Theological Aesthetical Thought since Carolingian Times as an introduction to 3 music articles in Part 3 of the volume....

Bibliography on Cold Regions Science and Technology. Volume 35, Part 2

Science.gov (United States)

1981-12-01

miMures [1480. p.»7-91, rus) 35-1088 Arbazov, \\.A. I sing liquid chlorides in wmtet on slippery loads (1480. p 1 I. 21, ■ us...3,-2*J I sing liquid chlondes in winter on slippery roads [ 1480. p, 11. Ryan, U L Safonova, T.A. ii...volumes, ins, 35-858 Problems of the Vulb. a cmieiit bibllographs , IISII. I»«p.rtls) 35-859 Open pit nulling in aistie regions Elm . S.S

The partial volume effect in the quantification of 1H magnetic resonance spectroscopy in Alzheimer's disease and aging.

Science.gov (United States)

Mato Abad, Virginia; Quirós, Alicia; García-Álvarez, Roberto; Loureiro, Javier Pereira; Alvarez-Linera, Juan; Frank, Ana; Hernández-Tamames, Juan Antonio

2014-01-01

1H-MRS variability increases due to normal aging and also as a result of atrophy in grey and white matter caused by neurodegeneration. In this work, an automatic process was developed to integrate data from spectra and high-resolution anatomical images to quantify metabolites, taking into account tissue partial volumes within the voxel of interest avoiding additional spectra acquisitions required for partial volume correction. To evaluate this method, we use a cohort of 135 subjects (47 male and 88 female, aged between 57 and 99 years) classified into 4 groups: 38 healthy participants, 20 amnesic mild cognitive impairment patients, 22 multi-domain mild cognitive impairment patients, and 55 Alzheimer's disease patients. Our findings suggest that knowing the voxel composition of white and grey matter and cerebrospinal fluid is necessary to avoid partial volume variations in a single-voxel study and to decrease part of the variability found in metabolites quantification, particularly in those studies involving elder patients and neurodegenerative diseases. The proposed method facilitates the use of 1H-MRS techniques in statistical studies in Alzheimer's disease, because it provides more accurate quantitative measurements, reduces the inter-subject variability, and improves statistical results when performing group comparisons.

7242 Volume 13 No. 1 January 2013 A SURVEY ON ...

African Journals Online (AJOL)

admn

2013-01-01

Jan 1, 2013 ... which was then used to calculate mass and cost handled by the marketers. For consumers, a ... used containers for measuring quantities of insects gathered are the 20 litre, 5 litre and .... eastern parts of Zimbabwe (Table 1).

ATWS: a reappraisal, part II, evaluation of societal risks due to reactor protection systems failure. Vol. 3. Pwr risk analysis. Phase report

International Nuclear Information System (INIS)

Lellouche, G.S.

1976-08-01

This document is the third volume of part 2 in a series of studies which will examine the basis for the problem of Anticipated Transients Without Scram (ATWS). The purpose of part 2 is an evaluation of societal risks due to RPS failure based on more current data and methodology than used in WASH-1270. This volume examines and documents the potential contribution to societal risk due to ATWS in the PWR. Volumes 1 and 2 described a similar analysis for the BWR

Openings: On the Journal of Homosexuality, Volume 1, Issue 1.

Science.gov (United States)

Gotkin, Kevin

2016-01-01

This article serves as one of the supplementary pieces of this special issue on "Mapping Queer Bioethics," in which we take a solipsistic turn to "map" the Journal of Homosexuality itself. Here, the author examines Volume 1, Issue 1 of the Journal of Homosexuality and asks whether the journal's first contributors might reveal a historically problematic relationship whereby the categories of front-line LGBT health advocates in the 1970s might be incommensurate with the post-AIDS, queer politics that would follow in decades to come.

Recovery of plasma volume after 1 week of exposure at 4,350 m

DEFF Research Database (Denmark)

Robach, Paul; Lafforgue, Eric; Olsen, Niels Vidiendal

2002-01-01

Plasma volume (PV) decreases at high altitude, but is rapidly restored upon return to sea-level (RSL). The aim of this study was (1) to describe PV recovery upon RSL with concomitant changes in major fluid regulating hormones, and (2) to test the hypothesis that PV recovery is promoted...... natriuretic factor (ANF) and arginine vasopressin (AVP) were measured at rest and during exercise. The subjects were divided into two groups 1 h before RSL, one group receiving PV expansion (475+/-219 ml) to ensure normovolemia (PVX, n=6), the others serving as controls (Control, n=4). PV decreased by 13...... groups, whereas water output dropped in RSL. PVX increased urine flow rate in RSL1 compared with subjects not given PVX. The present results suggest that PV recovery during early RSL is mainly due to a decreased diuresis, promoted at least in part by changes in fluid regulating hormones. However, neither...

Trends in Medicare Service Volume for Cataract Surgery and the Impact of the Medicare Physician Fee Schedule.

Science.gov (United States)

Gong, Dan; Jun, Lin; Tsai, James C

2017-08-01

To calculate the associations between Medicare payment and service volume for complex and noncomplex cataract surgeries. The 2005-2009 CMS Part B National Summary Data Files, CMS Part B Carrier Summary Data Files, and the Medicare Physician Fee Schedule. Conducting a retrospective, longitudinal analysis using a fixed-effects model of Medicare Part B carriers representing all 50 states and the District of Columbia from 2005 to 2009, we calculated the Medicare payment-service volume elasticities for noncomplex (CPT 66984) and complex (CPT 66982) cataract surgeries. Service volume data were extracted from the CMS Part B National Summary and Carrier Summary Data Files. Payment data were extracted from the Medicare Physician Fee Schedule. From 2005 to 2009, the proportion of total cataract services billed as complex increased from 3.2 to 6.7 percent. Every 1 percent decrease in Medicare payment was associated with a nonsignificant change in noncomplex cataract service volume (elasticity = 0.15, 95 percent CI [-0.09, 0.38]) but a statistically significant increase in complex cataract service volume (elasticity = -1.12, 95 percent CI [-1.60, -0.63]). Reduced Medicare payment was associated with a significant increase in complex cataract service volume but not in noncomplex cataract service volume, resulting in a shift toward performing a greater proportion of complex cataract surgeries from 2005 to 2009. © Health Research and Educational Trust.

Spectrum '86: Proceedings: Volume 1

International Nuclear Information System (INIS)

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

1987-07-01

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

Low-level radioactive waste from commercial nuclear reactors. Volume 3. Bibliographic abstracts of significant source references. Part 2. Bibliography for treatment, storage, disposal and transportation regulatory constraints

Energy Technology Data Exchange (ETDEWEB)

Jolley, R.L.; Rodgers, B.R.

1986-05-01

The overall task of this program was to provide an assessment of currently available technology for treating commercial low-level radioactive waste (LLRW), to initiate development of a methodology for choosing one technology for a given application, and to identify research needed to improve current treatment techniques and decision methodology. The resulting report is issued in four volumes. Volume 3 of this series is a collection of abstracts of most of the reference documents used for this study. Because of the large volume of literature, the abstracts have been printed in two separate parts. Federal, state, and local regulations affect the decision process for selecting technology applications. Regulations may favor a particular technology and may prevent application of others. Volume 3, part 2 presents abstracts of the regulatory constraint documents that relate to all phases of LLRW management (e.g., treatment, packaging, storage, transportation, and disposal).

Directory of Certificates of Compliance for Radioactive Materials Packages. Summary report of NRC approved packages. Volume 1, Revision 8

International Nuclear Information System (INIS)

1985-10-01

This directory contains a Summary Report of NRC Approved Packages (Volume 1), Certificates of Compliance (Volume 2), and a Summary Report of NRC Approved Quality Assurance Programs for Radioactive Material Packages (Volume 3). The purpose of this directory is to make available a convenient source of information on packagings which have been approved by the US Nuclear Regulatory Commission. To assist in identifying packaging, an index by Model Number and corresponding Certificate of Compliance number is included at the back of each volume of the directory. The Summary Report includes a listing of all users of each package design prior to the publication date of the directory. Shipments of radioactive material utilizing these packagings must be in accordance with the provisions of 49 CFR 173.471 and 10 CFR Part 71, as applicable. In satisfying the requirements of Section 71.12, it is the responsibility of the licensees to insure them that they have a copy of the current approval and conduct their transportation activities in accordance with an NRC approved quality assurance program. Copies of the current approval may be obtained from the US Nuclear Regulatory Commission Public Document Room files (see Docket No. listed on each certificate) at 1717 H Street, Washington, DC 20555. Note that the general license of 10 CFR 71.12 does not authorize the receipt, possession, use or transfer of byproduct source, or special nuclear material; such authorization must be obtained pursuant to 10 CFR Parts 30 to 36, 40, 50, or 70

Directory of certificates of compliance for radioactive materials packages. Summary report of NRC approved packages. Volume 1. Revision 9

International Nuclear Information System (INIS)

1986-10-01

This directory contains a Summary Report of NRC Approved Packages (Volume 1), Certificates of Compliance (Volume 2), and a Summary Report of NRC Approved Quality Assurance Programs for Radioactive Material Packages (Volume 3). The purpose of this directory is to make available a convenient source of information on packagings which have been approved by the US Nuclear Regulatory Commission. To assist in identifying packaging, an index by Model Number and Corresponding Certificate of Compliance number is included at the back of each volume of the directory. The Summary Report includes a listing of all users of each package design prior to the publication date of the directory. Shipments of radioactive material utilizing these packagings must be in accordance with the provisions of 49 CFR 173.471 and 10 CFR Part 71, as applicable. In satisfying the requirements of Sections 71.12, it is the responsibility of the licensees to insure them that they have a copy of the current approval and conduct their transportation activities in accordance with an NRC approved quality assurance program. Copies of the current approval may be obtained from the US Nuclear Regulatory Commission Public Document Room files (see Docket No. listed on each certificate) at 1717 H Street, Washington, DC 20555. Note that the general license of 10 CFR 71.12 does not authorize the receipt, possession, use or transfer of byproduct source, or special nuclear material; such authorization must be obtained pursuant to 10 CFR Parts 30 to 36, 40, 50, or 70

Directory of certificates of compliance for radioactive materials packages. Summary report of NRC approved packages. Volume 1, Revision 7

International Nuclear Information System (INIS)

1984-11-01

This directory contains a Summary Report of NRC Approved Packages (Volume 1), Certificates of Compliance (Volume 2), and a Summary Report of NRC Approved Quality Assurance Programs for Radioactive Material Packages (Volume 3). The purpose of this directory is to make available a convenient source of information on packagings which have been approved by the US Nuclear Regulatory Commission. To assist in identifying packaging, an index by Model Number and corresponding Certificate of Compliance number is included at the back of each volume of the directory. The Summary Report includes a listing of all users of each package design prior to the publication date of the directory. Shipments of radioactive material utilizing these packagings must be in accordance with the provisions of 49 CFR 173.471 and 10 CFR Part 71, as applicable. In satisfying the requirements of Section 71.12, it is the responsibility of the licensees to insure that they have a copy of the current approval and conduct their transportation activities in accordance with an NRC approved quality assurance program. Copies of the current approval may be obtained from the US Nuclear Regulatory Commission Public Document Room files (see Docket No. listed on each certificate) at 1717 H Street, Washington, DC 20555. Note that the general license of 10 CFR 71.12 does not authorize the receipt, possession, use or transfer of byproduct source, or special nuclear material; such authorization must be obtained pursuant to 10 CFR Parts 30 to 36, 40, 50, or 70

Prototypical Rod Construction Demonstration Project. Phase 3, Final report: Volume 1, Cold checkout test report, Book 3

Energy Technology Data Exchange (ETDEWEB)

1993-05-01

The objective of Phase 3 of the Prototypical Rod consolidation Demonstration Project (PRCDP) was to procure, fabricate, assemble, and test the Prototypical Rod consolidation System as described in the NUS Phase 2 Final Design Report. This effort required providing the materials, components, and fabricated parts which makes up all of the system equipment. In addition, it included the assembly, installation, and setup of this equipment at the Cold Test Facility. During the Phase 3 effort the system was tested on a component, subsystem, and system level. This volume 1, discusses the PRCDP Phase 3 Test Program that was conducted by the HALLIBURTON NUS Environmental Corporation under contract AC07-86ID12651 with the United States Department of Energy. This document, Volume 1, Book 3 discusses the following topics: Downender Test Results and Analysis Report; NFBC Canister Upender Test Results and Analysis Report; Fuel Assembly Handling Fixture Test Results and Analysis Report; and Fuel Canister Upender Test Results and Analysis Report.

Mg II ABSORPTION CHARACTERISTICS OF A VOLUME-LIMITED SAMPLE OF GALAXIES AT z ∼ 0.1

International Nuclear Information System (INIS)

Barton, Elizabeth J.; Cooke, Jeff

2009-01-01

We present an initial survey of Mg II absorption characteristics in the halos of a carefully constructed, volume-limited subsample of galaxies embedded in the spectroscopic part of the Sloan Digital Sky Survey (SDSS). We observed quasars near sightlines to 20 low-redshift (z ∼ 0.1), luminous (M r + 5log h ≤-20.5) galaxies in SDSS DR4 and DR6 with the LRIS-B spectrograph on the Keck I telescope. The primary systematic criteria for the targeted galaxies are a redshift z ∼> 0.1 and the presence of an appropriate bright background quasar within a projected 75 h -1 kpc of its center, although we preferentially sample galaxies with lower impact parameters and slightly more star formation within this range. Of the observed systems, six exhibit strong (W eq (2796) ≥ 0.3 A) Mg II absorption at the galaxy's redshift, six systems have upper limits which preclude strong Mg II absorption, while the remaining observations rule out very strong (W eq (2796) ≥ 1-2 A) absorption. The absorbers fall at higher impact parameters than many non-absorber sightlines, indicating a covering fraction f c ∼ -1 kpc (f c ∼ 0.25). The data are consistent with a possible dependence of covering fraction and/or absorption halo size on the environment or star-forming properties of the central galaxy.

Site Environmental Report for 2011, Volumes 1& 2

Energy Technology Data Exchange (ETDEWEB)

Baskin, David; Bauters, Tim; Borglin, Ned; Fox, Robert; Horst, Blair; Jelinski, John; Lackner, Ginny; Philliber, Jeff; Rothermich, Nancy; Thorson, Patrick; Wahl, Linnea; Xu, Suying

2012-09-12

The Site Environmental Report for 2011 summarizes Berkeley Lab’s environmental management performance, presents environmental monitoring results, and describes significant programs for calendar year (CY) 2011. Throughout this report, “Berkeley Lab” or “LBNL” refers both to (1) the multiprogram scientific facility the UC manages and operates on the 202-acre university-owned site located in the hills above the UC Berkeley campus, and the site itself, and (2) the UC as managing and operating contractor for Ernest Orlando Lawrence Berkeley National Laboratory. The report is separated into two volumes. Volume I is organized into an executive summary followed by six chapters that include an overview of LBNL, a discussion of its Environmental Management System (EMS), the status of environmental programs, summarized results from surveillance and monitoring activities, and quality assurance (QA) measures. Volume II contains individual data results from surveillance and monitoring activities.

Construction of a Liposome Dialyzer for preparation of high-value, small-volume liposome formulations

Science.gov (United States)

Adamala, Katarzyna; Engelhart, Aaron E.; Kamat, Neha P.; Jin, Lin; Szostak, Jack W.

2016-01-01

The liposome dialyzer is a small-volume equilibrium dialysis device, built from commercially available materials, that is designed for rapid exchange of small volumes of an extraliposomal reagent pool against a liposome preparation. The dialyzer is prepared by modification of commercially available dialysis cartridges and consists of a reactor with two 300 µL chambers and a 1.56 cm2 dialysis surface area. The dialyzer is prepared in three stages: 1) disassembly of dialysis cartridges to obtain required parts; 2) assembly of the dialyzer; and 3) sealing the dialyzer with epoxy. Preparation of the dialyser takes about 1.5 h, not including overnight epoxy curing. Each round of dialysis takes 1–24 h, depending on the analyte and membrane employed. We previously used the dialyzer for small-volume nonenzymatic RNA synthesis reactions inside fatty acid vesicles. In this protocol, we demonstrate other applications, including removal of unencapsulated calcein from vesicles, remote loading, and vesicle microscopy. PMID:26020615

Human choice and climate change. Volume 1: The societal framework

International Nuclear Information System (INIS)

Raynor, S.; Malone, E.

1998-01-01

This book is Volume 1 of a four-volume set which assesses social science research that is relevant to global climate change from a wide-ranging interdisciplinary perspective. Attention is focused on the societal framework as it relates to climate change. This series is indispensable reading for scientists and engineers wishing to make an effective contribution to the climate change policy debate

Pathology annual. Part 1/Volume 23

International Nuclear Information System (INIS)

Rosen, P.P.; Fechner, R.E.

1988-01-01

This book contains 11 papers. Some of the titles are: Evaluation of Breast Biopsy Specimens in Patients Considered for Treatment by Conservative Surgery and Radiation Therapy for Early Breast Cancer; Magnetic Resonance Imaging of the Human Female Breast: Current Status and Pathologic Correlations; Ovarian Sex Cord-Stromal Tumors: Problems in Differential Diagnosis; and Vascular Lesions Following Radiation

12 CFR 513.1 - Scope of part.

Science.gov (United States)

2010-01-01

... 12 Banks and Banking 5 2010-01-01 2010-01-01 false Scope of part. 513.1 Section 513.1 Banks and Banking OFFICE OF THRIFT SUPERVISION, DEPARTMENT OF THE TREASURY PRACTICE BEFORE THE OFFICE § 513.1 Scope of part. This part prescribes rules with regard to general practice before the Office on one's own...

Fusion Technology 1996. Proceedings. Volume 1 and 2

International Nuclear Information System (INIS)

Varandas, C.; Serra, F.

1997-01-01

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

Hydrogeology of the 200 Areas low-level burial grounds: An interim report: Volume 1, Text

Energy Technology Data Exchange (ETDEWEB)

Last, G.V.; Bjornstad, B.N.; Bergeron, M.P.; Wallace, D.W.; Newcomer, D.R.; Schramke, J.A.; Chamness, M.A.; Cline, C.S.; Airhart, S.P.; Wilbur, J.S.

1989-01-01

This report presents information derived from the installation of 35 ground-water monitoring wells around six low-level radioactive/hazardous waste burial grounds located in the 200 Areas of the Hanford Site in southeastern Washington State. This information was collected between May 20, 1987 and August 1, 1988. The contents of this report have been divided into two volumes. This volume contains the main text. Volume 2 contains the appendixes, including data and supporting information that verify content and results found in the main text. This report documents information collected by the Pacific Northwest Laboratory at the request of Westinghouse Hanford Company. Presented in this report are the preliminary interpretations of the hydrogeologic environment of six low-level burial grounds, which comprise four waste management areas (WMAs) located in the 200 Areas of the Hanford Site. This information and its accompanying interpretations were derived from sampling and testing activities associated with the construction of 35 ground-water monitoring wells as well as a multitude of previously existing boreholes. The new monitoring wells were installed as part of a ground-water monitoring program initiated in 1986. This ground-water monitoring program is based on requirements for interim status facilities in compliance with the Resource Conservation and Recovery Act (1976).

Target volumes in gastric cancer radiation therapy; Les volumes-cibles de la radiotherapie des adenocarcinomes gastriques

Energy Technology Data Exchange (ETDEWEB)

Caudry, M.; Maire, J.P. [Hopital Saint Andre, Service de Cancerologie, 33 - Bordeaux (France); Ratoanina, J.L.; Escarmant, P. [Hopital Clarac, Service de Radiotherapie et de Cancerologie, 97 - Fort de France (France)

2001-10-01

The spread of gastric adenocarcinoma may follow three main patterns: hemato-genic, lymphatic and intraperitoneal. A GTV should be considered in preoperative or exclusive radiation therapy. After non-radical surgery, a 'residual GTV' will be defined with the help of the surgeon. The CTV encompasses three intricated volumes. a) A 'tumor bed' volume. After radical surgery, local recurrences appear as frequent as distant metastases. The risk depends upon the depth of parietal invasion and the nodal status. Parietal infiltration may extend beyond macroscopic limits of the tumor, especially in dinitis plastica. Therefore this volume will include: the tumor and the remaining stomach or their 'bed of resection', a part of the transverse colon, the duodenum, the pancreas and the troncus of the portal vein. In postoperative RT, this CTV also includes the jejuno-gastric or jejuno-esophageal anastomosis. b) A peritoneal volume. For practical purposes, two degrees of spread must be considered: (1) contiguous microscopic extension from deeply invasive T3 and T4 tumors, that remain amenable to local sterilization with doses of 45-50 Gy, delivered in a CTV including the peritoneal cavity at the level of the gastric bed, and under the parietal incision; (2) true 'peritoneal carcinomatosis', with widespread seeds, where chemotherapy (systemic or intraperitoneal) is more appropriate. c) A lymphatic volume including the lymph node groups 1 to 16 of the Japanese classification. This volume must encompass the hepatic pedicle and the splenic hilum. In proximal tumors, it is possible to restrict the lover part of the CTV to the lymphatic volume, and therefore to avoid irradiation of large intestinal and renal volumes. In distal and proximal tumors, involvement of resection margins is of poor prognosis -a radiation boost must be delivered at this level. The CTV in tumors of the cardia should encompass the lover part of the thoracic esophagus and the

In Situ Manufacturing is a Necessary Part of Any Planetary Architecture

Science.gov (United States)

Edmunson, Jennifer E.; McLemore, Carole A.

2012-01-01

The key to any sustainable presence in space is the ability to manufacture necessary tools, parts, structures, spares, etc. in situ and on demand. Cost, volume, and up-mass constraints prohibit launching everything needed for long-duration or long-distance missions from Earth, including spare parts and replacement systems. There are many benefits to building items as-needed in situ using computer aided drafting (CAD) models and additive manufacturing technology: (1) Cost, up-mass, and volume savings for launch due to the ability to manufacture specific parts when needed. (2) CAD models can be generated on Earth and transmitted to the station or spacecraft, or they can be designed in situ for any task. Thus, multiple people in many locations can work on a single problem. (3) Items can be produced that will enhance the safety of crew and vehicles (e.g., latches or guards). (4) Items can be produced on-demand in a small amount of time (i.e., hours or days) compared to traditional manufacturing methods and, therefore, would not require the lengthy amount of time needed to machine the part from a solid block of material nor the wait time required if the part had to be launched from Earth. (5) Used and obsolete parts can be recycled into powder or wire feedstock for use in later manufacturing. (6) Ultimately, the ability to produce items as-needed will reduce mission risk, as one will have everything they need to fix a broken system or fashion a new part making it available on a more timely basis.

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

International Nuclear Information System (INIS)

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

1994-06-01

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

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

Energy Technology Data Exchange (ETDEWEB)

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

1994-06-01

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

Active materials for automotive adaptive forward lighting Part 1: system requirements vs. material properties

Science.gov (United States)

Keefe, Andrew C.; Browne, Alan L.; Johnson, Nancy L.

2011-04-01

Adaptive Frontlighting Systems (AFS in GM usage) improve visibility by automatically optimizing the beam pattern to accommodate road, driving and environmental conditions. By moving, modifying, and/or adding light during nighttime, inclement weather, or in sharp turns, the driver is presented with dynamic illumination not possible with static lighting systems The objective of this GM-HRL collaborative research project was to assess the potential of active materials to decrease the cost, mass, and packaging volume of current electric stepper-motor AFS designs. Solid-state active material actuators, if proved suitable for this application, could be less expensive than electric motors and have lower part count, reduced size and weight, and lower acoustic and EMF noise1. This paper documents Part 1 of the collaborative study, assessing technically mature, commercially available active materials for use as actuators. Candidate materials should reduce cost and improve AFS capabilities, such as increased angular velocity on swivel. Additional benefits to AFS resulting from active materials actuators were to be identified as well such as lower part count. In addition, several notional approaches to AFS were documented to illustrate the potential function, which is developed more fully in Part 2. Part 1 was successful in verifying the feasibility of using two active materials for AFS: shape memory alloys, and piezoelectrics. In particular, this demonstration showed that all application requirements including those on actuation speed, force, and cyclic stability to effect manipulation of the filament assembly and/or the reflector could be met by piezoelectrics (as ultrasonic motors) and SMA wire actuators.

Acid-base titrations by stepwise addition of equal volumes of titrant with special reference to automatic titrations-III Presentation of a fully automatic titration apparatus and of results supporting the theories given in the preceding parts.

Science.gov (United States)

Pehrsson, L; Ingman, F

1977-02-01

This paper forms Part III of a series in which the first two parts describe methods for evaluating titrations performed by stepwise addition of equal volumes of titrant. The great advantage of these methods is that they do not require an accurate calibration of the electrode system. This property makes the methods very suitable for routine work. e.g., in automatic analysis. An apparatus for performing such titrations automatically is presented. Further, results of titrations of monoprotic acids, a diprotic acid, an ampholyte, a mixture of an acid with its conjugate base, and mixtures of two acids with a small difference between the stability constants are given. Most of these titrations cannot be evaluated by the Gran or Hofstee methods but yield results having errors of the order of 0.1% if the methods proposed in Parts I and II of this series are employed. The advantages of the method of stepwise addition of equal volumes of titrant combined with the proposed evaluation methods, in comparison with common methods such as titration to a preset pH, are that all the data are used in the evaluation, permitting a statistical treatment and giving better possibilities for tracing systematic errors.

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

Energy Technology Data Exchange (ETDEWEB)

Fellows, R.L. [ed.

1993-02-26

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

Approved Site Treatment Plan, Volumes 1 and 2. Revision 4

Energy Technology Data Exchange (ETDEWEB)

Helmich, E.H.; Molen, G.; Noller, D.

1996-03-22

The US Department of Energy, Savannah River Operations Office (DOE-SR), has prepared the Site Treatment Plan (STP) for Savannah River Site (SRS) mixed wastes in accordance with RCRA Section 3021(b), and SCDHEC has approved the STP (except for certain offsite wastes) and issued an order enforcing the STP commitments in Volume 1. DOE-SR and SCDHEC agree that this STP fulfills the requirements contained in the FFCAct, RCRA Section 3021, and therefore, pursuant to Section 105(a) of the FFCAct (RCRA Section 3021(b)(5)), DOE`s requirements are to implement the plan for the development of treatment capacities and technologies pursuant to RCRA Section 3021. Emerging and new technologies not yet considered may be identified to manage waste more safely, effectively, and at lower cost than technologies currently identified in the plan. DOE will continue to evaluate and develop technologies that offer potential advantages in public acceptance, privatization, consolidation, risk abatement, performance, and life-cycle cost. Should technologies that offer such advantages be identified, DOE may request a revision/modification of the STP in accordance with the provisions of Consent Order 95-22-HW. The Compliance Plan Volume (Volume 1) identifies project activity schedule milestones for achieving compliance with Land Disposal Restrictions (LDR). Information regarding the technical evaluation of treatment options for SRS mixed wastes is contained in the Background Volume (Volume 2) and is provided for information.

Approved Site Treatment Plan, Volumes 1 and 2. Revision 4

International Nuclear Information System (INIS)

Helmich, E.H.; Molen, G.; Noller, D.

1996-01-01

The US Department of Energy, Savannah River Operations Office (DOE-SR), has prepared the Site Treatment Plan (STP) for Savannah River Site (SRS) mixed wastes in accordance with RCRA Section 3021(b), and SCDHEC has approved the STP (except for certain offsite wastes) and issued an order enforcing the STP commitments in Volume 1. DOE-SR and SCDHEC agree that this STP fulfills the requirements contained in the FFCAct, RCRA Section 3021, and therefore, pursuant to Section 105(a) of the FFCAct (RCRA Section 3021(b)(5)), DOE's requirements are to implement the plan for the development of treatment capacities and technologies pursuant to RCRA Section 3021. Emerging and new technologies not yet considered may be identified to manage waste more safely, effectively, and at lower cost than technologies currently identified in the plan. DOE will continue to evaluate and develop technologies that offer potential advantages in public acceptance, privatization, consolidation, risk abatement, performance, and life-cycle cost. Should technologies that offer such advantages be identified, DOE may request a revision/modification of the STP in accordance with the provisions of Consent Order 95-22-HW. The Compliance Plan Volume (Volume 1) identifies project activity schedule milestones for achieving compliance with Land Disposal Restrictions (LDR). Information regarding the technical evaluation of treatment options for SRS mixed wastes is contained in the Background Volume (Volume 2) and is provided for information

Liquid Metal Engineering and Technology. Volume 1

International Nuclear Information System (INIS)

1988-01-01

These proceedings of the fourth international conference on liquid metal engineering and technology volume 1, are devided into 3 sections bearing on: - Apparatus and components for liquid metal (29 papers) - Liquid metal leaks, fires and fumes (10 papers) - Cleaning, decontamination, waste disposal (14 papers) [fr

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

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.

Diversion Path Analysis handbook. Volume 3 (of 4 volumes). Computer Program 1

International Nuclear Information System (INIS)

Schleter, J.C.

1978-11-01

The FORTRAN IV computer program, DPA Computer Program 1 (DPACP-1), is used to assemble and tabulate the data for Specific Diversion Paths (SDPs) identified when performing a Diversion Path Analysis (DPA) in accord with the methodology given in Volume 1. The program requires 255498 bytes exclusive of the operating system. The data assembled and tabulated by DPACP-1 are used by the DPA team to assist in analyzing vulnerabilities, in a plant's material control and material accounting subsystems, to diversion of special nuclear material (SNM) by a knowledgable insider. Based on this analysis, the DPA team can identify, and propose to plant management, modifications to the plant's safeguards system that would eliminate, or reduce the severity of, the identified vulnerabilities. The data are also used by plant supervision when investigating a potential diversion

Target volumes in gastric cancer radiation therapy

International Nuclear Information System (INIS)

Caudry, M.; Maire, J.P.; Ratoanina, J.L.; Escarmant, P.

2001-01-01

The spread of gastric adenocarcinoma may follow three main patterns: hemato-genic, lymphatic and intraperitoneal. A GTV should be considered in preoperative or exclusive radiation therapy. After non-radical surgery, a 'residual GTV' will be defined with the help of the surgeon. The CTV encompasses three intricated volumes. a) A 'tumor bed' volume. After radical surgery, local recurrences appear as frequent as distant metastases. The risk depends upon the depth of parietal invasion and the nodal status. Parietal infiltration may extend beyond macroscopic limits of the tumor, especially in dinitis plastica. Therefore this volume will include: the tumor and the remaining stomach or their 'bed of resection', a part of the transverse colon, the duodenum, the pancreas and the troncus of the portal vein. In postoperative RT, this CTV also includes the jejuno-gastric or jejuno-esophageal anastomosis. b) A peritoneal volume. For practical purposes, two degrees of spread must be considered: (1) contiguous microscopic extension from deeply invasive T3 and T4 tumors, that remain amenable to local sterilization with doses of 45-50 Gy, delivered in a CTV including the peritoneal cavity at the level of the gastric bed, and under the parietal incision; (2) true 'peritoneal carcinomatosis', with widespread seeds, where chemotherapy (systemic or intraperitoneal) is more appropriate. c) A lymphatic volume including the lymph node groups 1 to 16 of the Japanese classification. This volume must encompass the hepatic pedicle and the splenic hilum. In proximal tumors, it is possible to restrict the lover part of the CTV to the lymphatic volume, and therefore to avoid irradiation of large intestinal and renal volumes. In distal and proximal tumors, involvement of resection margins is of poor prognosis -a radiation boost must be delivered at this level. The CTV in tumors of the cardia should encompass the lover part of the thoracic esophagus and the corresponding posterior mediastinum. In

FY01 Supplemental Science and Performance Analyses, Volume 1: Scientific Bases and Analyses, Part 1 and 2

International Nuclear Information System (INIS)

Dobson, David

2001-01-01

The U.S. Department of Energy (DOE) is considering the possible recommendation of a site at Yucca Mountain, Nevada, for development as a geologic repository for the disposal of high-level radioactive waste and spent nuclear fuel. To facilitate public review and comment, in May 2001 the DOE released the Yucca Mountain Science and Engineering Report (S and ER) (DOE 2001 [DIRS 153849]), which presents technical information supporting the consideration of the possible site recommendation. The report summarizes the results of more than 20 years of scientific and engineering studies. A decision to recommend the site has not been made: the DOE has provided the S and ER and its supporting documents as an aid to the public in formulating comments on the possible recommendation. When the S and ER (DOE 2001 [DIRS 153849]) was released, the DOE acknowledged that technical and scientific analyses of the site were ongoing. Therefore, the DOE noted in the Federal Register Notice accompanying the report (66 FR 23 013 [DIRS 155009], p. 2) that additional technical information would be released before the dates, locations, and times for public hearings on the possible recommendation were announced. This information includes: (1) the results of additional technical studies of a potential repository at Yucca Mountain, contained in this FY01 Supplemental Science and Performance Analyses: Vol. 1, Scientific Bases and Analyses; and FY01 Supplemental Science and Performance Analyses: Vol. 2, Performance Analyses (McNeish 2001 [DIRS 155023]) (collectively referred to as the SSPA) and (2) a preliminary evaluation of the Yucca Mountain site's preclosure and postclosure performance against the DOE's proposed site suitability guidelines (10 CFR Part 963 [64 FR 67054] [DIRS 124754]). By making the large amount of information developed on Yucca Mountain available in stages, the DOE intends to provide the public and interested parties with time to review the available materials and to formulate

A Quantitative Analysis of the Relationship between Medicare Payment and Service Volume for Glaucoma Procedures from 2005 through 2009.

Science.gov (United States)

Gong, Dan; Jun, Lin; Tsai, James C

2015-05-01

To calculate the association between Medicare payment and service volume for 6 commonly performed glaucoma procedures. Retrospective, longitudinal database study. A 100% dataset of all glaucoma procedures performed on Medicare Part B beneficiaries within the United States from 2005 to 2009. Fixed-effects regression model using Medicare Part B carrier data for all 50 states and the District of Columbia, controlling for time-invariant carrier-specific characteristics, national trends in glaucoma service volume, Medicare beneficiary population, number of ophthalmologists, and income per capita. Payment-volume elasticities, defined as the percent change in service volume per 1% change in Medicare payment, for laser trabeculoplasty (Current Procedural Terminology [CPT] code 65855), trabeculectomy without previous surgery (CPT code 66170), trabeculectomy with previous surgery (CPT code 66172), aqueous shunt to reservoir (CPT code 66180), laser iridotomy (CPT code 66761), and scleral reinforcement with graft (CPT code 67255). The payment-volume elasticity was nonsignificant for 4 of 6 procedures studied: laser trabeculoplasty (elasticity, -0.27; 95% confidence interval [CI], -1.31 to 0.77; P = 0.61), trabeculectomy without previous surgery (elasticity, -0.42; 95% CI, -0.85 to 0.01; P = 0.053), trabeculectomy with previous surgery (elasticity, -0.28; 95% CI, -0.83 to 0.28; P = 0.32), and aqueous shunt to reservoir (elasticity, -0.47; 95% CI, -3.32 to 2.37; P = 0.74). Two procedures yielded significant associations between Medicare payment and service volume. For laser iridotomy, the payment-volume elasticity was -1.06 (95% CI, -1.39 to -0.72; P payment, laser iridotomy service volume increased by 1.06%. For scleral reinforcement with graft, the payment-volume elasticity was -2.92 (95% CI, -5.72 to -0.12; P = 0.041): for every 1% decrease in CPT code 67255 payment, scleral reinforcement with graft service volume increased by 2.92%. This study calculated the association

44 CFR 1.6 - Ex parte communications.

Science.gov (United States)

2010-10-01

... 44 Emergency Management and Assistance 1 2010-10-01 2010-10-01 false Ex parte communications. 1.6 Section 1.6 Emergency Management and Assistance FEDERAL EMERGENCY MANAGEMENT AGENCY, DEPARTMENT OF HOMELAND SECURITY GENERAL RULEMAKING; POLICY AND PROCEDURES General § 1.6 Ex parte communications. In...

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

International Nuclear Information System (INIS)

DeHart, M.D.

1995-03-01

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

Mathematical model of a utility firm. Final technical report, Part IIA

Energy Technology Data Exchange (ETDEWEB)

1983-08-21

This volume is part of a project aimed at developing an understanding of the dynamical processes that evolve within an electric utility firm, and without it. The volume covers organizational dynamics and many-person symmetric games. (DLC)

History of CERN. Volume 3

International Nuclear Information System (INIS)

Krige, J.

1996-01-01

The present volume continues the story of the history of the European Organization for Nuclear Research (CERN) in Geneva, Switzerland, concentrating on the years between the mid 1960s and the late 1970s. Whereas the first two volumes were the product of a team of historians, this book is rather a collection of studies by authors with very different professional backgrounds and institutional locations. It also differs from the predecessor volumes in the fact that it consists of distinct case studies dealing with a number of issues deemed important. The first part of this volume, containing contributions by historians of science, perceives the laboratory as being at the node of a complex of interconnected relationships between scientists and science managers on the staff, the users in the member states, and the governments which were called upon to finance the laboratory. In part 2 the physical results, obtained at CERN, are surveyed, while in part 3 two chapters are presented, one on engineering and technology, and the other on the research and development of electronic position detectors

Lincoln Laboratory Journal. Volume 22, Number 1, 2016

Science.gov (United States)

2016-06-09

different service models—infrastructure as a service (IaaS), platform as a service (PaaS), and software as a service ( SaaS )—that target system... SaaS Full-fledged applications Low Google Gmail, Microsoft Office 365, Facebook 126 LINCOLN LABORATORY JOURNAL n VOLUME 22, NUMBER 1, 2016 SECURE AND

VIPRE-01. a thermal-hydraulic analysis code for reactor cores. Volume 1. Mathematical modeling

International Nuclear Information System (INIS)

Stewart, C.W.; Cuta, J.M.; Koontz, A.S.; Kelly, J.M.; Basehore, K.L.; George, T.L.; Rowe, D.S.

1983-04-01

VIPRE (Versatile Internals and Component Program for Reactors; EPRI) has been developed for nuclear power utility thermal-hydraulic analysis applications. It is designed to help evaluate nuclear reactor core safety limits including minimum departure from nucleate boiling ratio (MDNBR), critical power ratio (CPR), fuel and clad temperatures, and coolant state in normal operation and assumed accident conditions. This volume (Volume 1: Mathematical Modeling) explains the major thermal hydraulic models and supporting correlations in detail

Mirror Advanced Reactor Study (MARS). Final report. Volume 1-A. Commercial fusion electric plant

International Nuclear Information System (INIS)

Donohue, M.L.; Price, M.E.

1984-07-01

Volume 1-A contains the following chapters: (1) plasma engineering, (2) magnets, (3) ecr heating systems, (4) anchor ion-cyclotron resonance heating system, (5) sloshing ion neutral beam, (6) end cell structure, (7) end plasma technology, (8) fueling, (9) startup ion cyclotron resonant heating systems, and (10) end cell radiation analysis

Oak Ridge Health Studies Phase 1 report, Volume 2, Part B, Dose Reconstruction Feasibility Study

International Nuclear Information System (INIS)

Brorby, G.P.; Bruce, G.M.; Widner, T.E.

1993-09-01

While each of the three different screening comparisons made in this report (i.e., within-medium evaluation, between-media evaluation and relative importance grouping) individually provides information potentially of value in focusing future studies, each one is subject to a variety of limitations, the most important being associated with the absence or variable quality of environmental data for a number of the contaminants and media. These screening exercises are intended to provide an initial framework for approaching the study of an extremely complex site. Other approaches could very well yield somewhat different priorities, and the identification or reinterpretation of data in subsequent detailed studies are likely to invalidate some of the results of these screening exercises. However, these evaluations provide a logical approach to defining initial off- site health impact study priorities for the ORR. Therefore, while care must be taken in attempting to make any broad generalizations or greatly simplifying assumptions with regard to the potential health hazards posed by the complex releases from the Reservation, Table 6-1 represents an attempt to summarize a set of recommendations that are derived from the screening exercises presented in this report. Table 6-1 identifies the facilities, processes and contaminants believed to have the highest potential for resulting in off-site health impacts. Table 6-2 identifies contaminants for which no ranking could be performed as part of this feasibility study, because of the absence of any appropriate data for any environmental medium

Market projections of cellulose nanomaterial-enabled products-- Part 2: Volume estimates

Science.gov (United States)

John Cowie; E.M. (Ted) Bilek; Theodore H. Wegner; Jo Anne Shatkin

2014-01-01

Nanocellulose has enormous potential to provide an important materials platform in numerous product sectors. This study builds on previous work by the same authors in which likely high-volume, low-volume, and novel applications for cellulosic nanomaterials were identified. In particular, this study creates a transparent methodology and estimates the potential annual...

A study in derived algebraic geometry volume I : correspondences and duality

CERN Document Server

Gaitsgory, Dennis

2017-01-01

Derived algebraic geometry is a far-reaching generalization of algebraic geometry. It has found numerous applications in various parts of mathematics, most prominently in representation theory. This volume develops the theory of ind-coherent sheaves in the context of derived algebraic geometry. Ind-coherent sheaves are a "renormalization" of quasi-coherent sheaves and provide a natural setting for Grothendieck-Serre duality as well as geometric incarnations of numerous categories of interest in representation theory. This volume consists of three parts and an appendix. The first part is a survey of homotopical algebra in the setting of \\infty-categories and the basics of derived algebraic geometry. The second part builds the theory of ind-coherent sheaves as a functor out of the category of correspondences and studies the relationship between ind-coherent and quasi-coherent sheaves. The third part sets up the general machinery of the \\mathrm{(}\\infty, 2\\mathrm{)}-category of correspondences needed for the sec...

Mirror Advanced Reactor Study (MARS). Final report. Volume 1-A. Commercial fusion electric plant

Energy Technology Data Exchange (ETDEWEB)

Donohue, M.L.; Price, M.E. (eds.)

1984-07-01

Volume 1-A contains the following chapters: (1) plasma engineering, (2) magnets, (3) ecr heating systems, (4) anchor ion-cyclotron resonance heating system, (5) sloshing ion neutral beam, (6) end cell structure, (7) end plasma technology, (8) fueling, (9) startup ion cyclotron resonant heating systems, and (10) end cell radiation analysis. (MOW)

C2H4ArF2 1,1-Difluoroethane - argon (1/1)

Science.gov (United States)

Demaison, J.

This document is part of Part 1 of Subvolume D 'Asymmetric Top Molecules' of Volume 29 'Molecular Constants Mostly from Microwave, Molecular Beam, and Sub-Doppler Laser Spectroscopy' of Landolt-Börnstein - Group II 'Molecules and Radicals'.

Excess molar volumes and viscosities of binary mixtures of 1,2

Indian Academy of Sciences (India)

Home; Journals; Journal of Chemical Sciences; Volume 113; Issue 3. Excess molar volumes and viscosities of binary mixtures of 1,2-diethoxyethane with chloroalkanes ... The Bloomfield and Dewan model has been used to calculate viscosity ...

Changes in forced expiratory volume in 1 second over time in COPD

DEFF Research Database (Denmark)

Vestbo, Jørgen; Edwards, Lisa D; Scanlon, Paul D

2011-01-01

A key feature of chronic obstructive pulmonary disease (COPD) is an accelerated rate of decline in forced expiratory volume in 1 second (FEV(1)), but data on the variability and determinants of this change in patients who have established disease are scarce.......A key feature of chronic obstructive pulmonary disease (COPD) is an accelerated rate of decline in forced expiratory volume in 1 second (FEV(1)), but data on the variability and determinants of this change in patients who have established disease are scarce....

A Selection of Experimental Test Cases for the Validation of CFD Codes (Recueil de cas d’essai experimentaux pour la validation des codes de l’aerodynamique numerique). Volume 1

Science.gov (United States)

1994-08-01

volume H1. Le rapport ext accompagnt5 doun jeo die disqoettex contenant les donn~es appropri~es Li bous let cas d’essai. (’es disqoettes sont disponibles ...GERMANY PURPL’Sb OF THE TESi The tests are part of a larger effort to establish a database of experimental measurements for missile configurations

Prediction of the volume flux of the thermal plume above a sitting person

DEFF Research Database (Denmark)

Zukowska, Daria; Popiolek, Zbigniew J.; Melikov, Arsen Krikor

2009-01-01

The paper presents a verification of a relatively simple method of volume flux calculation applied to the asymmetrical thermal plume generated by a sitting person in a condition of an upward piston flow. The method is based on a model of a thermal plume above a point heat source in an unbounded...... space. The plume volume flux, V, can be calculated based on the following equation: V = kv*Qexp(1/3)*(zt-zv)exp(5/3). In the equation zt is the distance from the measuring plane to the top of the heat source and Qc is the convective part of the heat loss. A value of the entrainment coefficient, kv...

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 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.

Australian Chemistry Test Item Bank: Years 11 & 12. Volume 1.

Science.gov (United States)

Commons, C., Ed.; Martin, P., Ed.

Volume 1 of the Australian Chemistry Test Item Bank, consisting of two volumes, contains nearly 2000 multiple-choice items related to the chemistry taught in Year 11 and Year 12 courses in Australia. Items which were written during 1979 and 1980 were initially published in the "ACER Chemistry Test Item Collection" and in the "ACER…

Acute effects of volume-oriented incentive spirometry on chest wall volumes in patients after a stroke.

Science.gov (United States)

Lima, Illia Ndf; Fregonezi, Guilherme Af; Melo, Rodrigo; Cabral, Elis Ea; Aliverti, Andrea; Campos, Tânia F; Ferreira, Gardênia Mh

2014-07-01

The aim of the present study was to assess how volume-oriented incentive spirometry applied to patients after a stroke modifies the total and compartmental chest wall volume variations, including both the right and left hemithoraces, compared with controls. Twenty poststroke patients and 20 age-matched healthy subjects were studied by optoelectronic plethysmography during spontaneous quiet breathing (QB), during incentive spirometry, and during the recovery period after incentive spirometry. Incentive spirometry was associated with an increased chest wall volume measured at the pulmonary rib cage, abdominal rib cage and abdominal compartment (P = .001) and under 3 conditions (P spirometry, and postincentive spirometry, respectively. Under all 3 conditions, the contribution of the abdominal compartment to VT was greater in the stroke subjects (54.1, 43.2, and 48.9%) than in the control subjects (43.7, 40.8, and 46.1%, P = .039). In the vast majority of subjects (13/20 and 18/20 during QB and incentive spirometry, respectively), abdominal expansion precedes rib cage expansion during inspiration. Greater asymmetry between the right and left hemithoracic expansions occurred in stroke subjects compared with control subjects, but it decreased during QB (62.5%, P = .002), during incentive spirometry (19.7%), and postincentive spirometry (67.6%, P = .14). Incentive spirometry promotes increased expansion in all compartments of the chest wall and reduces asymmetric expansion between the right and left parts of the pulmonary rib cage; therefore, it should be considered as a tool for rehabilitation. Copyright © 2014 by Daedalus Enterprises.

Construction of a liposome dialyzer for the preparation of high-value, small-volume liposome formulations.

Science.gov (United States)

Adamala, Katarzyna; Engelhart, Aaron E; Kamat, Neha P; Jin, Lin; Szostak, Jack W

2015-06-01

The liposome dialyzer is a small-volume equilibrium dialysis device, built from commercially available materials, that is designed for the rapid exchange of small volumes of an extraliposomal reagent pool against a liposome preparation. The dialyzer is prepared by modification of commercially available dialysis cartridges (Slide-A-Lyzer cassettes), and it consists of a reactor with two 300-μl chambers and a 1.56-cm(2) dialysis surface area. The dialyzer is prepared in three stages: (i) disassembling the dialysis cartridges to obtain the required parts, (ii) assembling the dialyzer and (iii) sealing the dialyzer with epoxy. Preparation of the dialyzer takes ∼1.5 h, not including overnight epoxy curing. Each round of dialysis takes 1-24 h, depending on the analyte and membrane used. We previously used the dialyzer for small-volume non-enzymatic RNA synthesis reactions inside fatty acid vesicles. In this protocol, we demonstrate other applications, including removal of unencapsulated calcein from vesicles, remote loading and vesicle microscopy.

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

International Nuclear Information System (INIS)

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

2006-01-01

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

The Feasibility of Teaching Science via a Socio-Historical Approach. Part 2. Classroom Materials. Practical Paper No. 303. (Part 1 of 2 Parts).

Science.gov (United States)

Agin, Michael Lawrence

This publication, part 1 of two parts, presents the narrative materials for the teaching of the concept--the development of atomic energy and its social implications--growing out of a study made to determine the feasibility of teaching scientific concepts related to the social and historical developments of science and selected concepts related to…

European Science Notes. Volume 40, Number 1.

Science.gov (United States)

1986-01-01

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

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

International Nuclear Information System (INIS)

1988-09-01

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

Aprende Ajedrez con Rey - Parte 1

OpenAIRE

ESTÉVEZ MONTERO, RAÚL; Lloret Mauri, Jaime

2016-01-01

Es una pieza audiovisual creada con el objeto de atraer la atención de los niños de muy corta edad con el ajedrez y familiarizarlos con todas sus piezas y movimientos. Es una animación dirigida a un público infantil presentada por dibujos animados en 2D, en la que se ha intentado respetar en todo momento el argot de la comunidad ajedredística. En este video se presenta la primera parte. Estévez Montero, R.; Lloret Mauri, J. (2016). Aprende Ajedrez con Rey - Parte 1. http://hdl.handle.net/1...

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

International Nuclear Information System (INIS)

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

1988-03-01

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

12 CFR 516.1 - What does this part do?

Science.gov (United States)

2010-01-01

... 12 Banks and Banking 5 2010-01-01 2010-01-01 false What does this part do? 516.1 Section 516.1 Banks and Banking OFFICE OF THRIFT SUPERVISION, DEPARTMENT OF THE TREASURY APPLICATION PROCESSING PROCEDURES § 516.1 What does this part do? (a) This part explains OTS procedures for processing applications...

The analysis of subsidence associated with geothermal development. Volume 1. Handbook

Energy Technology Data Exchange (ETDEWEB)

Atherton, R.W.; Finnemore, E.J.; Gillam, M.L.

1976-09-01

This study evaluates the state of knowledge of subsidence associated with geothermal development, and provides preliminary methods to assess the potential of land subsidence for any specific geothermal site. The results of this study are presented in three volumes. Volume 1 is designed to serve as a concise reference, a handbook, for the evaluation of the potential for land subsidence from the development of geothermal resources.

A pilot study to monitor changes in spirometry and lung volume, following an exacerbation of Chronic Obstructive Pulmonary Disease (COPD), as part of a supported discharge program.

Science.gov (United States)

Cushen, Breda; McCormack, Niamh; Hennigan, Kerrie; Sulaiman, Imran; Costello, Richard W; Deering, Brenda

2016-10-01

One-third of patients with an exacerbation of Chronic Obstructive Pulmonary Disease(COPD) are re-hospitalised at 90 days. Exacerbation recovery is associated with reductions in lung hyperinflation and improvements in symptoms and physical activity. We assessed the feasibility of monitoring these clinical parameters in the home. We hypothesised that the degree of change in spirometry and lung volumes differs between those who had an uneventful recovery and those who experienced a further exacerbation. Hospitalised patients with an acute exacerbation of COPD referred for a supported discharge program participated in the study. Spirometry and Inspiratory Vital Capacity(IVC) were measured in the home at Days 1, 14 and 42 post-discharge. Patients also completed Medical Research Council(MRC), Borg and COPD Assessment Test(CAT) scores and were provided with a tri-axial accelerometer. Any new exacerbation events were recorded. Sixty-five patients with 72 exacerbation episodes were recruited. Fifty percent experienced a second exacerbation. Adequate IVC measurements were achieved by 90%, while only 70% completed spirometry. Uneventful recovery was accompanied by significant improvements in physiological measurements at day14, improved symptom scores and step count, p volumes, symptoms and step count following a COPD exacerbation may help to identify patients at risk of re-exacerbation. It is feasible to carry out these assessments in the home as part of a supported discharge programme. Copyright © 2016 Elsevier Ltd. All rights reserved.

12 CFR 559.1 - What does this part cover?

Science.gov (United States)

2010-01-01

... 12 Banks and Banking 5 2010-01-01 2010-01-01 false What does this part cover? 559.1 Section 559.1 Banks and Banking OFFICE OF THRIFT SUPERVISION, DEPARTMENT OF THE TREASURY SUBORDINATE ORGANIZATIONS § 559.1 What does this part cover? (a) OTS is issuing this part 559 pursuant to its general rulemaking...

Workshop on Advanced Technologies for Planetary Instruments, part 1

International Nuclear Information System (INIS)

Appleby, J.F.

1993-01-01

This meeting was conceived in response to new challenges facing NASA's robotic solar system exploration program. This volume contains papers presented at the Workshop on Advanced Technologies for Planetary Instruments on 28-30 Apr. 1993. This meeting was conceived in response to new challenges facing NASA's robotic solar system exploration program. Over the past several years, SDIO has sponsored a significant technology development program aimed, in part, at the production of instruments with these characteristics. This workshop provided an opportunity for specialists from the planetary science and DOD communities to establish contacts, to explore common technical ground in an open forum, and more specifically, to discuss the applicability of SDIO's technology base to planetary science instruments

Geometry of lengths, areas, and volumes two-dimensional spaces, volume 1

CERN Document Server

Cannon, James W

2017-01-01

This is the first of a three volume collection devoted to the geometry, topology, and curvature of 2-dimensional spaces. The collection provides a guided tour through a wide range of topics by one of the twentieth century's masters of geometric topology. The books are accessible to college and graduate students and provide perspective and insight to mathematicians at all levels who are interested in geometry and topology. The first volume begins with length measurement as dominated by the Pythagorean Theorem (three proofs) with application to number theory; areas measured by slicing and scaling, where Archimedes uses the physical weights and balances to calculate spherical volume and is led to the invention of calculus; areas by cut and paste, leading to the Bolyai-Gerwien theorem on squaring polygons; areas by counting, leading to the theory of continued fractions, the efficient rational approximation of real numbers, and Minkowski's theorem on convex bodies; straight-edge and compass constructions, giving c...

A test of alternative estimators for volume at time 1 from remeasured point samples

Science.gov (United States)

Francis A. Roesch; Edwin J. Green; Charles T. Scott

1993-01-01

Two estimators for volume at time 1 for use with permanent horizontal point samples are evaluated. One estimator, used traditionally, uses only the trees sampled at time 1, while the second estimator, originally presented by Roesch and coauthors (F.A. Roesch, Jr., E.J. Green, and C.T. Scott. 1989. For. Sci. 35(2):281-293). takes advantage of additional sample...

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

Science.gov (United States)

Brazil.

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

Cumulative indices for Spectrochima Acta, Part A and Spectrochimica Acta, Part B

International Nuclear Information System (INIS)

Scheeline, A.; Williams, B.; Williksen, E.; Jeffrey Steinfeld,; McEnroe, B.

1998-01-01

This article is an electronic publication in Spectrochimica Acta Electronica (SAE), a section of Spectrochimica Acta, Part B (SAB). The hardcopy text is accompanied by an electronic archive, stored on the SAE homepage at http://www.elsevier.nl/locate/sabe. The archive contains data, index and program files. The main article discusses the bibliographical purpose of the program and data files. A collective index for Spectrochimica Acta for volumes since it was split into Parts A and B, and continuing through 1991 for SAA and 1997 for SAB, is presented in DBF format, along with rudimentary data entry and access software. (Copyright (c) 1998 Elsevier Science B.V., Amsterdam. All rights reserved.)

12 CFR 557.1 - What does this part do?

Science.gov (United States)

2010-01-01

... 12 Banks and Banking 5 2010-01-01 2010-01-01 false What does this part do? 557.1 Section 557.1 Banks and Banking OFFICE OF THRIFT SUPERVISION, DEPARTMENT OF THE TREASURY DEPOSITS General § 557.1 What does this part do? This part applies to the deposit activities of savings associations. If you are a...

Update on rheumatology: part 1.

Science.gov (United States)

Neal-Boylan, Leslie

2009-05-01

There are many rheumatic diseases. Part 1 of this 2 part series on rheumatology presented a few of those most commonly seen in the community. Home health clinicians can be helpful in managing these diseases and preventing progression by watching for new symptoms or acute attacks of pain or disability, ensuring that patients take their medications appropriately, reminding patients to see their rheumatology providers and have their lab work done regularly, and reporting adverse effects to medications promptly. Additionally, as with most home health patients, an interdisciplinary approach that includes physical and occupational therapy, social work, nursing, nutrition, and other disciplines as needed should be implemented so that all patient needs are met and the patient is discharged at the highest level of self-care that is possible. Part 2 of this series will discuss the care of the patient with rheumatic disease at home and will provide a more in-depth look at lab diagnosis of rheumatic diseases.

Potential impacts of OCS oil and gas activities on fisheries. Volume 1. Annotated bibliography and database descriptions for target species distribution and abundance studies. Section 1, Part 1. Final report

International Nuclear Information System (INIS)

Tear, L.M.

1989-10-01

The purpose of the volume is to present an annotated bibliography of unpublished and grey literature related to the distribution and abundance of select species of finfish and shellfish along the coasts of the United States. The volume also includes descriptions of databases that contain information related to target species' distribution and abundance. An index is provided at the end of each section to help the reader locate studies or databases related to a particular species

Environmental contaminants in food. Volume II-Part B: Working papers

International Nuclear Information System (INIS)

1980-01-01

This volume contains working papers written for Office of Technology Assessment (OTA) to assist in preparation of the report Environmental Contaminants in Food. The contents include: (1) Toxic substances in food information systems: design and management; (2) Assessment of carcinogenic risks from PCBs in food; (3) Economic analysis of alternative action levels in the regulation of environmental contaminants in food; (4) Analysis of foods for radioactivity; (5) Approaches to monitoring environmental contaminants in food; (6) Analytical systems for the determination of metals in food and water supplies; (7) Assessment of methods for regulating 'unavoidable' contaminants in the food supply; and (8) Consumer risk from environmental contaminants in food

Advanced complex analysis a comprehensive course in analysis, part 2b

CERN Document Server

Simon, Barry

2015-01-01

A Comprehensive Course in Analysis by Poincaré Prize winner Barry Simon is a five-volume set that can serve as a graduate-level analysis textbook with a lot of additional bonus information, including hundreds of problems and numerous notes that extend the text and provide important historical background. Depth and breadth of exposition make this set a valuable reference source for almost all areas of classical analysis. Part 2B provides a comprehensive look at a number of subjects of complex analysis not included in Part 2A. Presented in this volume are the theory of conformal metrics (includ

Progress in passive solar energy systems. Volume 8. Part 1

Energy Technology Data Exchange (ETDEWEB)

Hayes, J.; Andrejko, D.A.

1983-01-01

This book presents the papers given at a conference sponsored by the US DOE, the Solar Energy Research Institute, SolarVision, Inc., and the Southern California Solar Energy Society. The topics considered at the conference included sizing solar energy systems for agricultural applications, a farm scale ethanol production plant, the EEC wind energy RandD program, the passive solar performance assessment of an earth-sheltered house, the ARCO 1 MW photovoltaic power plant, the performance of a dendritic web photovoltaic module, second generation point focused concentrators, linear fresnel lens concentrating photovoltaic collectors, photovoltaic conversion efficiency, amorphous silicon thin film solar cells, a photovoltaic system for a shopping center, photovoltaic power generation for the utility industry, spectral solar radiation, and the analysis of insolation data.

Human genome program report. Part 1, overview and progress

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-11-01

This report contains Part 1 of a two-part report to reflect research and progress in the U.S. Department of Energy Human Genome Program from 1994 through 1996, with specified updates made just before publication. Part 1 consists of the program overview and report on progress.

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

KAUST Repository

Matson, Samira M.; Rä tzke, Klaus; Shaikh, Muhammad Qasim; Litvinova, Elena G.; Shishatskiy, Sergey M.; Peinemann, Klaus-Viktor; Khotimskiy, Valeriy S.

2012-01-01

The relationship between poly(1-trimethylsilyl-1-propyne) (PTMSP) and poly(1-trimethylger- myl-1-propyne) (PTMGP) microstructure, gas permeability and structure of free volume is reported. n-Butane/methane mixed-gas permeation properties of PTMSP

Three-body unitarity in the finite volume

Energy Technology Data Exchange (ETDEWEB)

Mai, M. [The George Washington University, Washington, DC (United States); Doering, M. [The George Washington University, Washington, DC (United States); Thomas Jefferson National Accelerator Facility, Newport News, VA (United States)

2017-12-15

The physical interpretation of lattice QCD simulations, performed in a small volume, requires an extrapolation to the infinite volume. A method is proposed to perform such an extrapolation for three interacting particles at energies above threshold. For this, a recently formulated relativistic 3 → 3 amplitude based on the isobar formulation is adapted to the finite volume. The guiding principle is two- and three-body unitarity that imposes the imaginary parts of the amplitude in the infinite volume. In turn, these imaginary parts dictate the leading power-law finite-volume effects. It is demonstrated that finite-volume poles arising from the singular interaction, from the external two-body sub-amplitudes, and from the disconnected topology cancel exactly leaving only the genuine three-body eigenvalues. The corresponding quantization condition is derived for the case of three identical scalar-isoscalar particles and its numerical implementation is demonstrated. (orig.)

Essays on the History of Rocketry and Astronautics: Proceedings of the Third through the Sixth History Symposia of the International Academy of Astronautics, volume 1

Science.gov (United States)

Hall, R. C. (Editor)

1977-01-01

This two volume publication presents the proceedings of the third through sixth history symposia of the International Academy of Astronautics. Thirty-nine papers are divided into four categories: (1) Early Solid Propellant Rocketry; (2) Rocketry and Astronautics: Concepts, Theory, and Analyses after 1880; (3) The Development of Liquid and Solid Propellant Rockets from 1880 to 1945; and (4) Rocketry and Astronautics after 1945. Categories 1 and 2 will be found in volume 1 and the remainder in volume 2. Among other diciplines, Rocketry and Astronautics encompasses the physical and engineering sciences including fluid mechanics, thermodynamics, vibration theory, structural mechanics, and celestial mechanics. Papers presented in these two volumes range from those of empirical experimenters who used the time-honored cut and try methods to scientists wielding theoretical principles. The work traces the coupling of the physical and engineering sciences, industrial advances, and state support that produced the awesome progress in rocketry and astronautics for the most part within living memory. The proceedings of the four symposia present in these two volumes contain information on the work of leading investigators and their associates carried out in the first two-thirds of the twentieth century.

Water Resources Data Ohio: Water year 1994. Volume 1, Ohio River Basin excluding Project Data

Energy Technology Data Exchange (ETDEWEB)

NONE

1994-12-31

The Water Resources Division of the US Geological Survey (USGS) in cooperation with State agencies, obtains a large amount of data each water year (a water year is the 12-month period from October 1 through September 30 and is identified by the calendar year in which it ends) pertaining to the water resources of Ohio. These data, accumulated during many years, constitute a valuable data base for developing an improved understanding of the water resources of the State. To make these data readily available to interested parties outside the USGS, they are published annually in this report series entitled ``Water Resources Data--Ohio.`` This report (in two volumes) includes records on surface water and ground water in the State. Specifically, it contains: (1) Discharge records for streamflow-gaging stations, miscellaneous sites, and crest-stage stations; (2) stage and content records for streams, lakes, and reservoirs; (3) water-quality data for streamflow-gaging stations, wells, synoptic sites, and partial-record sit -aid (4) water-level data for observation wells. Locations of lake-and streamflow-gaging stations, water-quality stations, and observation wells for which data are presented in this volume are shown in figures 8a through 8b. The data in this report represent that part of the National Water Data System collected by the USGS and cooperating State and Federal agencies in Ohio. This series of annual reports for Ohio began with the 1961 water year with a report that contained only data relating to the quantities of surface water. For the 1964 water year, a similar report was introduced that contained only data relating to water quality. Beginning with the 1975 water year, the report was changed to present (in two or three volumes) data on quantities of surface water, quality of surface and ground water, and ground-water levels.

Digital dental photography. Part 1: an overview.

Science.gov (United States)

Ahmad, I

2009-04-25

This paper is the first article in a new ten-part series on digital dental photography. Part 1 previews and outlines the contents of the subsequent papers and in addition, defines the aims and objectives of a digital dental image and the features that are required for an ideal intra-oral picture.

American Academic: A National Survey of Part-time/Adjunct Faculty. Volume 2

Science.gov (United States)

American Federation of Teachers (NJ), 2010

2010-01-01

Plainly, part-time/adjunct faculty members now play a vital role in educating the nation's college students. Even so, the data and research on part-time/adjunct faculty members have tended to be pretty spotty. This survey, conducted by Hart Research Associates on behalf of the American Federation of Teachers, is one of the first nationwide…

A NEW RECIPE FOR OBTAINING CENTRAL VOLUME DENSITIES OF PRESTELLAR CORES FROM SIZE MEASUREMENTS

International Nuclear Information System (INIS)

Tassis, Konstantinos; Yorke, Harold W.

2011-01-01

We propose a simple analytical method for estimating the central volume density of prestellar molecular cloud cores from their column density profiles. Prestellar cores feature a flat central part of the column density and volume density profiles of the same size indicating the existence of a uniform-density inner region. The size of this region is set by the thermal pressure force which depends only on the central volume density and temperature of the core, and can provide a direct measurement of the central volume density. Thus, a simple length measurement can immediately yield a central density estimate independent of any dynamical model for the core and without the need for fitting. Using the radius at which the column density is 90% of the central value as an estimate of the size of the flat inner part of the column density profile yields an estimate of the central volume density within a factor of two for well-resolved cores.

Proceedings of the seventh symposium on containment of underground nuclear explosions. Volume 1

Energy Technology Data Exchange (ETDEWEB)

Olsen, C.W. [ed.

1993-12-31

This is Volume 1 of two unclassified volumes of a meeting of workers at all levels in the science and technology of containment. Papers on containment and related geological, geophysical, engineering, chemical, and computational topics were included. Particular topics included in this volume are: General containment,tunnel and LOS topics, cavity conditions, and LYNER and chemical kiloton. Individual papers are indexed separately on the data base.

Nuclear medicine. 1 part. Manual

International Nuclear Information System (INIS)

Shlygina, O.E.; Borisenko, A.R.

2006-01-01

Current manual is urged to give wide-scale readers a submission on a key principles and methods of nuclear medicine, and it opportunities and restrictions in diagnostics and treatment of different diseases. Nuclear medicine is differing first of all by combination of diverse knowledge fields: special knowledge of a doctor, knowledge of physical processes bases, related with radiation, grounds of radiopharmaceutics, dosimetry. In the base of the book the 5th edition of 'Nuclear medicine' manual in 2 parts of German authors - Schicha, G.; Schober, O. is applied. In the book publishing the stuff of the Institute of Nuclear Physics of the National Nuclear Center of Republic of Kazakhstan has been worked. Modifications undergo practically all chapters: especially the second one, forth and sixth was enlarged. The 1 part of the book was published due to support of IAEA within the Technical cooperation project 'Implementation of Nuclear Medicine and Biophysics Center' (KAZ/6/007). The manual second part - devoted to applications of nuclear medicine methods for diagnostics and treatment - will be published in 2007

31 CFR 30.1 - Q-1: What definitions apply in this part?

Science.gov (United States)

2010-07-01

... 31 Money and Finance: Treasury 1 2010-07-01 2010-07-01 false Q-1: What definitions apply in this part? 30.1 Section 30.1 Money and Finance: Treasury Office of the Secretary of the Treasury TARP STANDARDS FOR COMPENSATION AND CORPORATE GOVERNANCE § 30.1 Q-1: What definitions apply in this part...

A Simple Measure to Assess Hyperinflation and Air Trapping: 1-Forced Expiratory Volume in Three Second / Forced Vital Capacity

Directory of Open Access Journals (Sweden)

Sermin Börekçi

2017-04-01

Full Text Available Background: Several recent studies have suggested that 1 minus-forced expiratory volume expired in 3 seconds / forced vital capacity (1-FEV3/FVC may be an indicator of distal airway obstruction and a promising measure to evaluate small airways dysfunction. Aims: To investigate the associations of 1-FEV3/FVC with the spirometric measures and lung volumes that assess small airways dysfunction and reflects hyperinflation and air trapping. Study Design: Retrospective cross-sectional study. Methods: Retrospective assessment of a total of 1110 cases who underwent body plethysmographic lung volume estimations between a time span from 2005 to 2012. Patients were assigned into two groups: firstly by FEV1/FVC (FEV1/FVC <70% vs. FEV1/FVC ≥70%; secondly by FEV3/FVC < lower limits of normal (LLN (FEV3/FVC < LLN vs. FEV3/FVC ≥ LLN. Spirometric indices and lung volumes measured by whole-body plethysmography were compared in groups. Also the correlation of spirometric indices with measured lung volumes were assessed in the whole-study population and in subgroups stratified according to FEV1/FVC and FEV3/FVC. Results: Six hundred seven (54.7% were male and 503 (45.3% were female, with a mean age of 52.5±15.6 years. Mean FEV3/FVC and 1-FEV3/FVC were 87.05%, 12.95%, respectively. The mean 1-FEV3/FVC was 4.9% in the FEV1/FVC ≥70% group (n=644 vs. 24.1% in the FEV1/FVC <70% group (n=466. A positive correlation was found between 1-FEV3/FVC and residual volume (r=0.70; p<0.0001, functional residual capacity-pleth (r=0.61; p<0.0001, and total lung capacity (r=0.47; p<0.0001. 1-FEV3/FVC was negatively correlated with forced expiratory flow25-75 (r=−0.84; p<0.0001. The upper limit of 95% confidence interval for 1-FEV3/FVC was 13.7%. 1-FEV3/FVC showed significant correlations with parameters of air trapping and hyperinflation measured by whole-body plethysmography. Importantly, these correlations were higher in study participants with FEV1/FVC <70% or FEV3/FVC

Nuclear criticality safety experiments, calculations, and analyses: 1958 to 1982. Volume 1. Lookup tables

International Nuclear Information System (INIS)

Koponen, B.L.; Hampel, V.E.

1982-01-01

This compilation contains 688 complete summaries of papers on nuclear criticality safety as presented at meetings of the American Nuclear Society (ANS). The selected papers contain criticality parameters for fissile materials derived from experiments and calculations, as well as criticality safety analyses for fissile material processing, transport, and storage. The compilation was developed as a component of the Nuclear Criticality Information System (NCIS) now under development at the Lawrence Livermore National Laboratory. The compilation is presented in two volumes: Volume 1 contains a directory to the ANS Transaction volume and page number where each summary was originally published, the author concordance, and the subject concordance derived from the keyphrases in titles. Volume 2 contains - in chronological order - the full-text summaries, reproduced here by permission of the American Nuclear Society from their Transactions, volumes 1-41

HYDRA-II: A hydrothermal analysis computer code: Volume 1, Equations and numerics

International Nuclear Information System (INIS)

McCann, R.A.

1987-04-01

HYDRA-II is a hydrothermal computer code capable of three-dimensional analysis of coupled conduction, convection, and thermal radiation problems. This code is especially appropriate for simulating the steady-state performance of spent fuel storage systems. The code has been evaluated for this application for the US Department of Energy's Commercial Spent Fuel Management Program. HYDRA-II provides a finite difference solution in Cartesian coordinates to the equations governing the conservation of mass, momentum, and energy. A cylindrical coordinate system may also be used to enclose the Cartesian coordinate system. This exterior coordinate system is useful for modeling cylindrical cask bodies. The difference equations for conservation of momentum are enhanced by the incorporation of directional porosities and permeabilities that aid in modeling solid structures whose dimensions may be smaller than the computational mesh. The equation for conservation of energy permits of modeling of orthotropic physical properties and film resistances. Several automated procedures are available to model radiation transfer within enclosures and from fuel rod to fuel rod. The documentation of HYDRA-II is presented in three separate volumes. This volume, Volume I - Equations and Numerics, describes the basic differential equations, illustrates how the difference equations are formulated, and gives the solution procedures employed. Volume II - User's Manual contains code flow charts, discusses the code structure, provides detailed instructions for preparing an input file, and illustrates the operation of the code by means of a model problem. The final volume, Volume III - Verification/Validation Assessments, presents results of numerical simulations of single- and multiassembly storage systems and comparisons with experimental data. 4 refs

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.

Petroleum supply annual 1996: Volume 1

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-06-01

The Petroleum Supply Annual (PSA) contains information on the supply and disposition of crude oil and petroleum products. The publication reflects data that were collected from the petroleum industry during 1996 through annual and monthly surveys. The PSA is divided into two volumes. This first volume contains three sections: Summary Statistics, Detailed Statistics, and Refinery Capacity; each with final annual data. The summary statistics section show 16 years of data depicting the balance between supply, disposition and ending stocks for various commodities including crude oil, motor gasoline, distillate fuel oil, residual fuel oil, jet fuel propane/propylene, and liquefied petroleum gases. The detailed statistics section provide 1996 detailed statistics on supply and disposition, refinery operations, imports and exports, stocks, and transportation of crude oil and petroleum products. The refinery capacity contain listings of refineries and associated crude oil distillation and downstream capacities by State, as of January 1, 1997, as well as summaries of corporate refinery capacities and refinery storage capacities. In addition, refinery receipts of crude oil by method of transportation for 1996 are provided. Also included are fuels consumed at refineries, and lists of shutdowns, sales, reactivations, and mergers during 1995 and 1996. 16 figs., 59 tabs.

Petroleum supply annual 1996: Volume 1

International Nuclear Information System (INIS)

1997-06-01

The Petroleum Supply Annual (PSA) contains information on the supply and disposition of crude oil and petroleum products. The publication reflects data that were collected from the petroleum industry during 1996 through annual and monthly surveys. The PSA is divided into two volumes. This first volume contains three sections: Summary Statistics, Detailed Statistics, and Refinery Capacity; each with final annual data. The summary statistics section show 16 years of data depicting the balance between supply, disposition and ending stocks for various commodities including crude oil, motor gasoline, distillate fuel oil, residual fuel oil, jet fuel propane/propylene, and liquefied petroleum gases. The detailed statistics section provide 1996 detailed statistics on supply and disposition, refinery operations, imports and exports, stocks, and transportation of crude oil and petroleum products. The refinery capacity contain listings of refineries and associated crude oil distillation and downstream capacities by State, as of January 1, 1997, as well as summaries of corporate refinery capacities and refinery storage capacities. In addition, refinery receipts of crude oil by method of transportation for 1996 are provided. Also included are fuels consumed at refineries, and lists of shutdowns, sales, reactivations, and mergers during 1995 and 1996. 16 figs., 59 tabs

Information and Communication Technologies in Africa Volume 1 ...

International Development Research Centre (IDRC) Digital Library (Canada)

Volume 1 looks at the introduction, adoption, and utilization of ICTs at the community level. In various contexts – geographical, technological, socioeconomic, cultural, and institutional – the book explores the questions of community participation. It looks at how communities in sub-Saharan Africa have reacted to the changes ...

KAPSE Interface Team (KIT) Public Report. Volume 8, Part 1

Science.gov (United States)

1989-10-01

visitors were introduced. Mike Tedd of the University of Wales represented the United Kingdom on the KIT for Sue Bond , who will be the primary...CAIS subprogram callable by APSE tools.I 2.1 Scope of the CAIS. The CAIS shall provide interfaces sufficient to support the use of APSEs for wide

Solar engineering 1995: Proceedings. Volume 1

International Nuclear Information System (INIS)

Stine, W.B.; Tanaka, Tadayoshi; Claridge, D.E.

1995-01-01

This is Volume 1 of the papers presented at the 1995 ASME/JSME/JSES International Solar Energy Conference. The topics of the papers include wind energy, heat pump performance, ground source and solar chemical heat pumps, analysis of measured building energy data, thermal storage, system modeling of buildings, evaluation of the Federal Building energy Efficiency program, sustainable projects, bioconversion, solar chemistry, solar detoxification innovative concepts and industrial applications, solar thermal power systems, DISH/engine power systems, power towers, solar thermal power advanced development, and solar thermal process heating and cooling

Journal of Air Transportation, Volume 9, No. 1. Volume 9, No. 1

Science.gov (United States)

Bowen, Brent D. (Editor)

2004-01-01

The articles in this issue include: 1) Are Four Year Universities Better than Two-Year Colleges at Preparing Students to Pass the FAA Aircraft Mechanic Certification Written Examinations? 2) Assessing Perceived Risk of Consumers in Internet Airline Reservations Services; 3) Perceptions of Communication Training Among Collegiate Flight Educators; 4) Ethics Education in University Aviation Management Programs in the U.S.: Part Three - Qualitative Analysis and Recommendations; 5) Airline Flight Operations Internships Perspectives; 6) Applying Data Mining Techniques to Forecast Number of Airline Passengers in Saudi Arabia (Domestic and International Travels).

Helical post stellarator. Part 1: Vacuum configuration

International Nuclear Information System (INIS)

Moroz, P.E.

1997-08-01

Results on a novel type of stellarator configuration, the Helical Post Stellarator (HPS), are presented. This configuration is different significantly from all previously known stellarators due to its unique geometrical characteristics and unique physical properties. Among those are: the magnetic field has only one toroidal period (M = 1), the plasma has an extremely low aspect ratio, A ∼ 1, and the variation of the magnetic field, B, along field lines features a helical ripple on the inside of the torus. Among the main advantages of a HPS for a fusion program are extremely compact, modular, and simple design compatible with significant rotational transform, large plasma volume, and improved particle transport characteristics

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

International Nuclear Information System (INIS)

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

1985-04-01

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

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

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

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.

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

International Nuclear Information System (INIS)

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

1995-10-01

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

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

Energy Technology Data Exchange (ETDEWEB)

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

1995-10-01

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

Compilation of reports of the Advisory Committee on Reactor Safeguards, 1957-1984. Volume 5. Generic Subjects H-R

International Nuclear Information System (INIS)

1985-04-01

This six-volume compilation contains over 1000 reports prepared by the Advisory Committee on Reactor Safeguards from September 1957 through December 1984. The reports are divided into two groups: Part 1: ACRS Reports on Project Reviews, and Part 2: ACRS Reports on Generic Subjects. Part 1 contains ACRS reports alphabetized by project name and within project name by chronological order. Part 2 categorizes the reports by the most appropriate generic subject area and within subject area by chronological order. This volume presents generic subjects arranged alphabetically from H to R

Compilation of reports of the Advisory Committee on Reactor Safeguards, 1957-1984. Volume 3. Project Reviews Q-Z

International Nuclear Information System (INIS)

1985-04-01

This six-volume compilation contains over 1000 reports prepared by the Advisory Committee on Reactor Safeguards from September 1957 through December 1984. The reports are divided into two groups: Part 1: ACRS Resports on Project Reviews, and Part 2: ACRS Reports on Generic Subjects. Part 1 contains ACRS reports alphabetized by project name and within project name by chronological order. Part 2 categorizes the reports by the most appropriate generic subject area and within subject area by chronological order. This volume includes reports arranged alpbabetically from Q to Z

Volume Decomposition and Feature Recognition for Hexahedral Mesh Generation

Energy Technology Data Exchange (ETDEWEB)

GADH,RAJIT; LU,YONG; TAUTGES,TIMOTHY J.

1999-09-27

Considerable progress has been made on automatic hexahedral mesh generation in recent years. Several automatic meshing algorithms have proven to be very reliable on certain classes of geometry. While it is always worth pursuing general algorithms viable on more general geometry, a combination of the well-established algorithms is ready to take on classes of complicated geometry. By partitioning the entire geometry into meshable pieces matched with appropriate meshing algorithm the original geometry becomes meshable and may achieve better mesh quality. Each meshable portion is recognized as a meshing feature. This paper, which is a part of the feature based meshing methodology, presents the work on shape recognition and volume decomposition to automatically decompose a CAD model into meshable volumes. There are four phases in this approach: (1) Feature Determination to extinct decomposition features, (2) Cutting Surfaces Generation to form the ''tailored'' cutting surfaces, (3) Body Decomposition to get the imprinted volumes; and (4) Meshing Algorithm Assignment to match volumes decomposed with appropriate meshing algorithms. The feature determination procedure is based on the CLoop feature recognition algorithm that is extended to be more general. Results are demonstrated over several parts with complicated topology and geometry.

Karoo biome: a preliminary sythesis. Part 1 - physical environment

CSIR Research Space (South Africa)

Cowling, RM

1986-01-01

Full Text Available . It is a multi-authored publication covering a wide range of topics. This first volume summarizes what is currently known on the physical environment of the biome; namely geology, soils, climate, hydrology, geohydrology and soil erosion. Other aspects...

Phase-ambiguity resolution for QPSK modulation systems. Part 1: A review

Science.gov (United States)

Nguyen, Tien Manh

1989-01-01

Part 1 reviews the current phase-ambiguity resolution techniques for QPSK coherent modulation systems. Here, those known and published methods of resolving phase ambiguity for QPSK with and without Forward-Error-Correcting (FEC) are discussed. The necessary background is provided for a complete understanding of the second part where a new technique will be discussed. An appropriate technique to the Consultative Committee for Space Data Systems (CCSDS) is recommended for consideration in future standards on phase-ambiguity resolution for QPSK coherent modulation systems.

Mechanical Behaviour of Materials Volume 1 Micro- and Macroscopic Constitutive Behaviour

CERN Document Server

François, Dominique; Zaoui, André

2012-01-01

Advances in technology are demanding ever-increasing mastery over the materials being used: the challenge is to gain a better understanding of their behaviour, and more particularly of the relations between their microstructure and their macroscopic properties.   This work, of which this is the first volume, aims to provide the means by which this challenge may be met. Starting from the mechanics of deformation, it develops the laws governing macroscopic behaviour – expressed as the constitutive equations – always taking account of the physical phenomena which underlie rheological behaviour. The most recent developments are presented, in particular those concerning heterogeneous materials such as metallic alloys, polymers and composites. Each chapter is devoted to one of the major classes of material behaviour.   As the subtitles indicate, Volume 1 deals with micro- and macroscopic constitutive behaviour and Volume 2 with damage and fracture mechanics. A third volume will be devoted to exercises and the...

Geoscience data base handbook for modeling a nuclear waste repository. Volume 1

International Nuclear Information System (INIS)

Isherwood, D.

1979-12-01

This handbook contains reference information on parameters that should be considered in analyzing or modeling a proposed nuclear waste repository site. Only those parameters and values that best represent the natural environment are included. Rare extremes are avoided. Where laboratory and field data are inadequate, theoretical treatments and informed engineering judgements are presented. Volume 1 contains a data base on salt as a repository medium. Chapters on the geology of bedded and dome salt, the geomechanics of salt, hydrology, geochemistry, natural and man-made features, and seismology provide compiled data and related information useful for studying a proposed repository in salt. These and other data will be needed to derive generic deep geologic modeling parameters and will also serve as background for the verification of source data that may be presented in licensing applications for nuclear waste repositories. Volume 2 is the result of a scoping study for a data base on the geology, geomechanics, and hydrology of shale, granite, and basalt as alternative repository media. Except for the geomechanics of shale, most of the sections contain relatively complete compilations of the available data, as well as discussions of the properties that are unique to each rock type

Computer program for calculation of complex chemical equilibrium compositions and applications. Part 1: Analysis

Science.gov (United States)

Gordon, Sanford; Mcbride, Bonnie J.

1994-01-01

This report presents the latest in a number of versions of chemical equilibrium and applications programs developed at the NASA Lewis Research Center over more than 40 years. These programs have changed over the years to include additional features and improved calculation techniques and to take advantage of constantly improving computer capabilities. The minimization-of-free-energy approach to chemical equilibrium calculations has been used in all versions of the program since 1967. The two principal purposes of this report are presented in two parts. The first purpose, which is accomplished here in part 1, is to present in detail a number of topics of general interest in complex equilibrium calculations. These topics include mathematical analyses and techniques for obtaining chemical equilibrium; formulas for obtaining thermodynamic and transport mixture properties and thermodynamic derivatives; criteria for inclusion of condensed phases; calculations at a triple point; inclusion of ionized species; and various applications, such as constant-pressure or constant-volume combustion, rocket performance based on either a finite- or infinite-chamber-area model, shock wave calculations, and Chapman-Jouguet detonations. The second purpose of this report, to facilitate the use of the computer code, is accomplished in part 2, entitled 'Users Manual and Program Description'. Various aspects of the computer code are discussed, and a number of examples are given to illustrate its versatility.

Development of modelling and forecasting in geology. (Volume 1)

International Nuclear Information System (INIS)

Afzali, H.; Fourniguet, J.; Peaudecerf, P.

1990-01-01

To assess the long-term safety of radioactive waste disposal systems, validation of predictive models is essential and large efforts should be given to barriers, particularly geologic barriers. This work appears in the form of four volumes, the subject of the first part is described below. Soils and rocks erosion depends upon climate, relief, lithology and human activities (deforesting). In the world, mechanical erosion is evaluated from 5 to 8 cm per 1000 years (mean denudation ratio). Rocks weathering solubilize chemical elements in the running water and rocks fracturation becomes more easily under erosion effects. Alteration front progress is 0.3-3 cm per 1000 years in temperate zones and 4-7 cm per 1000 years in tropical zones. 5 figs., 14 tabs., 80 refs

Lung volumes during sustained microgravity on Spacelab SLS-1

Science.gov (United States)

Elliott, Ann R.; Prisk, G. Kim; Guy, Harold J. B.; West, John B.

1994-01-01

Gravity is known to influence the mechanical behavior of the lung and chest wall. However, the effect of sustained microgravity (microgravity) on lung volumes has not been reported. Pulmonary function tests were performed by four subjects before, during, and after 9 days of microgravity exposure. Ground measurements were made in standing and supine postures. Tests were performed using a bag-in-box-and-flowmeter system and a respiratory mass spectrometer. Measurements included functional residual capacity (FRC), expiratory reserve volume (ERV), residual volume (RV), inspiratory and expiratory vital capacities (IVC and EVC), and tidal volume (V9sub T)). Total lung capacity (TLC) was derived from the measured EVC and RV values. With preflight standing values as a comparison, FRC was significantly reduced by 15% (approximately 500 ml) in microgravity and 32% in the supine posture. ERV was reduced by 10 - 20% in microgravity and decreased by 64% in the supine posture. RV was significantly reduced by 18% (310 ml) in microgravity but did not significantly change in the supine posture compared with standing. IVC and EVC were slightly reduced during the first 24 h of microgravity but returned to 1-G standing values within 72 h of microgravity exposure. IVC and EVC in the supine posture were significantly reduced by 12% compared with standing. During microgravity, V(sub T) decreased by 15% (approximately 90 ml), but supine V(sub T) was unchanged compared with preflight standing values. TLC decreased by approximately 8% during microgravity and in the supine posture compared with preflight standing. The reductions in FRC, ERV, and RV during microgravity are probably due to the cranial shift of the diaphragm, an increase in intrathoracic blood volume, and more uniform alveolar expansion.

Calculus: A Computer Oriented Presentation, Part 1 [and] Part 2.

Science.gov (United States)

Stenberg, Warren; Walker, Robert J.

Parts one and two of a one-year computer-oriented calculus course (without analytic geometry) are presented. The ideas of calculus are introduced and motivated through computer (i.e., algorithmic) concepts. An introduction to computing via algorithms and a simple flow chart language allows the book to be self-contained, except that material on…

Variant of a volume-of-fluid method for surface tension-dominant two ...

Indian Academy of Sciences (India)

2013-12-27

Dec 27, 2013 ... face tension-dominant two-phase flows are explained. ... for one particular fluid inside a cell as its material volume divided by the total ... the reconstructed interface and the velocity field, and the final part ..... Welch S W J and Wilson J 2000 A volume of fluid based method for fluid flows with phase change. J.

SCALE: A modular code system for performing standardized computer analyses for licensing evaluation. Functional modules F9--F16 -- Volume 2, Part 2, Revision 4

Energy Technology Data Exchange (ETDEWEB)

West, J.T.; Hoffman, T.J.; Emmett, M.B.; Childs, K.W.; Petrie, L.M.; Landers, N.F.; Bryan, C.B.; Giles, G.E. [Oak Ridge National Lab., TN (United States)

1995-04-01

SCALE--a modular code system for Standardized Computer Analyses Licensing Evaluation--has been developed by Oak Ridge National Laboratory at the request of the US Nuclear Regulatory Commission. The SCALE system utilizes well-established computer codes and methods within standard analysis sequences that (1) allow an input format designed for the occasional user and/or novice, (2) automate the data processing and coupling between modules, and (3) provide accurate and reliable results. System development has been directed at problem-dependent cross-section processing and analysis of criticality safety, shielding, heat transfer, and depletion/decay problems. Since the initial release of SCALE in 1980, the code system has been heavily used for evaluation of nuclear fuel facility and package designs. This revision documents Version 4.2 of the system. The manual is divided into three volumes: Volume 1--for the control module documentation, Volume 2--for functional module documentation; and Volume 3--for documentation of the data libraries and subroutine libraries. This volume discusses the following functional modules: MORSE-SGC; HEATING 7.2; KENO V.a; JUNEBUG-II; HEATPLOT-S; REGPLOT 6; PLORIGEN; and OCULAR.

SCALE: A modular code system for performing standardized computer analyses for licensing evaluation. Functional modules F9--F16 -- Volume 2, Part 2, Revision 4

International Nuclear Information System (INIS)

West, J.T.; Hoffman, T.J.; Emmett, M.B.; Childs, K.W.; Petrie, L.M.; Landers, N.F.; Bryan, C.B.; Giles, G.E.

1995-04-01

SCALE--a modular code system for Standardized Computer Analyses Licensing Evaluation--has been developed by Oak Ridge National Laboratory at the request of the US Nuclear Regulatory Commission. The SCALE system utilizes well-established computer codes and methods within standard analysis sequences that (1) allow an input format designed for the occasional user and/or novice, (2) automate the data processing and coupling between modules, and (3) provide accurate and reliable results. System development has been directed at problem-dependent cross-section processing and analysis of criticality safety, shielding, heat transfer, and depletion/decay problems. Since the initial release of SCALE in 1980, the code system has been heavily used for evaluation of nuclear fuel facility and package designs. This revision documents Version 4.2 of the system. The manual is divided into three volumes: Volume 1--for the control module documentation, Volume 2--for functional module documentation; and Volume 3--for documentation of the data libraries and subroutine libraries. This volume discusses the following functional modules: MORSE-SGC; HEATING 7.2; KENO V.a; JUNEBUG-II; HEATPLOT-S; REGPLOT 6; PLORIGEN; and OCULAR

C2H4ArF2 1,2-Difluoroethane - argon (1/1)

Science.gov (United States)

Demaison, J.

This document is part of Part 1 of Subvolume D 'Asymmetric Top Molecules' of Volume 29 'Molecular Constants Mostly from Microwave, Molecular Beam, and Sub-Doppler Laser Spectroscopy' of Landolt-Börnstein - Group II 'Molecules and Radicals'.

Statistical evaluations concerning the failure behaviour of formed parts with superheated steam flow. Pt. 1

International Nuclear Information System (INIS)

Oude-Hengel, H.H.; Vorwerk, K.; Heuser, F.W.; Boesebeck, K.

1976-01-01

Statistical evaluations concerning the failure behaviour of formed parts with superheated-steam flow were carried out using data from VdTUEV inventory and failure statistics. Due to the great number of results, the findings will be published in two volumes. This first part will describe and classify the stock of data and will make preliminary quantitative statements on failure behaviour. More differentiated statements are made possible by including the operation time and the number of start-ups per failed part. On the basis of time-constant failure rates some materials-specific statements are given. (orig./ORU) [de

Small-Volume Injections: Evaluation of Volume Administration Deviation From Intended Injection Volumes.

Science.gov (United States)

Muffly, Matthew K; Chen, Michael I; Claure, Rebecca E; Drover, David R; Efron, Bradley; Fitch, William L; Hammer, Gregory B

2017-10-01

In the perioperative period, anesthesiologists and postanesthesia care unit (PACU) nurses routinely prepare and administer small-volume IV injections, yet the accuracy of delivered medication volumes in this setting has not been described. In this ex vivo study, we sought to characterize the degree to which small-volume injections (≤0.5 mL) deviated from the intended injection volumes among a group of pediatric anesthesiologists and pediatric postanesthesia care unit (PACU) nurses. We hypothesized that as the intended injection volumes decreased, the deviation from those intended injection volumes would increase. Ten attending pediatric anesthesiologists and 10 pediatric PACU nurses each performed a series of 10 injections into a simulated patient IV setup. Practitioners used separate 1-mL tuberculin syringes with removable 18-gauge needles (Becton-Dickinson & Company, Franklin Lakes, NJ) to aspirate 5 different volumes (0.025, 0.05, 0.1, 0.25, and 0.5 mL) of 0.25 mM Lucifer Yellow (LY) fluorescent dye constituted in saline (Sigma Aldrich, St. Louis, MO) from a rubber-stoppered vial. Each participant then injected the specified volume of LY fluorescent dye via a 3-way stopcock into IV tubing with free-flowing 0.9% sodium chloride (10 mL/min). The injected volume of LY fluorescent dye and 0.9% sodium chloride then drained into a collection vial for laboratory analysis. Microplate fluorescence wavelength detection (Infinite M1000; Tecan, Mannedorf, Switzerland) was used to measure the fluorescence of the collected fluid. Administered injection volumes were calculated based on the fluorescence of the collected fluid using a calibration curve of known LY volumes and associated fluorescence.To determine whether deviation of the administered volumes from the intended injection volumes increased at lower injection volumes, we compared the proportional injection volume error (loge [administered volume/intended volume]) for each of the 5 injection volumes using a linear

Increased CSF-BACE1 activity associated with decreased hippocampus volume in Alzheimer's disease.

LENUS (Irish Health Repository)

Ewers, Michael

2012-02-01

The enzyme beta-secretase (BACE1) is essentially involved in the production of cerebral amyloidogenic pathology in Alzheimer\\'s disease (AD). The measurement of BACE1 activity in cerebrospinal fluid (CSF) has been reported, which may render CSF measurement of BACE1 a potential biomarker candidate of AD. In order to investigate whether BACE1 protein activity is correlated with regional brain atrophy in AD, we investigated the association between CSF levels of BACE1 and MRI-assessed hippocampus volume in patients with AD (n = 30). An increase in CSF-BACE1 activity was associated with decreased left and right hippocampus volume corrected for global head volume in the AD patients. Boot-strapped regression analysis showed that increased CSF levels of BACE1 activity were associated with increased CSF concentration of total tau but not amyloid-beta1-42 in AD. White matter hyperintensities did not influence the results. BACE1 activity and protein levels were significantly increased in AD compared to 19 elderly healthy controls. Thus, the CSF biomarker candidate of BACE1 activity was associated with hippocampus atrophy in AD in a robust manner and may reflect neurotoxic amyloid-beta-related processes.

Environmental epidemiology, Volume 1: Public health and hazardous wastes

International Nuclear Information System (INIS)

Anon.

1991-01-01

Environmental Epidemiology, Volume 1, represents the first of several planned volumes on the uses of epidemiologic techniques to study environmental public health issues. This text focuses on environmental epidemiology as it relates to hazardous waste in the United States. This study was commissioned by the Agency for Toxic Substances and Disease Registry to examine available data for evidence of adverse health effects on human populations exposed to hazardous waste. The committee was also asked to identify data gaps which were impediments to analyzing hazardous waste health effects and to suggest ways that such environmental health assessments might be improved. The committee's solution to the paucity of data on this issue was to concentrate in this volume on identifying the available, peer-reviewed data and, consequently, the major data gaps. The study opens with a recapitulation of the context of hazardous waste sites in the United States, the approaches currently used by state and federal epidemiologists in analyzing hazardous waste exposure and effects, and candid assessment of the problems associated with environmental exposure assessment. From that context, the committee then presents the data currently available to assess human exposures through air, domestic water consumption, soil, and the food chain. The general focus here is on biomarker data as the date of choice. As with all NAS reports, this one closes with general conclusions and recommendations. Environmental health risk assessors will find this volume a valuable resource

Redefining the Boundaries of Language Study. Issues in Language Program Direction: A Series of Annual Volumes.

Science.gov (United States)

Kramsch, Claire, Ed.

The papers in this volume fall into five categories. After "Introduction: Making the Invisible Visible" (Claire Kramsch), Part 1, "Theoretical Boundaries," includes "The Metamorphosis of the Foreign Language Director, or: Waking Up to Theory" (Mark Webber) and "Subjects-in-Process: Revisioning TA Development…

Resource Conservation and Recovery Act, Part B permit application [for the Waste Isolation Pilot Plant (WIPP)]. Volume 1, Revision 3

Energy Technology Data Exchange (ETDEWEB)

1993-03-01

This volume includes the following chapters: Waste Isolation Pilot Plant RCRA A permit application; facility description; waste analysis plan; groundwater monitoring; procedures to prevent hazards; RCRA contingency plan; personnel training; corrective action for solid waste management units; and other Federal laws.

Oak Ridge K-25 Site Technology Logic Diagram. Volume 3, Technology evaluation data sheets; Part B, Remedial action, robotics/automation, waste management

Energy Technology Data Exchange (ETDEWEB)

Fellows, R.L. [ed.

1993-02-26

The Oak Ridge K-25 Technology Logic Diagram (TLD), a decision support tool for the K-25 Site, was developed to provide a planning document that relates environmental restoration (ER) and waste management (WN) problems at the Oak Ridge K-25 Site. The TLD technique identifies the research necessary to develop these technologies to a state that allows for technology transfer and application to waste management, remediation, decontamination, and decommissioning activities. The TLD consists of four separate volumes-Vol. 1, Vol. 2, Vol. 3A, and Vol. 3B. Volume 1 provides introductory and overview information about the TLD. Volume 2 contains logic diagrams. Volume 3 has been divided into two separate volumes to facilitate handling and use. This volume 3 B provides the Technology Evaluation Data Sheets (TEDS) for ER/WM activities (Remedial Action Robotics and Automation, Waste Management) that are referenced by a TEDS code number in Vol. 2 of the TLD. Each of these sheets represents a single logic trace across the TLD. These sheets contain more detail than each technology in Vol. 2. The TEDS are arranged alphanumerically by the TEDS code number in the upper right corner of each data sheet. Volume 3 can be used in two ways: (1) technologies that are identified from Vol. 2 can be referenced directly in Vol. 3 by using the TEDS codes, and (2) technologies and general technology areas (alternatives) can be located in the index in the front of this volume.

The Aalborg Survey / Part 1 - Web Based Survey

DEFF Research Database (Denmark)

Harder, Henrik; Christensen, Cecilie Breinholm

Background and purpose The Aalborg Survey consists of four independent parts: a web, GPS and an interview based survey and a literature study, which together form a consistent investigation and research into use of urban space, and specifically into young people’s use of urban space: what young......) and the research focus within the cluster of Mobility and Tracking Technologies (MoTT), AAU. Summary / Part 1 Web Base Survey The 1st part of the research project Diverse Urban Spaces (DUS) has been carried out during the period from December 1st 2007 to February 1st 2008 as a Web Based Survey of the 27.040 gross...... [statistikbanken.dk, a] young people aged 14-23 living in Aalborg Municipality in 2008. The web based questionnaire has been distributed among the group of young people studying at upper secondary schools in Aalborg, i.e. 7.680 young people [statistikbanken.dk, b]. The resulting data from those respondents who...

Influence of bladder and rectal volume on spatial variability of a bladder tumor during radical radiotherapy

International Nuclear Information System (INIS)

Pos, Floris J.; Koedooder, Kees; Hulshof, Maarten C.C.M.; Tienhoven, Geertjan van; Gonzalez Gonzalez, Dionisio

2003-01-01

Purpose: To assess the spatial variability of a bladder tumor relative to the planning target volume boundaries during radical radiotherapy, and furthermore to develop strategies to reduce spatial variability. Methods and Materials: Seventeen patients with solitary T2-T4N0M0 bladder cancer were treated with a technique delivering 40 Gy/2 Gy in 20 fractions to the whole bladder with a concomitant boost to the bladder tumor of 20 Gy in 1 Gy fractions in an overall time of 4 weeks. CT scans were made weekly, immediately after treatment, and matched with the planning CT scan. Spatial variability of the tumor, as well as bladder volume and rectal diameter, were scored for each patient each week. Results: In 65% of patients, a part of the tumor appeared outside the planning target volume boundaries at least one time during the course of radiotherapy. No consistent relation of this variability with time was found. Bladder volumes and rectal diameters showed marked variability during the course of treatment. A large initial bladder volume and rectal diameter predicted a large volume variation and a large tumor spatial variability. Conclusion: In this study, a margin of 1.5 to 2 cm seemed to be inadequate in 65% of the patients with respect to spatial variability. Bladder volume and rectal diameter were found to be predictive for spatial variability of a bladder tumor during concomitant boost radiotherapy

Influence of bladder and rectal volume on spatial variability of a bladder tumor during radical radiotherapy

Energy Technology Data Exchange (ETDEWEB)

Pos, Floris J; Koedooder, Kees; Hulshof, Maarten C.C.M.; Tienhoven, Geertjan van; Gonzalez Gonzalez, Dionisio

2003-03-01

Purpose: To assess the spatial variability of a bladder tumor relative to the planning target volume boundaries during radical radiotherapy, and furthermore to develop strategies to reduce spatial variability. Methods and Materials: Seventeen patients with solitary T2-T4N0M0 bladder cancer were treated with a technique delivering 40 Gy/2 Gy in 20 fractions to the whole bladder with a concomitant boost to the bladder tumor of 20 Gy in 1 Gy fractions in an overall time of 4 weeks. CT scans were made weekly, immediately after treatment, and matched with the planning CT scan. Spatial variability of the tumor, as well as bladder volume and rectal diameter, were scored for each patient each week. Results: In 65% of patients, a part of the tumor appeared outside the planning target volume boundaries at least one time during the course of radiotherapy. No consistent relation of this variability with time was found. Bladder volumes and rectal diameters showed marked variability during the course of treatment. A large initial bladder volume and rectal diameter predicted a large volume variation and a large tumor spatial variability. Conclusion: In this study, a margin of 1.5 to 2 cm seemed to be inadequate in 65% of the patients with respect to spatial variability. Bladder volume and rectal diameter were found to be predictive for spatial variability of a bladder tumor during concomitant boost radiotherapy.

OCCUPATIONAL EDUCATION--PLANNING AND PROGRAMMING. VOLUME TWO.

Science.gov (United States)

KOTZ, ARNOLD

ADDITIONAL POSITION PAPERS BASED ON INFORMATION GATHERED IN THE RECONNAISSANCE SURVEYS OF PLANNING AND PROGRAMING IN OCCUPATIONAL EDUCATION, REPORTED IN VOLUME ONE (VT 005 041), ARE PRESENTED. PART IV, CONCERNED WITH PROGRAM STRUCTURE AND BUDGETING AND THEIR RELATION TO THE PLANNING PROCESS, INCLUDES THE PAPERS--(1) "CURRENT POLICIES AND…

Compilation of reports of the Advisory Committee on Reactor Safeguards, 1957-1984. Volume 6. Generic Subjects R-Z, Appendices

International Nuclear Information System (INIS)

1985-04-01

This six-volume compilation contains over 1000 reports prepared by the Advisory Committee on Reactor Safeguards from September 1957 through December 1984. The reports are divided into two groups: Part 1: ACRS Reports on Project Reviews, and Part 2: ACRS Reports on Generic Subjects. Part 1 contains ACRS reports alphabetized by project name and within project name by chronological order. Part 2 categorizes the reports by the most appropriate generic subject area and within subject area by chronological order. This volume contains the generic subjects with an alphabetical listing from R to Z

Common variants at 1p36 are associated with superior frontal gyrus volume.

Science.gov (United States)

Hashimoto, R; Ikeda, M; Yamashita, F; Ohi, K; Yamamori, H; Yasuda, Y; Fujimoto, M; Fukunaga, M; Nemoto, K; Takahashi, T; Tochigi, M; Onitsuka, T; Yamasue, H; Matsuo, K; Iidaka, T; Iwata, N; Suzuki, M; Takeda, M; Kasai, K; Ozaki, N

2014-10-21

The superior frontal gyrus (SFG), an area of the brain frequently found to have reduced gray matter in patients with schizophrenia, is involved in self-awareness and emotion, which are impaired in schizophrenia. However, no genome-wide association studies of SFG volume have investigated in patients with schizophrenia. To identify single-nucleotide polymorphisms (SNPs) associated with SFG volumes, we demonstrated a genome-wide association study (GWAS) of gray matter volumes in the right or left SFG of 158 patients with schizophrenia and 378 healthy subjects. We attempted to bioinformatically ascertain the potential effects of the top hit polymorphism on the expression levels of genes at the genome-wide region. We found associations between five variants on 1p36.12 and the right SFG volume at a widely used benchmark for genome-wide significance (P5.0 × 10(-8)); however, the rs4654899 polymorphism was identified as the locus with the second strongest association with the volume of the left SFG (P=1.5 × 10(-6)). In silico analyses revealed a proxy SNP of rs4654899 had effect on gene expression of two genes, HP1BP3 lying 3' to EIF4G3 (P=7.8 × 10(-6)) and CAPN14 at 2p (P=6.3 × 10(-6)), which are expressed in moderate-to-high levels throughout the adult human SFG. These results contribute to understand genetic architecture of a brain structure possibly linked to the pathophysiology of schizophrenia.

ABAQUS-EPGEN: a general-purpose finite element code. Volume 3. Example problems manual

International Nuclear Information System (INIS)

Hibbitt, H.D.; Karlsson, B.I.; Sorensen, E.P.

1983-03-01

This volume is the Example and Verification Problems Manual for ABAQUS/EPGEN. Companion volumes are the User's, Theory and Systems Manuals. This volume contains two major parts. The bulk of the manual (Sections 1-8) contains worked examples that are discussed in detail, while Appendix A documents a large set of basic verification cases that provide the fundamental check of the elements in the code. The examples in Sections 1-8 illustrate and verify significant aspects of the program's capability. Most of these problems provide verification, but they have also been chosen to allow discussion of modeling and analysis techniques. Appendix A contains basic verification cases. Each of these cases verifies one element in the program's library. The verification consists of applying all possible load or flux types (including thermal loading of stress elements), and all possible foundation or film/radiation conditions, and checking the resulting force and stress solutions or flux and temperature results. This manual provides program verification. All of the problems described in the manual are run and the results checked, for each release of the program, and these verification results are made available

Workplace Bullying in Healthcare: Part 1.

Science.gov (United States)

Lamberth, Becky

2015-01-01

Bullying is a repetitive and a busive behavior in which the victim suffers from abuse, humiliation, or intimidation to such an extent that it interferes with job performance. Victims of bullying have three possible legal solutions: harassment, hostile work environment, and intentional/negligent infliction of emotional distress. However, the elements necessary to fulfill the legal definitions are subjective and difficult at best to satisfy. Hospitals are hesitant to terminate any employee, which would result in open staff positions that are difficult to fill. Replacing staff with specific skills, costly. This make recruitmen cost a significant factor in retaining staff members who demonstrate poor behavior. Part 1 will focus on terminology and concerns related to bullying. Part 2 will discuss the legal protection afforded the bully and possible organizational solutions. Part 3 will address managers who have been accused of bullying by disgruntled employees and what to do about it.

Evaluation of potential severe accidents during low power and shutdown operations at Surry, Unit 1: Evaluation of severe accident risk during mid-loop operations. Main report. Volume 6. Part 1

Energy Technology Data Exchange (ETDEWEB)

Jo, J.; Lin, C.C.; Neymotin, L. [Brookhaven National Lab., Upton, NY (United States)] [and others

1995-05-01

During 1989, the Nuclear Regulatory Commission (NRC) initiated an extensive program to carefully examine the potential risks during low power and shutdown operations. The program includes two parallel projects being performed by Brookhaven National Laboratory (BNL) and Sandia National Laboratories (SNL). Two plants, Surry (pressurized water reactor) and Grand Gulf (boiling water reactor), were selected as the plants to be studied. The objectives of the program are to assess the risks of severe accidents initiated during plant operational states other than full power operation and to compare the estimated core damage frequencies, important accident sequences and other qualitative and quantitative results with those accidents initiated during full power operation as assessed in NUREG-1150. The scope of the program includes that of a level-3 PRA. A phased approach was used in the level-1 program. In phase 1 which was completed in Fall 1991, a coarse screening analysis including internal fire and flood was performed for all plant operational states (POSs). The objective of the phase 1 study was to identify potential vulnerable plant configurations, to characterize (on a high, medium, or low basis) the potential core damage accident scenarios, and to provide a foundation for a detailed phase 2 analysis. In phase 2, mid-loop operation was selected as the plant configuration to be analyzed based on the results of the phase 1 study. The objective of the phase 2 study is to perform a detailed analysis of the potential accident scenarios that may occur during mid-loop operation, and compare the results with those of NUREG-1150. The results of the phase 2 level 2/3 study are the subject of this volume of NUREG/CR-6144, Volume 6.

Evaluation of potential severe accidents during low power and shutdown operations at Surry, Unit 1: Evaluation of severe accident risk during mid-loop operations. Main report. Volume 6. Part 1

International Nuclear Information System (INIS)

Jo, J.; Lin, C.C.; Neymotin, L.

1995-05-01

During 1989, the Nuclear Regulatory Commission (NRC) initiated an extensive program to carefully examine the potential risks during low power and shutdown operations. The program includes two parallel projects being performed by Brookhaven National Laboratory (BNL) and Sandia National Laboratories (SNL). Two plants, Surry (pressurized water reactor) and Grand Gulf (boiling water reactor), were selected as the plants to be studied. The objectives of the program are to assess the risks of severe accidents initiated during plant operational states other than full power operation and to compare the estimated core damage frequencies, important accident sequences and other qualitative and quantitative results with those accidents initiated during full power operation as assessed in NUREG-1150. The scope of the program includes that of a level-3 PRA. A phased approach was used in the level-1 program. In phase 1 which was completed in Fall 1991, a coarse screening analysis including internal fire and flood was performed for all plant operational states (POSs). The objective of the phase 1 study was to identify potential vulnerable plant configurations, to characterize (on a high, medium, or low basis) the potential core damage accident scenarios, and to provide a foundation for a detailed phase 2 analysis. In phase 2, mid-loop operation was selected as the plant configuration to be analyzed based on the results of the phase 1 study. The objective of the phase 2 study is to perform a detailed analysis of the potential accident scenarios that may occur during mid-loop operation, and compare the results with those of NUREG-1150. The results of the phase 2 level 2/3 study are the subject of this volume of NUREG/CR-6144, Volume 6

Kidney volume in type 1 (insulin-dependent) diabetic patients with normal or increased urinary albumin excretion

DEFF Research Database (Denmark)

Feldt-Rasmussen, B; Hegedüs, L; Mathiesen, E R

1991-01-01

Forty-seven patients with type 1 (insulin-dependent) diabetes mellitus and 14 normal subjects had renal volume determined by an ultrasonic technique. Renal volume of 299 +/- 49 ml/1.73 m2 (mean +/- SD) in type 1 diabetic patients with normal urinary albumin excretion exceeded that in the normal...... subjects (245 +/- 53 ml/1.73 m2, p less than 0.05). Compared with diabetic patients with normal urinary albumin excretion, renal volume was significantly higher in patients with microalbuminuria (372 +/- 24 ml/1.73 m2, p less than 0.05) and patients with clinical nephropathy (352 +/- 48 ml/1.73 m2, p less...... than 0.05). In a multiple linear regression with HbA1c, urinary albumin excretion, age, diabetes duration and mean blood pressure as independent variables, variations in HbA1c could account for 33% of the variations in kidney volume (n = 47, r = 0.57, p less than 0.01). The other variables played...

42 CFR 456.1 - Basis and purpose of part.

Science.gov (United States)

2010-10-01

... admission review) 1902(a)(30)1903(g)(1)(C) 1903(i)(4) Subpart D—Utilization Control: Mental Hospitals... (CONTINUED) MEDICAL ASSISTANCE PROGRAMS UTILIZATION CONTROL General Provisions § 456.1 Basis and purpose of part. (a) This part prescribes requirements concerning control of the utilization of Medicaid services...

NRC action plan developed as a result of the TMI-2 accident. Volume 2

International Nuclear Information System (INIS)

1980-05-01

The Action Plan provides a comprehensive and integrated plan for all actions judged necessary by the Nuclear Regulatory Commission to correct or improve the regulation and operation of nuclear facilities based on the experience from the accident at the Three Mile Island, Unit 2, nuclear facility and the official studies and investigations of the accident. The tables included in this volume list the recommendations from the various organizations and task forces investigating the accident at Three Mile Island. The tables are annotated to provide easy references to the associated parts of the Action Plan in Volume 1. The tables are also annotated to provide a shorthand indication of how the various recommendations are treated in the Action Plan

Strategic Insights. Volume 10, Issue 1, Spring 2011

Science.gov (United States)

2011-01-01

weapons in our arsenal and ban chemical and biological weapons. With persistence, there are solutions. A way around the attribution problem may be to...metal and plastic . America needs the ability to carpet bomb in cyberspace to create the deterrent we lack.13 In other words, Williamson was not only...Insights • Spring 2011 Volume 10, Issue 1 25 Cyber Conflict Between Taiwan and China Yao-chung Chang Introduction The Republic of China ( Taiwan

Cost Analysis of an Air Brayton Receiver for a Solar Thermal Electric Power System in Selected Annual Production Volumes

Science.gov (United States)

1981-01-01

Pioneer Engineering and Manufacturing Company estimated the cost of manufacturing and Air Brayton Receiver for a Solar Thermal Electric Power System as designed by the AiResearch Division of the Garrett Corporation. Production costs were estimated at annual volumes of 100; 1,000; 5,000; 10,000; 50,000; 100,000 and 1,000,000 units. These costs included direct labor, direct material and manufacturing burden. A make or buy analysis was made of each part of each volume. At high volumes special fabrication concepts were used to reduce operation cycle times. All costs were estimated at an assumed 100% plant capacity. Economic feasibility determined the level of production at which special concepts were to be introduced. Estimated costs were based on the economics of the last half of 1980. Tooling and capital equipment costs were estimated for ach volume. Infrastructure and personnel requirements were also estimated.

Characterization of radioactive waste forms. Progress report for 1986 Volume 1

International Nuclear Information System (INIS)

Glasser, F.P.; McCulloch, C.

1988-01-01

The Council of Ministers of the European Communities adopted the third five-year EC programme of research on radioactive waste management and disposal in March 1985. It was recognized that the inevitable production of radioactive waste required perfecting and demonstrating systems for managing the waste produced by the nuclear industry, ensuring at the various stages the best possible protection of man and the environment. Task 3 of the programme 'evaluation of conditioned waste and qualification of engineered barriers' is subdivided into five sections. This book, in two volumes, is a compilation of reports on the progress achieved in four of the sections during 1986, the first year of the third programme. Volume 1 is concerned with Sections 1 and 5, 'Research on low -and medium- active waste' and 'Quality control methods'. Volume 2 covers Section 2 'HLW form characterization' and Section 3 'Other engineered barriers'. Section 4 'Development of standard test methods' is not included in this edition, as results from an interlaboratory round robin test now in progress will only be available for inclusion for the year 1988

17 CFR 289.1 - Applicability of this part.

Science.gov (United States)

2010-04-01

... CORPORATION ACT § 289.1 Applicability of this part. This part (Regulation IFC) prescribes the reports to be filed with the Securities and Exchange Commission by the International Finance Corporation (“IFC”) pursuant to section 13(a) of the International Finance Corporation Act. ...

RASISME DALAM FILM 99 CAHAYA DI LANGIT EROPA PART 1 (ANALISIS SEMIOTIKA DALAM FILM 99 CAHAYA DI LANGIT EROPA PART 1

Directory of Open Access Journals (Sweden)

Vallen Nur Rita

2016-09-01

Full Text Available Stereotip merupakan pernyataan negatif dari prasangka. Prasangka inilah yang kemudian dijadikan alasan untuk melakukan diskriminasi terhadap kelompok rasial tertentu. Stereotip dan prasangka kemudian merujuk pada suatu paham yang mempercayai adanya superioritas yang menolak adanya kesetaraan manusia yaitu rasisme. Perilaku maupun tindakan rasisme tersebut banyak muncul dalam beberapa scene film 99 Cahaya Di Langit Eropa Part 1. Tujuan dari penelitian ini adalah untuk mengetahui bagaimana simbol-simbol digunakan untuk menggambarkan rasisme di dalam film 99 Cahaya Di Langit Eropa Part 1. Metode yang digunakan oleh peneliti adalah semiotika Roland Barthes. Model Roland Barthes terdiri dari tiga tahap analisis yaitu denotasi, konotasi, mitos. Peneliti melakukan analisis menggunakan tanda verbal dan nonverbal yang terdapat dalam film “99 Cahaya di Langit Eropa Part 1”. Dalam menganalisis film 99 Cahaya di Langit Eropa Part 1, dikelompokkan menjadi beberapa kategori yang berhubungan dengan perilaku rasisme, antara lain : stereotip, prasangka, diskriminasi

Discovery of pyrazolo[1,5-a]pyrimidine-based CHK1 inhibitors: A template-based approach-Part 2

Energy Technology Data Exchange (ETDEWEB)

Labroli, Marc; Paruch, Kamil; Dwyer, Michael P.; Alvarez, Carmen; Keertikar, Kartik; Poker, Cory; Rossman, Randall; Duca, Jose S.; Fischmann, Thierry O.; Madison, Vincent; Parry, David; Davis, Nicole; Seghezzi, Wolfgang; Wiswell, Derek; Guzi, Timothy J. [Merck

2013-11-20

Previous efforts by our group have established pyrazolo[1,5-a]pyrimidine as a viable core for the development of potent and selective CDK inhibitors. As part of an effort to utilize the pyrazolo[1,5-a]pyrimidine core as a template for the design and synthesis of potent and selective kinase inhibitors, we focused on a key regulator in the cell cycle progression, CHK1. Continued SAR development of the pyrazolo[1,5-a]pyrimidine core at the C5 and C6 positions, in conjunction with previously disclosed SAR at the C3 and C7 positions, led to the discovery of potent and selective CHK1 inhibitors.

Bibliography on Cold Regions Science and Technology, Volume 45, Part 1

Science.gov (United States)

1991-12-01

Island. High pressure ice, Amorphous ice, Molecular struc- tVelikaia prilednikovala sistema stoka Severnol Ev- over the past three years. The work has...Maad land shelf III detrmine the eel5 uty andu stra in 1Ii the eI t he netl t I \\ A -In iinosmasuet n ihei toC . I SN- it-i H ului-cho - nasurenrenis

Textbook of Military Medicine. Part 1. Warfare, Weaponry, and the Casualty. Volume 2. Medical Consequences of Nuclear Warfare

Science.gov (United States)

1989-04-01

controlled in part by a restricted-fiber diet and in cutaneous insertion after 36 hours, even if a venous part by medication. Drugs such as diphenoxylate...301-, of the total caloric requirement can be supplied jig/day), manganese (> 0.8 mg/day), and iron (> 2 as lipids. However, short-term peripheral...collects in the thyroid, field-portable dedicated fluorometer for other bio- where sufficient concentrations may lead to hypo - logical dosimeters

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

Energy Technology Data Exchange (ETDEWEB)

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

1988-03-01

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

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

Energy Technology Data Exchange (ETDEWEB)

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

1995-04-01

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

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

International Nuclear Information System (INIS)

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

1995-04-01

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

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

International Nuclear Information System (INIS)

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

1995-03-01

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

Hazard Ranking System evaluation of CERCLA [Comprehensive Environmental Response, Compensation, and Liability Act] inactive waste sites at Hanford: Volume 1, Evaluation methods and results

International Nuclear Information System (INIS)

Stenner, R.D.; Cramer, K.H.; Higley, K.A.; Jette, S.J.; Lamar, D.A.; McLaughlin, T.J.; Sherwood, D.R.; Van Houten, N.C.

1988-10-01

The purpose of this report is to formally document the individual site Hazard Ranking System (HRS) evaluations conducted as part of the preliminary assessment/site inspection (PA/SI) activities at the US Department of Energy (DOE) Hanford Site. These activities were carried out pursuant to the DOE orders that describe the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) Program addressing the cleanup of inactive waste sites. These orders incorporate the US Environmental Protection Agency methodology, which is based on the Superfund Amendments and Reauthorization Act of 1986 (SARA). The methodology includes six parts: PA/SI, remedial investigation/feasibility study, record of decision, design and implementation of remedial action, operation and monitoring, and verification monitoring. Volume 1 of this report discusses the CERCLA inactive waste-site evaluation process, assumptions, and results of the HRS methodology employed. Volume 2 presents the data on the individual CERCLA engineered-facility sites at Hanford, as contained in the Hanford Inactive Site Surveillance (HISS) Data Base. Volume 3 presents the data on the individual CERCLA unplanned-release sites at Hanford, as contained in the HISS Data Base. 34 refs., 43 figs., 47 tabs

Hazard Ranking System evaluation of CERCLA (Comprehensive Environmental Response, Compensation, and Liability Act) inactive waste sites at Hanford: Volume 1, Evaluation methods and results

Energy Technology Data Exchange (ETDEWEB)

Stenner, R.D.; Cramer, K.H.; Higley, K.A.; Jette, S.J.; Lamar, D.A.; McLaughlin, T.J.; Sherwood, D.R.; Van Houten, N.C.

1988-10-01

The purpose of this report is to formally document the individual site Hazard Ranking System (HRS) evaluations conducted as part of the preliminary assessment/site inspection (PA/SI) activities at the US Department of Energy (DOE) Hanford Site. These activities were carried out pursuant to the DOE orders that describe the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) Program addressing the cleanup of inactive waste sites. These orders incorporate the US Environmental Protection Agency methodology, which is based on the Superfund Amendments and Reauthorization Act of 1986 (SARA). The methodology includes six parts: PA/SI, remedial investigation/feasibility study, record of decision, design and implementation of remedial action, operation and monitoring, and verification monitoring. Volume 1 of this report discusses the CERCLA inactive waste-site evaluation process, assumptions, and results of the HRS methodology employed. Volume 2 presents the data on the individual CERCLA engineered-facility sites at Hanford, as contained in the Hanford Inactive Site Surveillance (HISS) Data Base. Volume 3 presents the data on the individual CERCLA unplanned-release sites at Hanford, as contained in the HISS Data Base. 34 refs., 43 figs., 47 tabs.

Transportation Sector Model of the National Energy Modeling System. Volume 2 -- Appendices: Part 3

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-01-01

This Appendix consists of two unpublished reports produced by Energy and Environmental Analysis, Inc., under contract to Oak Ridge National Laboratory. These two reports formed the basis for the subsequent development of the Fuel Economy Model described in Volume 1. They are included in order to document more completely the efforts undertaken to construct a comprehensive model of automobile fuel economy. The supplemental reports are as follows: Supplement 1--Documentation Attributes of Technologies to Improve Automotive Fuel Economy; Supplement 2--Analysis of the Fuel Economy Boundary for 2010 and Comparison to Prototypes.

Cell and Tissue Organization in the Circulatory and Ventilatory Systems Volume 1 Signaling in Cell Organization, Fate, and Activity, Part A Cell Structure and Environment

CERN Document Server

Thiriet, Marc

2011-01-01

The volumes in this authoritative series present a multidisciplinary approach to modeling and simulation of flows in the cardiovascular and ventilatory systems, especially multiscale modeling and coupled simulations. The cardiovascular and respiratory systems are tightly coupled, as their primary function is to supply oxygen to and remove carbon dioxide from the body's cells. Because physiological conduits have deformable and reactive walls, macroscopic flow behavior and prediction must be coupled to nano- and microscopic events in a corrector scheme of regulated mechanisms. Therefore, investigation of flows of blood and air in physiological conduits requires an understanding of the biology, chemistry, and physics of these systems together with the mathematical tools to describe their functioning.  The present volume is devoted to cellular events that allow adaptation to environmental conditions, particularly mechanotransduction. It begins with cell organization and a survey of cell types in the vasculatur...

Economic impacts of Alberta's oil sands, volume 1

International Nuclear Information System (INIS)

Timilsina, G.R.; LeBlanc, N.; Walden, T.

2005-01-01

In 2004, the international media recognized Alberta's oil sands as part of the global oil reserves, thereby establishing Canada as second to Saudi Arabia as potential oil producing nations. The economic impacts of Alberta's oil sands industry on economies were assessed at regional, provincial and international levels for the 2000 to 2020 period. A customized input-output model was used to assess economic impacts, which were measured in terms of changes in gross domestic product; employment and labour income; and, government revenues. Cumulative impacts on employment by sector and by jurisdiction were also presented. An investment of $100 billion is expected through 2020, resulting in production of crude bitumen and synthetic crude oil outputs valued at about $531 billion. The impact of the oil sands industry on local employment was also evaluated. It was shown that activities in the oil sands industry will lead to significant economic impact in Alberta, Ontario, Quebec and the rest of Canada. Alberta's local economy would be the main beneficiary of oil sands activities with nearly 3.6 million person years employment created in Alberta during the 2000 to 2020. Another 3 million person years employment would be created in other Canadian provinces and outside Canada during the same time period. A sensitivity analysis on the responsiveness to oil prices and the removal of various constraints incorporated in the main analysis was also presented. The federal government will be the largest recipient of revenues generated to to oil sands activities. The results of the study were compared with that of the National Task Force on Oil Sands Strategies. This first volume revealed the results of the study while the second volume includes the data and detailed results. 48 refs., 57 tabs., 28 figs

Pulsed power bibliography. Volume 1: Indices

Science.gov (United States)

Bemesderfer, J.; Druce, R. L.; Frantz, B.; Guenther, A. H.; Kristiansen, M.; Oloughlin, J. P.; Pendleton, W. K.

1983-08-01

Pulsed power and high-voltage technologies are playing an ever increasing role in weapons' effects simulation, fusion power research, power distribution, materials processing and medical research. It is a rapidly expanding field of applied physics as evidenced by the growth in published literature. Three years ago, the Air Force Weapons Laboratory (AFWL) initiated a project to compile a computerized data base of pulsed power research papers. The data base is stored on our IBM System 2000. This AFWL Technical Report is the first release of the bibliography to date. It contains about 2,500 full bibliographic citations, original sources, availability, key words and abstract. There are three indices: Subject, Personal Author, and Corporate Author. There are 30 main subject headings, from Breakdown Studies to Switching. The indices are contained in Volume 1.

Volume holographic memory

Directory of Open Access Journals (Sweden)

Cornelia Denz

2000-05-01

Full Text Available Volume holography represents a promising alternative to existing storage technologies. Its parallel data storage leads to high capacities combined with short access times and high transfer rates. The design and realization of a compact volume holographic storage demonstrator is presented. The technique of phase-coded multiplexing implemented to superimpose many data pages in a single location enables to store up to 480 holograms per storage location without any moving parts. Results of analog and digital data storage are shown and real time optical image processing is demonstrated.

Electroanalytical chemistry. Volume 14

International Nuclear Information System (INIS)

Bard, A.J.

1986-01-01

This volume is part of a series aimed at authoritative reviews of electroanalytical techniques and related areas of investigation. Volume 14 clearly maintains the high standards and proven usefulness of the series. Topics covered include conformation change and isomerization associated with electrode reactions, infrared vibrational spectroscopy of the electrode-solution interface, and precision in linear sweep and cyclic voltametry. A short history of electrochemical techniques which include the term square wave is provided

Environmental Toxicology: A Guide to Information Sources. Volume 7 in the "Man and the Environment Information Guide" Series.

Science.gov (United States)

Rudd, Robert L.

This annotated bibliography on environmental toxicology brings together a diverse set of information sources from the physical, social, and natural sciences. These sources include periodical literature, government documents, scientific journals, and teaching materials. The volume is divided into sixteen sections organized into four parts: (1)…

Phased mission methodology. A state of the art report: Parts A, B and C

International Nuclear Information System (INIS)

Terpstra, K.; Van Driel, G.; Kafka, P.; Polke, H.

1986-01-01

A complex system has to perform a number of different tasks. Sometimes these tasks must be performed at the same time, but in a lot of cases the system has to perform its tasks subsequently. The execution of the different tasks is effected by parts of the system, so-called subsystems more or less dependent by means of processes and/or shared equipment. Examples of such complex systems can be found, for instance, in modern space travel, in nuclear power plants, in military weapon systems, etc. A phased mission is a task for a complex system to be performed in parts (subtasks), one part after the other. The present report covers the work carried out under the tripartite concert between the European Communities (CEC), the Gesellschaft fuer Reaktorsicherheit mbH (GRS) and the Netherlands Energy Research Foundation (ECN). The scope of the studies is to assess the practical usefulness of phased mission analyses. The present volume consists of three parts: Part A: Phased mission analysis. A review of mathematical modelling and of a number of existing computer programs; Part B: Example for the application of phased mission methods in reliability and risk studies; and, Part C: Calculation results for a phased mission - Part C1 - Phased mission calculation for a reference heat removal system - Part C2 - Application of phased mission methods in reliability and risk studies

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)

Oak Ridge Health Studies Phase 1 report, Volume 2: Part A, Dose Reconstruction Feasibility Study

International Nuclear Information System (INIS)

Bruce, G.M.; Buddenbaum, J.E.; Lamb, J.K.; Widner, T.E.

1993-09-01

The Phase I feasibility study has focused on determining the availability of information for estimating exposures of the public to chemicals and radionuclides released as a result of historical operation of the facilities at the Oak Ridge Reservation (ORR). The estimation of such past exposures is frequently called dose reconstruction. The initial project tasks, Tasks 1 and 2 were designed to identify and collect information that documents the history of activities at the ORR that resulted in the release of contamination and to characterize the availability of data that could be used to estimate the magnitude of the contaminant releases or public exposures. A history of operations that are likely to have generated off-site releases has been documented as a result of Task 1 activities. The activities required to perform this task involved the extensive review of historical operation records and interviews with present and past employees as well as other knowledgeable individuals. The investigation process is documented in this report. The Task 1 investigations have led to the documentation of an overview of the activities that have taken place at each of the major complexes, including routine operations, waste management practices, special projects, and accidents and incidents. Historical activities that appear to warrant the highest priority in any further investigations were identified based on their likely association with off-site emissions of hazardous materials as indicated by the documentation reviewed or information obtained in interviews

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

Energy Technology Data Exchange (ETDEWEB)

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

1997-06-01

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

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

International Nuclear Information System (INIS)

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

1997-06-01

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

Helicopter Transparent Enclosures. Volume 1. Design Handbook

Science.gov (United States)

1979-01-01

Armour Research Foundation, "Engineering Design Factors for Laminated Aircraft Windshields, Part 2," WADC-TR-53-99, Wright Air Devel- opment Center...77L~i- -- - -- References .. l,. Islir~ger, Armour Research Foundation, "Engineering Design Factors for Laminated Aircraft Windshields, Parts 1 ahd I...of having separate heating and forming devices, often used with acrylic, will rarely be feasible with polycarbonates. 29.7 Forming Methods Drape

USAF Test Pilot School. Flying Qualities Textbook, Volume 2, Part 1

Science.gov (United States)

1986-04-01

Qualities Flight Testing, Performance and Flying Qaulities Branch, Flight Test Engneerd ision, 6510th Test Wing, Air Force Flight Mayst Ce1ter, Edwards...For these aircraft, the program manager may re*uire a mil spec written specifically for the aircraft and control system involwd. 5.20.2 _EL k,Tt...OR MANAGED IN CONTEXT OF MISSION, WITH AVAILABLE PILOT ATTENTION. S UNCONTROLLABLE CONTROL WILL BE LOST DURING SOME PORTION OF MISSION. ACCEPTABLE

12 CFR 533.1 - Purpose and scope of this part.

Science.gov (United States)

2010-01-01

... REPORTING OF CRA-RELATED AGREEMENTS § 533.1 Purpose and scope of this part. (a) General. This part... Community Reinvestment Act. This part does not affect in any way the Community Reinvestment Act of 1977 (CRA... interpretations or administration of the CRA or Community Reinvestment rule. (d) Examples. (1) The examples in...

Solvent extraction equipment evaluation study. Part 1. Review of the literature

Energy Technology Data Exchange (ETDEWEB)

Geier, R.G.; Browne, L.M. (comps.)

1977-01-01

This is Part 1 of a three-part document that reviews the solvent extraction contactors available for use in radiochemical reprocessing plants. The three parts are: Part 1: A Review of the Literature, Part 2: Workshop Proceedings, Part 3: A Summary. The main objective of the document is to provide an information base to aid in contactor selection and design of future reprocessing plants. The Literature Review (Part 1) brings together scattered data on all major contactors in use today. It contains an annotated bibliography of the citations used in the review and a complete listing of all the citations screened prior to the review. These bibliographies should aid in determining which reports would be most useful if additional information is desired.

Solvent extraction equipment evaluation study. Part 1. Review of the literature

International Nuclear Information System (INIS)

Geier, R.G.; Browne, L.M.

1977-01-01

This is Part 1 of a three-part document that reviews the solvent extraction contactors available for use in radiochemical reprocessing plants. The three parts are: Part 1: A Review of the Literature, Part 2: Workshop Proceedings, Part 3: A Summary. The main objective of the document is to provide an information base to aid in contactor selection and design of future reprocessing plants. The Literature Review (Part 1) brings together scattered data on all major contactors in use today. It contains an annotated bibliography of the citations used in the review and a complete listing of all the citations screened prior to the review. These bibliographies should aid in determining which reports would be most useful if additional information is desired

Implementing statistical equating for MRCP(UK) Parts 1 and 2.

Science.gov (United States)

McManus, I C; Chis, Liliana; Fox, Ray; Waller, Derek; Tang, Peter

2014-09-26

The MRCP(UK) exam, in 2008 and 2010, changed the standard-setting of its Part 1 and Part 2 examinations from a hybrid Angoff/Hofstee method to statistical equating using Item Response Theory, the reference group being UK graduates. The present paper considers the implementation of the change, the question of whether the pass rate increased amongst non-UK candidates, any possible role of Differential Item Functioning (DIF), and changes in examination predictive validity after the change. Analysis of data of MRCP(UK) Part 1 exam from 2003 to 2013 and Part 2 exam from 2005 to 2013. Inspection suggested that Part 1 pass rates were stable after the introduction of statistical equating, but showed greater annual variation probably due to stronger candidates taking the examination earlier. Pass rates seemed to have increased in non-UK graduates after equating was introduced, but was not associated with any changes in DIF after statistical equating. Statistical modelling of the pass rates for non-UK graduates found that pass rates, in both Part 1 and Part 2, were increasing year on year, with the changes probably beginning before the introduction of equating. The predictive validity of Part 1 for Part 2 was higher with statistical equating than with the previous hybrid Angoff/Hofstee method, confirming the utility of IRT-based statistical equating. Statistical equating was successfully introduced into the MRCP(UK) Part 1 and Part 2 written examinations, resulting in higher predictive validity than the previous Angoff/Hofstee standard setting. Concerns about an artefactual increase in pass rates for non-UK candidates after equating were shown not to be well-founded. Most likely the changes resulted from a genuine increase in candidate ability, albeit for reasons which remain unclear, coupled with a cognitive illusion giving the impression of a step-change immediately after equating began. Statistical equating provides a robust standard-setting method, with a better

Improving nursing morale in a climate of cost containment. Part 1. Organizational assessment.

Science.gov (United States)

Haw, M A; Claus, E G; Durbin-Lafferty, E; Iversen, S M

1984-10-01

Faced with declining resources for health care and greater pressures to improve productivity of nursing staff, nursing administrators must act now to develop organizational responses to morale problems among nursing staff. As part of a two-part series for JONA, the authors describe low-cost organizational approaches that address nursing morale. Presented in Part 1 is a low-cost diagnostic process for assessing needs of staff and appraising organizational dimensions contributing to morale. Assessment findings provide clear direction for developing organizational approaches for improving morale.

Colorado Conference on iterative methods. Volume 1

Energy Technology Data Exchange (ETDEWEB)

NONE

1994-12-31

The conference provided a forum on many aspects of iterative methods. Volume I topics were:Session: domain decomposition, nonlinear problems, integral equations and inverse problems, eigenvalue problems, iterative software kernels. Volume II presents nonsymmetric solvers, parallel computation, theory of iterative methods, software and programming environment, ODE solvers, multigrid and multilevel methods, applications, robust iterative methods, preconditioners, Toeplitz and circulation solvers, and saddle point problems. Individual papers are indexed separately on the EDB.

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

Science.gov (United States)

1984-01-01

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

Cell Volume Regulation and Signaling in 3T3-L1 Pre-adipocytes and Adipocytes

DEFF Research Database (Denmark)

Eduardsen, Kathrine; Larsen, Susanne; Novak, Ivana

2011-01-01

Caveolae have been implicated in sensing of cell volume perturbations, yet evidence is still limited and findings contradictory. Here, we investigated the possible role of caveolae in cell volume regulation and volume sensitive signaling in an adipocyte system with high (3T3-L1 adipocytes......); intermediate (3T3-L1 pre-adipocytes); and low (cholesterol-depleted 3T3-L1 pre-adipocytes) caveolae levels. Using large-angle light scattering, we show that compared to pre-adipocytes, differentiated adipocytes exhibit several-fold increased rates of volume restoration following osmotic cell swelling (RVD......) and osmotic cell shrinkage (RVI), accompanied by increased swelling-activated taurine efflux. However, caveolin-1 distribution was not detectably altered after osmotic swelling or shrinkage, and caveolae integrity, as studied by cholesterol depletion or expression of dominant negative Cav-1, was not required...

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.

Ambient temperature and volume of perihematomal edema in acute intracerebral haemorrhage: the INTERACT1 study.

Science.gov (United States)

Zheng, Danni; Arima, Hisatomi; Heeley, Emma; Karpin, Anne; Yang, Jie; Chalmers, John; Anderson, Craig S

2015-01-01

As no human data exist, we aimed to determine the relation between ambient temperature and volume of perihematomal 'cerebral' edema in acute spontaneous intracerebral haemorrhage (ICH) among Chinese participants of the pilot phase, Intensive Blood Pressure Reduction in Acute Cerebral Haemorrhage Trial (INTERACT1). INTERACT1 was a multicenter, open, blind outcome assessed, randomized controlled trial of intensive (systolic target ambient temperature (mean, minimum, maximum, and range) on the day of each participant's ICH obtained from China Meteorological Data Sharing Service System were linked to other data including edema volumes. Multivariable regression analyses were performed to evaluate association between ambient temperature and edema volumes. A generalized linear regression model with a generalized estimating equations approach (GEE) was used to assess any association of ambient temperature and change in edema volume over 72 h. A total of 250 of all 384 Chinese participants had complete data that showed positive associations between ambient temperature (mean and minimum temperatures) and edema volumes at each time point over 72 h after hospital admission (all P ambient temperature and perihematomal edema volume in acute spontaneous ICH. © 2014 World Stroke Organization.

Report of a CSNI workshop on uncertainty analysis methods. Volume 1 + 2

International Nuclear Information System (INIS)

Wickett, A.J.; Yadigaroglu, G.

1994-08-01

The OECD NEA CSNI Principal Working Group 2 (PWG2) Task Group on Thermal Hydraulic System Behaviour (TGTHSB) has, in recent years, received presentations of a variety of different methods to analyze the uncertainty in the calculations of advanced unbiased (best estimate) codes. Proposals were also made for an International Standard Problem (ISP) to compare the uncertainty analysis methods. The objectives for the Workshop were to discuss and fully understand the principles of uncertainty analysis relevant to LOCA modelling and like problems, to examine the underlying issues from first principles, in preference to comparing and contrasting the currently proposed methods, to reach consensus on the issues identified as far as possible while not avoiding the controversial aspects, to identify as clearly as possible unreconciled differences, and to issue a Status Report. Eight uncertainty analysis methods were presented. A structured discussion of various aspects of uncertainty analysis followed - the need for uncertainty analysis, identification and ranking of uncertainties, characterisation, quantification and combination of uncertainties and applications, resources and future developments. As a result, the objectives set out above were, to a very large extent, achieved. Plans for the ISP were also discussed. Volume 1 contains a record of the discussions on uncertainty methods. Volume 2 is a compilation of descriptions of the eight uncertainty analysis methods presented at the workshop

41 CFR 105-1.000-50 - Scope of part.

Science.gov (United States)

2010-07-01

... 41 Public Contracts and Property Management 3 2010-07-01 2010-07-01 false Scope of part. 105-1.000-50 Section 105-1.000-50 Public Contracts and Property Management Federal Property Management Regulations System (Continued) GENERAL SERVICES ADMINISTRATION 1-INTRODUCTION § 105-1.000-50 Scope of part...

Physics Letters B, Volume 716, Issue 1- Cover Page

CERN Multimedia

CERN

2012-01-01

The cover page of the Physics Letters B Journal, Volume 716, Issue 1, dedicated to the observation of a new particle in the search for the Standard Model Higgs boson. To celebrate this historical discovery, Elsevier reprinted the ATLAS and the CMS articles together with a foreword by Peter Higgs and the other scientists that predicted the existence of the so-called Higgs boson and published this in a separate booklet.

NASA Aerospace Flight Battery Program: Generic Safety, Handling and Qualification Guidelines for Lithium-Ion (Li-Ion) Batteries; Availability of Source Materials for Lithium-Ion (Li-Ion) Batteries; Maintaining Technical Communications Related to Aerospace Batteries (NASA Aerospace Battery Workshop). Volume 1, Part 1

Science.gov (United States)

Manzo, Michelle A.; Brewer, Jeffrey C.; Bugga, Ratnakumar V.; Darcy, Eric C.; Jeevarajan, Judith A.; McKissock, Barbara I.; Schmitz, Paul C.

2010-01-01

This NASA Aerospace Flight Battery Systems Working Group was chartered within the NASA Engineering and Safety Center (NESC). The Battery Working Group was tasked to complete tasks and to propose proactive work to address battery related, agency-wide issues on an annual basis. In its first year of operation, this proactive program addressed various aspects of the validation and verification of aerospace battery systems for NASA missions. Studies were performed, issues were discussed and in many cases, test programs were executed to generate recommendations and guidelines to reduce risk associated with various aspects of implementing battery technology in the aerospace industry. This document contains Part 1 - Volume I: Generic Safety, Handling and Qualification Guidelines for Lithium-Ion (Li-Ion) Batteries, Availability of Source Materials for Lithium-Ion (Li-Ion) Batteries, and Maintaining Technical Communications Related to Aerospace Batteries (NASA Aerospace Battery Workshop).

Quadrennial Review of Military Compensation (6th). Executive Summary. Volumes 1 thru 1C, and Volumes 2 thru 3

Science.gov (United States)

1988-08-01

CIVILIAN EARNINGS PROFILE: ENLISTED SOURCE: SYLLOGISTICS 2-24 6th ORNC Esport -Volum 11 participation and higher than that of civilian counterparts in...7-26 6th QRNC esport - Volume I m Eliminate the existing 80 percent limiltation onmeai/entertairment deductions incurred in connection with the

SCDAP/RELAP5/MOD 3.1 code manual: Interface theory. Volume 1

International Nuclear Information System (INIS)

Coryell, E.W.

1995-06-01

The SCDAP/RELAP5 code has been developed for best estimate transient simulation of light water reactor coolant systems during a severe accident. The code models the coupled behavior of the reactor coolant system, core, fission product released during a severe accident transient as well as large and small break loss of coolant accidents, operational transients such as anticipated transient without SCRAM, loss of off-site power, loss of feedwater, and loss of flow. A generic modeling approach is used that permits as much of a particular system to be modeled as necessary. Control system and secondary system components are included to permit modeling of plant controls, turbines, condensers, and secondary feedwater conditioning systems. This volume describes the organization and manner of the interface between severe accident models which are resident in the SCDAP portion of the code and hydrodynamic models which are resident in the RELAP5 portion of the code. A description of the organization and structure of SCDAP/RELAP5 is presented. Additional information is provided regarding the manner in which models in one portion of the code impact other parts of the code, and models which are dependent on and derive information from other subcodes

16 CFR Figure 1 to Part 1203 - Anatomical Planes

Science.gov (United States)

2010-01-01

... 16 Commercial Practices 2 2010-01-01 2010-01-01 false Anatomical Planes 1 Figure 1 to Part 1203 Commercial Practices CONSUMER PRODUCT SAFETY COMMISSION CONSUMER PRODUCT SAFETY ACT REGULATIONS SAFETY STANDARD FOR BICYCLE HELMETS Pt. 1203, Fig. 1 Figure 1 to Part 1203—Anatomical Planes ER10MR98.001 ...

38 CFR 1.893 - Establishing and converting part-time positions.

Science.gov (United States)

2010-07-01

... converting part-time positions. 1.893 Section 1.893 Pensions, Bonuses, and Veterans' Relief DEPARTMENT OF VETERANS AFFAIRS GENERAL PROVISIONS Part-Time Career Employment Program § 1.893 Establishing and converting part-time positions. Position management and other internal reviews may indicate that positions may be...

Minimization of the volume and Pu content of the waste generated at a plutonium fuel fabrication plant

International Nuclear Information System (INIS)

Pauwels, H.

1992-01-01

The amounts of waste generated during 1987, 1989 and a past reference period have been reported in great detail. The main conclusions which can be drawn from these figures are: (i) for all kinds of waste, the waste-to-product ratio has decreased very substantially during the past few years. This reduction results partly from a scale effect, i.e. the better load factor of the plant, and partly from Belgonucleare's continuous effort to minimize the radioactive waste arisings; (ii) the ratio of the Pu content of the waste to the total Pu throughput of the plant has also decreased substantially; (iii) the mean Pu content of the solid Pu contaminated waste equals 1.39 g Pu per unit volume of 25 l. Only for a small fraction of this waste (<5% by volume) does the Pu content exceed 5 g per unit volume of 25 l; (iv) even after the implementation of waste reducing measures, some 45% of the solid Pu contaminated waste is generated by operations which involve the handling and transfer of powders. Finally, some 63% of the total amount of Pu in the waste can be imputed to these operations