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Sample records for technical appendix volume

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

Energy Technology Data Exchange (ETDEWEB)

United States. Bonneville Power Administration.

1993-12-01

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

Science.gov (United States)

2010-10-01

... 46 Shipping 7 2010-10-01 2010-10-01 false Substance Technical Guidelines, Benzene B Appendix B to... Subpart C to Part 197—Substance Technical Guidelines, Benzene I. Physical and Chemical Data (a) Substance... temperature: 580 °C (1076 °F). (3) Flammable limits in air, % by volume: Lower: 1.3%, Upper: 7.5%. (4...
36 CFR Appendix D to Part 1191 - Technical

Science.gov (United States)

2010-07-01

... 36 Parks, Forests, and Public Property 3 2010-07-01 2010-07-01 false Technical D Appendix D to Part 1191 Parks, Forests, and Public Property ARCHITECTURAL AND TRANSPORTATION BARRIERS COMPLIANCE...; ARCHITECTURAL BARRIERS ACT (ABA) ACCESSIBILITY GUIDELINES Pt. 1191, App. D Appendix D to Part 1191—Technical...
Design and Construction Rules for Mechanical equipments of FBR nuclear islands: RCC-MR. Tome 1, Volume Z: Other technical appendixes

International Nuclear Information System (INIS)

1985-06-01

This book is the 7th of a whole set of 12 which constitute the present edition of the RCC-MR. The technical appendixes of this volume deal with the following characteristics and rules: calculation of screwed assemblies, analysis taking into account creep, welded joint characteristics, elastoplastic analysis of a structure under cyclic loads, elasto-visco-plastic analysis under cyclic loads, calculation rules of revolution shells under external presure and of cylinders under axial compression, design rules of linear supports, calculation rules of convex bottoms under internal pressure [fr
1991 Pacific Northwest Loads and Resources Study, Technical Appendix: Volume 1.

Energy Technology Data Exchange (ETDEWEB)

United States. Bonneville Power Administration.

1992-03-01

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

Science.gov (United States)

Rose, Heather; Sonstelie, Jon; Weston, Margaret

2010-01-01

This is a technical appendix for the report, "Pathways for School Finance in California" (ED515651). "Pathways for School Finance in California" simulates alternatives to California's current school finance system. This appendix provides more information about the revenues used in those simulations. The first section describes…
Nondestructive verification and assay systems for spent fuels. Technical appendixes

International Nuclear Information System (INIS)

Cobb, D.D.; Phillips, J.R.; Baker, M.P.

1982-04-01

Six technical appendixes are presented that provide important supporting technical information for the study of the application of nondestructive measurements to spent-fuel storage. Each appendix addresses a particular technical subject in a reasonably self-contained fashion. Appendix A is a comparison of spent-fuel data predicted by reactor operators with measured data from reprocessors. This comparison indicates a rather high level of uncertainty in previous burnup calculations. Appendix B describes a series of nondestructive measurements at the GE-Morris Operation Spent-Fuel Storage Facility. This series of experiments successfully demonstrated a technique for reproducible positioning of fuel assemblies for nondestructive measurement. The experimental results indicate the importance of measuring the axial and angular burnup profiles of irradiated fuel assemblies for quantitative determination of spent-fuel parameters. Appendix C is a reasonably comprehensive bibliography of reports and symposia papers on spent-fuel nondestructive measurements to April 1981. Appendix D is a compendium of spent-fuel calculations that includes isotope production and depletion calculations using the EPRI-CINDER code, calculations of neutron and gamma-ray source terms, and correlations of these sources with burnup and plutonium content. Appendix E describes the pulsed-neutron technique and its potential application to spent-fuel measurements. Although not yet developed, the technique holds the promise of providing separate measurements of the uranium and plutonium fissile isotopes. Appendix F describes the experimental program and facilities at Los Alamos for the development of spent-fuel nondestructive measurement systems. Measurements are reported showing that the active neutron method is sensitive to the replacement of a single fuel rod with a dummy rod in an unirradiated uranium fuel assembly
Technical justifications for the tests and criteria in the waste form technical position appendix on cement stabilization

International Nuclear Information System (INIS)

Siskind, B.; Cowgill, M.G.

1992-01-01

As part of its technical assistance to the Nuclear Regulatory Commission (NRC), Brookhaven National Laboratory (BNL) developed a background document for the cement stabilization appendix, Appendix A, to Rev. 1 of the Technical Position on Waste Form (TP). Here we present an overview of this background document, which provides technical justification for the stability tests to be performed on cement-stabilized waste forms and for the criteria posed in each test, especially for those tests which have been changed from their counterparts in the May 1983 Rev. 0 TP. We address guidelines for procedures from Appendix A which are considered in less detail or not at all in the Rev. 0 of the TP, namely, qualification specimen preparation (mixing, curing, storage), statistical sampling and analysis, process control program specimen preparation and examination, and surveillance specimens. For each waste form qualification test, criterion or procedural guidelines, we consider the reason for its inclusion in Appendix A, the changes from Rev. 0 of the TP (if applicable), and a discussion of the justification or rationale for these changes
Technical justifications for the tests and criteria in the waste form Technical position appendix on cement stabilization

International Nuclear Information System (INIS)

Siskind, B.; Cowgill, M.G.

1992-01-01

As part of its technical assistance to the Nuclear Regulatory Commission (NRC), Brookhaven National Laboratory (BNL) developed a background document for the cement stabilization appendix. Appendix A, to Rev. 1 of the Technical Position on Waste Form (TP). Here we present an overview of this background document, which provides technical justification for the stability tests to be performed on cement-stabilized waste forms and for the criteria posed in each test) especially for those tests which have been changed from their counterparts in the May 1983 Rev. 0 TP. We address guidelines for procedures from Appendix A which are considered in less detail or not at all in the Rev. 0 of the TP, namely, qualification specimen preparation (mixing, curing, storage), statistical sampling and analysis, process control program specimen preparation and examination, and surveillance specimens. For each waste form qualification test, criterion or procedural guideline, we consider the reason for its inclusion in Appendix A, the changes from Rev. 0 of the TP (if applicable), and a discussion of the justification or rationale for these changes. (author)
Recovery of Navy distillate fuel from reclaimed product. Volume I. Technical discussion

Energy Technology Data Exchange (ETDEWEB)

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

1984-11-01

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

International Nuclear Information System (INIS)

1997-01-01

This study, conducted by Black and Veatch, was funded by the U.S. Trade and Development Agency. The report presents a technical and commercial analysis for the development of three nearly identical electricity generating facilities (biomass steam power plants) in the towns of Chachgoengsao, Suphan Buri, and Pichit in Thailand. Volume 2 of the study contains the following appendix: Detailed Financial Analysis Results
10 CFR Appendix III to Part 960 - Application of the System and Technical Guidelines During the Siting Process

Science.gov (United States)

2010-01-01

... 960—Application of the System and Technical Guidelines During the Siting Process 1. This appendix... 10 Energy 4 2010-01-01 2010-01-01 false Application of the System and Technical Guidelines During the Siting Process III Appendix III to Part 960 Energy DEPARTMENT OF ENERGY GENERAL GUIDELINES FOR THE...
A Curriculum Activities Guide to Water Pollution and Environmental Studies, Volume II - Appendices.

Science.gov (United States)

Hershey, John T., Ed.; And Others

This publication, Volume II of a two volume set of water pollution studies, contains seven appendices which support the studies. Appendix 1, Water Quality Parameters, consolidates the technical aspects of water quality including chemical, biological, computer program, and equipment information. Appendix 2, Implementation, outlines techniques…
Lawrence Berkeley National Laboratory 1995 site environmental report: Volume 2, Data appendix

International Nuclear Information System (INIS)

1996-07-01

Ernest Orlando Lawrence Berkeley National Laboratory presents Volume II, Data Appendix as a reference document to supplement the 1995 Site Environmental Report. Volume II contains the raw environmental monitoring and sampling data used to generate many of the summary results included in the main report. Supplemental data is provided for sitewide activities involving the media of stack and ambient air quality, rainwater, surface water, stormwater, wastewater, and soil and sediment. Volume II also contains supplemental data on the special preoperational monitoring study for the new Hazardous Waste Handling Facility. The Table of Contents provides a cross-reference to the data tables of the main report and this appendix. Data are given in System International (SI) units
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.
Global Spent Fuel Logistics Systems Study (GSFLS). Volume 2A. GSFLS visit findings (appendix). Interim report

International Nuclear Information System (INIS)

1978-01-01

This appendix is a part of the interim report documentation for the Global Spent Fuel Logistics System (GSFLS) study. This appendix provides the legal/regulatory reference material, supportive of Volume 2 - GSFLS Visit Finding and Evaluations; and certain background material on British Nuclear Fuel Limited
Stirling Space Engine Program. Volume 2; Appendixes A, B, C and D

Science.gov (United States)

Dhar, Manmohan

1999-01-01

The objective of this program was to develop the technology necessary for operating Stirling power converters in a space environment and to demonstrate this technology in full-scale engine tests. Volume 2 of the report includes the following appendices: Appendix A: Heater Head Development (Starfish Heater Head Program, 1/10th Segment and Full-Scale Heat Pipes, and Sodium Filling and Processing); Appendix B: Component Test Power Converter (CTPC) Component Development (High-temperature Organic Materials, Heat Exchanger Fabrication, Beryllium Issues, Sodium Issues, Wear Couple Tests, Pressure Boundary Penetrations, Heating System Heaters, and Cooler Flow Test); Appendix C: Udimet Testing (Selection of the Reference Material for the Space Stirling Engine Heater Head, Udimet 720LI Creep Test Result Update, Final Summary of Space Stirling Endurance Engine Udimet 720L1 Fatigue Testing Results, Udimet 720l1 Weld Development Summary, and Udimet 720L1 Creep Test Final Results Summary), and Appendix D: CTPC Component Development Photos.
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.
Global Spent Fuel Logistics Systems Study (GSFLS). Volume 2A. GSFLS visit findings (appendix). Interim report

Energy Technology Data Exchange (ETDEWEB)

None

1978-01-31

This appendix is a part of the interim report documentation for the Global Spent Fuel Logistics System (GSFLS) study. This appendix provides the legal/regulatory reference material, supportive of Volume 2 - GSFLS Visit Finding and Evaluations; and certain background material on British Nuclear Fuel Limited (BNFL).
Stratified charge rotary engine critical technology enablement. Volume 2: Appendixes

Science.gov (United States)

Irion, C. E.; Mount, R. E.

1992-01-01

This second volume of appendixes is a companion to Volume 1 of this report which summarizes results of a critical technology enablement effort with the stratified charge rotary engine (SCRE) focusing on a power section of 0.67 liters (40 cu. in.) per rotor in single and two rotor versions. The work is a continuation of prior NASA Contracts NAS3-23056 and NAS3-24628. Technical objectives are multi-fuel capability, including civil and military jet fuel and DF-2, fuel efficiency of 0.355 Lbs/BHP-Hr. at best cruise condition above 50 percent power, altitude capability of up to 10Km (33,000 ft.) cruise, 2000 hour TBO and reduced coolant heat rejection. Critical technologies for SCRE's that have the potential for competitive performance and cost in a representative light-aircraft environment were examined. Objectives were: the development and utilization of advanced analytical tools, i.e. higher speed and enhanced three dimensional combustion modeling; identification of critical technologies; development of improved instrumentation; and to isolate and quantitatively identify the contribution to performance and efficiency of critical components or subsystems. A family of four-stage third-order explicit Runge-Kutta schemes is derived that required only two locations and has desirable stability characteristics. Error control is achieved by embedding a second-order scheme within the four-stage procedure. Certain schemes are identified that are as efficient and accurate as conventional embedded schemes of comparable order and require fewer storage locations.

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

Energy Technology Data Exchange (ETDEWEB)

None

1982-01-01

Report XI, Technical Audit, is a compendium of research material used during the Initial Effort in making engineering comparisons and decisions. Volumes 4 and 5 of Report XI present those studies which provide a Critical Review of the Design Basis. The Critical Review Report, prepared by Intercontinental Econergy Associates, Inc., summarizes findings from an extensive review of the data base for the H-Coal process design. Volume 4 presents this review and assessment, and includes supporting material; specifically, Design Data Tabulation (Appendix A), Process Flow Sheets (Appendix B), and References (Appendix C). Volume 5 is a continuation of the references of Appendix C. Studies of a proprietary nature are noted and referenced, but are not included in these volumes. They are included in the Limited Access versions of these reports and may be reviewed by properly cleared personnel in the offices of Ashland Synthetic Fuels, Inc.
Nuclear powerplant standardization: light water reactors. Volume 2. Appendixes

International Nuclear Information System (INIS)

1981-06-01

This volume contains working papers written for OTA to assist in preparation of the report, NUCLEAR POWERPLANT STANDARDIZATION: LIGHT WATER REACTORS. Included in the appendixes are the following: the current state of standardization, an application of the principles of the Naval Reactors Program to commercial reactors; the NRC and standardization, impacts of nuclear powerplant standardization on public health and safety, descriptions of current control room designs and Duke Power's letter, Admiral Rickover's testimony, a history of standardization in the NRC, and details on the impact of standardization on public health and safety
Data summary of municipal solid waste management alternatives. Volume 4, Appendix B: RDF technologies

Energy Technology Data Exchange (ETDEWEB)

None

1992-10-01

This appendix contains background information, technical descriptions, economic data, mass and energy balances, and information on environmental releases for the refuse derived fuels (RDF) option in municipal solid waste management alternatives. Demonstration programs at St. Louis, Missouri; Franklin, Ohio; and Delaware are discussed. Information on pellet production and cofiring with coal is also presented.
The Fukushima Daiichi Accident. Technical Volume 4/5. Radiological Consequences. 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
No-migration variance petition. Volume 3, Revision 1: Appendix B, Attachments A through D

Energy Technology Data Exchange (ETDEWEB)

1990-03-01

Volume III contains the following attachments: TRUPACT-II content codes (TRUCON); TRUPACT-II chemical list; chemical compatibility analysis for Rocky Flats Plant waste forms (Appendix 2.10.12 of TRUPACT-II safety analysis report); and chemical compatibility analyses for waste forms across all sites.
Analysis and forecast of electrical distribution system materials. Final report. Volume III. Appendix

Energy Technology Data Exchange (ETDEWEB)

Love, C G

1976-08-23

These appendixes are referenced in Volume II of this report. They contain the detailed electrical distribution equipment requirements and input material requirements forecasts. Forecasts are given for three electric energy usage scenarios. Also included are data on worldwide reserves and demand for 30 raw materials required for the manufacture of electrical distribution equipment.
Ground-water monitoring compliance projects for Hanford Site facilities: Progress report, January 1-March 31, 1988: Volume 3, Appendix A

International Nuclear Information System (INIS)

1988-05-01

This appendix is one of nine volumes, and presents data describing wells completed at the Hanford Site during the fourth quarter of calendar year 1987 (October through December). The data in this volume of Appendix A cover the following wells: 299-E32-2; 299-E32-3; 299-E32-4; 299-E33-28; 299-E33-29. The data are presented in the following order: Well Completion Report/Title III Inspection List, Inspection Plan, As-Built Diagram, Logging Charts, and Drill Logs
32 CFR Appendix D to Part 286 - DD Form 2086-1, “Record of Freedom of Information (FOI) Processing Cost for Technical Data”

Science.gov (United States)

2010-07-01

... 32 National Defense 2 2010-07-01 2010-07-01 false DD Form 2086-1, âRecord of Freedom of Information (FOI) Processing Cost for Technical Dataâ D Appendix D to Part 286 National Defense Department of... FREEDOM OF INFORMATION ACT PROGRAM REGULATION Pt. 286, App. D Appendix D to Part 286—DD Form 2086-1...
Hydrogeology of the 200 Areas low-level burial grounds: An interim report: Volume 2, Appendixes

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 form 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. Volume 1 contains the main text. This Volume contains the appendixes, including data and supporting information that verify content and results found in the main text.
International Linear Collider Technical Design Report (Volumes 1 through 4)

Energy Technology Data Exchange (ETDEWEB)

Harrison M.

2013-03-27

The design report consists of four volumes: Volume 1, Executive Summary; Volume 2, Physics; Volume 3, Accelerator (Part I, R and D in the Technical Design Phase, and Part II, Baseline Design); and Volume 4, Detectors.
Safe operation of critical assemblies and research reactors. Code of practice and Technical appendix. 1971 ed

International Nuclear Information System (INIS)

Cox, J.

1971-01-01

This book is in two parts. The first is a Code of Practice for the Safe Operation of Critical Assemblies and Research Reactors, prepared as a result of a meeting of experts which took place in Vienna on 20-24 May 1968. The Code has been prepared by the International Atomic Energy Agency in co-operation with the World Health Organization, and its publication is sponsored by both organizations. In addition, the Code was approved by the Board of Governors of the International Atomic Energy Agency on 16 December 1968 as part of the Agency's safety standards, which are applied to operations undertaken by Member States with the assistance of the Agency. The Board, in approving the publication of the present book, also recommended Member States to take the Code into account in the formulation of national regulations and recommendations. The second part of the book is a Technical Appendix to give information and illustrative samples that would be helpful in implementing the Code of Practice. This second part, although published under the same cover, is not part of the Code. An extensive Bibliography, amplifying the Technical Appendix, is included at the end.
Programs of Study as a State Policy Mandate: A Longitudinal Study of the South Carolina Personal Pathways to Success Initiative. Technical Appendix B

Science.gov (United States)

Hammond, Cathy; Drew, Sam F.; Withington, Cairen; Griffith, Cathy; Swiger, Caroline M.; Mobley, Catherine; Sharp, Julia L.; Stringfield, Samuel C.; Stipanovic, Natalie; Daugherty, Lindsay

2013-01-01

This Technical Appendix discusses how researchers from the National Research Center for Career and Technical Education (NRCCTE) conducted the five-year longitudinal study of South Carolina's Personal Pathway to Success initiative, which was authorized by the state's Education and Economic Development Act (EEDA) in 2005, and how they defined and…
The Fukushima Daiichi Accident. Technical Volume 3/5. Emergency Preparedness and Response. 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
Ground-water monitoring compliance projects for Hanford site facilities: Progress report for the period, January 1-March 31, 1988: Volume 6, Appendix (contd)

International Nuclear Information System (INIS)

1988-05-01

This appendix is one of nine volumes, and presents data describing wells completed at the Hanford Site during the fourth quarter of calendar year 1987 (October through December). The data in this volume of Appendix B cover the following wells: 299-W7-5; 299-W7-6; 299-W8-1; 299-W9-1; 299-W10-13. The data are presented in the following order: Well Completion Report/Title III Inspection List, Inspection Plan, As-Built Diagram, Logging Charts, and Drill Logs
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
The Fukushima Daiichi Accident. Technical Volume 4/5. Radiological Consequences

International Nuclear Information System (INIS)

2015-08-01

This technical volume describes the consequences associated with radioactivity and radiation from the accident at the Fukushima Daiichi nuclear power plant (NPP) for people and the environment. A number of international organizations have already issued reports on the potential health and environmental consequences of the accident, notably the World Health Organization (WHO) and the United Nations Scientific Committee on the Effects of Atomic Radiation (UNSCEAR). The intention of the assessments presented in this volume is to build on their work, using more recent data where available. Quantitative information arising from both personal and environmental monitoring has been provided by the Government of Japan. Section 4.1 provides the best estimates of the magnitude and form of radioactive releases during the accident to the atmosphere and directly into the surrounding sea. It also explains the movement of the discharged radionuclides through air and water and the eventual deposition of the atmospheric activity on land in Japan and other countries worldwide, as well as on the open oceans. The goal is to provide a consolidated repository of information on releases to, and levels of radionuclides in, the environment. Some of this information is used in the analyses in subsequent sections of this volume. Section 4.2 gives an overview of exposures to the main groups of emergency workers at the Fukushima Daiichi NPP, to groups of off-site workers and to members of the public. Where sufficient data are available, average effective dose and thyroid equivalent doses derived from personal measurements are compared with the results of previous assessments for specific locations, population groups and time periods. Section 4.3 summarizes relevant aspects of the system of radiation protection in place at the time of the accident. It includes an overview of the legislation and guidance used to implement the radiation protection framework in Japan. This section also provides a
Advanced Concepts of Naval Engineering Maintenance Training. Volume 2. Appendix F

Science.gov (United States)

1976-05-01

maintenance instruction, the Hagan Automatic Boiler Control (ABC) course. These job requirements also included the tasks, skills, and knowledges for all...Pressure 1 3/4 NAVTRAEQÜIPCEN 74-C-0151-1 TABLE OF CONTENTS VOLUME II OF II APPENDIX F Page Hagan Automatic Boiler Controls Systems (FAS) 6...a c a ■* w ■H u 0 M « s? u ’• B n J-riH 3 o c 0 hhO a a o -i •H -I 0 -H 9J ■ a a oi « C -a u <rl « vi) •a - 8 ai >> u u
Ground-water monitoring compliance projects for Hanford site facilities: Progress report for the period January 1 to March 31, 1988: Volume 5, Appendix B

Energy Technology Data Exchange (ETDEWEB)

None

1988-05-01

This appendix is one of nine volumes, and presents data describing wells completed at the Hanford Site during the fourth quarter of calendar year 1987 (October through December). The data in this volume of Appendix B cover the following wells: 299-W6-2; 299-W7-1; 299-W7-2; 299-W7-3; 299-W7-4. The data are presented in the following order: Well Completion Report/Title III Inspection List, Inspection Plan, As-Built Diagram, Logging Charts, and Drill Logs.
Ground-water monitoring compliance projects for Hanford site facilities: Progress report for the period, January 1-March 31, 1988: Volume 6, Appendix B (contd)

Energy Technology Data Exchange (ETDEWEB)

1988-05-01

This appendix is one of nine volumes, and presents data describing wells completed at the Hanford Site during the fourth quarter of calendar year 1987 (October through December). The data in this volume of Appendix B cover the following wells: 299-W7-5; 299-W7-6; 299-W8-1; 299-W9-1; 299-W10-13. The data are presented in the following order: Well Completion Report/Title III Inspection List, Inspection Plan, As-Built Diagram, Logging Charts, and Drill Logs.

Ground-water monitoring compliance projects for Hanford site facilities: Progress report for the period January 1 to March 31, 1988: Volume 7, Appendix B (contd)

Energy Technology Data Exchange (ETDEWEB)

1988-05-01

This appendix is one of nine volumes, and presents data describing wwlls completed at the Hanford Site during the fourth quarter of calendar year 1987 (October through December). The data in this volume of Appendix B cover the following wells: 299-W10-14; 299-W15-15; 299-W15-16; 299-W15-17; 299-W15-18. The data are presented in the following order: Well Completion Report/Title III Inspection List, Inspection Plan, As-Built Diagram, Logging Charts, and Drill Logs.
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
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
Ground-water monitoring compliance projects for Hanford site facilities: Progress report for the period January 1 to March 31, 1988: Volume 4, Appendix A (contd)

Energy Technology Data Exchange (ETDEWEB)

1988-05-01

This appendix is one of nine volumes, and presents data describing wells completed at the Hanford Site during the fourth quarter of calendar year 1987 (October through December). The data in this volume of Appendix A cover the following wells: 299-E33-30; 299-E34-2; 299-E34-3; 299-E34-4; 299-E34-5; 299-E34-6. The data are presented in the following order: Well Completion Report/Title III Inspection List, Inspection Plan, As-Built Diagram, Logging Charts, and Drill Logs.
Technical Specifications, South Texas Project, Unit No. 1 (Docket No. 50-498): Appendix ''A'' to License No. NPF-76

International Nuclear Information System (INIS)

1988-03-01

The South Texas Project, Unit No. 1, Technical Specifications were prepared by the US Nuclear Regulatory Commission to set forth the limits, operating conditions, and other requirements applicable to a nuclear reactor facility as set forth in Section 50.36 of 10 CFR 50 for the protection of the health and safety of the public. This report is Appendix A to License No. NPF-76
Preliminary thermal and thermomechanical modeling for the near surface test facility heater experiments at Hanford. Volume II: Appendix D

International Nuclear Information System (INIS)

Chan, T.; Remer, J.S.

1978-12-01

Appendix D is a complete set of figures illustrating the detailed calculations necessary for designing the heater experiments at the Near Surface Test Facility (NSTF) at Hanford, Washington. The discussion of the thermal and thermomechanical modeling that yielded these calculations is presented in Volume 1. A summary of the figures and the models they illustrate is given in table D1. The most important figures have also been included in the discussion in Volume 1, and Table D2 lists the figure numbers in this volume that correspond to figure numbers used there
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
Laboratory Evaluation of In Situ Chemical Oxidation for Groundwater Remediation, Test Area North, Operable Unit 1-07B, Idaho National Engineering and Environmental Laboratory, Volume Three - Appendix F

Energy Technology Data Exchange (ETDEWEB)

Cline, S.R.; Denton, D.L.; Giaquinto, J.M.; McCracken, M.K.; Starr, R.C.

1999-04-01

This appendix supports the results and discussion of the laboratory work performed to evaluate the feasibility of in situ chemical oxidation for Idaho National Environmental and Engineering Laboratory's (INEEL) Test Area North (TAN) which is contained in ORNL/TM-13711/V1. This volume contains Appendix F. Appendix F is essentially a photocopy of the ORNL researchers' laboratory notebooks from the Environmental Sciences Division (ESD) and the Radioactive Materials Analytical Laboratory (RMAL).
Industrial Sector Technology Use Model (ISTUM): industrial energy use in the United States, 1974-2000. Volume 3. Appendix on service and fuel demands. Final report

Energy Technology Data Exchange (ETDEWEB)

1979-10-01

This book is the third volume of the ISTUM report. The first volume of the report describes the primary model logic and the model's data inputs. The second volume lists and evaluates the results of one model run. This and the fourth volume give supplementary information in two sets of model data - the energy consumption base and technology descriptions. Chapter III of Vol. I, Book 1 describes the ISTUM demand base and explains how that demand base was developed. This volume serves as a set of appendices to that chapter. The chapter on demands in Vol. I describes the assumptions and methodology used in constructing the ISTUM demand base; this volume simply lists tables of data from that demand base. This book divides the demand tables into two appendices. Appendix III-1 contains detailed tables on ISTUM fuel-consumption estimates, service-demand forecasts, and size and load-factor distributions. Appendix III-2 contains tables detailing ISTUM allocations of each industry's fuel consumption to service sectors. The tables show how the ECDB was used to develop the ISTUM demand base.
Technical and economic feasibility study of enhanced oil recovery in six Colombian fields. Appendix C. Export trade information

Energy Technology Data Exchange (ETDEWEB)

1986-09-01

The primary objectives of the study were to determine which of the reservoirs in the principal fields were amenable to enhanced oil recovery (EOR) processes, to evaluate which process was the most effective from both a technical and economic point of view, and to propose the steps required to further investigate the recommended EOR methods at the laboratory and field (pilot) level. Appendix C is divided into three sections: (A) Casabe Field; (B) La Cira Field; and (C) Tibu-Barco.
Validation of the Cumberland Energyplex concept. Volume 3. Appendixes. Final report

Energy Technology Data Exchange (ETDEWEB)

Barkhordar, P.M.; Crooks, G.; Martin, P.J.

1979-06-01

This volume contains brief appendixes of three types: (1) some topics, although their analyses were not directly requested in the contract work statement, are examined because they are central to determining the validity of the Energyplex concept (e.g., socioeconomic effects and anaerobic digestion of animal wastes to recovery energy). (2) Methane from Illinois coal beds is discussed as a potential energy resource; however detailed analysis has been prevented by the paucity of necessary geological data. (3) Those Energyplex elements whose brief examination revealed some barrier are noted. For example, recovering energy from the relatively small amount of municipal waste generated by Charleston and Mattoon shows no economic promise, and cement production in the southeast quadrant of Illinois appears to be limited by inadequate quantities of limestone of the proper quality.
Recovery of Navy distillate fuel from reclaimed product. Volume II. Literature review

Energy Technology Data Exchange (ETDEWEB)

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

1984-11-01

In an effort to assist the Navy to better utilize its waste hydrocarbons, NIPER, with support from the US Department of Energy, is conducting research designed to ultimately develop a practical technique for converting Reclaimed Product (RP) into specification Naval Distillate Fuel (F-76). This first phase of the project was focused on reviewing the literature and available information from equipment manufacturers. The literature survey has been carefully culled for methodology applicable to the conversion of RP into diesel fuel suitable for Navy use. Based upon the results of this study, a second phase has been developed and outlined in which experiments will be performed to determine the most practical recycling technologies. It is realized that the final selection of one particular technology may be site-specific due to vast differences in RP volume and available facilities. A final phase, if funded, would involve full-scale testing of one of the recommended techniques at a refueling depot. The Phase I investigations are published in two volumes. Volume 1, Technical Discussion, includes the narrative and Appendices I and II. Appendix III, a detailed Literature Review, includes both a narrative portion and an annotated bibliography containing about 800 references and abstracts. This appendix, because of its volume, has been published separately as Volume 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.
Draft 1992 Resource Program : Technical Report.

Energy Technology Data Exchange (ETDEWEB)

United States. Bonneville Power Administration.

1992-01-01

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

Energy Technology Data Exchange (ETDEWEB)

United States. Bonneville Power Administration.

1992-01-01

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

International Nuclear Information System (INIS)

1992-12-01

This appendix to the main report entitled ''Exposition Concerning Small Windmills'' includes background information on the report, profiles of the participating companies and of those visited in Denmark and abroad, questionnaires and interview schemes sent to the participating companies, surveys of producers of Danish and foreign producers of small windmills and an appendix to the economical calculations found within the report. (AB)
Analysis of internal events for the Unit 1 of the Laguna Verde Nuclear Power Station. Appendixes

International Nuclear Information System (INIS)

Huerta B, A.; Lopez M, R.

1995-01-01

This volume contains the appendices for the accident sequences analysis for those internally initiated events for Laguna Verde Unit 1, Nuclear Power Plant. The appendix A presents the comments raised by the Sandia National Laboratories technical staff as a result of the review of the Internal Event Analysis for Laguna Verde Unit 1 Nuclear Power Plant. This review was performed during a joint Sandia/CNSNS multi-day meeting by the end 1992. Also included is a brief evaluation on the applicability of these comments to the present study. The appendix B presents the fault tree models printed for each of the systems included and.analyzed in the Internal Event Analysis for LVNPP. The appendice C presents the outputs of the TEMAC code, used for the cuantification of the dominant accident sequences as well as for the final core damage evaluation. (Author)
Analysis of internal events for the Unit 1 of the Laguna Verde Nuclear Power Station. Appendixes

International Nuclear Information System (INIS)

Huerta B, A.; Lopez M, R.

1995-01-01

This volume contains the appendices for the accident sequences analysis for those internally initiated events for Laguna Verde Unit 1, Nuclear Power Plant. The appendix A presents the comments raised by the Sandia National Laboratories technical staff as a result of the review of the Internal Event Analysis for Laguna Verde Unit 1 Nuclear Power Plant. This review was performed during a joint Sandia/CNSNS multi-day meeting by the end 1992. Also included is a brief evaluation on the applicability of these comments to the present study. The appendix B presents the fault tree models printed for each of the systems included and analyzed in the Internal Event Analysis for LVNPP. The appendice C presents the outputs of the TEMAC code, used for the cuantification of the dominant accident sequences as well as for the final core damage evaluation. (Author)
Benefit-Cost Analysis of Integrated Paratransit Systems : Volume 6. Technical Appendices.

Science.gov (United States)

1979-09-01

This last volume, includes five technical appendices which document the methodologies used in the benefit-cost analysis. They are the following: Scenario analysis methodology; Impact estimation; Example of impact estimation; Sensitivity analysis; Agg...
Pollutant Assessments Group procedures manual: Volume 2, Technical procedures

Energy Technology Data Exchange (ETDEWEB)

1992-03-01

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

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

International Nuclear Information System (INIS)

1995-04-01

This report documents the results of the combined effort of the NRC and the industry to produce improved Standard Technical Specifications (STS), Revision 1 for Combustion Engineering Plants. The changes reflected in Revision 1 resulted from the experience gained from license amendment applications to convert to these improved STS or to adopt partial improvements to existing technical specifications. This NUREG is the result of extensive public technical meetings and discussions between the Nuclear Regulatory Commission (NRC) staff and various nuclear power plant licensees, Nuclear Steam Supply System (NSSS) Owners Groups, NSSS vendors, and the Nuclear Energy Institute (NEI). The improved STS were developed based on the criteria in the Final Commission Policy Statement on Technical Specifications Improvements for Nuclear Power Reactors, dated July 22, 1993. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. Volume 1 contains the Specifications for all chapters and sections of the improved STS. Volume 2 contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1--3.3 of the improved STS Volume 3 contains the Bases for Sections 3.4--3.9 of the improved STS
Remedial investigation report on Waste Area Grouping 5 at Oak Ridge National Laboratory, Oak Ridge, Tennessee. Volume 2, Appendix A: Characterization methods and data summary

International Nuclear Information System (INIS)

1995-03-01

This appendix presents background regulatory and technical information regarding the solid waste management units (SWMUs) at Waste Area Grouping (WAG) 5 to address requirements established by the Federal Facility Agreement (FFA) for the Oak Ridge Reservation (ORR). The Department of energy (DOE) agreed to conduct remedial investigations (RIs) under the FFA at various sites at Oak Ridge National Laboratory (ORNL), including SWMUs and other areas of concern on WAG 5. The appendix gives an overview of the regulatory background to provide the context in which the WAG 5 RI was planned and implemented and documents how historical sources of data, many of which are SWMU-specific, were evaluated and used
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.
Technical Safety Appraisal of the Rocky Flats Plant

Energy Technology Data Exchange (ETDEWEB)

Brown, Blake P.

1989-01-01

This report provides the results of a Technical Safety Appraisal (TSA) of the Rocky Flats Plant (RFP) conducted November 14 to 18 and November 28 to December 9, 1988. This appraisal covered the effectiveness and improvements in the RFP safety program across the site, evaluating progress to date against standards of accepted practice. The appraisal included coverage of the timeliness and effectiveness of actions taken in response to the recommendations/concerns in three previous Technical Safety Appraisals (TSAs) of RFP Bldg. 707 conducted in July 1986, Bldgs. 771/774 conducted in October/November 1986, and Bldgs. 776/777 conducted in January/February 1988. Results of this appraisal are given in Section IV for each of 14 technical safety areas at RFP. These results include a discussion, conclusions and any new safety concerns for each technical safety area. Appendix A contains a description of the system for categorizing concerns, and the concerns are tabulated in Appendix B. Appendix C reports on the evaluation of the contractor's actions and the current status of each of the 230 recommendations and concerns contained in the three previous TSA reports.
Gas Reactor International Cooperative program. Pebble bed reactor plant: screening evaluation. Volume 3. Appendix A. Equipment list

International Nuclear Information System (INIS)

1979-11-01

This report consists of three volumes which describe the design concepts and screening evaluation for a 3000 MW(t) Pebble Bed Reactor Multiplex Plant (PBR-MX). The Multiplex plant produces both electricity and transportable chemical energy via the thermochemical pipeline (TCP). The evaluation was limited to a direct cycle plant which has the steam generators and steam reformers in the primary circuit. Volume 1 reports the overall plant and reactor system and was prepared by the General Electric Company. Core scoping studies were performed which evaluated the effects of annular and cylindrical core configurations, radial blanket zones, burnup, and ball heavy metal loadings. The reactor system, including the PCRV, was investigated for both the annular and cylindrical core configurations. Volume 3 is an Appendix containing the equipment list for the plant and was also prepared by United Engineers and Constructors, Inc. It tabulates the major components of the plant and describes each in terms of quantity, type, orientation, etc., to provide a basis for cost estimation
Descriptions of reference LWR facilities for analysis of nuclear fuel cycles. Appendixes

International Nuclear Information System (INIS)

Schneider, K.J.; Kabele, T.J.

1979-09-01

The appendixes present the calculations that were used to derive the release factors discussed for each fuel cycle facility in Volume I. Appendix A presents release factor calculations for a surface mine, underground mine, milling facility, conversion facility, diffusion enrichment facility, fuel fabrication facility, PWR, BWR, and reprocessing facility. Appendix B contains additional release factors calculated for a BWR, PWR, and a reprocessing facility. Appendix C presents release factors for a UO 2 fuel fabrication facility
Standard technical specifications: Babcock and Wilcox plants. Volume 3, Revision 1: Bases (Sections 3.4--3.9)

International Nuclear Information System (INIS)

1995-04-01

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

Energy Technology Data Exchange (ETDEWEB)

1994-06-01

The US Department of Energy (DOE) has prepared this report to assist its management in making two decisions. The first decision, which is programmatic, is to determine the management program for DOE spent nuclear fuel. The second decision is on the future direction of environmental restoration, waste management, and spent nuclear fuel management activities at the Idaho National Engineering Laboratory. Volume 1 of the EIS, which supports the programmatic decision, considers the effects of spent nuclear fuel management on the quality of the human and natural environment for planning years 1995 through 2035. DOE has derived the information and analysis results in Volume 1 from several site-specific appendixes. Volume 2 of the EIS, which supports the INEL-specific decision, describes environmental impacts for various environmental restoration, waste management, and spent nuclear fuel management alternatives for planning years 1995 through 2005. This Appendix B to Volume 1 considers the impacts on the INEL environment of the implementation of various DOE-wide spent nuclear fuel management alternatives. The Naval Nuclear Propulsion Program, which is a joint Navy/DOE program, is responsible for spent naval nuclear fuel examination at the INEL. For this appendix, naval fuel that has been examined at the Naval Reactors Facility and turned over to DOE for storage is termed naval-type fuel. This appendix evaluates the management of DOE spent nuclear fuel including naval-type fuel.
Performance evaluation of the technical capabilities of DOE sites for disposal of mixed low-level waste. Volume 2: Technical basis and discussion of results

International Nuclear Information System (INIS)

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

1996-03-01

A team of analysts designed and conducted a performance evaluation to estimate the technical capabilities of fifteen Department of Energy sites for disposal of mixed low-level waste (i.e., waste that contains both low-level radioactive materials and hazardous constituents). Volume 1 summarizes the process for selecting the fifteen sites, the methodology used in the evaluation, and the conclusions derived from the evaluation. Volume 2 first describes the screening process used to determine the sites to be considered in the PEs. This volume then provides the technical details of the methodology for conducting the performance evaluations. It also provides a comparison and analysis of the overall results for all sites that were evaluated. Volume 3 contains detailed evaluations of the fifteen sites and discussions of the results for each site
Technical support for GEIS: radioactive waste isoltaion in geologic formations. Volume 19. Thermal analyses

International Nuclear Information System (INIS)

1978-04-01

This volume, Y/OWI/TM-36/19, ''Thermal Analyses,'' is one of a 23-volume series, ''Technical Support for GEIS: Radioactive Waste Isolation in Geologic Formations,'' Y/OWI/TM-36, which supplements the ''Contribution to Draft Generic Environmental Impact Statement on Commercial Waste Management: Radioactive Waste Isolation in Geologic Formations,'' Y/OWI/TM-44. The series provides a more complete technical basis for the preconceptual designs, resource requirements, and environmental source terms associated with isolating commercial LWR wastes in underground repositories in salt, granite, shale and basalt. Wastes are considered from three fuel cycles: uranium and plutonium recycling, no recycling of spent fuel and uranium-only recycling. This volume discusses the thermal impacts of the isolated high level and spent-fuel wastes in geologic formations. A detailed account of the methodologies employed is given as well as selected results of the analyses
Advanced transportation system studies technical area 3: Alternate propulsion subsystem concepts, volume 3

Science.gov (United States)

Levak, Daniel

1993-01-01

The objective of this contract was to provide definition of alternate propulsion systems for both earth-to-orbit (ETO) and in-space vehicles (upper stages and space transfer vehicles). For such propulsion systems, technical data to describe performance, weight, dimensions, etc. was provided along with programmatic information such as cost, schedule, needed facilities, etc. Advanced technology and advanced development needs were determined and provided. This volume separately presents the various program cost estimates that were generated under three tasks: the F-1A Restart Task, the J-2S Restart Task, and the SSME Upper Stage Use Task. The conclusions, technical results, and the program cost estimates are described in more detail in Volume 1 - Executive Summary and in individual Final Task Reports.
Standard Technical Specifications General Electric plants, BWR/4:Bases (Sections 3.4-3.10). Volume 3, Revision 1

International Nuclear Information System (INIS)

1995-04-01

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

International Nuclear Information System (INIS)

1995-04-01

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

International Nuclear Information System (INIS)

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

1995-06-01

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

Energy Technology Data Exchange (ETDEWEB)

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

1995-06-01

The work documented in this report was performed in support of the US Nuclear Regulatory Commission to examine the technical basis for candidate guidelines that could be considered in reviewing and evaluating high integrity computer e following software development and assurance activities: Requirements specification; design; coding; verification and validation, inclukding static analysis and dynamic testing; safety analysis; operation and maintenance; configuration management; quality assurance; and planning and management. Each activity (framework element) was subdivided into technical areas (framework subelements). The report describes the development of approximately 200 candidate guidelines that span the entire ran e identification, categorization and prioritization of technical basis for those candidate guidelines; and the identification, categorization and prioritization of research needs for improving the technical basis. The report has two volumes: Volume 1, Executive Summary includes an overview of the framwork and of each framework element, the complete set of candidate guidelines, the results of the assessment of the technical basis for each candidate guideline, and a discussion of research needs that support the regulatory function; this document, Volume 2, is the main report.
Global Spent Fuel Logistics Systems Study (GSFLS). Volume 3A. GSFLS technical analysis (appendix). Interim report

International Nuclear Information System (INIS)

1978-01-01

This report is a part of the interim report documentation for the Global Spent Fuel Logistics System (GSFLS) study. The technical and financial considerations underlying a global spent fuel logistics systems have been studied and are reported. The Pacific Basin is used as a model throughout this report; however the stated methodology and, in many cases, considerations and conclusions are applicable to other global regions. Spent fuel discharge profiles for Pacific Basin Countries were used to determine the technical systems requirements for alternative concepts. Functional analyses and flows were generated to define both system design requirements and logistics parameters. A technology review was made to ascertain the state-of-the-art of relevant GSFLS technical systems. Modular GSFLS facility designs were developed using the information generated from the functional analysis and technology review. The modular facility designs were used as a basis for siting and cost estimates for various GSFLS alternatives. Various GSFLS concepts were analyzed from a financial and economic perspective in order to provide total concepts costs and ascertain financial and economic sensitivities to key GSFLS variations. Results of the study include quantification of GSFLS facility and hardware requirements; drawings of relevant GSFLS facility designs; system cost estimates; financial reports - including user service charges; and comparative analyses of various GSFLS alternatives
Global Spent Fuel Logistics Systems Study (GSFLS). Volume 3A. GSFLS technical analysis (appendix). Interim report

Energy Technology Data Exchange (ETDEWEB)

Kriger, A.

1978-01-31

This report is a part of the interim report documentation for the Global Spent Fuel Logistics System (GSFLS) study. The technical and financial considerations underlying a global spent fuel logistics systems have been studied and are reported. The Pacific Basin is used as a model throughout this report; however the stated methodology and, in many cases, considerations and conclusions are applicable to other global regions. Spent fuel discharge profiles for Pacific Basin Countries were used to determine the technical systems requirements for alternative concepts. Functional analyses and flows were generated to define both system design requirements and logistics parameters. A technology review was made to ascertain the state-of-the-art of relevant GSFLS technical systems. Modular GSFLS facility designs were developed using the information generated from the functional analysis and technology review. The modular facility designs were used as a basis for siting and cost estimates for various GSFLS alternatives. Various GSFLS concepts were analyzed from a financial and economic perspective in order to provide total concepts costs and ascertain financial and economic sensitivities to key GSFLS variations. Results of the study include quantification of GSFLS facility and hardware requirements; drawings of relevant GSFLS facility designs; system cost estimates; financial reports - including user service charges; and comparative analyses of various GSFLS alternatives.
Abbreviations [Annex to The Fukushima Daiichi Accident, Technical Volume 5/5

International Nuclear Information System (INIS)

2015-01-01

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

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

Energy Technology Data Exchange (ETDEWEB)

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

1989-04-01

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

International Nuclear Information System (INIS)

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

1995-06-01

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

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 second of a two-volume document that summarizes a joint project by the US Nuclear Regulatory and the Commission of European Communities 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 two-volume report, which examines mechanisms and uncertainties of transfer through the food chain, is the first in a series of five such reports. A panel of sixteen experts was formed to compile credible and traceable uncertainty distributions for food chain transfer that affect calculations of offsite radiological consequences. Seven of the experts reported on transfer into the food chain through soil and plants, nine reported on transfer via food products from animals, and two reported on both. The expert judgment elicitation procedure and its outcomes are described in these volumes. This volume contains seven appendices. Appendix A presents a brief discussion of the MAACS and COSYMA model codes. Appendix B is the structure document and elicitation questionnaire for the expert panel on soils and plants. Appendix C presents the rationales and responses of each of the members of the soils and plants expert panel. Appendix D is the structure document and elicitation questionnaire for the expert panel on animal transfer. The rationales and responses of each of the experts on animal transfer are given in Appendix E. Brief biographies of the food chain expert panel members are provided in Appendix F. Aggregated results of expert responses are presented in graph format in Appendix G.
Probabilistic accident consequence uncertainty analysis: Food chain uncertainty assessment. Volume 2: Appendices

International Nuclear Information System (INIS)

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

1997-06-01

This volume is the second of a two-volume document that summarizes a joint project by the US Nuclear Regulatory and the Commission of European Communities 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 two-volume report, which examines mechanisms and uncertainties of transfer through the food chain, is the first in a series of five such reports. A panel of sixteen experts was formed to compile credible and traceable uncertainty distributions for food chain transfer that affect calculations of offsite radiological consequences. Seven of the experts reported on transfer into the food chain through soil and plants, nine reported on transfer via food products from animals, and two reported on both. The expert judgment elicitation procedure and its outcomes are described in these volumes. This volume contains seven appendices. Appendix A presents a brief discussion of the MAACS and COSYMA model codes. Appendix B is the structure document and elicitation questionnaire for the expert panel on soils and plants. Appendix C presents the rationales and responses of each of the members of the soils and plants expert panel. Appendix D is the structure document and elicitation questionnaire for the expert panel on animal transfer. The rationales and responses of each of the experts on animal transfer are given in Appendix E. Brief biographies of the food chain expert panel members are provided in Appendix F. Aggregated results of expert responses are presented in graph format in Appendix G
Technical Reports (Part I). End of Project Report, 1968-1971, Volume III.

Science.gov (United States)

Western Nevada Regional Education Center, Lovelock.

The pamphlets included in this volume are technical reports prepared as outgrowths of the Student Information Systems of the Western Nevada Regional Education Center (WN-REC) funded by a Title III (Elementary and Secondary Education Act) grant. These reports describe methods of interpreting the printouts from the Student Information System;…
Draft Programmatic Environmental Impact Statement for Stockpile Stewardship and Management: Volume 3, Appendix I, Appendix J, Appendix K

International Nuclear Information System (INIS)

1996-02-01

In response to the end of the Cold War and changes in the world's political regimes, United States is no longer producing new nuclear weapons. Instead, the US nuclear weapons program is reducing the size of the nuclear stockpile by dismantling existing weapons. DOE has been directed to maintain the safety and reliability of the reduced nuclear weapons stockpile in the absence of underground testing. Therefore, DOE has developed a stewardship and management program to provide a single highly integrated technical program. The stockpile stewardship portion of the PEIS evaluates the potential impacts of three proposed facilities: the National Ignition Facility, the Contained Firing facility, and the Atlas Facility. This volume contains appendices for these 3 facilities; alternatives affecting LANL, LLNL, SNL, and NTS are addressed. Impacts on land resources, site infrastructure, air qualaity, water resources, geology and soils, biotic resources, cultural resources, etc., are evaluated. This PEIS presents unclassified information only
Third International Mathematics and Science Study 1999 Video Study Technical Report: Volume 2--Science. Technical Report. NCES 2011-049

Science.gov (United States)

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

2011-01-01

This second volume of the Third International Mathematics and Science Study (TIMSS) 1999 Video Study Technical Report focuses on every aspect of the planning, implementation, processing, analysis, and reporting of the science components of the TIMSS 1999 Video Study. The report is intended to serve as a record of the actions and documentation of…
Tank Waste Remediation System, Hanford Site, Richland, Washington. Final Environmental Impact Statement. Volume VI

International Nuclear Information System (INIS)

1996-08-01

The U.S. Department Of Energy and the Washington State Department of Ecology added Appendix L (Volume 6), Response to Public Comments, to the Tank Waste Remediation System (TWRS) Final Environmental Impact Statement (EIS) for the Hanford Site, Richland, Washington, to fully address and respond to public comments on the Draft EIS. In addition, DOE considered public comments, along with other factors such as programmatic need, short- and long-term impacts, technical feasibility, and cost, in arriving at DOE's preferred alternative. During the public comment period for the Draft EIS, more than 350 individuals, agencies, Tribal Nations, and organizations provided comments. This volume represents a broad spectrum of private citizens; businesses; local, State, and Federal officials; Tribal Nations; and public interest groups
DOE standard: Integration of environment, safety, and health into facility disposition activities. Volume 2: Appendices

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-05-01

This volume contains the appendices that provide additional environment, safety, and health (ES and H) information to complement Volume 1 of this Standard. Appendix A provides a set of candidate DOE ES and H directives and external regulations, organized by hazard types that may be used to identify potentially applicable directives to a specific facility disposition activity. Appendix B offers examples and lessons learned that illustrate implementation of ES and H approaches discussed in Section 3 of Volume 1. Appendix C contains ISMS performance expectations to guide a project team in developing and implementing an effective ISMS and in developing specific performance criteria for use in facility disposition. Appendix D provides guidance for identifying potential Applicable or Relevant and Appropriate Requirements (ARARs) when decommissioning facilities fall under the Comprehensive Environmental Response, Compensation, Liability Act (CERCLA) process. Appendix E discusses ES and H considerations for dispositioning facilities by privatization. Appendix F is an overview of the WSS process. Appendix G provides a copy of two DOE Office of Nuclear Safety Policy and Standards memoranda that form the bases for some of the guidance discussed within the Standard. Appendix H gives information on available hazard analysis techniques and references. Appendix I provides a supplemental discussion to Sections 3.3.4, Hazard Baseline Documentation, and 3.3.6, Environmental Permits. Appendix J presents a sample readiness evaluation checklist.
DOE standard: Integration of environment, safety, and health into facility disposition activities. Volume 2: Appendices

International Nuclear Information System (INIS)

1998-05-01

This volume contains the appendices that provide additional environment, safety, and health (ES and H) information to complement Volume 1 of this Standard. Appendix A provides a set of candidate DOE ES and H directives and external regulations, organized by hazard types that may be used to identify potentially applicable directives to a specific facility disposition activity. Appendix B offers examples and lessons learned that illustrate implementation of ES and H approaches discussed in Section 3 of Volume 1. Appendix C contains ISMS performance expectations to guide a project team in developing and implementing an effective ISMS and in developing specific performance criteria for use in facility disposition. Appendix D provides guidance for identifying potential Applicable or Relevant and Appropriate Requirements (ARARs) when decommissioning facilities fall under the Comprehensive Environmental Response, Compensation, Liability Act (CERCLA) process. Appendix E discusses ES and H considerations for dispositioning facilities by privatization. Appendix F is an overview of the WSS process. Appendix G provides a copy of two DOE Office of Nuclear Safety Policy and Standards memoranda that form the bases for some of the guidance discussed within the Standard. Appendix H gives information on available hazard analysis techniques and references. Appendix I provides a supplemental discussion to Sections 3.3.4, Hazard Baseline Documentation, and 3.3.6, Environmental Permits. Appendix J presents a sample readiness evaluation checklist
Technical Reports (Part II). End of Project Report, 1968-1971, Volume IV.

Science.gov (United States)

Western Nevada Regional Education Center, Lovelock.

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

Energy Technology Data Exchange (ETDEWEB)

None

1982-06-30

Public Law 96-540, Section 213, directs the Secretary of Energy to develop a plan for a cooperative program to provide assistance in the stabilization and management of defense-related uranium mill tailings commingled with other tailings. In developing the plan, the Secretary is further directed to: (1) establish the amount and condition of tailings generated under federal contracts; (2) examine appropriate methodologies for establishing the extent of federal assistance; and (3) consult with the owners and operators of each site. This technical report summarizes US Department of Energy (DOE) and contractor activities in pursuit of items (1), (2), and (3) above. Recommendations regarding policy and a cooperative plan for federal assistance are under separate cover as Volume I.
Technical support for GEIS: radioactive waste isolation in geologic formations. Volume 23. Environmental effluent analyses

International Nuclear Information System (INIS)

1978-04-01

This volume, Y/OWI/TM-36/23, ''Environmental Effluent Analysis,'' is one of a 23-volume series, ''Technical Support for GEIS: Radioactive Waste Isolation in Geologic Formations,'' Y/OWI/TM-36, which supplements the ''Contribution to Drat Generic Environmental Impact Statement on Commercial Waste Management: Radioactive Waste Isolation in Geologic Formations,'' Y/OWI/TM-44. The series provides a more complete technical basis for the preconceptual designs, resource requirements, and environmental source terms associated with isolating commercial LWR wastes in underground repositories in salt, granite, shale and basalt. Wastes are considered from three fuel cycles: uranium and plutonium recycling, no recycling of spent fuel and uranium-only recycling. This volume discusses the releases to the environment of radioactive and non-radioactive materials that arise during facility construction and waste handling operations, as well as releases that could occur in the event of an operational accident. The results of the analyses are presented along with a detailed description of the analytical methodologies employed
Minutes of the IFMIF technical meeting

International Nuclear Information System (INIS)

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

2004-03-01

The IFMIF Technical Meeting was held on December 4-5, 2003 at Shiran-kaikan, Kyoto University. The main objectives are 1) to finalize the Comprehensive Design Report (CDR), 2) to discuss IFMIF cost and organization, 3) to review technical status of major systems, transition phase activities and EVEDA plan. This report presents a brief summary of the results of the meeting. Agenda, participants list and presentation materials are attached as Appendix. (author)
45 CFR Appendix A to Part 1210 - Standard for Examiners

Science.gov (United States)

2010-10-01

... SERVICE VISTA TRAINEE DESELECTION AND VOLUNTEER EARLY TERMINATION PROCEDURES Pt. 1210, App. A Appendix A... administrative, managerial, professional, investigative, or technical work which has demonstrated the possession... and confidence of others. (iii) A good working knowledge of: —The relationship between Volunteer...
Strategic analysis for safeguards systems: a feasibility study. Volume 2. Appendix

International Nuclear Information System (INIS)

Goldman, A.J.

1984-12-01

This appendix provides detailed information regarding game theory (strategic analysis) and its potential role in safeguards to supplement the main body of this report. In particualr, it includes an extensive, though not comprehensive review of literature on game theory and on other topics that relate to the formulation of a game-theoretic model (e.g. the payoff functions). The appendix describes the basic form and components of game theory models, and the solvability of various models. It then discusses three basic issues related to the use of strategic analysis in material accounting: (1) its understandability; (2) its viability in regulatory settings; and (3) difficulties in the use of mixed strategies. Each of the components of a game theoretic model are then discussed and related to the present context
Strategic analysis for safeguards systems: a feasibility study. Volume 2. Appendix

Energy Technology Data Exchange (ETDEWEB)

Goldman, A J

1984-12-01

This appendix provides detailed information regarding game theory (strategic analysis) and its potential role in safeguards to supplement the main body of this report. In particualr, it includes an extensive, though not comprehensive review of literature on game theory and on other topics that relate to the formulation of a game-theoretic model (e.g. the payoff functions). The appendix describes the basic form and components of game theory models, and the solvability of various models. It then discusses three basic issues related to the use of strategic analysis in material accounting: (1) its understandability; (2) its viability in regulatory settings; and (3) difficulties in the use of mixed strategies. Each of the components of a game theoretic model are then discussed and related to the present context.
Remedial investigation report on Waste Area Grouping 5 at Oak Ridge National Laboratory, Oak Ridge, Tennessee. Volume 2 -- Appendix A: Characterization methods and data summary

International Nuclear Information System (INIS)

1995-09-01

This document provides the Environmental Restoration Program with information about the results of investigations performed at Waste Area Grouping (WAG) 5. It includes information on risk assessments that have evaluated long-term impacts to human health and the environment. Information provided in this document forms the basis for decisions regarding the need for subsequent remediation work at WAG 5. This appendix presents background regulatory and technical information regarding the solid waste management units (SWMUs) at WAG 5 to address requirements established by the Federal Facility Agreement (FFA) for the Oak Ridge Reservation (ORR). The US Department of Energy (DOE) agreed to conduct remedial investigations (RIs) under the FFA at various sites at Oak Ridge National Laboratory (ORNL), including SWMUs and other areas of concern on WAG 5. The appendix gives an overview of the regulatory background to provide the context in which the WAG 5 RI was planned and implemented and documents how historical sources of data, many of which are SWMU-specific, were evaluated and used.
45 CFR Appendix A to Part 1211 - Standards for Examiners

Science.gov (United States)

2010-10-01

... SERVICE VOLUNTEER GRIEVANCE PROCEDURES Pt. 1211, App. A Appendix A to Part 1211—Standards for Examiners An..., professional, investigative, or technical work which has demonstrated the possession of: (i) The personal... confidence of others. (iii) A good working knowledge of: The relationship between volunteer administration...
Advanced Transportation System Studies. Technical Area 3: Alternate Propulsion Subsystems Concepts. Volume 3; Program Cost Estimates

Science.gov (United States)

Levack, Daniel J. H.

2000-01-01

The objective of this contract was to provide definition of alternate propulsion systems for both earth-to-orbit (ETO) and in-space vehicles (upper stages and space transfer vehicles). For such propulsion systems, technical data to describe performance, weight, dimensions, etc. was provided along with programmatic information such as cost, schedule, needed facilities, etc. Advanced technology and advanced development needs were determined and provided. This volume separately presents the various program cost estimates that were generated under three tasks: the F- IA Restart Task, the J-2S Restart Task, and the SSME Upper Stage Use Task. The conclusions, technical results , and the program cost estimates are described in more detail in Volume I - Executive Summary and in individual Final Task Reports.

Direct utilization of geothermal energy: a technical handbook

Energy Technology Data Exchange (ETDEWEB)

Anderson, D.N; Lund, J.W. (eds.)

1979-01-01

This technical handbook includes comprehensive discussions on nature and occurrence of the geothermal resource, its development, utilization, economics, financing, and regulation. Information on pricing parameters for the direct use of geothermal energy is included as an appendix. (MRH)
INDOT Technical Training Plan : Appendix H

Science.gov (United States)

2012-04-01

The study provides the background documents necessary for the development of a Technical Training Plan and makes recommendations for the content and structure of such a plan for the District Operations, Operations, Capital Program Management, and Eng...
INDOT Technical Training Plan : Appendix L

Science.gov (United States)

2012-04-01

The study provides the background documents necessary for the development of a Technical Training Plan and makes recommendations for the content and structure of such a plan for the District Operations, Operations, Capital Program Management, and Eng...
INDOT Technical Training Plan : Appendix D

Science.gov (United States)

2012-04-01

The study provides the background documents necessary for the development of a Technical Training Plan and makes recommendations for the content and structure of such a plan for the District Operations, Operations, Capital Program Management, and Eng...
INDOT Technical Training Plan : Appendix A

Science.gov (United States)

2012-04-01

The study provides the background documents necessary for the development of a Technical Training Plan and makes recommendations for the content and structure of such a plan for the District Operations, Operations, Capital Program Management, and Eng...
INDOT Technical Training Plan : Appendix G

Science.gov (United States)

2012-04-01

The study provides the background documents necessary for the development of a Technical Training Plan and makes recommendations for the content and structure of such a plan for the District Operations, Operations, Capital Program Management, and Eng...
INDOT Technical Training Plan : Appendix P

Science.gov (United States)

2012-04-01

The study provides the background documents necessary for the development of a Technical Training Plan and makes recommendations for the content and structure of such a plan for the District Operations, Operations, Capital Program Management, and Eng...
INDOT Technical Training Plan : Appendix I

Science.gov (United States)

2012-04-01

The study provides the background documents necessary for the development of a Technical Training Plan and makes recommendations for the content and structure of such a plan for the District Operations, Operations, Capital Program Management, and Eng...
INDOT Technical Training Plan : Appendix M

Science.gov (United States)

2012-04-01

The study provides the background documents necessary for the development of a Technical Training Plan and makes recommendations for the content and structure of such a plan for the District Operations, Operations, Capital Program Management, and Eng...
INDOT Technical Training Plan : Appendix F

Science.gov (United States)

2012-04-01

The study provides the background documents necessary for the development of a Technical Training Plan and makes recommendations for the content and structure of such a plan for the District Operations, Operations, Capital Program Management, and Eng...
INDOT Technical Training Plan : Appendix E

Science.gov (United States)

2012-04-01

The study provides the background documents necessary for the development of a Technical Training Plan and makes recommendations for the content and structure of such a plan for the District Operations, Operations, Capital Program Management, and Eng...
INDOT Technical Training Plan : Appendix O

Science.gov (United States)

2012-04-01

The study provides the background documents necessary for the development of a Technical Training Plan and makes recommendations for the content and structure of such a plan for the District Operations, Operations, Capital Program Management, and Eng...
INDOT Technical Training Plan : Appendix J

Science.gov (United States)

2012-04-01

The study provides the background documents necessary for the development of a Technical Training Plan and makes recommendations for the content and structure of such a plan for the District Operations, Operations, Capital Program Management, and Eng...
INDOT Technical Training Plan : Appendix K

Science.gov (United States)

2012-04-01

The study provides the background documents necessary for the development of a Technical Training Plan and makes recommendations for the content and structure of such a plan for the District Operations, Operations, Capital Program Management, and Eng...
INDOT Technical Training Plan : Appendix B

Science.gov (United States)

2012-04-01

The study provides the background documents necessary for the development of a Technical Training Plan and makes recommendations for the content and structure of such a plan for the District Operations, Operations, Capital Program Management, and Eng...
INDOT Technical Training Plan : Appendix N

Science.gov (United States)

2012-04-01

The study provides the background documents necessary for the development of a Technical Training Plan and makes recommendations for the content and structure of such a plan for the District Operations, Operations, Capital Program Management, and Eng...
INDOT Technical Training Plan : Appendix C

Science.gov (United States)

2012-04-01

The study provides the background documents necessary for the development of a Technical Training Plan and makes recommendations for the content and structure of such a plan for the District Operations, Operations, Capital Program Management, and Eng...
Technology Demonstration of the Zero Emissions Chromium Electroplating System; Appendix I: CHPPM Report on Air Sampling

National Research Council Canada - National Science Library

Hay, K. J; Maloney, Stephen W; Cannon, John J; Phelps, Max R; Modrell, Jason

2008-01-01

This volume is an Appendix to the main report, Volume 1, which documents the demonstration of a technology developed by PRD, Inc, for control of chromium emissions during hard chromium electroplating...
Comparative assessment of TRU waste forms and processes. Volume II. Waste form data, process descriptions, and costs

International Nuclear Information System (INIS)

Ross, W.A.; Lokken, R.O.; May, R.P.; Roberts, F.P.; Thornhill, R.E.; Timmerman, C.L.; Treat, R.L.; Westsik, J.H. Jr.

1982-09-01

This volume contains supporting information for the comparative assessment of the transuranic waste forms and processes summarized in Volume I. Detailed data on the characterization of the waste forms selected for the assessment, process descriptions, and cost information are provided. The purpose of this volume is to provide additional information that may be useful when using the data in Volume I and to provide greater detail on particular waste forms and processes. Volume II is divided into two sections and two appendixes. The first section provides information on the preparation of the waste form specimens used in this study and additional characterization data in support of that in Volume I. The second section includes detailed process descriptions for the eight processes evaluated. Appendix A lists the results of MCC-1 leach test and Appendix B lists additional cost data. 56 figures, 12 tables
Implementing California's School Funding Formula: Will High-Need Students Benefit? Technical Appendix

Science.gov (United States)

Hill, Laura; Ugo, Iwunze

2015-01-01

Intended to accompany "Implementing California's School Funding Formula: Will High-Need Students Benefit?," this appendix examines the extent to which school shares of high-need students vary relative to their district concentrations by grouping approximately 950 school districts by their share of high-need students, arraying them into…

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

Energy Technology Data Exchange (ETDEWEB)

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

1993-08-01

These Appendices describe various technologies that may be applicable to the Mixed Waste Treatment Plant (MWTP) Chemical/Physical Treatment System (CPTS). These technologies were identified by the CPTS Technical Support Group (TSG) as potentially applicable to a variety of separation, volume reduction, and decontamination requirements. The purpose was to identify all available and developing technologies, and their characteristics, for subsequent evaluation for specific requirements identified for the CPTS. However, the technologies described herein are not necessarily all inclusive, nor are they necessarily all applicable.
Synthesis Gas Demonstration Plant, Baskett, Kentucky: environmental report. [Contains chapter 4 and appendix 4A

Energy Technology Data Exchange (ETDEWEB)

None

1980-01-01

This volume contains chapter 4 and Appendix 4A which include descriptions of use of adjacent land and water (within miles of the proposed site), baseline ecology, air quality, meteorology, noise, hydrology, water quality, geology, soils and socio-economic factors. Appendix 4A includes detailed ecological surveys made in the area including the methods used. (LTN)
The International Linear Collider Technical Design Report - Volume 2: Physics

CERN Document Server

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

2013-01-01

The International Linear Collider Technical Design Report (TDR) describes in four volumes the physics case and the design of a 500 GeV centre-of-mass energy linear electron-positron collider based on superconducting radio-frequency technology using Niobium cavities as the accelerating structures. The accelerator can be extended to 1 TeV and also run as a Higgs factory at around 250 GeV and on the Z0 pole. A comprehensive value estimate of the accelerator is give, together with associated uncertainties. It is shown that no significant technical issues remain to be solved. Once a site is selected and the necessary site-dependent engineering is carried out, construction can begin immediately. The TDR also gives baseline documentation for two high-performance detectors that can share the ILC luminosity by being moved into and out of the beam line in a "push-pull" configuration. These detectors, ILD and SiD, are described in detail. They form the basis for a world-class experimental programme that promises to incr...
The International Linear Collider Technical Design Report - Volume 4: Detectors

CERN Document Server

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

2013-01-01

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

International Nuclear Information System (INIS)

1995-11-01

The System Operation Review (SOR) is a study and environmental compliance process being used by the three Federal agencies to analyze future operations of the system and river use issues. The goal of the SOR is to achieve a coordinated system operation strategy for the river that better meets the needs of all river users. This technical appendix addresses only the effects of alternative system operating strategies for managing the Columbia River system. The purpose of this technical appendix is to provide the environmental review necessary to enter into agreements regarding the distribution between Federal and non-Federal project owners with respect to delivery of the Canadian Entitlement obligation to Canada for the period 1998 through 2024
On-Line Monitoring of Instrument Channel Performance: Volume 3: Applications to Nuclear Power Plant Technical Specification Instrumentation

International Nuclear Information System (INIS)

Davis, E.; Rasmussen, B.

2004-01-01

This report is a guide for a technical specification change submittal and subsequent implementation of on-line monitoring for safety-related applications. This report is the third in a three-volume set. Volume 1, ''Guidelines for Model Development and Implementation'', presents the various tasks that must be completed to prepare models for and to implement an on-line monitoring system
Reinforced soil structures. Volume II, Summary of research and systems information

Science.gov (United States)

1989-11-01

Volume II was essentially prepared as an Appendix of supporting information for Volume I. This volume contains much of the supporting theory and a summary of the research used to verify the design approach contained in Volume I, as well as general in...
Analysis of internal events for the Unit 1 of the Laguna Verde Nuclear Power Station. Appendixes; Analisis de eventos internos para la Unidad 1 de la Central Nucleoelectrica de Laguna Verde. Apendices

Energy Technology Data Exchange (ETDEWEB)

Huerta B, A; Lopez M, R [Comision Nacional de Seguridad Nuclear y Salvaguardias, 03000 Mexico D.F. (Mexico)

1995-07-01

This volume contains the appendices for the accident sequences analysis for those internally initiated events for Laguna Verde Unit 1, Nuclear Power Plant. The appendix A presents the comments raised by the Sandia National Laboratories technical staff as a result of the review of the Internal Event Analysis for Laguna Verde Unit 1 Nuclear Power Plant. This review was performed during a joint Sandia/CNSNS multi-day meeting by the end 1992. Also included is a brief evaluation on the applicability of these comments to the present study. The appendix B presents the fault tree models printed for each of the systems included and.analyzed in the Internal Event Analysis for LVNPP. The appendice C presents the outputs of the TEMAC code, used for the cuantification of the dominant accident sequences as well as for the final core damage evaluation. (Author)
ON-Line Monitoring of Instrument Channel Performance: Volume 3: Applications to Nuclear Power Plant Technical Specification Instrumentation

Energy Technology Data Exchange (ETDEWEB)

E Davis, B Rasmussen

2004-12-31

This report is a guide for a technical specification change submittal and subsequent implementation of on-line monitoring for safety-related applications. This report is the third in a three-volume set. Volume 1, ''Guidelines for Model Development and Implementation'', presents the various tasks that must be completed to prepare models for and to implement an on-line monitoring system.
The International Linear Collider Technical Design Report - Volume 3.I: Accelerator \\& in the Technical Design Phase

Energy Technology Data Exchange (ETDEWEB)

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

2013-06-26

The International Linear Collider Technical Design Report (TDR) describes in four volumes the physics case and the design of a 500 GeV centre-of-mass energy linear electron-positron collider based on superconducting radio-frequency technology using Niobium cavities as the accelerating structures. The accelerator can be extended to 1 TeV and also run as a Higgs factory at around 250 GeV and on the Z0 pole. A comprehensive value estimate of the accelerator is give, together with associated uncertainties. It is shown that no significant technical issues remain to be solved. Once a site is selected and the necessary site-dependent engineering is carried out, construction can begin immediately. The TDR also gives baseline documentation for two high-performance detectors that can share the ILC luminosity by being moved into and out of the beam line in a "push-pull" configuration. These detectors, ILD and SiD, are described in detail. They form the basis for a world-class experimental programme that promises to increase significantly our understanding of the fundamental processes that govern the evolution of the Universe.
The 1978 National Fire-Danger Rating System: technical documentation

Science.gov (United States)

Larry S. Bradshaw; John E. Deeming; Robert E. Burgan; Jack D. Cohen

1984-01-01

The National Fire-Danger Rating System (NFDRS), implemented in 1972, has been revised and reissued as the 1978 NFDRS. This report describes the full developmental history of the NFDRS, including purpose, technical foundation, and structure. Includes an extensive bibliography and appendixes.
Standard technical specifications combustion engineering plants: Bases (Sections 2.0--3.3). Volume 2, Revision 1

International Nuclear Information System (INIS)

1995-04-01

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

Energy Technology Data Exchange (ETDEWEB)

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

2013-06-26

The International Linear Collider Technical Design Report (TDR) describes in four volumes the physics case and the design of a 500 GeV centre-of-mass energy linear electron-positron collider based on superconducting radio-frequency technology using Niobium cavities as the accelerating structures. The accelerator can be extended to 1 TeV and also run as a Higgs factory at around 250 GeV and on the Z0 pole. A comprehensive value estimate of the accelerator is give, together with associated uncertainties. It is shown that no significant technical issues remain to be solved. Once a site is selected and the necessary site-dependent engineering is carried out, construction can begin immediately. The TDR also gives baseline documentation for two high-performance detectors that can share the ILC luminosity by being moved into and out of the beam line in a "push-pull" configuration. These detectors, ILD and SiD, are described in detail. They form the basis for a world-class experimental programme that promises to increase significantly our understanding of the fundamental processes that govern the evolution of the Universe.
The International Linear Collider Technical Design Report - Volume 4: Detectors

Energy Technology Data Exchange (ETDEWEB)

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

2013-06-26

The International Linear Collider Technical Design Report (TDR) describes in four volumes the physics case and the design of a 500 GeV centre-of-mass energy linear electron-positron collider based on superconducting radio-frequency technology using Niobium cavities as the accelerating structures. The accelerator can be extended to 1 TeV and also run as a Higgs factory at around 250 GeV and on the Z0 pole. A comprehensive value estimate of the accelerator is give, together with associated uncertainties. It is shown that no significant technical issues remain to be solved. Once a site is selected and the necessary site-dependent engineering is carried out, construction can begin immediately. The TDR also gives baseline documentation for two high-performance detectors that can share the ILC luminosity by being moved into and out of the beam line in a "push-pull" configuration. These detectors, ILD and SiD, are described in detail. They form the basis for a world-class experimental programme that promises to increase significantly our understanding of the fundamental processes that govern the evolution of the Universe.
Final report from VFL Technologies for the pilot-scale thermal treatment of Lower East Fork Poplar Creek floodplain soils. LEFPC appendices. Volume 6. Appendix VI-X

International Nuclear Information System (INIS)

1994-09-01

This final report from VFL Technologies for the pilot-scale thermal treatment of lower East Fork Poplar Creek floodplain soils dated September 1994 contains LEFPC Appendices, Volume 6, Appendix VI - X. These appendices cover the following areas: chain of custody, miscellaneous process calculations (residence time and orifice plate calculations), waste management (mercury and radiation confirmatory testing before and after final verification run), health and safety (training, respirator fit test and radiation work permits), and transportation (soil receipt documentation)
Kress indirect dry cooling system, Bethlehem Steel's Coke Plant demonstration at Sparrows Point, Maryland. Volume 2. Appendices G-N. Final report, February 1990-February 1992

International Nuclear Information System (INIS)

Ossman, A.G.

1993-05-01

The report provides an evaluation of the Kress Indirect Dry Cooling (KIDC) process. The KIDC process is an innovative system for the handling and cooling of coke produced from a slot type by-product coke oven battery. The report is based on the test work and demonstration of the system at Bethlehem Steel Corporation's Sparrows Point facility in 1991. The report covers both environmental and operational impacts of the KIDC process. The report, Volume 2, contains appendices G-N. Volume 1, PB93-191302, contains the technical report as well as appendices A-F. Volume 2 contains appendixes on coke quality data, blast furnace balwax model report, KIDC operating cost and maintenance requirements, Kress box thickness readings, KIDC coke discharge temperature, QA/QC program, door leak data, and coal data
Technical support for GEIS: radioactive waste isolation in geologic formations. Volume 22. Nuclear considerations for repository design

International Nuclear Information System (INIS)

1978-04-01

This volume, Y/OWI/TM-36/22, ''Nuclear Considerations for Repository Design,'' is one of a 23-volume series, ''Technical Support for GEIS: Radioactive Waste Isolation in Geologic Formations,'' Y/OWI/TM-36, which supplements the ''Contribution to Draft Generic Environmental Impact Statement on Commercial Waste Management: Radioactive Waste Isolation in Geologic Formations,'' Y/OWI/TM-44. The series provides a more complete technical basis for the preconceptual designs, resource requirements, and environmental source terms associated with isolating commercial LWR wastes in underground repositories in salt, granite, shale and basalt. Wastes are considered from three fuel cycles: uranium and plutonium recycling, no recycling of spent fuel and uranium-only recycling. Included in this volume are baseline design considerations such as characteristics of canisters, drums, casks, overpacks, and shipping containers; maximum allowable and actual decay-heat levels; and canister radiation levels. Other topics include safeguard and protection considerations; occupational radiation exposure including ALARA programs; shielding of canisters, transporters and forklift trucks; monitoring considerations; mine water treatment; canister integrity; and criticality calculations
Final Programmatic Environmental Impact Statement for stockpile stewardship and management: Volume 3

International Nuclear Information System (INIS)

1996-09-01

The Department of Energy (DOE) has been directed by the President and Congress to maintain the safety and reliability of the reduced nuclear weapons stockpile in the absence of underground nuclear testing. In order to fulfill that responsibility, DOE has developed a Stockpile Stewardship and Management Program to provide a single highly integrated technical program for maintaining the continued safety and reliability of the nuclear stockpile. The Stockpile Stewardship and Management Programmatic Environmental Impact Statement (PEIS) describes and analyzes alternative ways to implement the proposed actions for the Stockpile Stewardship and Management Program. This document consists of Volume III, Appendix I entitled ''National Ignition Facility Project-Specific Analysis,'' which investigates the environmental impacts resulting from constructing and operating the proposed National Ignition Facility
K Basin spent fuel sludge treatment alternatives study. Volume 2, Technical options

International Nuclear Information System (INIS)

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

1995-01-01

Approximately 2100 metric tons of irradiated N Reactor fuel are stored in the KE and KW Basins at the Hanford Site, Richland, Washington. Corrosion of the fuel has led to the formation of sludges, both within the storage canisters and on the basin floors. Concern about the degraded condition of the fuel and the potential for leakage from the basins in proximity to the Columbia River has resulted in DOE's commitment in the Tri-Party Agreement (TPA) to Milestone M-34-00-T08 to remove the fuel and sludges by a December 2002 target date. To support the planning for this expedited removal action, the implications of sludge management under various scenarios are examined. This report, Volume 2 of two volumes, describes the technical options for managing the sludges, including schedule and cost impacts, and assesses strategies for establishing a preferred path
Isotope Brayton ground demonstration testing and flight qualification. Volume 1. Technical program

Energy Technology Data Exchange (ETDEWEB)

1974-12-09

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

Verifying seismic design of nuclear reactors by testing. Volume 2: appendix, theoretical discussions

International Nuclear Information System (INIS)

1979-01-01

Theoretical discussions on seismic design testing are presented under the following appendix headings: system functions, pulse optimization program, system identification, and motion response calculations from inertance measurements of a nuclear power plant
Remedial investigation/feasibility study for the David Witherspoon, Inc., 901 Site, Knoxville, Tennessee: Volume 2, Appendixes

International Nuclear Information System (INIS)

1996-10-01

This document contains the appendixes for the remedial investigation and feasibility study for the David Witherspoon, Inc., 901 site in Knoxville, Tennessee. The following topics are covered in the appendixes: (A) David Witherspoon, Inc., 901 Site Historical Data, (B) Fieldwork Plans for the David Witherspoon, Inc., 901 Site, (C) Risk Assessment, (D) Remediation Technology Discussion, (E) Engineering Support Documentation, (F) Applicable or Relevant and Appropriate Requirements, and (G) Cost Estimate Documentation
Remedial investigation/feasibility study for the David Witherspoon, Inc., 901 Site, Knoxville, Tennessee: Volume 2, Appendixes

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-10-01

This document contains the appendixes for the remedial investigation and feasibility study for the David Witherspoon, Inc., 901 site in Knoxville, Tennessee. The following topics are covered in the appendixes: (A) David Witherspoon, Inc., 901 Site Historical Data, (B) Fieldwork Plans for the David Witherspoon, Inc., 901 Site, (C) Risk Assessment, (D) Remediation Technology Discussion, (E) Engineering Support Documentation, (F) Applicable or Relevant and Appropriate Requirements, and (G) Cost Estimate Documentation.
Local bone graft harvesting and volumes in posterolateral lumbar fusion: a technical report.

Science.gov (United States)

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

2011-06-01

In lumbar surgery, local bone graft is often harvested and used in posterolateral fusion procedures. The volume of local bone graft available for posterolateral fusion has not been determined in North American patients. Some authors have described this as minimal, but others have suggested the volume was sufficient to be reliably used as a stand-alone bone graft substitute for single-level fusion. To describe the technique used and determine the volume of local bone graft available in a cohort of patients undergoing single-level primary posterolateral fusion by the authors harvesting technique. Technical description and cohort report. Consecutive patients undergoing lumbar posterolateral fusion with or without instrumentation for degenerative processes. Local bone graft volume. Consecutive patients undergoing lumbar posterolateral fusion with or without instrumentation for degenerative processes of were studied. Local bone graft was harvested by a standard method in each patient and the volume measured by a standard procedure. Twenty-five patients were studied, and of these 11 (44%) had a previous decompression. The mean volume of local bone graft harvested was measured to be 25 cc (range, 12-36 cc). Local bone graft was augmented by iliac crest bone in six of 25 patients (24%) if the posterolateral fusion bed was not well packed with local bone alone. There was a trend to greater local bone graft volumes in men and in patients without previous decompression. Large volumes of local bone can be harvested during posterolateral lumbar fusion surgery. Even in patients with previous decompression the volume harvested is similar to that reported harvested from the posterior iliac crest for single-level fusion. Copyright © 2011 Elsevier Inc. All rights reserved.
Mixed waste focus area integrated technical baseline report. Phase I, Volume 2: Revision 0

International Nuclear Information System (INIS)

1996-01-01

This document (Volume 2) contains the Appendices A through J for the Mixed Waste Focus Area Integrated Technical Baseline Report Phase I for the Idaho National Engineering Laboratory. Included are: Waste Type Managers' Resumes, detailed information on wastewater, combustible organics, debris, unique waste, and inorganic homogeneous solids and soils, and waste data information. A detailed list of technology deficiencies and site needs identification is also provided
The International Linear Collider Technical Design Report - Volume 3.I: Accelerator R&D in the Technical Design Phase

CERN Document Server

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

2013-01-01

The International Linear Collider Technical Design Report (TDR) describes in four volumes the physics case and the design of a 500 GeV centre-of-mass energy linear electron-positron collider based on superconducting radio-frequency technology using Niobium cavities as the accelerating structures. The accelerator can be extended to 1 TeV and also run as a Higgs factory at around 250 GeV and on the Z0 pole. A comprehensive value estimate of the accelerator is give, together with associated uncertainties. It is shown that no significant technical issues remain to be solved. Once a site is selected and the necessary site-dependent engineering is carried out, construction can begin immediately. The TDR also gives baseline documentation for two high-performance detectors that can share the ILC luminosity by being moved into and out of the beam line in a "push-pull" configuration. These detectors, ILD and SiD, are described in detail. They form the basis for a world-class experimental programme that promises to incr...
On the Rise: The Role of Career and Technical Education in Arizona's Future. 21st Century Career and Technical Education Pathways

Science.gov (United States)

Gupta, Sapna

2013-01-01

This report examines the potential of Career and Technical Education (CTE) in Arizona in terms of providing employers certified skills need to compete regionally, nationally and internationally and students avenues for higher education, quality of life and job satisfaction. An appendix on "Estimating the Effect of CTE on High School…
The Fukushima Daiichi Accident. Technical Volume 3/5. Emergency Preparedness and Response

International Nuclear Information System (INIS)

2015-08-01

This volume describes the key events and response actions from the onset of the accident at the Fukushima Daiichi nuclear power plant (NPP), operated by the Tokyo Electric Power Company (TEPCO), on 11 March 2011. It also describes the national emergency preparedness and response (EPR) system in place in Japan and the international EPR framework prior to the accident. It is divided into five sections. Section 3.1 describes the initial actions taken by Japan in response to the accident, involving: identification of the accident, notification of off-site authorities and activation of the response; mitigatory actions taken on-site; and initial off-site response. Section 3.2 describes the protective measures taken for personnel in response to the natural disaster, protection of emergency workers, medical management of emergency workers and the voluntary involvement of members of the public in the emergency response. Section 3.3 describes the protective actions and other response actions taken by Japan to protect the public. It addresses urgent and early protective actions; the use of a dose projection model, the System for Prediction of Environmental Emergency Dose Information (SPEEDI), as a basis for decisions on protective actions during the accident; environmental monitoring; provision of information to the public and international community; and issues related to international trade and waste management. Section 3.4 describes the transition from the emergency phase to the recovery phase. It also addresses the national analysis of the accident and the emergency response. Section 3.5 describes the response by the IAEA, other international organizations within the Inter- Agency Committee on Radiological and Nuclear Emergencies (IACRNE), the actions of IAEA Member States with regard to protective actions recommended to their nationals in Japan and the provision of international assistance. A summary, observations and lessons conclude each section. There are three
K Basin spent fuel sludge treatment alternatives study. Volume 2, Technical options

Energy Technology Data Exchange (ETDEWEB)

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

1995-01-01

Approximately 2100 metric tons of irradiated N Reactor fuel are stored in the KE and KW Basins at the Hanford Site, Richland, Washington. Corrosion of the fuel has led to the formation of sludges, both within the storage canisters and on the basin floors. Concern about the degraded condition of the fuel and the potential for leakage from the basins in proximity to the Columbia River has resulted in DOE`s commitment in the Tri-Party Agreement (TPA) to Milestone M-34-00-T08 to remove the fuel and sludges by a December 2002 target date. To support the planning for this expedited removal action, the implications of sludge management under various scenarios are examined. This report, Volume 2 of two volumes, describes the technical options for managing the sludges, including schedule and cost impacts, and assesses strategies for establishing a preferred path.
Technical-evaluation report on the proposed technical-specification changes for the inservice surveillance of safety-related hydraulic and mechanical snubbers at the Millstone Nuclear Power Station, Unit 2 (Docket No. 50-336)

International Nuclear Information System (INIS)

Selan, J.C.

1983-01-01

This report documents the technical evaluation of the proposed Technical Specification changes to Limiting Conditions for Operation, Surveillance Requirements and Bases for safety-related hydraulic and mechanical snubbers at the Millstone Nuclear Power Station, Unit 2. The evaluation is to determine whether the proposed Technical Specifications are in conformance with the model Standard Technical Specification set forth by the NRC. A check list, Appendix A of this report, compares the licensee's submittal with the NRC requirements and includes Proposed Resolution of the Deviations
Technical support for GEIS: radioactive waste isolation in geologic formations. Volume 10. Repository preconceptual design studies: granite

International Nuclear Information System (INIS)

1978-04-01

This volume, Volume 10 ''Repository Preconceptual Design Studies: Granite,'' is one of a 23-volume series, ''Technical Support for GEIS: Radioactive Waste Isolation in Geologic Formations,'' Y/OWI/TM-36, which supplements the ''Contribution to Draft Generic Environmental Impact Statement on Commercial Waste Management: Radioactive Waste Isolation in Geologic Formations,'' Y/OWI/TM-44. The series provides a more complete technical basis for the preconceptual designs, resource requirements, and environmental source terms associated with isolating commercial LWR wastes in underground repositories in salt, granite, shale and basalt. Wastes are considered from three fuel cycles: uranium and plutonium recycling, no recycling of spent fuel and uranium-only recycling. This document describes a preconceptual design for a nuclear waste storage facility in granite. The facility design consists of several chambers excavated deep within a geologic formation together with access shafts and supportive surface structures. The facility design provides for: receiving and unloading waste containers; lowering them down shafts to the mine level; transporting them to the proper storage area, and emplacing them in mined storage rooms. Drawings of the facility design are contained in TM-36/11, ''Drawings for Repository Preconceptual Design Studies: Granite.''
Technical support for GEIS: radioactive waste isolation in geologic formations. Volume 8. Repository preconceptual design studies: salt

International Nuclear Information System (INIS)

1978-04-01

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

International Nuclear Information System (INIS)

Mayberry, J.L.; Huebner, T.L.; Ross, W.; Nakaoka, R.; Schumacher, R.; Cunnane, J.; Singh, D.; Darnell, R.; Greenhalgh, W.

1993-08-01

This report presents information on low-level mixed waste forms.The descriptions of the low-level mixed waste (LLMW) streams that are considered by the Mixed Waste Integrated Program (MWIP) are given in Appendix A. This information was taken from descriptions generated by the Mixed Waste Treatment Program (MWTP). Appendix B provides a list of characteristic properties initially considered by the Final Waste Form (FWF) Working Group (WG). A description of facilities available to test the various FWFs discussed in Volume I of DOE/MWIP-3 are given in Appendix C. Appendix D provides a summary of numerous articles that were reviewed on testing of FWFS. Information that was collected by the tests on the characteristic properties considered in this report are documented in Appendix D. The articles reviewed are not a comprehensive list, but are provided to give an indication of the data that are available
Technical Evaluation Report on the Fluid Dynamics Panel Symposium on Validation of Computational Fluid Dynamics

Science.gov (United States)

1989-05-01

separately each of the papers presented and makes general comments on the seven major topic sessions. In addition, a Poster Presentation was reviewed in...Appendix to this report. The Poster Papers, also listed in an Appendix, are published in CP437 Volume I. Le pr6sent rapport fait le point et donne une...ConfErence AGARD CP 437 Volume I dont une liste en est donn6e h I’annexe au pr6sent rapport. Une liste des r6unions d’information/exposition est
Ecological evaluation of proposed discharge of dredged material from Oakland Harbor into ocean waters (Phase 3 B of -42-foot project). Volume 2, Appendixes

Energy Technology Data Exchange (ETDEWEB)

Kohn, N.P.; Ward, J.A.; Mayhew, H.L.; Word, J.Q.; Barrows, E.S.; Goodwin, S.M.; Lefkovitz, L.F. [Battelle/Marine Sciences Lab., Sequim, WA (United States)

1992-06-01

The Water Resources Development Act of 1986 (Public Law 99-662) authorized the US Army Corps of Engineers (USACE) San Francisco District, to deepen and widen the navigational channels of the Oakland Inner and Outer Harbors to accommodate deeper-draft vessels. The USACE is considering several disposal options for the dredged material removed during these channel improvements including open-water disposal. Dredged material proposed for open-water disposal must be evaluated to determine the potential impacts of the disposal activity on the water column and disposal site environments. The USACE requested that Battelle/Marine Sciences Laboratory (MSL) conduct studies to evaluate open-water disposal options for Oakland Harbor sediments. This request developed into the Oakland Harbor Phase III Program. This is Volume 2 of a two-volume report that presents information gathered to determine the suitability of ocean disposal of sediments dredged from Oakland Harbor. This volume contains the Appendixes (A through N), which provide details of the data analyses and full presentation of the data and results.
Technical procedures for water resources: Volume 4, Deaf Smith County site, Texas: Environmental Field Program: Final draft

International Nuclear Information System (INIS)

1987-08-01

This volume contains Technical Procedures pursuant to the water Resources Site Study Plan: including Collection, Preservation, and Shipment of Ground-Water Samples; Inventory Current Water Use and Estimating Projected Water Use; Estimation of Precipitation Depth, Duration, Frequence; Estimation of Probable Maximum Precipitation; Calculation of Floodplains
Technical evaluation report of the Fort St. Vrain final draft upgraded technical specifications

International Nuclear Information System (INIS)

Kimura, C.Y.

1989-01-01

This report is a technical evaluation of the final draft of the Fort St. Vrain (FSV) Upgraded Technical Specifications (UT/S) as issued by Public Service of Colorado (PSC) on May 27, 1988 with subsequent supplemental updates issued on June 15, 1988 and August 5, 1988. It has been compared for consistency, and safety conservatism with the Fort St. Vrain (FSV) Updated Final Safety Analysis Report (FSAR), the FSV Safety Evaluation Report (SER), the Facility Operating License, DPR-34, and all amendments to the Facility Operating License issued as of June 1, 1988, and Appendix A to the Operating License DPR-34, Technical Specifications. Because of the age of the plant, no supplements to the Fort St. Vrain SER have been issued since the original SER was not issued as a WASH or a NUREG report. This made it necessary to review all amendments to the Facility Operating License since they would contain the safety evaluations done to support changes to the Facility Operating License. The upgraded Fort St. Vrain Technical Specifications were also broadly compared with the latest Westinghouse Standard Technical Specifications (WSTS) to assure that what was proposed for Fort St. Vrain was consistent with the latest NRC staff practices for standard technical specifications
Technical-evaluation report on the proposed technical-specification changes for the inservice surveillance of safety-related hydraulic and mechanical snubbers at the James A. Fitzpatrick Nuclear Power Plant (Docket No. 50-333)

International Nuclear Information System (INIS)

Selan, J.C.

1983-01-01

This report documents the technical evaluation of the proposed Technical Specification changes to Limiting Conditions for Operation, Surveillance Requirements and Bases for safety-related hydraulic and mechanical snubbers at the James A. FitzPatrick Nuclear Power Plant. The evaluation is to determine whether the proposed Technical Specifications are in conformance with the model Standard Technical Specification set forth by the NRC. A check list, Appendix A of this report, compares the licensee's submittal with the NRC requirements and includes Proposed Resolution of the Deviations
The International Linear Collider Technical Design Report - Volume 1: Executive Summary

Energy Technology Data Exchange (ETDEWEB)

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

2013-06-26

The International Linear Collider Technical Design Report (TDR) describes in four volumes the physics case and the design of a 500 GeV centre-of-mass energy linear electron-positron collider based on superconducting radio-frequency technology using Niobium cavities as the accelerating structures. The accelerator can be extended to 1 TeV and also run as a Higgs factory at around 250 GeV and on the Z0 pole. A comprehensive value estimate of the accelerator is give, together with associated uncertainties. It is shown that no significant technical issues remain to be solved. Once a site is selected and the necessary site-dependent engineering is carried out, construction can begin immediately. The TDR also gives baseline documentation for two high-performance detectors that can share the ILC luminosity by being moved into and out of the beam line in a "push-pull" configuration. These detectors, ILD and SiD, are described in detail. They form the basis for a world-class experimental programme that promises to increase significantly our understanding of the fundamental processes that govern the evolution of the Universe.
LLCEDATA and LLCECALC for Windows version 1.0, Volume 2: Technical manual

Energy Technology Data Exchange (ETDEWEB)

McFadden, J.G.

1998-09-04

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

SLIM-MAUD: an approach to assessing human error probabilities using structured expert judgment. Volume II. Detailed analysis of the technical issues

International Nuclear Information System (INIS)

Embrey, D.E.; Humphreys, P.; Rosa, E.A.; Kirwan, B.; Rea, K.

1984-07-01

This two-volume report presents the procedures and analyses performed in developing an approach for structuring expert judgments to estimate human error probabilities. Volume I presents an overview of work performed in developing the approach: SLIM-MAUD (Success Likelihood Index Methodology, implemented through the use of an interactive computer program called MAUD-Multi-Attribute Utility Decomposition). Volume II provides a more detailed analysis of the technical issues underlying the approach
Technical-evaluation report on the proposed technical-specification changes for the inservice surveillance of safety-related hydraulic and mechanical snubbers at the Indian Point Nuclear Power Plant, Unit 3 (Docket No. 50-286)

International Nuclear Information System (INIS)

Selan, J.C.

1983-01-01

This report documents the technical evaluation of the proposed Technical Specification changes to Limiting Conditions for Operation, Surveillance Requirements and Bases for safety-related hydraulic and mechanical snubbers at the Indian Point Nuclear Power Plant, Unit 3. The evaluation is to determine whether the proposed Technical Specifications are in conformance with the model Standard Technical Specification set forth by the NRC. A check list, Appendix A of this report, compares the licensee's submittal with the NRC requirements and includes Proposed Resolution of the Deviations
Wetlands Research Program. Corps of Engineers Wetlands Delineation Manual. Appendix C. Sections 1 and 2. Region 2 - Southeast.

Science.gov (United States)

1987-01-01

22 7.V.: 14 -1b Jil -7 1 N.- .- WETLANDS RESEARCH PROGRAM TECHNICAL REPORT Y-87-1 CORPS OF ENGINEERS WETLANDS DELINEATION MANUAL APPENDIX C SECTIONS ...ARMYLA- US Army Corps of Engineers Washington, DC 20314-1000 B , , , -I *. 4 -w *" APPENDIX C SECTION 1 NATIONAL LIST OF PLANT SPECIES THAT OCCUR IN...Redtop FACW A. hiernalia (Walter) B.S.P. Winter bent FAC A. scabra Wilid. Rough bentgrass FAC A. st~nfyaL. Carpet bentgrass FACW Aletris aurea
Practical experience and lessons learned through implementation of Appendix VIII performance demonstration requirements

International Nuclear Information System (INIS)

Ashwin, P.J.; Becker, F.L.; Latiolais, C.L.; Spanner, J.C.

1996-01-01

To provide the US nuclear industry with a uniform implementation of the Performance Demonstration requirements within the 1989 edition of ASME Section XI, Appendix VIII, representatives from all US nuclear utilities formed the Performance Demonstration Initiative (PDI). The PDI recognized the potential benefits that Appendix VIII offered the nuclear industry and initiated a proactive approach to implement the requirements. In doing so it was expected that performance demonstration of ultrasonic examination procedures would allow for improvement in the efficiency and credibility of inservice inspection to be realized. Explicit within the performance demonstration requirements of Appendix VIII is the need for a Performance Demonstration Administrator, a difficult requirement to fulfill. Not only must the administrator exhibit the attributes of understanding the demonstration requirements, but also have solid technical knowledge, integrity and be able to interface with the industry at all levels, from operations to regulatory. For the nuclear industry, the EPRI NDE Center is an obvious choice to fulfill this position. This paper provides a brief background of the PDI, a nuclear industry-wide initiative to implement the performance demonstration requirements of Appendix VIII. Even though the consensus approach adopted by the PDI is discussed, the paper's primary objective is to provide examples of the lessons learned by the Center through the specific requirements of Appendix VIII
Technical and economic assessment of fluidized bed augmented compressed air energy storage system. Volume III. Preconceptual design

Energy Technology Data Exchange (ETDEWEB)

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

1981-09-01

A technical and economic assessment of fluidized bed combustion augmented compressed air energy storage systems is presented. The results of this assessment effort are presented in three volumes. Volume III - Preconceptual Design contains the system analysis which led to the identification of a preferred component configuration for a fluidized bed combustion augmented compressed air energy storage system, the results of the effort which transformed the preferred configuration into preconceptual power plant design, and an introductory evaluation of the performance of the power plant system during part-load operation and while load following.
Technical support for GEIS: radioactive waste isolation in geologic formations. Volume 21. Ground water movement and nuclide transport

Energy Technology Data Exchange (ETDEWEB)

None

1978-04-01

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

International Nuclear Information System (INIS)

1975-01-01

The appendixes contain information on alarm levels for detection of theft, computer simulation of theft detection capabilities, benefits and liabilities related to real-time material control, cost analysis, and impact of collocated facilities on the real-time material control concept
Columbia River System Operation Review final environmental impact statement. Appendix T: Comments and responses

International Nuclear Information System (INIS)

1995-11-01

The System Operation Review (SOR) is a study and environmental compliance process being used by the three Federal agencies to analyze future operations of the system and river use issues. The goal of the SOR is to achieve a coordinated system operation strategy for the river that better meets the needs of all river users. This technical appendix addresses only the effects of alternative system operating strategies for managing the Columbia River system. This appendix documents the public and agency review of the SOR Draft EIS and how the SOR agencies used the review to formulate the FINAL EIS. The appendix includes a summary of the review process, a discussion of the nature of the comments, a list of all commentors, reproductions of comment letters, and responses to all comments. Changes in the EIS text in response to comments are noted in the responses
Technical procedures for water resources, Deaf Smith County site, Texas: Volume 1: Environmental Field Program: Final draft

International Nuclear Information System (INIS)

1987-08-01

This volume contains Technical Procedures pursuant to the Water Resources Site Study Plan including, determination of basin topographic characteristics, determination of channel and playa lake characteristics, operation of a stream gaging station, operation of a playa lake stage gaging system, and processing of data from a playa lake stage gaging system
The System 80+ Standard Plant design control document. Volume 17

International Nuclear Information System (INIS)

1997-01-01

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

Energy Technology Data Exchange (ETDEWEB)

Dietlmeier, W.; Gossner, S.; Gueldner, W.; Hoertner, H.; von Linden, J.; Preischl, W.; Reichart, G.; Spindler, H.; Volmer, G.; Zipf, G.

1981-01-01

Based on the event tree analysis as documented in the Appendix 1, the failure probabilities of the system functions required to control the initiating events are evaluated in this Appendix 2. The reliability investigations necessary for the evaluation of the event sequences are performed mostly by means of the fault tree analysis. The methods of the reliability analysis, the composition and function of the systems important to safety and the functional tests performed on these systems are dealt with in detail. The comprehensive documentation of the reliability analyses as performed for the internal events necessitated a division of this Appendix 2 into two volumes.
Remedial actions at the former Vanadium Corporation of America uranium mill site, Durango, La Plata County, Colorado. Volume II. Appendices. Final Environmental Impact Statement

International Nuclear Information System (INIS)

1985-10-01

Volume 2 contains the following: addendums to Appendices A - Conceptual Designs and Engineering Evaluations for Remedial Action Alternative 3b, D - Meteorological and Air-Quality Information, F - Water Resources Information, H - Radiological Information, I - Information on Populations, Socioeconomics, and Land Use; Appendix K - List of Agencies, Organizations, and Persons Receiving Copies of this Statement; Appendix L - Wildlife Mitigation Plan; Appendix M - Seismic Evaluation; Appendix N - Tourism Evaluation; and Appendix O - Permits, Licenses, and Approvals
Standard Technical Specifications, Westinghouse plants

International Nuclear Information System (INIS)

1992-09-01

This NUREG contains improved Standard Technical Specifications (STS) for Westinghouse Plants and documents the positions of the Nuclear Regulatory Commission based on the Westinghouse Owners Group's proposed STS. This document is the result of extensive technical meetings and discussions among the NRC staff, the Nuclear Steam Supply System (NSSS) Owners Groups, the NSSS vendors, and the Nuclear Management and Resources Council (NUMARC). The improved STS were developed based on the criteria in the interim Commission Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, dated February 6, 1987. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. Volume 1 contains the Specifications for all chapters and sections of the improved STS. Volume 2 contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1--3.3 of the improved STS. This document, Volume 3, contains the Bases for Sections 3.4--3.9 of the improved STS
Standard Technical Specifications, Westinghouse Plants

International Nuclear Information System (INIS)

1992-09-01

This NUREG contains improved Standard Technical Specifications (STS) for Westinghouse Plants and documents the positions of the Nuclear Regulatory Commission based on the Westinghouse Owners Group's proposed STS. This document is the result of extensive technical meetings and discussions among the NRC staff, the Nuclear Steam Supply System (NSSS) Owners Groups, the NSSS vendors, and the Nuclear Management and Resources Council (NUMARC). The improved STS were developed based on the criteria in the interim Commission Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, dated February 6, 1987. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. Volume 1 contains the Specifications for all chapters and sections of the improved STS. Volume 2 contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1--3.3 of the unproved STS. Volume 3 contains the Bases for Sections 3.4--3.9 of the improved STS which contain information on safety limits, reactivity control systems, power distribution limits, and instrumentation
Standard Technical Specifications, Westinghouse plants

International Nuclear Information System (INIS)

1992-09-01

This NUREG contains improved Standard Technical Specifications (STS) for Westinghouse Plants and documents the positions of the Nuclear Regulatory Commission based on the Westinghouse Owners Group's proposed STS. This document is the result of extensive technical meetings and discussions among the NRC staff, the Nuclear Steam Supply System (NSSS) Owners Groups, the NSSS vendors, and the Nuclear Management and Resources Council (NUMARC). The improved STS were developed based on the criteria in the interim Commission Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, dated February 6, 1987. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. This document, Volume 1, contains the Specifications for all chapters and sections of the improved STS. Volume 2 contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1--3.3 of the improved STS. Volume 3 contains the Bases for Sections 3.4--3.9 of the improved STS
Precursors to potential severe core damage accidents: 1994, a status report. Volume 22: Appendix I

International Nuclear Information System (INIS)

Belles, R.J.; Cletcher, J.W.; Copinger, D.A.; Vanden Heuvel, L.N.; Dolan, B.W.; Minarick, J.W.

1995-12-01

Nine operational events that affected eleven commercial light-water reactors (LWRs) during 1994 and that are considered to be precursors to potential severe core damage are described. All these events had conditional probabilities of subsequent severe core damage greater than or equal to 1.0 x 10 -6 . These events were identified by computer-screening the 1994 licensee event reports from commercial LWRs to identify those that could be potential precursors. Candidate precursors were then selected and evaluated in a process similar to that used in previous assessments. Selected events underwent engineering evaluation that identified, analyzed, and documented the precursors. Other events designated by the Nuclear Regulatory Commission (NRC) also underwent a similar evaluation. Finally, documented precursors were submitted for review by licensees and NRC headquarters and regional offices to ensure that the plant design and its response to the precursor were correctly characterized. This study is a continuation of earlier work, which evaluated 1969--1981 and 1984--1993 events. The report discusses the general rationale for this study, the selection and documentation of events as precursors, and the estimation of conditional probabilities of subsequent severe core damage for events. This document is bound in two volumes: Vol. 21 contains the main report and Appendices A--H; Vol. 22 contains Appendix 1
Precursors to potential severe core damage accidents: 1994, a status report. Volume 22: Appendix I

Energy Technology Data Exchange (ETDEWEB)

Belles, R.J.; Cletcher, J.W.; Copinger, D.A.; Vanden Heuvel, L.N. [Oak Ridge National Lab., TN (United States); Dolan, B.W.; Minarick, J.W. [Oak Ridge National Lab., TN (United States)]|[Science Applications International Corp., Oak Ridge, TN (United States)

1995-12-01

Nine operational events that affected eleven commercial light-water reactors (LWRs) during 1994 and that are considered to be precursors to potential severe core damage are described. All these events had conditional probabilities of subsequent severe core damage greater than or equal to 1.0 {times} 10{sup {minus}6}. These events were identified by computer-screening the 1994 licensee event reports from commercial LWRs to identify those that could be potential precursors. Candidate precursors were then selected and evaluated in a process similar to that used in previous assessments. Selected events underwent engineering evaluation that identified, analyzed, and documented the precursors. Other events designated by the Nuclear Regulatory Commission (NRC) also underwent a similar evaluation. Finally, documented precursors were submitted for review by licensees and NRC headquarters and regional offices to ensure that the plant design and its response to the precursor were correctly characterized. This study is a continuation of earlier work, which evaluated 1969--1981 and 1984--1993 events. The report discusses the general rationale for this study, the selection and documentation of events as precursors, and the estimation of conditional probabilities of subsequent severe core damage for events. This document is bound in two volumes: Vol. 21 contains the main report and Appendices A--H; Vol. 22 contains Appendix 1.
Tank waste source term inventory validation. Volume II. Letter report

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-04-01

This document comprises Volume II of the Letter Report entitled Tank Waste Source Term Inventory Validation. This volume contains Appendix C, Radionuclide Tables, and Appendix D, Chemical Analyte Tables. The sample data for selection of 11 radionuclides and 24 chemical analytes were extracted from six separate sample data sets, were arranged in a tabular format and were plotted on scatter plots for all of the 149 single-shell tanks, the 24 double-shell tanks and the four aging waste tanks. The solid and liquid sample data was placed in separate tables and plots. The sample data and plots were compiled from the following data sets: characterization raw sample data, recent core samples, D. Braun data base, Wastren (Van Vleet) data base, TRAC and HTCE inventories.
Tank waste source term inventory validation. Volume II. Letter report

International Nuclear Information System (INIS)

1995-04-01

This document comprises Volume II of the Letter Report entitled Tank Waste Source Term Inventory Validation. This volume contains Appendix C, Radionuclide Tables, and Appendix D, Chemical Analyte Tables. The sample data for selection of 11 radionuclides and 24 chemical analytes were extracted from six separate sample data sets, were arranged in a tabular format and were plotted on scatter plots for all of the 149 single-shell tanks, the 24 double-shell tanks and the four aging waste tanks. The solid and liquid sample data was placed in separate tables and plots. The sample data and plots were compiled from the following data sets: characterization raw sample data, recent core samples, D. Braun data base, Wastren (Van Vleet) data base, TRAC and HTCE inventories
Site Environmental Report for 1998 Volume II

International Nuclear Information System (INIS)

Ruggieri, Michael

1999-01-01

Volume II of the Site Environment Report for 1998 is provided by Ernest Orlando Lawrence Berkeley National Laboratory as a supplemental appendix to the report printed in volume I. Volume II contains the environmental monitoring and sampling data used to generate summary results in the main report for routine and non routine activities at the Laboratory (except for groundwater sampling data, which may be found in the reports referred to in chapter 6). Data presented in the tables are given in International System of Units (SI) units of measure

US Department of Energy interim mixed waste inventory report: Waste streams, treatment capacities and technologies: Volume 6, Appendices

International Nuclear Information System (INIS)

1993-04-01

This volume contains Appendix A--Federal Facility Compliance Act of 1992, Appendix B--Technology Development, and Appendix C--Other Materials. Appendix B supplies details concerning the technology development activities supported by DOE in the area of mixed waste management. Two parts of this appendix are important. The more important of the two is the collection of technology development summaries. There are 267 summaries collected from several sources, which are described. The second important part consists of tables which group technologies by one several attributes such as target site and cross-complex applicability as well as relationship to Resource Conservation Recovery Act Best Demonstrated Available Technologies (RCRA BDATs)
The International Linear Collider Technical Design Report - Volume 3.II: Accelerator Baseline Design

CERN Document Server

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

2013-01-01

The International Linear Collider Technical Design Report (TDR) describes in four volumes the physics case and the design of a 500 GeV centre-of-mass energy linear electron-positron collider based on superconducting radio-frequency technology using Niobium cavities as the accelerating structures. The accelerator can be extended to 1 TeV and also run as a Higgs factory at around 250 GeV and on the Z0 pole. A comprehensive value estimate of the accelerator is give, together with associated uncertainties. It is shown that no significant technical issues remain to be solved. Once a site is selected and the necessary site-dependent engineering is carried out, construction can begin immediately. The TDR also gives baseline documentation for two high-performance detectors that can share the ILC luminosity by being moved into and out of the beam line in a "push-pull" configuration. These detectors, ILD and SiD, are described in detail. They form the basis for a world-class experimental programme that promises to incr...
2011 PERFORMANCE ASSESSMENT COMMUNITY OF PRACTICE TECHNICAL EXCHANGE - SUMMARY

Energy Technology Data Exchange (ETDEWEB)

Seitz, R.

2011-12-30

exchange was the use of panel discussions to solicit feedback from regulators and practitioners. This report summarizes discussions and recommendations from the steering committee meeting and presentations and feedback obtained at the technical exchange. Appendix I includes the steering committee meeting agenda and Appendix II includes the agenda for the technical exchange and a screenshot of the presentations and video files that are available online.
Performance evaluation of the technical capabilities of DOE sites for disposal of mixed low-level waste: Volume 3, Site evaluations

Energy Technology Data Exchange (ETDEWEB)

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

1996-03-01

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

International Nuclear Information System (INIS)

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

1996-03-01

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

International Nuclear Information System (INIS)

1992-09-01

This report documents the results of the combined effort of the NRC and the industry to produce improved Standard Technical Specifications (STS) for Combustion Engineering Plants. The improved STS wee developed based on the criteria in the interim Commission Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, dated February 6, 1987. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. This document, Volume 1, contains the Specifications for all chapters and sections of the improved STS. Volume 2 contains the Bases for Sections 3.4--3.9 of the improved STS
Columbia River System Operation Review final environmental impact statement. Appendix Q: Regional forum

International Nuclear Information System (INIS)

1995-11-01

The System Operation Review (SOR) is a study and environmental compliance process being used by the three Federal agencies to analyze future operations of the system and river use issues. The goal of the SOR is to achieve a coordinated system operation strategy for the river that better meets the needs of all river users. This technical appendix addresses only the effects of alternative system operating strategies for managing the Columbia River system. The SOR is currently developing a System Operating Strategy (SOS) that will guide the physical operations of the Columbia River system. The SOR is also addressing the institutional arrangements that must be in place to make needed changes to the SOS in the future, or make interpretations of the strategy in the light of changing water conditions or river needs. For convenience, this future institutional arrangement is referred to as ''The Columbia River Regional Forum,'' or simply ''the Forum,'' even though the nature of this institution is still to be determined. This appendix and the Final Environmental Impact Statement (EIS) identify the Forum as an administrative process that will not result in impacts to the environment and will not require analysis in a NEPA context. The composition of and procedures followed by a decision making body cannot--in and of themselves--be used to predict a particular decision with definable impacts on the environment. Nevertheless, because of the relationship to the other SOR actions, the SOR lead agencies have prepared this Technical Appendix to provide opportunities for review and comment on the Forum alternatives
Recommendations for a Department of Energy Nuclear Energy R and D Agenda Volume 2 Appendices

International Nuclear Information System (INIS)

1997-01-01

The current US nuclear energy policy is primarily formulated as part of the nation's overall energy policy. In addition, nuclear energy policy is impacted by other US policies, such as those for defense and environment, and by international obligations through their effects on nuclear weapons dismantlement and stewardship, continued reliance on space and naval nuclear power sources, defense waste cleanup, and on nuclear nonproliferation. This volume is composed of the following appendices: Appendix 1--Objectives of the Federal Government Nuclear Energy Related Policies and Research and Development Programs; Appendix 2--Nuclear Energy and Related R and D in the US; Appendix 3--Summary of Issues That Drive Nuclear Energy Research and Development; Appendix 4: Options for Policy and Research and Development; Appendix 5--Pros and Cons of Objectives and Options; and Appendices 6--Recommendations
Recommendations for a Department of Energy Nuclear Energy R and D Agenda Volume 2 Appendices

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-12-01

The current US nuclear energy policy is primarily formulated as part of the nation`s overall energy policy. In addition, nuclear energy policy is impacted by other US policies, such as those for defense and environment, and by international obligations through their effects on nuclear weapons dismantlement and stewardship, continued reliance on space and naval nuclear power sources, defense waste cleanup, and on nuclear nonproliferation. This volume is composed of the following appendices: Appendix 1--Objectives of the Federal Government Nuclear Energy Related Policies and Research and Development Programs; Appendix 2--Nuclear Energy and Related R and D in the US; Appendix 3--Summary of Issues That Drive Nuclear Energy Research and Development; Appendix 4: Options for Policy and Research and Development; Appendix 5--Pros and Cons of Objectives and Options; and Appendices 6--Recommendations.
Department of Energy Programmatic Spent Nuclear Fuel Management and Idaho National Engineering Laboratory Environmental Restoration and Waste Management Programs, Draft Environmental Impact Statement. Volume 1, Appendix D: Part A, Naval Spent Nuclear Fuel Management

Energy Technology Data Exchange (ETDEWEB)

1994-06-01

Volume 1 to the Department of Energy`s Programmatic Spent Nuclear Fuel Management and Idaho National Engineering Laboratory Environmental Management Programs Environmental Impact Statement evaluates a range of alternatives for managing naval spent nuclear fuel expected to be removed from US Navy nuclear-powered vessels and prototype reactors through the year 2035. The Environmental Impact Statement (EIS) considers a range of alternatives for examining and storing naval spent nuclear fuel, including alternatives that terminate examination and involve storage close to the refueling or defueling site. The EIS covers the potential environmental impacts of each alternative, as well as cost impacts and impacts to the Naval Nuclear Propulsion Program mission. This Appendix covers aspects of the alternatives that involve managing naval spent nuclear fuel at four naval shipyards and the Naval Nuclear Propulsion Program Kesselring Site in West Milton, New York. This Appendix also covers the impacts of alternatives that involve examining naval spent nuclear fuel at the Expended Core Facility in Idaho and the potential impacts of constructing and operating an inspection facility at any of the Department of Energy (DOE) facilities considered in the EIS. This Appendix also considers the impacts of the alternative involving limited spent nuclear fuel examinations at Puget Sound Naval Shipyard. This Appendix does not address the impacts associated with storing naval spent nuclear fuel after it has been inspected and transferred to DOE facilities. These impacts are addressed in separate appendices for each DOE site.
Cognitive, Social, and Literacy Competencies: The Chelsea Bank Simulation Project. Year One: Final Report. [Volume 2]: Appendices.

Science.gov (United States)

Duffy, Thomas; And Others

This supplementary volume presents appendixes A-E associated with a 1-year study which determined what secondary school students were doing as they engaged in the Chelsea Bank computer software simulation activities. Appendixes present the SCANS Analysis Coding Sheet; coding problem analysis of 50 video segments; student and teacher interview…
Technical support for GEIS: radioactive waste isolation in geologic formations. Volume 5. Baseline rock properties-granite

International Nuclear Information System (INIS)

1978-04-01

This volume, Y/OWI/TM-36/5, Baseline Rock Properties--Granite, is one of a 23-volume series, ''Technical Support for GEIS: Radioactive Waste Isolation in Geologic Formations, Y/OWI/TM-36'' which supplements a ''Contribution to Draft Generic Environmental Impact Statement on Commercial Waste Management: Radioactive Waste Isolation in Geologic Formations, Y/OWI/TM-44.'' The series provides a more complete technical basis for the preconceptual designs, resource requirements, and environmental source terms associated with isolating commercial LWR wastes in underground repositories in salt, granite, shale and basalt. Wastes are considered from three fuel cycles: uranium and plutonium recycling, no recycling of spent fuel and uranium-only recycling. This report, on the rock properties of typical granites, includes an evaluation of the various test results reported in the literature. Firstly, a literature survey was made in order to obtain a feel for the range of rock properties encountered. Then, granites representative of different geologic ages and from different parts of the United States were selected and studied in further detail. Some of the special characteristics of granite, such as anisotropy, creep and weathering were also investigated. Lastly, intact properties for a typical granite were selected and rock mass properties were derived using appropriate correction factors
The Fukushima Daiichi Accident. Technical Volume 2/5. Safety Assessment

International Nuclear Information System (INIS)

2015-08-01

Technical Volume 1 of this report has described what happened during the accident at the Fukushima Daiichi nuclear power plant (NPP). This volume begins (Section 2.1) with a review of how the design basis of the site for external events was assessed initially and then reassessed over the life of the NPP. The section also describes the physical changes that were made to the units as a result. The remainder of the volume describes the treatment of beyond design basis events in the safety assessment of the site, the accident management provisions, the effectiveness of regulatory programmes, human and organizational factors and the safety culture, and the role of operating experience. Further background information is contained in three annexes included on the CD-ROM of this Technical Volume which describe analytical investigations of the accident along with information on topics such as system performance, defence in depth and severe accident phenomena. Section 2.2 provides an assessment of the systems that failed, resulting in a failure to maintain the fundamental safety functions in Units 1–3, which were in operation at the time of the tsunami and in which the reactor pressure vessels (RPV) and containment vessels failed. The section also describes Units 4-6, which were shut down at the time of the tsunami, and the site’s central spent fuel storage facility. Section 2.3 discusses the probabilistic and deterministic safety assessments of beyond design basis accidents (BDBAs) that had been performed for the plant and the insights from these assessments that had led to changes in the plant’s design. The section pays particular attention to the assessment of extreme natural hazards, such as the one which led to the total loss of AC power supply on the site. The additional loss of DC power supply in Units 1 and 2 played a key role in the progression of the accident because it impeded the diagnosis of plant conditions and made the operators unaware of the status of
Technical specifications Catawba Nuclear Station, Unit 1 (Docket No. 50-413). Appendix A to License No. NPF-31

International Nuclear Information System (INIS)

1984-12-01

This appendix includes: definitions, safety limits and limiting safety system settings, limiting conditions for operation and surveillance requirements, bases, design features, and administrative controls
DART II documentation. Volume III. Appendices

Energy Technology Data Exchange (ETDEWEB)

1979-10-01

The DART II is a remote, interactive, microprocessor-based data acquistion system suitable for use with air monitors. This volume of DART II documentation contains the following appendixes: adjustment and calibration procedures; mother board signature list; schematic diagrams; device specification sheets; ROM program listing; 6800 microprocessor instruction list, octal listing; and cable lists. (RWR)
Technical specifications, Catawba Nuclear Station, Unit 1 (Docket No. 50-413). Appendix A to License No. NPF-24

International Nuclear Information System (INIS)

Anderson, F.D.

1984-07-01

This appendix comprises the following: definitions, safety limits and limiting safety system settings, limiting conditions for operation and surveillance requirements, design features, and administrative controls
Plutonium working group report on environmental, safety and health vulnerabilities associated with the department's plutonium storage. Volume II, Appendix B, Part 13: Sites with small plutonium holdings site assessment team report

International Nuclear Information System (INIS)

1994-09-01

This Appendix contains the initial responses to the Question Set received from each of the sites with small plutonium holdings. The WGAT report for sites with small plutonium holdings was then prepared, based on these initial site responses plus supplemental information obtained via telephone request with the site contractor and/or DOE Field Office personnel. These supplements serve to clarify information in the initial question set responses and/or obtain additional information. This WGAT report is published as Volume II, Part 13
Federal Logistics Information System (FLIS) Procedures Manual. Volume 3. Development and Maintenance of Item Logistics Data Tools.

Science.gov (United States)

1995-01-01

Ammunition for cannon with illu- to fight fires minating projectile started by Ammunition for cannon with incen- explosion. diary projectile...OSNABURG Ozu Aya JEAN 146 DoD 4100.39-M Volume 3 APPENDIX 3-3-B SAMPLE OF NEW CONCEPT FIIG FIIG SAMPLE INC 00000 APPENDIX C Table 32 Palm Beach PLAIN
Standard Technical Specifications, Combustion Engineering plants

International Nuclear Information System (INIS)

1992-09-01

This NUREG contains improved Standard Technical Specifications (M) for Combustion Engineering (CE) Plants and documents the positions of the Nuclear Regulatory Commission based on the CE Owners Group's proposed STS. This document is the result of extensive technical meetings and discussions among the NRC staff, the Nuclear Steam Supply System (NSSS) Owners Groups, the NSSS vendors, and the Nuclear Management and Resources Council (NUMARC). The improved STS were developed based on the criteria in the interim Commission Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, dated February 6, 1987. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. Volume 1 contains the Specifications for all chapters and sections of the improved STS. This document Volume 2 contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1--3.3 of the improved STS. Volume 3 contains the Bases for Sections 3.4--3.9 of the improved STS
Standard Technical Specifications, Combustion Engineering plants

International Nuclear Information System (INIS)

1992-09-01

This NUREG contains improved Standard Technical Specifications (STS) for Combustion Engineering (CE) Plants and documents the positions of the Nuclear Regulatory Commission based on the CE Owners Group's proposed STS. This document is the result of extensive technical meetings and discussions among the NRC staff, the Nuclear Steam Supply System (NSSS) Owners Groups, the NSSS vendors, and the Nuclear Management and Resources Council (NUMARC). The improved STS were developed based on the criteria in the interim Commission Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, dated February 6, 1987. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. Volume 1 contains the Specifications for all chapters and sections of the improved SM. Volume 2 contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1--3.3 of the improved STS. This document Volume 3 contains the Bases for Sections 3.4--3.9 of the improved M

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

Science.gov (United States)

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

1984-01-01

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

International Nuclear Information System (INIS)

1995-11-01

The System Operation Review (SOR) is a study and environmental compliance process being used by the three Federal agencies to analyze future operations of the system and river use issues. The goal of the SOR is to achieve a coordinated system operation strategy for the river that better meets the needs of all river users. This technical appendix addresses only the effects of alternative system operating strategies for managing the Columbia River system. The Navigation Technical Appendix presents the analysis of the various SOR alternatives in terms of their potential affects on the congressionally authorized navigation system within the Columbia and Snake river waterways. The focus of the study, impacts to the authorized navigation, improvements/developments, reflects on one of the continuing historical missions of the US Army Corps of Engineers: to promote safe commercial navigation of the nation's waterways benefiting the development of commerce within the US. The study and evaluation process involved Scoping, Screening and Full Scale Evaluation. During screening two models were developed; one was used to evaluate the effects of the various alternatives on navigation through the Snake River Projects and the other the effects on the Dworshak Pool. Full Scale Analysis was expanded to included a study of effects throughout the system
Percutaneous Image-Guided Cryoablation of Challenging Mediastinal Lesions Using Large-Volume Hydrodissection: Technical Considerations and Outcomes

Energy Technology Data Exchange (ETDEWEB)

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

2016-11-15

ObjectiveThis study was designed to describe the technique of percutaneous image-guided cryoablation with large-volume hydrodissection for the treatment of challenging mediastinal lesions.MethodsBetween March 2014 and June 2015, three patients (mean age 62.7 years) with four neoplastic anterior mediastinal lesions underwent five cryoablation procedures using large-volume hydrodissection. Procedures were performed under general anaesthesia using CT guidance. Lesion characteristics, hydrodissection and cryoablation data, technical success, complications, and clinical outcomes were assessed using retrospective chart review.ResultsLesions (mean size 2.7 cm; range 2–4.3 cm) were in contact with great vessels (n = 13), trachea (n = 3), and mediastinal nerves (n = 6). Hydrodissection was performed intercostally (n = 4), suprasternally (n = 2), transsternally (n = 1), or via the sternoclavicular joint (n = 1) using 1–3 spinal needles over 13.4 (range 7–26) minutes; 450 ml of dilute contrast was injected (range 300–600 ml) and increased mean lesion-collateral structure distance from 1.9 to 7.7 mm. Vulnerable mediastinal nerves were identified in four of five procedures. Technical success was 100 %, with one immediate complication (recurrent laryngeal nerve injury). Mean follow-up period was 15 months. One lesion demonstrated residual disease on restaging PET-CT and was retreated to achieve complete ablation. At last follow-up, two patients remained disease-free, and one patient developed distant disease after 1 year without local recurrence.ConclusionsCryoablation using large-volume hydrodissection is a feasible technique, enabling safe and effective treatment of challenging mediastinal lesions.
Nuclear physics: appendix to the Daresbury annual report 1990/91

International Nuclear Information System (INIS)

1991-01-01

This nuclear physics chapter of the Annual Report of the Daresbury Laboratory of the United Kingdom Science and Engineering Research Council describes the work of the Nuclear Structure Facility. In the limited space available it necessarily provides only a broad outline of the facility, its development and a flavour of the research in a selection of a few highlighted topics. This appendix complements the first volume of the Report reproducing users' short camera ready scientific reports. These describe the progress and results of each experimental proposal. Reports are grouped in five sections: research into nuclear structure with contributions ordered in increasing Z number of the nuclei studies; investigations of nuclear reaction mechanisms; nuclear theory; atomic physics; and accelerator operations, developments and instrumentation. The appendix forms a compact record of the work of the Nuclear Structure Facility for the year 1990/91. (author)
The International Linear Collider Technical Design Report - Volume 3.II: Accelerator Baseline Design

Energy Technology Data Exchange (ETDEWEB)

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

2013-06-26

The International Linear Collider Technical Design Report (TDR) describes in four volumes the physics case and the design of a 500 GeV centre-of-mass energy linear electron-positron collider based on superconducting radio-frequency technology using Niobium cavities as the accelerating structures. The accelerator can be extended to 1 TeV and also run as a Higgs factory at around 250 GeV and on the Z0 pole. A comprehensive value estimate of the accelerator is give, together with associated uncertainties. It is shown that no significant technical issues remain to be solved. Once a site is selected and the necessary site-dependent engineering is carried out, construction can begin immediately. The TDR also gives baseline documentation for two high-performance detectors that can share the ILC luminosity by being moved into and out of the beam line in a "push-pull" configuration. These detectors, ILD and SiD, are described in detail. They form the basis for a world-class experimental programme that promises to increase significantly our understanding of the fundamental processes that govern the evolution of the Universe.
Impacts of Outer Continental Shelf (OCS) development on recreation and tourism. Volume 2. Final report and case studies

Energy Technology Data Exchange (ETDEWEB)

1987-04-01

The final report for the project is comprised of five volumes. The volume presents the study conclusions, summarizes the methodology used (more detail is found in Volume 3), discusses four case study applications of the model, and contains profiles of coastal communities in an Appendix.
Columbia River System Operation Review : Final Environmental Impact Statement, Appendix D: Exhibits.

Energy Technology Data Exchange (ETDEWEB)

Columbia River System Operation Review (U.S.)

1995-11-01

The Columbia River and its tributaries are the primary water system in the Pacific Northwest, draining some 219,000 square miles in seven states and another 39,500 square miles in British Columbia. Beginning in the 1930`s, the Columbia River has been significantly modified by construction of 30 major dams on the river and its tributaries, along with dozens of non-Federal projects. Construction and subsequent operation of these water development projects have contributed to eight primary uses of the river system, including navigation, flood control, irrigation, electric power generation, fish migration, fish and wildlife habitat, recreation, and water supply and quality considerations. Increasing stress on the water development of the Columbia River and its tributaries has led primary Federal agencies to undertake intensive analysis and evaluation of the operation of these projects. These agencies are the U.S. Army Corps of Engineers and the Bureau of Reclamation, who operate the large Federal dams on the river, and the Bonneville Power Administration who sells the power generated at the dams. This review, termed the System Operation Review (SOR), has as its ultimate goal to define a strategy for future operation of the major Columbia River projects which effectively considers the needs of all river uses. This volume, Appendix D: Cultural resources appendix, Technical imput includes the following: Development of geomorphology based framework for cultural resources management, Dworshak Reservoir, Idaho; Impact profiles for SOR reservoirs; comments from the following Native American tribes: Burns Paiute Tribe; Coville Confederated Tribes; Confederated Tribes of the Warm Springs Indian Reservation; Confederated Tribes and bands of the Yakama Indian Nation (comments); Nez Perce Tribe; Coeur D`Alene Tribe; Spokane Tribe of Indians; The confederated Tribes of the Umatilla Indian Reservation.
Technical summary of groundwater quality protection program at Savannah River Plant. Volume 1. Site geohydrology, and solid and hazardous wastes

International Nuclear Information System (INIS)

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

1983-12-01

The program for protecting the quality of groundwater underlying the Savannah River Plant (SRP) is described in this technical summary report. The report is divided into two volumes. Volume I contains a discussion of the general site geohydrology and of both active and inactive sites used for disposal of solid and hazardous wastes. Volume II includes a discussion of radioactive waste disposal. Most information contained in these two volumes is current as of December 1983. The groundwater quality protection program has several elements which, taken collectively, are designed to achieve three major goals. These goals are to evaluate the impact on groundwater quality as a result of SRP operations, to restore or protect groundwater quality by taking corrective action as necessary, and to ensure disposal of waste materials in accordance with regulatory guidelines
Performance evaluation of the technical capabilities of DOE sites for disposal of mixed low-level waste. Volume 1: Executive summary

International Nuclear Information System (INIS)

1996-03-01

A team of analysts designed and conducted a performance evaluation (PE) to estimate the technical capabilities of fifteen Department of Energy sites for disposal of mixed low-level waste (i.e., waste that contains both low-level radioactive materials and hazardous constituents). Volume 1 summarizes the process for selecting the fifteen sites, the methodology used in the evaluation, and the conclusions derived from the evaluation. Volume 1 is an executive summary both of the PE methodology and of the results obtained from the PEs. While this volume briefly reviews the scope and method of analyses, its main objective is to emphasize the important insights and conclusions derived from the conduct of the PEs. Volume 2 provides details about the site-selection process, the performance-evaluation methodology, and the overall results of the analysis. Volume 3 contains detailed evaluations of the fifteen sites and discussions of the results for each site
Technical support for GEIS: radioactive waste isolation in geologic formations. Volume 7. Baseline rock properties-basalt

International Nuclear Information System (INIS)

1978-04-01

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

International Nuclear Information System (INIS)

1992-09-01

This NUREG contains improved Standard Technical Specifications (STS) for Babcock and Wilcox (B ampersand W) Plants and documents the positions of the Nuclear Regulatory Commission based on the B ampersand W Owners Group's proposed STS. This document is the result of extensive technical meetings and discussions among the NRC staff, the Nuclear Steam Supply System (NSSS) Owners Groups, the NSSS vendors, and the Nuclear Management and Resources Council (NUMARC). The improved STS were developed based on the criteria in the interim Commission Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, dated February 6, 1987. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. Volume 1 contains the Specifications for all chapters and sections of the improved STS. This document Volume 2, contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1--3.3 of the improved STS. Volume 3 contains the Bases for Sections 3.4--3.10 of the improved STS
Abbreviations [Annex to The Fukushima Daiichi Accident, Technical Volume 2/5

International Nuclear Information System (INIS)

2015-01-01

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

Energy Technology Data Exchange (ETDEWEB)

2004-04-01

This report appendix describes aspects of a project to demonstrate the technical and economic feasibility of aggregating distributed generating resources in New York State. This project demonstrates a system that allows distributed generation (DG) to participate in competitive markets in much the same way as large central-station power plants. This approach involves aggregating the distributed demand-side resources into a single transaction entity consistent with the requirements of the New York Independent System Operator (NYISO). This single entity then buys or sells capacity and energy (i.e., curtailment) in NYISO markets.
Technical and economic assessment of solar hybrid repowering: conceptual design and cost estimate

Energy Technology Data Exchange (ETDEWEB)

None

1978-09-01

This volume contains the appendix to the conceptual design and cost estimate report on solar repowering the Reeves Unit No. 2 power plant in Albuquerque, New Mexico. Included are the engineering drawings and the work breakdown structure estimate report. (WHK)
Risk based technique for improving technical specifications

International Nuclear Information System (INIS)

Kim, I. S.; Jae, M. S.; Kim, B. S.; Hwang, S. W.; Kang, K. M.; Park, S. S.; Yu, Y. S.

2001-03-01

The objective of this study is to develop the systematic guidance for reviewing the documents associated with the changes of technical specifications. The work done in this fiscal year is the following : surveys in TS requirements, TS improvements and TS regulations in foreign countries as well as Korea, surveys on the state-of-the-art of RITSs and their use in Korea, development of a decision-making framework for both the licensee and the regulation agency, description of risk measures, assessment methodology on STI/AOT, and adverse effects caused by periodic maintenance, which are explained in appendix. The results of this study might contribute to enhancing the quality of the current technical specifications and contribute to preparing the risk informed regulation program using the decision-making framework developed in this study
Proceedings of the 2010 AFMS Medical Research Symposium. Volume 5. Nursing Track: Abstracts and Presentations

Science.gov (United States)

2011-03-15

Management Education at a Military Hospital .................................................................. 29 Proceedings of the 2010 AFMS... education information is in Appendix C of this volume. Appendices D-L are copies of presentation slides from the plenary sessions.  Volume 2. This volume...women who have menstruation as compared to deployed women who do not have menstruation ? This study is a descriptive co relational research design. The
Installation restoration program site investigation. Gulfport Field Training Site, Mississippi Air National Guard Gulfport-Biloxi Regional Airport Gulfport, Mississippi. Volume 2. Final report

Energy Technology Data Exchange (ETDEWEB)

NONE

1992-12-01

Site Investigation Report, Volume: 2. A Site Investigation was performed at 3 sites at the Combat Readiness Training Center, Gulfport-Bolixi. The 3 sites investigated are the: Former Fire Training Area (Site 1), the Former JP-4 Bulk Storage Area, Mill Road (Site 2), and the Motor Pool Above-Ground Diesel Fuel Storage Tank Area (Site 3). The findings of this investigation recommended further investigation at the Fire Training Area and the JP-4 Bulk Storage Tank. At Site 3 the levels of contamination did not represent a risk to human health or the environment; therefore, no further action was recommended. Volume two of this report consisted of the following Appendixes: Site Photographs (A), Well Inventory (B), Boring Logs (C), CSL Technical Memorandum (D), Data Review and Validation (E), GPS Memorandum (F), Level C Analytical Data Summary Tables (G), Slug Test (H), Special-Status Species (I), and Representative Species of Less Mobile Fish and Wildlife (J).
Salt Repository Project. FY-84 technical project plan

International Nuclear Information System (INIS)

1984-08-01

The FY 84 technical plans for the Salt Repository Project (SRP) are briefly presented. The objectives of the project in relation to the Civilian Radioactive Waste Management (CRWM) program are discused and the technical activities directed toward accomplishing these objectives are detailed. A budget is presented for each of the Level 2 Work Breakdown Structure Tasks (Systems, Waste Package, Site, Repository, Regulatory and Institutional, Test Facilities, Exploratory Shaft, Land Acquisition, and Program Management) in an appendix. An overall description, current status, and planned activities are presented for each of the subtasks which make up the above-mentioned Level 2 tasks. Milestones and their definitions for the plan year, as well as milestones for the outyears are also presented at this same subtask level for each subtask
NATO Reference Mobility Model. Edition I. Users Guide. Volume I

Science.gov (United States)

1979-10-01

C TOTAL ERAKING FCRCE - SCIL /SLOPE/VEHICLE C --- ----.----------- C 275 R-2WJ58# VCLUIJE I PAGE A-103 APPEND-IX A - LISTING CF O.CFAt’ NRtPM C 1...sGCW vN1RAV ,SFTYPC 9TBF I- c r-------------------------~e e C tPAXIMUP BRAKING FCRCE * SCIL /SL OP E/V ENICLE/ DRIVER C --------------------- C C 1. VAR...CONTINUE GO TC 2160 ,ýObO IFl IST ,NE, 21 GC TG 2110i 317 R-20358, VOLUME I PAGE A-145 APPENDIX A - LISTING CF FRGG/iAM NAMM C 8. COARSE GRAINED SCIL IF
Backfilling and sealing of tunnels, shafts and boreholes. Volume 2: Appendices

International Nuclear Information System (INIS)

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

1984-12-01

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

SMACS - a system of computer programs for probabilistic seismic analysis of structures and subsystems. Volume II. Example problem

International Nuclear Information System (INIS)

Maslenikov, O.R.; Johnson, J.J.; Tiong, L.W.; Mraz, M.J.; Bumpus, S.; Gerhard, M.A.

1985-03-01

In this volume of the SMACS User's Manual an example problem is presented to demonstrate the type of problem that SMACS is capable of solving and to familiarize the user with format of the various data files involved. This volume is organized into thirteen appendices which follow a short description of the problem. Each appendix contains listings of the input and output files associated with each computer run that was necessary to solve the problem. In cases where one SMACS program uses data generated by another SMACS program, the data file is shown in the appendix for the programs which generated it
Appendix A : literature review.

Science.gov (United States)

2013-03-01

This appendix contains a review of the literature and other background information : germane to the experimental and analytical research presented in subsequent appendices. Table : 1 lists the sections and topics contained in this appendix and those ...
Appendix the theory of space with introduction, comments, and addenda

CERN Document Server

Kárteszi, F

1987-01-01

The epoch-making work of János Bolyai is presented here, together with a supplement outlining Hungarian political and science history to help the reader to get acquainted with the miserable fate of János Bolyai and with his intellectual world. A facsimile of a copy of Bolyai''s original 1831 Scientia Spatii (also known as the Appendix) is included, together with a translation. Comments and notes, and a survey of the effects of his work, complete the volume.
Scientific-technical reports by the GKSS in 1975

International Nuclear Information System (INIS)

1976-01-01

The scientific-technical reports of the GKSS which are for the use within the GKSS (internal reports), are summarized in the I-series, whereas the E-series contains the publications suitable for external circulation and for exchange of information with other research facilities and industrial undertakings. The survey contains data on titles and authors of all GKSS reports published in the year 1975. Of the external reports, abstracts and/or bibliographical data are reproduced in the appendix. (orig/LH) [de
Columbia River System Operation Review final environmental impact statement. Appendix L: Soils, geology and groundwater

International Nuclear Information System (INIS)

1995-11-01

The System Operation Review (SOR) is a study and environmental compliance process being used by the three Federal agencies to analyze future operations of the system and river use issues. The goal of the SOR is to achieve a coordinated system operation strategy for the river that better meets the needs of all river users. This technical appendix addresses only the effects of alternative system operating strategies for managing the Columbia River system. This appendix addresses the study of geology, soils, and groundwater concerns relative to the System Operation Review (SOR). Chapter 1 provides an overview of the study, scope, and process for this resource area. In order, the respective sections of this chapter discuss the relevant issues for the study, and the means by which the SOR team carried out the study
Experimental Facilities Division/User Program Division technical progress report 1999-2000

International Nuclear Information System (INIS)

2001-01-01

In October 1999, the two divisions of the Advanced Photon Source (APS), the Accelerator Systems Division (ASD) and the Experimental Facilities Division (XFD), were reorganized into four divisions (see high-level APS organizational chart, Fig. 1.1). In addition to ASD and XFD, two new divisions were created, the APS Operations Division (AOD), to oversee APS operations, and the User Program Division (UPD), to serve the APS user community by developing and maintaining the highest quality user technical and administration support. Previous XFD Progress Reports (ANL/APS/TB-30 and ANL/APS/TB-34) covered a much broader base, including APS user administrative support and what was previously XFD operations (front ends, interlocks, etc.) This Progress Report summarizes the main scientific and technical activities of XFD, and the technical support, research and development (R and D) activities of UPD from October 1998 through November 2000. The report is divided into four major sections, (1) Introduction, (2) SRI-CAT Beamlines, Technical Developments, and Scientific Applications, (3) User Technical Support, and (4) Major Plans for the Future. Sections 2 and 3 describe the technical activities and research accomplishments of the XFD and UPD personnel in supporting the synchrotron radiation instrumentation (SRI) collaborative access team (CAT) and the general APS user community. Also included in this report is a comprehensive list of publications (Appendix 1) and presentations (Appendix 2) by XFD and UPD staff during the time period covered by this report. The organization of section 2, SRI CAT Beamlines, Technical Developments, and Scientific Applications has been made along scientific techniques/disciplines and not ''geographical'' boundaries of the sectors in which the work was performed. Therefore items under the subsection X-ray Imaging and Microfocusing could have been (and were) performed on several different beamlines by staff in different divisions. The management of
Columbia River System Operation Review final environmental impact statement. Appendix E: Flood control

International Nuclear Information System (INIS)

1995-11-01

The System Operation Review (SOR) is a study and environmental compliance process being used by the three Federal agencies to analyze future operations of the system and river use issues. The goal of the SOR is to achieve a coordinated system operation strategy for the river that better meets the needs of all river users. This technical appendix addresses only the effects of alternative system operating strategies for managing the Columbia River system. The Corps of Engineers, Bonneville Power Administration, and Bureau of Reclamation conducted a scoping process consisting of a series of regionwide public meetings and solicitation of written comments in the summer of 1990. Comments on flood control issues were received from all parts of the Columbia river basin. This appendix includes issues raised in the public scoping process, as well as those brought for consideration by members of the Flood Control Work Group
Technical specifications Shoreham Nuclear Power Station, Unit No. 1 (Docket No. 50-322). Appendix A to License No. NPF-19

International Nuclear Information System (INIS)

1984-12-01

This appendix includes definitions, safety limits and limiting safety system settings, limiting conditions for operation and surveillance requirements, bases, design features, and administrative controls
The System 80+ Standard Plant design control document. Volume 20

International Nuclear Information System (INIS)

1997-01-01

This Design Control Document (DCD) is a repository of information comprising the System 80+trademark Standard Plant Design. The DCD also provides that design-related information to be incorporated by reference in the design certification rule for the System 80+ Standard Plant Design. Applicants for a combined license pursuant to 10 CFR 52 must ensure that the final Design Certification Rule and the associated Statements of Consideration are used when making all licensing decisions relevant to the System 80+ Standard Plant Design. The Design Control Document contains the DCD introduction, The Certified Design Material (CDM) [i.e., ''Tier 1''] and the Approved Design Material (ADM) [i.e., ''Tier 2''] for the System 80+ Standard Plant Design. The CDM includes the following sections: (1) Introductory material; (2) Certified Design Material for System 80+ systems and structures; (3) Certified Design Material for non-system-based aspects of the System 80+ Certified design; (4) Interface requirements; and (5) Site parameters. The ADM, to the extent applicable for the System 80+ Standard Plant Design, includes: (1) the information required for the final safety analysis report under 20 CFR 50.34; (2) other relevant information required by 10 CFR 52.47; and (3) emergency operations guidelines. This volume contains 2 technical specifications bases as part of Appendix 16 A Tech Spec Bases. They are TS B3.8 Electrical Power Technical Systems Bases and TS B3.9 Refueling Operations Bases. All 3 parts of section 17 (QA) and all 10 parts of section 18 (Human Factors) of the ADM Design and Analysis are contained in this volume. Topics covered in section 17 are: design phase QA; operations phase QA; and design phase reliability assurance. Topics covered by section 18 are: design team organization; design goals; design process; functional task analysis; control room configuration; information presentation; control and monitoring; verification and validation; and review documents
Columbia River final environmental impact statement. Appendix B: Air quality

International Nuclear Information System (INIS)

1995-11-01

The System Operation Review (SOR) is a study and environmental compliance process being used by the three Federal agencies to analyze future operations of the system and river use issues. The goal of the SOR is to achieve a coordinated system operation strategy for the river that better meets the needs of all river users. This technical appendix addresses only the effects of alternative system operating strategies for managing the Columbia River system. This appendix consists of eight chapters. Chapter 1 describes the air quality issues that were raised in the SOR scoping process and provides an overview of the study process used to evaluate air quality effects from various system operation alternatives. Chapter 2 describes the Federal, state, and local programs that regulate air quality and discusses the air quality standards that are relevant to the analysis. It also gives an overview of the limatology of the region and the existing air quality in the Columbia River Basin, including areas of non-attainment for relevant air quality standards. Chapter 3 presents the methods this study uses for the analysis of air quality and for the evaluation of human health effects from air pollutants. Chapter 4 provides the study results for the System Operating Strategy (SOS) alternatives and potential mitigation measures. Chapter 5 compares impacts on air quality and human health across alternatives, and discusses mitigation measures and cumulative effects. Chapters 6, 7, and 8 contain the list of preparers, glossary, and references, respectively. Technical exhibits supporting the analysis are also included
Standard Technical Specifications, General Electric Plants, BWR/6

International Nuclear Information System (INIS)

1992-09-01

This NUREG contains improved Standard Technical Specifications (STS) for General Electric Plants, BWR/4, and documents the positions of the Nuclear Regulatory Commission based on the BWR Owners Group's proposed STS. This document is the result of extensive technical meetings and discussions among the NRC staff, the Nuclear Steam Supply System (NSSS) Owners Groups, the NSSS vendors, and the Nuclear Management and Resources Council (NUMARC). The improved STS were developed based on the criteria in the interim Commission Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, dated February 6, 1987. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. Volume 1 contains the Specifications for all chapters and sections of the improved STS. Volume 2 contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1--3.3 of the improved STS. Volume 3, contains the Bases for Sections 3.4--3.10 of the improved STS
Standard Technical Specifications, General Electric plants, BWR/4

International Nuclear Information System (INIS)

1992-09-01

This NUREG contains improved Standard Technical Specifications (STS) for General Electric Plants, BWR/6, and documents the positions of the Nuclear Regulatory Commission based on the B ampersand W Owners Group's proposed STS. This document is the result of extensive technical meetings and discussions among the NRC staff, the Nuclear Steam Supply System (NSSS) Owners Groups, the NSSS vendors, and the Nuclear Management and Resources Council (NUMARC). The improved STS were developed based on the criteria in the interim Commission Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, dated February 6, 1987. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. Volume 1 contains the Specifications for all chapters and sections of the improved STS. Volume 2 contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1--3.3 of the improved STS. This document Volume 3, contains the Bases for Sections 3.4--3.10 of the improved STS
Standard Technical Specifications, General Electric plants, BWR/6

International Nuclear Information System (INIS)

1992-09-01

This NUREG contains improved Standard Technical Specifications (STS) for General Electric Plants, BWR/6, and documents the positions of the Nuclear Regulatory Commission based on the B ampersand W Owners Group's proposed STS. This document is the result of extensive technical meetings and discussions among the NRC staff, the Nuclear Steam Supply System (NSSS) Owners Groups, the NSSS vendors, and the Nuclear Management and Resources Council (NUMARC). The improved STS were developed based on the criteria in the interim Commission Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, dated February 6, 1987. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. Volume 1 contains the Specifications for all chapters and sections of the improved STS. This document Volume 2, contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1--3.3 of the improved STS. Volume 3 contains the Bases for Sections 3.4--3.10 of the improved STS
Standard Technical Specifications, General Electric Plants, BWR/6

International Nuclear Information System (INIS)

1992-09-01

This NUREG contains improved Standard Technical Specifications (STS) for General Electric Plants, BWR/6, and documents the positions of the Nuclear Regulatory Commission based on the B ampersand W Owners Group's proposed STS. This document is the result of extensive technical meetings and discussions among the NRC staff, the Nuclear Steam Supply System (NSSS) Owners Groups, the NSSS vendors, and the Nuclear Management and Resources Council (NUMARC). The improved STS were developed based on the criteria in the interim Commission Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, dated February 6, 1987. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. This document Volume 1, contains the Specifications for all chapters and sections of the improved STS. Volume 2 contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1--3.3 of the improved STS. Volume 3 contains the Bases for Sections 3.4--3.10 of the improved STS
Standard Technical Specifications, General Electric plants, BWR/4

International Nuclear Information System (INIS)

1992-09-01

This NUREG contains improved Standard Technical Specifications (STS) for General Electric Plants, BWR/6, and documents the positions of the Nuclear Regulatory Commission based on the BWR Owners Group's proposed STS. This document is the result of extensive technical meetings and discussions among the NRC staff, the Nuclear Steam Supply System (NSSS) Owners Groups, the NSSS vendors, and the Nuclear Management and Resources Council (NUMARC). The improved STS were developed based on the criteria in the interim Commission Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, dated February 6, 1987. The improved STS will be used as the basis for individual nuclear power plant licensees to develop improved plant-specific technical specifications. This report contains three volumes. This document Volume 1 contains the Specifications for all chapters and sections of the improved STS. Volume 2 contains the Bases for Chapters 2.0 and 3.0, and Sections 3.1--3.3 of the improved STS. Volume 3 contains the Bases for Sections 3.4--3.10 of the improved STS
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.
Nuclear proliferation and civilian nuclear power: report of the Nonproliferation Alternative Systems Assessment Program. Volume IX. Reactor and fuel cycle descriptions

Energy Technology Data Exchange (ETDEWEB)

1979-12-01

The Nonproliferation Alternative Systems Assessment Program (NASAP) has characterized and assessed various reactor/fuel-cycle systems. Volume IX provides, in summary form, the technical descriptions of the reactor/fuel-cycle systems studied. This includes the status of the system technology, as well as a discussion of the safety, environmental, and licensing needs from a technical perspective. This information was then used in developing the research, development, and demonstration (RD and D) program, including its cost and time frame, to advance the existing technology to the level needed for commercial use. Wherever possible, the cost data are given as ranges to reflect the uncertainties in the estimates. Volume IX is divided into three sections: Chapter 1, Reactor Systems; Chapter 2, Fuel-Cycle Systems; and the Appendixes. Chapter 1 contains the characterizations of the following 12 reactor types: light-water reactor; heavy-water reactor; water-cooled breeder reactor; high-temperature gas-cooled reactor; gas-cooled fast reactor; liquid-metal fast breeder reactor; spectral-shift-controlled reactor; accelerator-driven reactor; molten-salt reactor; gaseous-core reactor; tokamak fusion-fisson hybrid reactor; and fast mixed-spectrum reactor. Chapter 2 contains similar information developed for fuel-cycle facilities in the following categories: mining and milling; conversion and enrichment; fuel fabrication; spent fuel reprocessing; waste handling and disposal; and transportation of nuclear materials.
Nuclear proliferation and civilian nuclear power: report of the Nonproliferation Alternative Systems Assessment Program. Volume IX. Reactor and fuel cycle descriptions

International Nuclear Information System (INIS)

1979-12-01

The Nonproliferation Alternative Systems Assessment Program (NASAP) has characterized and assessed various reactor/fuel-cycle systems. Volume IX provides, in summary form, the technical descriptions of the reactor/fuel-cycle systems studied. This includes the status of the system technology, as well as a discussion of the safety, environmental, and licensing needs from a technical perspective. This information was then used in developing the research, development, and demonstration (RD and D) program, including its cost and time frame, to advance the existing technology to the level needed for commercial use. Wherever possible, the cost data are given as ranges to reflect the uncertainties in the estimates. Volume IX is divided into three sections: Chapter 1, Reactor Systems; Chapter 2, Fuel-Cycle Systems; and the Appendixes. Chapter 1 contains the characterizations of the following 12 reactor types: light-water reactor; heavy-water reactor; water-cooled breeder reactor; high-temperature gas-cooled reactor; gas-cooled fast reactor; liquid-metal fast breeder reactor; spectral-shift-controlled reactor; accelerator-driven reactor; molten-salt reactor; gaseous-core reactor; tokamak fusion-fisson hybrid reactor; and fast mixed-spectrum reactor. Chapter 2 contains similar information developed for fuel-cycle facilities in the following categories: mining and milling; conversion and enrichment; fuel fabrication; spent fuel reprocessing; waste handling and disposal; and transportation of nuclear materials
Emergency Victim Care. A Training Manual for Emergency Medical Technicians. Module 14. Appendix I: Communicating with Deaf and Hearing Impaired Patients. Appendix II: Medical Terminology. Appendix III: EMS Organizations. Appendix IV: Legislation (Ohio). Glossary of Terms. Index. Revised.

Science.gov (United States)

Ohio State Dept. of Education, Columbus. Div. of Vocational Education.

This training manual for emergency medical technicians, one of 14 modules that comprise the Emergency Victim Care textbook, contains appendixes, a glossary, and an index. The first appendix is an article on communicating with deaf and hearing-impaired patients. Appendix 2, the largest section in this manual, is an introduction to medical…
Heat plan Denmark 2010. Appendix report; Varmeplan Danmark 2010. Bilagsrapport

Energy Technology Data Exchange (ETDEWEB)

Dyrelund, A.; Fafner, K.; Ulbjerg, F. (and others)

2010-09-15

Heat Plan Denmark 2010 is an update of Heat Plan Denmark 2008 and confirms how the sector has reduced the CO{sub 2} emission in Denmark since 1980 and how this development can continue in a cost effective way to an almost CO{sub 2} neutral heating sector in 2030. The study is based on an overall least cost evaluation of the best existing technology taking into account the interaction between buildings, district heating and the power system with a large share of wind energy. The present appendix report contains the technical and economical documentation for the main report. (ln)

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

International Nuclear Information System (INIS)

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

2009-01-01

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

Energy Technology Data Exchange (ETDEWEB)

None

1992-10-01

This appendix on Mass Burn Technologies is the first in a series designed to identify, describe and assess the suitability of several currently or potentially available generic technologies for the management of municipal solid waste (MSW). These appendices, which cover eight core thermoconversion, bioconversion and recycling technologies, reflect public domain information gathered from many sources. Representative sources include: professional journal articles, conference proceedings, selected municipality solid waste management plans and subscription technology data bases. The information presented is intended to serve as background information that will facilitate the preparation of the technoeconomic and life cycle mass, energy and environmental analyses that are being developed for each of the technologies. Mass burn has been and continues to be the predominant technology in Europe for the management of MSW. In the United States, the majority of the existing waste-to-energy projects utilize this technology and nearly 90 percent of all currently planned facilities have selected mass burn systems. Mass burning generally refers to the direct feeding and combustion of municipal solid waste in a furnace without any significant waste preprocessing. The only materials typically removed from the waste stream prior to combustion are large bulky objects and potentially hazardous or undesirable wastes. The technology has evolved over the last 100 or so years from simple incineration to the most highly developed and commercially proven process available for both reducing the volume of MSW and for recovering energy in the forms of steam and electricity. In general, mass burn plants are considered to operate reliably with high availability.
Space Flight Human System Standards (SFHSS). Volume 2; Human Factors, Habitability and Environmental Factors" and Human Integration Design Handbook (HIDH)

Science.gov (United States)

Davis, Jeffrey R.; Fitts, David J.

2009-01-01

This viewgraph presentation reviews the standards for space flight hardware based on human capabilities and limitations. The contents include: 1) Scope; 2) Applicable documents; 3) General; 4) Human Physical Characteristics and Capabilities; 5) Human Performance and Cognition; 6) Natural and Induced Environments; 7) Habitability Functions; 8) Architecture; 9) Hardware and Equipment; 10) Crew Interfaces; 11) Spacesuits; 12) Operatons: Reserved; 13) Ground Maintenance and Assembly: Reserved; 14) Appendix A-Reference Documents; 15) Appendix N-Acronyms and 16) Appendix C-Definition. Volume 2 is supported by the Human Integration Design Handbook (HIDH)s.
Technical support for GEIS: radioactive waste isolation in geologic formations. Volume 6. Baseline rock properties-shale

International Nuclear Information System (INIS)

1978-04-01

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

Energy Technology Data Exchange (ETDEWEB)

Oregon. Dept. of Fish and Wildlife; Mount Hood National Forest (Or.)

1985-06-01

Studies were conducted to describe current habitat conditions in the White River basin above White River Falls and to evaluate the potential to produce anadromous fish. An inventory of spawning and rearing habitats, irrigation diversions, and enhancement opportunities for anadromous fish in the White River drainage was conducted. Survival of juvenile fish at White River Falls was estimated by releasing juvenile chinook and steelhead above the falls during high and low flow periods and recapturing them below the falls in 1983 and 1984. Four alternatives to provide upstream passage for adult salmon and steelhead were developd to a predesign level. The cost of adult passage and the estimated run size of anadromous fish were used to determine the benefit/cost of the preferred alternative. Possible effects of the introduction of anadromous fish on resident fish and on nearby Oak Springs Hatchery were evaluated. This included an inventory of resident species, a genetic study of native rainbow, and the identification of fish diseases in the basin. This volume contains appendices of habitat survey data, potential production, resident fish population data, upstream passage designs, and benefit/cost calculations. (ACR)
White Oak Creek watershed: Melton Valley area Remedial Investigation report, at the Oak Ridge National Laboratory, Oak Ridge, Tennessee: Volume 2, Appendixes A and B

International Nuclear Information System (INIS)

1996-11-01

This document contains Appendixes A ''Source Inventory Information for the Subbasins Evaluated for the White Oak Creek Watershed'' and B ''Human Health Risk Assessment for White Oak Creek / Melton Valley Area'' for the remedial investigation report for the White Oak Creek Watershed and Melton Valley Area. Appendix A identifies the waste types and contaminants for each subbasin in addition to the disposal methods. Appendix B identifies potential human health risks and hazards that may result from contaminants present in the different media within Oak Ridge National Laboratory sites
Fiscal Year 1986 Department of Energy authorization (basic research programs). Volume II-B. Hearing before the Subcommittee on Energy Development and Applications of the Committee on Science and Technology, US House of Representatives, Ninety-Ninth Congress, First Session, February 28, 1985

International Nuclear Information System (INIS)

Anon.

1985-01-01

Volume II-B of the hearing record contains Appendix 3 and Appendix 4 of Volume II-A. Appendix 3 provides supporting materials on the accomplishments and project summaries of the various departments under the Office of Basic Energy Sciences. This includes DOE supported work in engineering, chemistry, biology, mathematics, geology, and the energy sciences. Appendix 4 provides summaries of DOE supported work on high energy physics, which investigates the nature of matter and the behavior of matter and energy. Over 90% of the funding for this work comes from DOE, which is responsible for national planning in the effort to develop accelerator facilities, the superconducting super collider, and other physics programs
PFBC HGCU Test Facility. Technical progress report No. 24, Third quarter, CY 1995

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-10-01

This is the twenty-fourth and final Technical Progress Report submitted to the Department of Energy (DOE) in connection with the cooperative agreement between the DOE and Ohio Power Company for the Tidd PFBC Hot Gas Clean Up Test Facility. This report covers the work completed during the Third Quarter of CY 1995. All activity this quarter was directed toward the completion of the program final report. A draft copy of the final report was forwarded to DOE during this quarter, and DOE submitted their comments on the report to AEPSC. DOE requested that Westinghouse write an appendix to the report covering the performance of the fail-safe regenerator devices during Tad operation, and Westinghouse subsequently prepared the appendix. Additional DOE comments were incorporated into the report, and it will be issued in camera-ready form by the end of October, 1995, which is the program end date. Appendix 1 presents the results of filter candle posttest examination by Westinghouse performed on selected filter candles following final shutdown of the system.
Technical safety appraisal of buildings 9206 and 9212, Oak Ridge Y-12 plant

International Nuclear Information System (INIS)

1989-03-01

This report covers the results of a Safety Performance Review of the Y-12 Plant conducted during the period July 25 through August 3, 1988. A Safety Performance Review is a followup to assess changes in performance since the 1986 Technical Safety Appraisal (TSA). This review is patterned after a TSA and covered the overall safety performance at Y-12, evaluating progress to date against standards of accepted practice. The review included coverage of actions taken in response to recommendations in the TSA conducted in July--August 1986. Remaining issues were identified through an assessment of safety program deficiencies and their root causes. For each of the 14 safety-related functional areas at the Y-12 Plant, results of this review are listed in Section V. These results include a discussion, conclusions, and any new safety concerns for each program. Appendix A contains a description of the system for categorizing concerns, and the concerns are summarily tabulated in Appendix B for all programs. Appendix C describes the contractor's response and current status of each of the 59 recommendations contained in the 1986 TSA
Proposed nuclear weapons nonproliferation policy concerning foreign research reactor spent nuclear fuel: Appendix C, marine transport and associated environmental impacts. Volume 2

International Nuclear Information System (INIS)

1995-03-01

This is Appendix C to a Draft Environmental Statement on a Proposed Nuclear Weapon Nonproliferation Policy Concerning Foreign Research Reactor Spent Nuclear Fuel. Shipment of any material via ocean transport entails risks to both the ship's crew and the environment. The risks result directly from transportation-related accidents and, in the case of radioactive or other hazardous materials, also include exposure to the effects of the material itself. This appendix provides a description of the approach used to assess the risks associated with the transport of foreign research reactor spent nuclear fuel from a foreign port to a U.S. port(s) of entry. This appendix also includes a discussion of the shipping configuration of the foreign research reactor spent nuclear fuel, the possible types of vessels that could be used to make the shipments, the risk assessment methodology (addressing both incident-free and accident risks), and the results of the analyses. Analysis of activities in the port(s) is described in Appendix D. The incident-free and accident risk assessment results are presented in terms of the per shipment risk and total risks associated with the basic implementation of Management Alternative 1and other implementation alternatives. In addition, annual risks from incident-free transport are developed
Technical support for GEIS: radioactive waste isolation in geologic formations. Volume 16. Repository preconceptual design studies: BPNL waste forms in salt

International Nuclear Information System (INIS)

1978-04-01

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

International Nuclear Information System (INIS)

Piepel, G.F.; Hartley, S.A.; Redgate, P.E.

1996-03-01

This technical note presents empirical models developed in FYI 995 to predict durability as functions of glass composition. Models are presented for normalized releases of B, Li, Na, and Si from the 7-day Product Consistency Test (PCT) applied to quenched and canister centerline cooled (CCC) glasses as well as from the 28-day Materials Characterization Center-1 (MCC-1) test applied to quenched glasses. Models are presented for Composition Variation Study (CVS) data from low temperature melter (LTM) studies (Hrma, Piepel, et al. 1994) and high temperature melter (HTM) studies (Vienna et al. 1995). The data used for modeling in this technical note are listed in Appendix A
Technical specifications Diablo Canyon Nuclear Power Plant, Unit No. 1 (Docket No. 50-275). Appendix A to License No. DPR-80

International Nuclear Information System (INIS)

1984-11-01

This Appendix includes definitions, safety limits and limiting safety system settings, limiting conditions for opertion and surveillance requirements, bases, design features, and administrative controls
NASA University Research Centers Technical Advances in Aeronautics, Space Sciences and Technology, Earth Systems Sciences, Global Hydrology, and Education. Volumes 2 and 3

Science.gov (United States)

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

1998-01-01

This volume chronicles the proceedings of the 1998 NASA University Research Centers Technical Conference (URC-TC '98), held on February 22-25, 1998, in Huntsville, Alabama. The University Research Centers (URCS) are multidisciplinary research units established by NASA at 11 Historically Black Colleges or Universities (HBCU's) and 3 Other Minority Universities (OMU's) to conduct research work in areas of interest to NASA. The URC Technical Conferences bring together the faculty members and students from the URC's with representatives from other universities, NASA, and the aerospace industry to discuss recent advances in their fields.
Remedial investigation report on Waste Area Grouping 5 at Oak Ridge National Laboratory, Oak Ridge, Tennessee. Volume 3 -- Appendix B: Technical findings and conclusions

International Nuclear Information System (INIS)

1995-09-01

This document provides the Environmental Restoration Program with information about the results of investigations performed at Waste Area Grouping (WAG) 5. It includes information on risk assessments that have evaluated long-term impacts to human health and the environment. Information provided in this document forms the basis for decisions regarding the need for subsequent remediation work at WAG 5. Sections B1.1 through B1.4 present an overview of the environmental setting of WAG 5, including location, population, land uses, ecology, and climate, and Sects. B1.5 through B1.7 give site-specific details (e.g., topography, soils, geology, and hydrology). The remediation investigation (RI) of WAG 5 did not entail en exhaustive characterization of all physical attributes of the site; the information presented here focuses on those most relevant to the development and verification of the WAG 5 conceptual model. Most of the information presented in this appendix was derived from the RI field investigation, which was designed to complement the existing data base from earlier, site-specific studies of Solid Waste Storage Area (SWSA) 5 and related areas.
Assessment report no. 2 by the National Commission for assessment of researches and studies related to the management of radioactive materials and wastes. Volume 1 and 2

International Nuclear Information System (INIS)

2008-06-01

This report first discusses the social and economical challenges related to the downstream part of the nuclear fuel cycle, i.e. the direct and indirect cost of storage, the funding system of operators for waste management, and the industrial risk insurance. The second part deals with storage and disposal issues. It describes and comments researches, practices and knowledge related to their different aspects (management, control, transport, material long term behaviour, geological aspects of deep storage, search for an appropriate area, and storage of low level wastes). The third part gives an overview of studies and researches on separation and transmutation. The fourth part gives an overview of international activities in these domains (geological storage, human sciences, separation and transmutation). The second volume contains scientific and technical appendixes
Standard technical specifications: Babcock and Wilcox Plants. Revision 1

International Nuclear Information System (INIS)

1995-04-01

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

International Nuclear Information System (INIS)

1995-03-01

This is Appendix A to a draft Environmental Impact Statement on a Proposed Nuclear Weapons Nonproliferation Policy Concerning Foreign Research Reactor Spent Nuclear Fuel. This appendix addresses environmental justice for the acceptance of foreign research reactor spent nuclear fuel containing uranium enriched in the United States. Analyses of environmental justice concerns are provided in three areas: (1) potential ports of entry, (2) potential transportation routes from candidate ports of entry to interim management sites, and (3) areas surrounding potential interim management sites. These analyses lead to the conclusion that the alternatives analyzed in this Environmental Impact Statement (EIS) would result in no disproportionate adverse effects on minority populations or low-income communities surrounding the candidate ports, transport routes, or interim management sites
CT appearance of the normal appendix in adults

International Nuclear Information System (INIS)

Tamburrini, Stefania; Brunetti, Arturo; Brown, Michele; Sirlin, Claude B.; Casola, Giovanna

2005-01-01

The aims of this study were to identify (1) the normal range of the appendix on computed tomography (CT), (2) the correlation of patient age and sex with the visibility and appearance of the appendix on CT, and (3) the normal variations in wall thickness, intraluminal content, and location of the appendix. Three hundred seventy-two outpatients underwent abdominopelvic CT. The scans were reviewed on the picture archiving and communication system and appendiceal outer-to-outer wall diameter, wall thickness, location, content and its correlation with appendix diameter were analyzed. The appendix was visualized in 305/372 patients. Its location relative to the cecum was highly variable. The diameter range was 3-10 mm; in 42% of cases the diameter was greater than 6 mm. When the intraluminal content (185/305) was visualized, the diameter was slightly superior to the mean (p=0.0156). In 329 CT scans in which oral contrast material was given, the appendix was filled by contrast material in 74/329 patients. The appendix wall thickness was measurable in 22/305 patients (average 0.15 cm). There is significant overlap between the normal and abnormal CT appearance of the appendix. Consequently the diagnosis of acute appendicitis should be based not only on the appearance of the appendix but also on the presence of secondary signs. (orig.)
Technical support for GEIS: radioactive waste isolation in geologic formations. Volume 2. Commercial waste forms, packaging and projections for preconceptual repository design studies

International Nuclear Information System (INIS)

1978-04-01

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

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

International Nuclear Information System (INIS)

1987-08-01

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

International Nuclear Information System (INIS)

1992-09-01

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

International Nuclear Information System (INIS)

Shanahan, W.R.

1984-04-01

Four interim technical research memoranda are presented that describe the results of numerical simulations designed to investigate the dynamics of energetic plasma beams propagating across magnetic fields
Waste-Management Education and Research Consortium (WERC) annual progress report, 1991--1992. Appendixes

Energy Technology Data Exchange (ETDEWEB)

1992-04-07

This report contains the following appendices: Appendix A - Requirements for Undergraduate Level; Appendix B - Requirements for Graduate Level; Appendix C - Graduate Degree In Environmental Engineering; Appendix D - Non-degree Certificate Program; Appendix E - Curriculum for Associate Degree Program; Appendix F - Curriculum for NCC Program; Appendix G - Information 1991 Teleconference Series; Appendix H - Information on 1992 Teleconference Series; Appendix I - WERC interactive Television Courses; Appendix J - WERC Research Seminar Series; Appendix K - Sites for Hazardous/Radioactive Waste Management Series; Appendix L- Summary of Technology Development of the Second Year; Appendix M - List of Major Publications Resulting from WERC; Appendix N - Types of Equipment at WERC Laboratories.
Subseabed disposal program annual report, January-December 1980. Volume II. Appendices (principal investigator progress reports). Part 1

International Nuclear Information System (INIS)

Hinga, K.R.

1981-07-01

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 I, 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-Q; Part 2 contains Appendices R-MM. Separate abstracts have been prepared for each appendix for inclusion in the Energy Data Base
Subseabed disposal program annual report, January-December 1980. Volume II. Appendices (principal investigator progress reports). Part 1

Energy Technology Data Exchange (ETDEWEB)

Hinga, K.R. (ed.)

1981-07-01

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 I, 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-Q; Part 2 contains Appendices R-MM. Separate abstracts have been prepared for each appendix for inclusion in the Energy Data Base.
Interim reliability-evaluation program: analysis of the Browns Ferry, Unit 1, nuclear plant. Appendix B - system descriptions and fault trees

International Nuclear Information System (INIS)

Mays, S.E.; Poloski, J.P.; Sullivan, W.H.; Trainer, J.E.; Bertucio, R.C.; Leahy, T.J.

1982-07-01

This report describes a risk study of the Browns Ferry, Unit 1, nuclear plant. The study is one of four such studies sponsored by the NRC Office of Research, Division of Risk Assessment, as part of its Interim Reliability Evaluation Program (IREP), Phase II. This report is contained in four volumes: a main report and three appendixes. Appendix B provides a description of Browns Ferry, Unit 1, plant systems and the failure evaluation of those systems as they apply to accidents at Browns Ferry. Information is presented concerning front-line system fault analysis; support system fault analysis; human error models and probabilities; and generic control circuit analyses
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
Culturally relevant science: An approach to math science education for hispanics. Final technical report

Energy Technology Data Exchange (ETDEWEB)

Montellano, B.O. de

1996-11-14

This progress report summarizes results of a teacher workshop. A letter sent to 17 teachers who had participated in the workshop requested a report of any activities undertaken and copies of lesson plans and materials developed. Only nine responses were received, and not all of them demonstrated a satisfactory level of activity. Teachers who submitted materials showing the most promise were invited to participate in the Summer Writing Workshop. A partial first draft of a companion volume for the teacher`s manual was written which provides a rationale for culturally relevant science and presents the cultural and scientific background needed. The outline of the book is presented in Appendix 1. Appendix 2 is a sample chapter from the book.
Technical Requirements for Fabrication and Installation of Removable Shield for CNRF in HANARO

Energy Technology Data Exchange (ETDEWEB)

Ryu, Jeong Soo; Cho, Yeong Garp; Lee, Jung Hee; Shin, Jin Won

2008-04-15

This report details the technical requirements for the fabrication and installation of the removable shield for the Cold Neutron Research Facility (CNRF) in HANARO reactor hall. The removable shield is classified as non-nuclear safety (NNS), seismic category II, and quality class T. The main function of the removable shield is to do the biological shielding of neutrons and gamma from the CN port and the guides. The removable shield consists of block type walls and roofs that can be necessarily assembled, disassembled and moveable. These will be installed between the reactor pool wall and the CNS guide bunker in. This report describes technical requirements for the removable shield such as quality assurance, seismic analysis requirements, configuration, concrete compositions, fabrication and installation requirements, test and inspection, shipping, delivery, etc. Appendix is the technical specification of structural design and analysis. Attachments are composed of the technical specification for the fabrication of the removable shield, shielding design drawings and procurement quality requirements. These technical requirements will be provided to a contract for the manufacturing and installation.
Next Generation Nuclear Plant Project Technology Development Roadmaps: The Technical Path Forward for 750–800°C Reactor Outlet Temperature

Energy Technology Data Exchange (ETDEWEB)

John Collins

2009-08-01

This document presents the NGNP Critical PASSCs and defines their technical maturation path through Technology Development Roadmaps (TDRMs) and their associated Technology Readiness Levels (TRLs). As the critical PASSCs advance through increasing levels of technical maturity, project risk is reduced and the likelihood of within-budget and on-schedule completion is enhanced. The current supplier-generated TRLs and TDRMs for a 750–800°C reactor outlet temperature (ROT) specific to each supplier are collected in Appendix A.
Technology, safety and costs of decommissioning a reference small mixed oxide fuel fabrication plant. Volume 2. Appendices

Energy Technology Data Exchange (ETDEWEB)

Jenkins, C. E.; Murphy, E. S.; Schneider, K. J.

1979-01-01

Volume 2 contains appendixes on small MOX fuel fabrication facility description, site description, residual radionuclide inventory estimates, decommissioning, financing, radiation dose methodology, general considerations, packaging and shipping of radioactive materials, cost assessment, and safety (JRD)
Technical support for GEIS: radioactive waste isolation in geologic formations. Volume 2. Commercial waste forms, packaging and projections for preconceptual repository design studies

Energy Technology Data Exchange (ETDEWEB)

1978-04-01

This volume, Y/OWI/TM-36/2, ''Commercial Waste Forms, Packaging and Projections for Preconceptual Repository Design Studies,'' is one of a 23-volume series, ''Technical Support for GEIS: Radioactive Waste Isolation in Geologic Formations,'' Y/OWI/TM-36, which supplements the ''Contribution to Draft Generic Environmental Impact Statement on Commercial Waste Management: Radioactive Waste Isolation in Geologic Formations,'' Y/OWI/TM-44. The series provides a more complete technical basis for the preconceptual designs, resource requirements, and environmental source terms associated with isolating commercial LWR wastes in underground repositories in salt, granite, shale and basalt. Wastes are considered from three fuel cycles: uranium and plutonium recycling, no recycling of spent fuel and uranium-only recycling. This volume contains the data base for waste forms, packages, and projections from the commercial waste defined by the Office of Waste Isolation in ''Nuclear Waste Projections and Source Term Data for FY 1977,'' Y/OWI/TM-34. Also, as an alternative data base for repository design and analysis, waste forms, packages, and projections for commercial waste defined by Battelle Pacific Northwest Laboratory (BPNL) have been included. This data base consists of a reference case for use in the alternative design study and a definition of combustible wastes for use in mine fire and hydrogen generation analyses.
Documentation for Grants Equal to Tax model: Volume 1, Technical description

International Nuclear Information System (INIS)

1986-01-01

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

International Nuclear Information System (INIS)

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

1992-07-01

In situ vitrification (ISV) has been identified as an alternative technology for remediation of the acid pit and transuranic pits and trenches (TRU-PTs) at the Idaho National Engineering Laboratory (INEL) Subsurface Disposal Area (SDA). However, a number of technical issues must be resolved before ISV can be considered applicable to these waste sites. To assist in the ISV technology evaluation, an ISV Steering Committee was formed to identify, prioritize, and develop closure roadmaps for technical issues lated with ISV application at the SDA. The activities of the ISV Steering Committee are summarized in a three-volume report. Volume I identifies the systematic approach used to identify and prioritize the ISV technical issues and briefly discusses the methodology that will be employed to resolve these issues. Volumes 2 and 3 discuss each technical issue in greater detail and suggest specific closure roadmaps to be used in resolving technical issues associated with ISV at the SDA Acid Pit and TRU-PTS, respectively. The three-volume report is a working document that will be updated as necessary to reflect current evaluation strategy for the ISV technology. This is Volume 3
SAPHIRE 8 Volume 2 - Technical Reference

Energy Technology Data Exchange (ETDEWEB)

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

2011-03-01

The Systems Analysis Programs for Hands-on Integrated Reliability Evaluations (SAPHIRE) refers to a set of computer programs that were developed to create and analyze probabilistic risk assessment (PRAs). Herein information is provided on the principles used in the construction and operation of Version 8.0 of the SAPHIRE system. This report summarizes the fundamental mathematical concepts of sets and logic, fault trees, and probability. This volume then describes the algorithms used to construct a fault tree and to obtain the minimal cut sets. It gives the formulas used to obtain the probability of the top event from the minimal cut sets, and the formulas for probabilities that apply for various assumptions concerning reparability and mission time. It defines the measures of basic event importance that SAPHIRE can calculate. This volume gives an overview of uncertainty analysis using simple Monte Carlo sampling or Latin Hypercube sampling, and states the algorithms used by this program to generate random basic event probabilities from various distributions. Also covered are enhance capabilities such as seismic analysis, Workspace algorithms, cut set "recovery," end state manipulation, and use of "compound events."
Stochastic Simulations of Long-Range Forecasting Models. Volume 3. Technical Appendix

Science.gov (United States)

1975-10-31

The World Power Structure and the Inequa - lity of: Nat:ions. London: McGibbon and Kce. JOSHUA, W. (1971) Soviet Penetration into tlie Middle East...IPRT M NYEAR =■ % Non-Agricultural Employment for Period T-(J-l) for Nat’.on I = % Urbanization = ALOGIO (% Non-Agricultural Employment ) = ALOGIO
NEOPLASTIC LESIONS OF THE APPENDIX

Directory of Open Access Journals (Sweden)

Piotr Bryk

2013-11-01

Full Text Available The aim of the research was to present the clinical observations of neoplastic lesions of the appendix (one carcinoid and two mucous cysts and to discuss various manners of treatment and prognosis. Material and methods: The authors of the following paper present a description of three cases of appendix tumours, two patients with a mucous cyst and a patient with carcinoid, against the background of all the appendectomies performed at the Clinical Department of General, Endocrine and Oncological Surgery of the Provincial Polyclinical Hospital in Kielce in the years 2005–2011. Results : Within the 7-year period, a total of 11 719 surgical operations have been performed, where 834 (7.1% were that of appendectomy. Among all of the removed vermiform appendixes, neoplastic lesions occurred in three cases constituting a mere 0.3% of all of the appendectomies performed within that period. In two of the cases there was a suspicion of mucous cysts before the surgical operation. In none of the above-mentioned cases was is possible to ultimately establish the diagnosis before the operation. The patients were subjected to a simple appendectomy. The patients are in good clinical health, with no signs of relapse. Conclusions : The presented cases of patients with appendix tumours illustrate the difficulty of preoperative detection of a neoplastic lesion. This is mainly due to a scantily symptomatic course or symptoms typical of appendicitis. In light of this, histopathological examination of each appendix should be treated as obligatory.
Mixed strategies for energy conservation and alternative energy utilization (solar) in buildings. Final report. Volume III. Appendixes. [10 appendices

Energy Technology Data Exchange (ETDEWEB)

None

1977-06-01

This appendix summarizes building characteristics used to determine heating and cooling loads for each of the five building types in each of the four regions. For the selected five buildings, the following data are attached: new and existing construction characteristics; new and existing construction thermal resistance; floor plan and elevation; people load schedule; lighting load schedule; appliance load schedule; ventilation schedule; and hot water use schedule. For the five building types (single family, apartment buildings, commercial buildings, office buildings, and schools), data are compiled in 10 appendices. These are Building Characteristics; Alternate Energy Sources and Energy Conservation Techniques Description, Costs, Fuel Price Scenarios; Life Cycle Cost Model; Simulation Models; Solar Heating/Cooling System; Condensed Weather; Single and Multi-Family Dwelling Characteristics and Energy Conservation Techniques; Mixed Strategies for Energy Conservation and Alternative Energy Utilization in Buildings. An extensive bibliography is given in the final appendix. (MCW)
Technical description - interim storage, encapsulation and disposal of spent nuclear fuel

International Nuclear Information System (INIS)

2010-07-01

The purpose of the annex Technical description is, in accordance with Chapter 22 paragraph 1 Environmental Code to describe the candidate operations and facilities. In particular, things that are important for their environmental impact are described. SKB's goal of the appendix is to describe the facilities, activities, pollution sources, land usage and more during construction, operation and decommissioning, to the extent and on a level of detail, so that the Environment Court without requiring additions can prepare the matter for the government's admissibility test

Comprehensive Technical Report, General Electric Direct-Air-Cycle Aircraft Nuclear Propulsion Program, Program Summary and References

Energy Technology Data Exchange (ETDEWEB)

Thornton, G.; Rothstein, A.J.

1962-06-28

This is one of twenty-one volumes sumarizing the Aircraft Nuclear Propulsion Program of the General Electric Company. This volume discusses the background to the General Electric program, and summarizes the various direct-air-cycle nuclear test assemblies and power plants that were developed. Because of the requirements of high performance, low weight, and small size, vast improvements in existing technology were required to meet the flight objectives. The technological progress achieved during the program is also summarized. The last appendix contains a compilation of the abstracts, tables of contents, and reference lists of the other twenty volumes.
Columbia River System Operation Review final environmental impact statement. Appendix I: Power

International Nuclear Information System (INIS)

1995-11-01

The System Operation Review (SOR) is a study and environmental compliance process being used by the three Federal agencies to analyze future operations of the system and river use issues. The goal of the SOR is to achieve a coordinated system operation strategy for the river that better meets the needs of all river users. This technical appendix addresses only the effects of alternative system operating strategies for managing the Columbia River system. This appendix discusses the work performed by the SOR Power Work Group. The Power Work Group (PWG) had several major responsibilities: first, to determine the effects of each of the various system operating strategies (SOS) on the Northwest regional power system; second, given these effects, to determine what, if any, actions are required to meet forecasted regional energy consumption; and finally, to estimate the cost for serving the forecasted regional energy consumption. The Northwest regional power system consists of Federal and non-Federal hydroelectric power projects (hydropower or hydro projects) on the main stem of the Columbia and Snake Rivers, numerous smaller hydro projects on other river reaches, and a number of thermal plants (coal, nuclear and combustion turbines)
Rio Grande Floodway, Truth or Consequences Unit, NM, Cuchillo Negro Dam Foundation Report. Volume 3. Appendix E, Appendix F and Appendix G

Science.gov (United States)

1992-12-01

a 50 per cent reduction in explosives load. The explosives should be well distributed in the hole using decks and detonating cord do- nlines . Line...8217 Handbook Describing Practical Methods of Using Explosives for Various Purposes 0 Prepared by TECHNICAL MARKETING SERVICES - EXPLOSIVES Sixth Edition
Technical issues associated with in situ vitrification of the INEL Subsurface Disposal Area

International Nuclear Information System (INIS)

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

1992-01-01

In situ vitrification (ISV) has been identified as an alternative technology for remediation of the Acid Pit and Transuranic Pits and Trenches (TRU-PTs) that are present at the Idaho National Engineering Laboratory (INEL) Subsurface Disposal Area (SDA). However, a number of technical issues exist that must be resolved before ISV can be considered applicable to these waste sites. To assist in the ISV technology evaluation, an ISV Steering Committee was formed to identify, prioritize, and develop closure roadmaps for technical issues associated with ISV application at the INEL SDA. The activities of the ISV Steering Committee are summarized in three volumes of this report. Volume 1 identifies the systematic approach used to identify and prioritize the ISV technical issues, and briefly discusses the methodology that will be employed to resolve these issues. This document Volume 2 and Volume 3 discusses each technical issue in greater detail and suggest specific closure roadmaps to be used in resolving technical issues associated with ISV at the SDA Acid Pit and TRU-PTs, respectively
Subseabed disposal program annual report, January-December 1979. Volume II. Appendices (principal investigator progress reports). Part 1 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 I, 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 of each Appendix for inclusion in the Energy Data Base
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
T1 bright appendix sign to exclude acute appendicitis in pregnant women

International Nuclear Information System (INIS)

Shin, Ilah; An, Chansik; Lim, Joon Seok; Kim, Myeong-Jin; Chung, Yong Eun

2017-01-01

To evaluate the diagnostic value of the T1 bright appendix sign for the diagnosis of acute appendicitis in pregnant women. This retrospective study included 125 pregnant women with suspected appendicitis who underwent magnetic resonance (MR) imaging. The T1 bright appendix sign was defined as a high intensity signal filling more than half length of the appendix on T1-weighted imaging. Sensitivity, specificity, positive predictive value (PPV) and negative predictive value (NPV) of the T1 bright appendix sign for normal appendix identification were calculated in all patients and in those with borderline-sized appendices (6-7 mm). The T1 bright appendix sign was seen in 51% of patients with normal appendices, but only in 4.5% of patients with acute appendicitis. The overall sensitivity, specificity, PPV, and NPV of the T1 bright appendix sign for normal appendix diagnosis were 44.9%, 95.5%, 97.6%, and 30.0%, respectively. All four patients with borderline sized appendix with appendicitis showed negative T1 bright appendix sign. The T1 bright appendix sign is a specific finding for the diagnosis of a normal appendix in pregnant women with suspected acute appendicitis. (orig.)
T1 bright appendix sign to exclude acute appendicitis in pregnant women

Energy Technology Data Exchange (ETDEWEB)

Shin, Ilah; An, Chansik; Lim, Joon Seok; Kim, Myeong-Jin; Chung, Yong Eun [Yonsei University College of Medicine, Department of Radiology, Research Institute of Radiological Science, Severance Hospital, 50-1 Yonsei-ro, Seodaemun-gu, Seoul (Korea, Republic of)

2017-08-15

To evaluate the diagnostic value of the T1 bright appendix sign for the diagnosis of acute appendicitis in pregnant women. This retrospective study included 125 pregnant women with suspected appendicitis who underwent magnetic resonance (MR) imaging. The T1 bright appendix sign was defined as a high intensity signal filling more than half length of the appendix on T1-weighted imaging. Sensitivity, specificity, positive predictive value (PPV) and negative predictive value (NPV) of the T1 bright appendix sign for normal appendix identification were calculated in all patients and in those with borderline-sized appendices (6-7 mm). The T1 bright appendix sign was seen in 51% of patients with normal appendices, but only in 4.5% of patients with acute appendicitis. The overall sensitivity, specificity, PPV, and NPV of the T1 bright appendix sign for normal appendix diagnosis were 44.9%, 95.5%, 97.6%, and 30.0%, respectively. All four patients with borderline sized appendix with appendicitis showed negative T1 bright appendix sign. The T1 bright appendix sign is a specific finding for the diagnosis of a normal appendix in pregnant women with suspected acute appendicitis. (orig.)
MHD Advanced Power Train Phase I, Final Report, Volume 7

Energy Technology Data Exchange (ETDEWEB)

A. R. Jones

1985-08-01

This appendix provides additional data in support of the MHD/Steam Power Plant Analyses reported in report Volume 5. The data is in the form of 3PA/SUMARY computer code printouts. The order of presentation in all four cases is as follows: (1) Overall Performance; (2) Component/Subsystem Information; (3) Plant Cost Accounts Summary; and (4) Plant Costing Details and Cost of Electricity.
ONE OF THE LONGEST APPENDIX: A RARE CASE REPORT

Directory of Open Access Journals (Sweden)

Venkat Rao

2015-03-01

Full Text Available The vermiform appendix is an organ that can have variable sizes. We are prompted to report here one of the longest appendix removed, measuring about 16cm in length. INTRODUCTION : The vermiform appendix is an organ that can vary in size, site, and presence, as well as in other clinical and functional aspects. We describe here one of the longest appendix removed, measuring about 16cm in length in a case of acute appendicitis
T1 bright appendix sign to exclude acute appendicitis in pregnant women.

Science.gov (United States)

Shin, Ilah; An, Chansik; Lim, Joon Seok; Kim, Myeong-Jin; Chung, Yong Eun

2017-08-01

To evaluate the diagnostic value of the T1 bright appendix sign for the diagnosis of acute appendicitis in pregnant women. This retrospective study included 125 pregnant women with suspected appendicitis who underwent magnetic resonance (MR) imaging. The T1 bright appendix sign was defined as a high intensity signal filling more than half length of the appendix on T1-weighted imaging. Sensitivity, specificity, positive predictive value (PPV) and negative predictive value (NPV) of the T1 bright appendix sign for normal appendix identification were calculated in all patients and in those with borderline-sized appendices (6-7 mm). The T1 bright appendix sign was seen in 51% of patients with normal appendices, but only in 4.5% of patients with acute appendicitis. The overall sensitivity, specificity, PPV, and NPV of the T1 bright appendix sign for normal appendix diagnosis were 44.9%, 95.5%, 97.6%, and 30.0%, respectively. All four patients with borderline sized appendix with appendicitis showed negative T1 bright appendix sign. The T1 bright appendix sign is a specific finding for the diagnosis of a normal appendix in pregnant women with suspected acute appendicitis. • Magnetic resonance imaging is increasingly used in emergency settings. • Acute appendicitis is the most common cause of acute abdomen. • Magnetic resonance imaging is widely used in pregnant population. • T1 bright appendix sign can be a specific sign representing normal appendix.
10 CFR Appendix R to Part 50 - Fire Protection Program for Nuclear Power Facilities Operating Prior to January 1, 1979

Science.gov (United States)

2010-01-01

... service-water/fire-water uses the minimum volume for fire uses shall be ensured by means of dedicated... knowledge of his or her role in the fire fighting strategy for the area assumed to contain the fire... LICENSING OF PRODUCTION AND UTILIZATION FACILITIES Pt. 50, App. R Appendix R to Part 50—Fire Protection...
Expectation and task for constructing the volume reduction system of removed soils. In search of the technical integrity from the intermediate storage to final disposal

International Nuclear Information System (INIS)

Mori, Hisaki

2016-01-01

The intermediate storage volume of the removed soils and incineration ash in Fukushima is supposed about 22 million cubic meters. Within 30 years after starting the intermediate storage, the final disposal outside Fukushima prefecture to these removed soils and incineration ash is determined by the law. Because these removed soils are the very-very low radio activity, the volume reduction method is most effective to reduce the burden of the final disposal. As the volume reduction technology is the stage of research and development, the possibility of the introduction of the volume reduction technology that has the consistency of the final disposal technology is evaluated from the point of view of cost. Since this business is accompanied by economic and technical risk to implement private companies, this project is considered appropriate to be implemented as a national project. (author)
Technical specifications manual for the MARK-1 pulsed ionizing radiation detection system. Volume 1

Energy Technology Data Exchange (ETDEWEB)

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

1993-03-01

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

Science.gov (United States)

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

2005-01-01

This paper provides an analysis of Flight Technical Error (FTE) from recent SATS experiments, called the Higher Volume Operations (HVO) Simulation and Flight experiments, which NASA conducted to determine pilot acceptability of the HVO concept for normal operating conditions. Reported are FTE results from simulation and flight experiment data indicating the SATS HVO concept is viable and acceptable to low-time instrument rated pilots when compared with today s system (baseline). Described is the comparative FTE analysis of lateral, vertical, and airspeed deviations from the baseline and SATS HVO experimental flight procedures. Based on FTE analysis, all evaluation subjects, low-time instrument-rated pilots, flew the HVO procedures safely and proficiently in comparison to today s system. In all cases, the results of the flight experiment validated the results of the simulation experiment and confirm the utility of the simulation platform for comparative Human in the Loop (HITL) studies of SATS HVO and Baseline operations.
18 CFR Appendix B to Subpart H of... - Appendix B to Subpart H of Part 35

Science.gov (United States)

2010-04-01

... 18 Conservation of Power and Water Resources 1 2010-04-01 2010-04-01 false Appendix B to Subpart H of Part 35 B Appendix B to Subpart H of Part 35 Conservation of Power and Water Resources FEDERAL... SCHEDULES AND TARIFFS Wholesale Sales of Electric Energy, Capacity and Ancillary Services at Market-Based...
18 CFR Appendix A to Subpart H of... - Appendix A to Subpart H of Part 35

Science.gov (United States)

2010-04-01

... 18 Conservation of Power and Water Resources 1 2010-04-01 2010-04-01 false Appendix A to Subpart H of Part 35 A Appendix A to Subpart H of Part 35 Conservation of Power and Water Resources FEDERAL... SCHEDULES AND TARIFFS Wholesale Sales of Electric Energy, Capacity and Ancillary Services at Market-Based...
Target volume definition for external beam partial breast radiotherapy: Clinical, pathological and technical studies informing current approaches

International Nuclear Information System (INIS)

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

2010-01-01

Partial breast irradiation (PBI) is currently under investigation in several phase III trials and, following a recent consensus statement, its use off-study may increase despite ongoing uncertainty regarding optimal target volume definition. We review the clinical, pathological and technical evidence for target volume definition in external beam partial breast irradiation (EB-PBI). The optimal method of tumour bed (TB) delineation requires X-ray CT imaging of implanted excision cavity wall markers. The definition of clinical target volume (CTV) as TB plus concentric 15 mm margins is based on the anatomical distribution of multifocal and multicentric disease around the primary tumour in mastectomy specimens, and the clinical locations of local tumour relapse (LR) after breast conservation surgery. If the majority of LR originate from foci of residual invasive and/or intraduct disease in the vicinity of the TB after complete microscopic resection, CTV margin logically takes account of the position of primary tumour within the surgical resection specimen. The uncertain significance of independent primary tumours as sources of preventable LR, and of wound healing responses in stimulating LR, increases the difficulties in defining optimal CTV. These uncertainties may resolve after long-term follow-up of current PBI trials. By contrast, a commonly used 10 mm clinical to planning target volume (PTV) margin has a stronger evidence base, although departmental set-up errors need to be confirmed locally. A CTV-PTV margin >10 mm may be required in women with larger breasts and/or large seromas, whilst the role of image-guided radiotherapy with or without TB markers in reducing CTV-PTV margins needs to be explored.
14 CFR Appendix C to Part 420 - Risk Analysis

Science.gov (United States)

2010-01-01

.... Downrange from 100 nm beyond the launch point, world population data are available from: Total landmass area... appendix B. This appendix also provides an applicant options to simplify the method where population at... and, for an appendix B flight corridor, trajectory information. (2) Population data. Total population...
The System 80+ Standard Plant design control document. Volume 21

International Nuclear Information System (INIS)

1997-01-01

This Design Control Document (DCD) is a repository of information comprising the System 80+trademark Standard Plant Design. The DCD also provides that design-related information to be incorporated by reference in the design certification rule for the System 80+ Standard Plant Design. Applicants for a combined license pursuant to 10 CFR 52 must ensure that the final Design Certification Rule and the associated Statements of Consideration are used when making all licensing decisions relevant to the System 80+ Standard Plant Design. The Design Control Document contains the DCD introduction, The Certified Design Material (CDM) [i.e., ''Tier 1''] and the Approved Design Material (ADM) [i.e., ''Tier 2''] for the System 80+ Standard Plant Design. The CDM includes the following sections: (1) Introductory material; (2) Certified Design Material for System 80+ systems and structures; (3) Certified Design Material for non-system-based aspects of the System 80+ Certified design; (4) Interface requirements; and (5) Site parameters. The ADM, to the extent applicable for the System 80+ Standard Plant Design, includes: (1) the information required for the final safety analysis report under 20 CFR 50.34; (2) other relevant information required by 10 CFR 52.47; and (3) emergency operations guidelines. This volume contains parts 1--10 of section 19 (Probabilistic Risk Assessment) of the ADM Design and Analysis. Topics covered are: methodology; initiating event evaluation; accident sequence determination; data analysis; systems analysis; external events analysis; shutdown risk assessment; accident sequence quantification; and sensitivity analysis. Also included in this volume are Appendix 19.8A Shutdown Risk Assessment and Appendix A to Appendix 19.8A Request for Information

Gender Research in Africa into ICTs for Empowerment (GRACE ...

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

Final technical report - appendix D / citations of African women and ICTs : investigating technology, gender and empowerment (2009), as of 24 February 2012. Rapports. Final technical report - appendix B / publications, presentations and reports. Rapports. Final technical report - appendix A / information sharing and ...
10 CFR Appendix B to Part 20 - Annual Limits on Intake (ALIs) and Derived Air Concentrations (DACs) of Radionuclides for...

Science.gov (United States)

2010-01-01

... appendix are the annual intakes of a given radionuclide by “Reference Man” which would result in either (1... effects when the whole body is irradiated uniformly. The values of wT are listed under the definition of..., where 2×104 ml is the volume of air breathed per minute at work by “Reference Man” under working...
Spent nuclear fuel project technical databook

Energy Technology Data Exchange (ETDEWEB)

Reilly, M.A.

1998-07-22

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

International Nuclear Information System (INIS)

Reilly, M.A.

1998-01-01

The Spent Nuclear Fuel (SNF) project technical databook provides project-approved summary tables of selected parameters and derived physical quantities, with nominal design and safety basis values. It contains the parameters necessary for a complete documentation basis of the SNF Project technical and safety baseline. The databook is presented in two volumes. Volume 1 presents K Basins SNF related information. Volume 2 (not yet available) will present selected sludge and water information, as it relates to the sludge and water removal projects. The values, within this databook, shall be used as the foundation for analyses, modeling, assumptions, or other input to SNF project safety analyses or design. All analysis and modeling using a parameter available in this databook are required to use and cite the appropriate associated value, and document any changes to those values (i.e., analysis assumptions, equipment conditions, etc). Characterization and analysis efforts are ongoing to validate, or update these values
Assessment report no. 3 by the National Commission for assessment of researches and studies related to the management of radioactive materials and wastes. Volume 1 and 2

International Nuclear Information System (INIS)

2009-06-01

This report first gives a wide and precise overview of researches and studies performed in the field of nuclear waste storage and disposal: high and medium level waste deep storage, low level waste storage, other wastes (ore residues, tritiated wastes, CEA wastes, sealed sources), and of social and economical aspects related to this issue. The second part gives an overview of studies and researches on separation and transmutation (actors, impact of storage, sodium fast reactor prototype, tool availability, materials). The third part gives an overview of international activities in different domains: international legal framework, research laboratories or sites dedicated to underground storage, fast spectrum irradiation sources, impact of storage on the environment, governance and participation, new ways for separation and transmutation, nuclear data bases, economical and geopolitical issues, education and training. The second volume contains scientific and technical appendixes
Columbia River System Operation Review final environmental impact statement. Appendix K: Resident fish

International Nuclear Information System (INIS)

1995-11-01

The System Operation Review (SOR) is a study and environmental compliance process being used by the three Federal agencies to analyze future operations of the system and river use issues. The goal of the SOR is to achieve a coordinated system operation strategy for the river that better meets the needs of all river users. This technical appendix addresses only the effects of alternative system operating strategies for managing the Columbia River system. In this appendix the Resident Fish Work Group (RFWG) has attempted to characterize and evaluate impacts of dam operation on an extremely complex and diverse integrated resource. Not only is this required under the National Environmental Policy Act (NEPA) for SOR, there are resident fish populations that have status under the Federal Endangered Species Act (ESA) or equivalent state regulations (Kootenai River white sturgeon, Snake River white sturgeon, sandroller, shorthead and torrent sculpins, bull trout, westslope cutthroat trout, redband trout, and burbot). The RFWG has also attempted to develop operating alternatives that benefit not only resident fish, but anadromous fish, wildlife, and other human interests as well. The authors have recognized the co-evolution of resident fish, anadromous fish, and other integrated resources in the basin
International Nuclear Model. Volume 3. Program description

International Nuclear Information System (INIS)

Andress, D.

1985-01-01

This is Volume 3 of three volumes of documentation of the International Nuclear Model (INM). This volume presents the Program Description of the International Nuclear Model, which was developed for the Nuclear and Alternate Fuels Division (NAFD), Office of Coal, Nuclear, Electric and Alternate Fuels, Energy Information Administration (EIA), US Department of Energy (DOE). The International Nuclear Model (INM) is a comprehensive model of the commercial nuclear power industry. It simulates economic decisions for reactor deployment and fuel management decision based on an input set of technical economic and scenario parameters. The technical parameters include reactor operating characteristics, fuel cycle timing and mass loss factors, and enrichment tails assays. Economic parameters include fuel cycle costs, financial data, and tax alternatives. INM has a broad range of scenario options covering, for example, process constraints, interregional activities, reprocessing, and fuel management selection. INM reports reactor deployment schedules, electricity generation, and fuel cycle requirements and costs. It also has specialized reports for extended burnup and permanent disposal. Companion volumes to Volume 3 are: Volume 1 - Model Overview, and Volume 2 - Data Base Relationships
Standard Technical Specifications, General Electric plants, BWR/4

International Nuclear Information System (INIS)

1992-09-01

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

African Journals Online (AJOL)

Tumours of the appendix are emerging as diseases of increasing concern due to a rising incidence1. We present a case of mucinous cystadenoma of the appendix in an elderly patient. To our knowledge, this is the first report of mucinous cystadenoma of the appendix from Nigeria. Key Words: Appendiceal tumour, ...
Technical Performance Capability of Fourier Transform Profilometry for Quantitative Waste Volume Determination under Hanford Waste Tank Condition

International Nuclear Information System (INIS)

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

2009-01-01

The Hanford Site is currently in the process of an extensive effort to empty and close its radioactive single-shell and double-shell waste storage tanks. Before this can be accomplished, it is necessary to know how much residual material is left in a given waste tank and the chemical makeup of the residue. The Institute for Clean Energy Technology (ICET) at Mississippi State University is currently developing a quantitative in-tank inspection system based on Fourier Transform Profilometry (FTP). FTP is a non-contact, 3-D shape measurement technique. By projecting a fringe pattern onto a target surface and observing its deformation due to surface irregularities from a different view angle, FTP is capable of determining the height (depth) distribution (and hence volume distribution) of the target surface, thus reproducing the profile of the target accurately under a wide variety of conditions. Hence FTP has the potential to be utilized for quantitative determination of residual wastes within Hanford waste tanks. We report the results of a technical feasibility study to document the accuracy and precision of quantitative volume determination using the Fourier transform profilometry technique under simulated Hanford waste tank conditions. (authors)
INC93: international nuclear congress. Technical sessions summaries

International Nuclear Information System (INIS)

Boulton, J.

1993-01-01

The conference dealt mainly with safety, environmental and human aspects of nuclear energy, including waste management. This volume consists of summaries of the technical sessions contained in Volumes 2 and 3. The individual papers have also been abstracted separately for INIS, with the summaries abridged
INC93: international nuclear congress. Technical sessions summaries

Energy Technology Data Exchange (ETDEWEB)

Boulton, J

1994-12-31

The conference dealt mainly with safety, environmental and human aspects of nuclear energy, including waste management. This volume consists of summaries of the technical sessions contained in Volumes 2 and 3. The individual papers have also been abstracted separately for INIS, with the summaries abridged.
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
49 CFR Appendix B to Part 172 - Trefoil Symbol

Science.gov (United States)

2010-10-01

... 49 Transportation 2 2010-10-01 2010-10-01 false Trefoil Symbol B Appendix B to Part 172... SECURITY PLANS Pt. 172, App. B Appendix B to Part 172—Trefoil Symbol 1. Except as provided in paragraph 2 of this appendix, the trefoil symbol required for RADIOACTIVE labels and placards and required to be...
Volume and outcome of organ transplantation

NARCIS (Netherlands)

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

1992-01-01

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

DEFF Research Database (Denmark)

Christensen, F. A.; Brincker, Rune

1999-01-01

In this appendix the failure behaviour of lightly reinforced concrete beams is investigated. A numerical model based on the fictitious crack approach according to Hillerborg [1] is established in order to estimate the load-deflection curve for lightly reinforced concrete beams. The debonding...
Management of appendix mass in a Nigerian rural district | Umunna ...

African Journals Online (AJOL)

Background: The traditional management of an appendix mass is conservative, followed by interval appendicectomy. Interval appendicectomy is now controversial. Aim: To present an experience with the management of appendix mass among a rural people in Nigeria. Methods: Patients presenting with appendix masses ...
Routledge French technical dictionary

CERN Document Server

1994-01-01

The French-English volume of this highly acclaimed set consists of some 100,000 keywords in both French and English, drawn from the whole range of modern applied science and technical terminology. Covers over 70 subject areas, from engineering and chemistry to packaging, transportation, data processing and much more.
Office for Analysis and Evaluation of Operational Data 1996 annual report. Volume 10, Number 3: Technical training

International Nuclear Information System (INIS)

1997-12-01

This annual report of the US Nuclear Regulatory Commission's Office for Analysis and Evaluation of Operational Data (AEOD) describes activities conducted during 1996. The report is published in three parts. NUREG-1272, Vol. 10, No. 1, covers power reactors and presents an overview of the operating experience of the nuclear power industry from the NRC perspective, including comments about trends of some key performance measures. The report also includes the principal findings and issues identified in AEOD studies over the past year and summarizes information from such sources as licensee event reports and reports to the NRC's Operations Center. NUREG-1272, Vol. 10, No. 2, covers nuclear materials and presents a review of the events and concerns during 1996 associated with the use of licensed material in nonreactor applications, such as personnel overexposures and medical misadministrations. Both reports also contain a discussion of the Incident Investigation Team program and summarize both the Incident Investigation Team and Augmented Inspection Team reports. Each volume contains a list of the AEOD reports issued from CY 1980 through 1996. NUREG-1272, Vol. 10, No. 3, covers technical training and presents the activities of the Technical Training Center in support of the NRC's mission in 1996
Water Resources Investigation. Cape Girardeau - Jackson Metropolitan Area, Missouri. Volume 4. Appendix C. Public Views and Responses.

Science.gov (United States)

1983-12-01

and Corps of Engineers response. C-21 APPUWIX C C-3 Letter Pg m. Cape Girardeau Chamber of Commerce , 27 December 1983. C-24 n. U.S. Department of the...of erosion. Sincerely, Jack F. Rasmussen, P.E. Chief, Planning D ivision APPENDIX C C-23 Cape Girardeau Chamber of Commerce EXECUTIVE OFFICE December...Girardeau Chamber of Commerce has received and studied the Water Resources and Investigation, Cape Girardeau - Jackson area dated December, 1983 and we

FY 1996 Scientific and Technical Reports, Articles, Papers, and Presentations. Volume 1

Science.gov (United States)

Turner-Waits, Joyce E. (Compiler)

1996-01-01

This document presents formal NASA technical reports, papers published in technical journals, and presentations by MSFC personnel in FY96. It also includes papers of MSFC contractors. After being announced in STAR, all of the NASA series reports may be obtained from the National Technical Information Service, 5285 Port Royal Road, Springfield, VA 22161. The information in this report may be of value to the scientific and engineering community in determining what information has been published and what is available.
FAIR - Baseline technical report. Executive summary

International Nuclear Information System (INIS)

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

2006-09-01

This document presents the Executive Summary, the first of six volumes comprising the 2006 Baseline Technical Report (BTR) for the international FAIR project (Facility for Antiproton and Ion Research). The BTR provides the technical description, cost, schedule, and assessments of risk for the proposed new facility. The purpose of the BTR is to provide a reliable basis for the construction, commissioning and operation of FAIR. The BTR is one of the central documents requested by the FAIR International Steering Committee (ISC) and its working groups, in order to prepare the legal process and the decisions on the construction and operation of FAIR in an international framework. It provides the technical basis for legal contracts on contributions to be made by, so far, 13 countries within the international FAIR Consortium. The BTR begins with this extended Executive Summary as Volume 1, which is also intended for use as a stand-alone document. The Executive Summary provides brief summaries of the accelerator facilities, the scientific programs and experimental stations, civil construction and safety, and of the workproject structure, costs and schedule. (orig.)
49 CFR Appendix F to Part 240 - Medical Standards Guidelines

Science.gov (United States)

2010-10-01

... 49 Transportation 4 2010-10-01 2010-10-01 false Medical Standards Guidelines F Appendix F to Part 240 Transportation Other Regulations Relating to Transportation (Continued) FEDERAL RAILROAD.... F Appendix F to Part 240—Medical Standards Guidelines (1) The purpose of this appendix is to provide...
Interval Appendicectomy and Management of Appendix Mass ...

African Journals Online (AJOL)

A wholly conservative management without interval appendicectomy was instituted for 13 patients diagnosed as having appendix mass between 1998 and 2002 in the University of Benin Teaching Hospital, Benin City, Nigeria. Within three days of admission, one patient developed clinical features of ruptured appendix and ...
TORSION OF THE VERMIFORM APPENDIX: A CASE REPORT

Directory of Open Access Journals (Sweden)

Dr. Imtiaz Wani

2009-07-01

Full Text Available Torsion of the vermiform appendix is a rare condition with few cases reported in the literature. Various factors predispose to torsion. Various factors predispose to torsion. We report a case of primary torsion of the vermiform appendix. The clinical presentation was indistinguishable from acute appendicitis and the diagnosis was made at operation. Appendix was preileal in position and the direction of torsion was anticlockwise. There was intrinsic torsion with no obvious factor for torsion identified. Appendectomy was performed.
Technical reference manual for TIME4. Version 1.0, Volume 1

International Nuclear Information System (INIS)

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

1991-07-01

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

OpenAIRE

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

2016-01-01

Technical analysis is deemed to be a futile practice among academicians who propose efficient market hypothesis, typically the weak form market efficiency which strongly protests the application of past prices and trading volume data for prediction of future market movement. As candlestick charting is one of the oldest technical indicators for short term investment, therefore this study examines the predictability of candlestick charting with combination to trading volume for Malaysian stock ...
Tank Farms Technical Safety Requirements. Volume 1 and 2

International Nuclear Information System (INIS)

CASH, R.J.

2000-01-01

The Technical Safety Requirements (TSRs) define the acceptable conditions, safe boundaries, basis thereof, and controls to ensure safe operation during authorized activities, for facilities within the scope of the Tank Waste Remediation System (TWRS) Final Safety Analysis Report (FSAR)
STTR Phase 1 Final Technical Report for Project Entitled "Developing a Mobile Torrefaction Machine"

Energy Technology Data Exchange (ETDEWEB)

James, Joseph J. [President, ATP

2014-03-11

The goal of this project, sponsored by Agri-Tech Producers, LLC (ATP), the small business grantee, was to determine if the torrefaction technology, developed by North Carolina State University (NCSU), which ATP has licensed, could be feasibly deployed in a mobile unit. The study adds to the area investigated, by having ATP’s STTR Phase I team give thoughtful consideration to how to use NCSU’s technology in a mobile unit. The findings by ATP’s team were that NCSU’s technology would best perform in units 30’ by 80’ (See Spec Sheet for the Torre-Tech 5.0 Unit in the Appendix) and the technical effectiveness and economic feasibility investigation suggested that such units were not easily, efficiently or safely utilized in a forest or farm setting. (Note rendering of possible mobile system in the Appendix) Therefore, the findings by ATP’s team were that NCSU’s technology could not feasibly be deployed as a mobile unit.
Information management architecture for an integrated computing environment for the Environmental Restoration Program. Environmental Restoration Program, Volume 3, Interim technical architecture

International Nuclear Information System (INIS)

1994-09-01

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

DEFF Research Database (Denmark)

Christensen, F. A.; Henriksen, M. S.; Brincker, Rune

1999-01-01

In this appendix a model is formulated for the rotational capacity of reinforced concrete beams assuming rebar tension failure. The model is based on a classical approach and establishes the load-deflection curve of a reinforced concrete beam. The rotational capacity is then obtained as the area ...
Appendix A

DEFF Research Database (Denmark)

Henriksen, M. S.; Brincker, Rune; Heshe, Gert

1999-01-01

In this appendix a brief summary of experiments on reinforced concrete beams in three-point bending performed at Aalborg University is given. The aim of the investigation is to determine the full load-deflection curves for different beam sizes, different types of concrete and different amounts...
Initial Northwest Power Act Power Sales Contracts : Final Environmental Impact Statement. Volume 3, Appendix M, Contract Copies.

Energy Technology Data Exchange (ETDEWEB)

United States. Bonneville Power Administration.

1992-01-01

This report, is part of the final environmental impact statement of the Bonneville Power Administration, consists of an appendix of contract copies related to the following: Detailed Index to Generic Utility Power Sales Contracts, Text of Generic Utility Contract, Detailed Index to Generic DSI Power Sales Contracts, Text of Generic DSI Contract, Text of Residential Purchase and Sale Agreement (Residential Exchange), and Detailed Index to General Contract Provisions -- GCP Form PSC-2 (Incorporated into all three types of contracts as an Exhibit).
Nuclear facility decommissioning and site remedial actions: a selected bibliography. Volume 4

International Nuclear Information System (INIS)

Owen, P.T.; Knox, N.P.; Fielden, J.M.; Faust, R.A.

1983-09-01

This bibliography of 657 references with abstracts on the subject of nuclear facility decommissioning, uranium mill tailings management, and site remedial actions is the fourth in a series of annual reports prepared for the US Department of Energy, Division of Remedial Action Projects. Foreign as well as domestic documents of all types - technical reports, progress reports, journal articles, conference papers, symposium proceedings, theses, books, patents, legislation, and research project descriptions - have been references in this publication. The bibliography contains scientific (basic research as well as applied technology), economic, regulatory, and legal literature pertinent to the US Department of Energy's Remedial Action Program. Major chapters are: (1) Surplus Facilities Management Program; (2) Nuclear Facilities Decommissioning; (3) Formerly Utilized Sites Remedial Action Program; (4) Uranium Mill Tailings Remedial Action Program; (5) Grand Junction Remedial Action Program; and (6) Uranium Mill Tailings Management. Chapter sections for chapters 1 and 2 include: Design, Planning, and Regulations; Site Surveys; Decontamination Studies; Dismantlement and Demolition; Land Decontamination and Reclamation; Waste Disposal; and General studies. The references within each chapter or section are arranged alphabetically by leading author. References having no individual author are arranged by corporate author, or by title. Indexes are provided for the categories of author, corporate affiliation, title, publication description, geographic location, and keywords. Appendix A lists 264 bibliographic references to literature identified during this reporting period but not abstracted due to time constraints. Title and publication description indexes are given for this appendix. Appendix B defines frequently used acronyms, and Appendix C lists the recipients of this report according to their corporate affiliation
Nuclear facility decommissioning and site remedial actions: a selected bibliography. Volume 4

Energy Technology Data Exchange (ETDEWEB)

Owen, P.T.; Knox, N.P.; Fielden, J.M.; Faust, R.A.

1983-09-01

This bibliography of 657 references with abstracts on the subject of nuclear facility decommissioning, uranium mill tailings management, and site remedial actions is the fourth in a series of annual reports prepared for the US Department of Energy, Division of Remedial Action Projects. Foreign as well as domestic documents of all types - technical reports, progress reports, journal articles, conference papers, symposium proceedings, theses, books, patents, legislation, and research project descriptions - have been references in this publication. The bibliography contains scientific (basic research as well as applied technology), economic, regulatory, and legal literature pertinent to the US Department of Energy's Remedial Action Program. Major chapters are: (1) Surplus Facilities Management Program; (2) Nuclear Facilities Decommissioning; (3) Formerly Utilized Sites Remedial Action Program; (4) Uranium Mill Tailings Remedial Action Program; (5) Grand Junction Remedial Action Program; and (6) Uranium Mill Tailings Management. Chapter sections for chapters 1 and 2 include: Design, Planning, and Regulations; Site Surveys; Decontamination Studies; Dismantlement and Demolition; Land Decontamination and Reclamation; Waste Disposal; and General studies. The references within each chapter or section are arranged alphabetically by leading author. References having no individual author are arranged by corporate author, or by title. Indexes are provided for the categories of author, corporate affiliation, title, publication description, geographic location, and keywords. Appendix A lists 264 bibliographic references to literature identified during this reporting period but not abstracted due to time constraints. Title and publication description indexes are given for this appendix. Appendix B defines frequently used acronyms, and Appendix C lists the recipients of this report according to their corporate affiliation.
Proceedings: The Appendix 'K' relief workshop

International Nuclear Information System (INIS)

1989-11-01

The licensing and operation of commercial LWRs were impacted significantly when Appendix 'K' requirements for loss-of-coolant accident (LOCA) and emergency core cooling systems (ECCS) analyses were implemented in 1974. The Appendix K requirements included both criteria and mandatory assumptions for LOCA analysis. Plants must meet these criteria, using analysis methods that have included very conservative assumptions, such as estimating decay heat energy as 20% greater than the 1971 American Nuclear Society standard. Additional constraints were placed on the application of specific models and correlations. The Appendix K requirements had a significant impact on licensing, analysis, fuel design, reload management, plant operation, and some supporting equipment. The overall impact of Appendix K could be translated into increased costs of millions of dollars per year to utilities. The Appendix 'K' Relief Workshop provided an improved understanding of the trade-offs -- both benefits and efforts required -- inherent in continuing to use existing analysis methods or adopting BE analysis under revised NRC rule. A range of options is available to each utility. The workshop explored options and benefits to the utility industry from LOCA/ECCS rule change. A forum for complete and open discussion of the issues germaine to the question of BE methodology versus existing methodology in view of LOCA/ECCS rule changes was incorporated. Both regulatory and utility perspectives on the implementation of proposed changes were discussed. Existing and planned efforts in developing and implementing BE uncertainty methodologies for plant-licensing application have been included. The individual papers have been cataloged separately
The Q,T-catalan numbers and the space of diagonal harmonics with an appendix on the combinatorics of Macdonald polynomials

CERN Document Server

Haglund, James

2007-01-01

This book contains detailed descriptions of the many exciting recent developments in the combinatorics of the space of diagonal harmonics, a topic at the forefront of current research in algebraic combinatorics. These developments led in turn to some surprising discoveries in the combinatorics of Macdonald polynomials, which are described in Appendix A. The book is appropriate as a text for a topics course in algebraic combinatorics, a volume for self-study, or a reference text for researchers in any area which involves symmetric functions or lattice path combinatorics. The book contains expository discussions of some topics in the theory of symmetric functions, such as the practical uses of plethystic substitutions, which are not treated in depth in other texts. Exercises are interspersed throughout the text in strategic locations, with full solutions given in Appendix C.
Technical guideline technology according to the X-ray regulations

International Nuclear Information System (INIS)

2011-01-01

The guideline covers the required technical knowledge concerning radiation protection and knowledge concerning for the operation of X-ray devices for technical purposes and stray radiation sources requiring licensing, and requirements for the qualification of officially authorized inspectors. The guidelines includes the following chapters: (1) introductory regulations; (2) Volume of the required technical knowledge; (3) Acquirement and certification of the technical knowledge; (4) Actualization of the technical knowledge; (5)Approval of courses and other training measures; (6) Combination of courses and training measures according to the guideline; (7) Requirements for qualification of officially authorized inspectors; (8) Interim regulations.
32 CFR Appendix B to Part 275 - Obtaining Customer Authorization

Science.gov (United States)

2010-07-01

... 32 National Defense 2 2010-07-01 2010-07-01 false Obtaining Customer Authorization B Appendix B to... OF 1978 Pt. 275, App. B Appendix B to Part 275—Obtaining Customer Authorization A. A DoD law... feasible, obtain the customer's consent. B. Any authorization obtained under paragraph A. of this appendix...
The second iteration of the Systems Prioritization Method: A systems prioritization and decision-aiding tool for the Waste Isolation Pilot Plant: Volume 2, Summary of technical input and model implementation

Energy Technology Data Exchange (ETDEWEB)

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

1996-05-01

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

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

International Nuclear Information System (INIS)

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

1996-05-01

The Systems Prioritization Method (SPM) is a decision-aiding tool developed by Sandia National Laboratories (SNL). SPM provides an analytical basis for supporting programmatic decisions for the Waste Isolation Pilot Plant (WIPP) to meet selected portions of the applicable US EPA long-term performance regulations. The first iteration of SPM (SPM-1), the prototype for SPM< was completed in 1994. It served as a benchmark and a test bed for developing the tools needed for the second iteration of SPM (SPM-2). SPM-2, completed in 1995, is intended for programmatic decision making. This is Volume II of the three-volume final report of the second iteration of the SPM. It describes the technical input and model implementation for SPM-2, and presents the SPM-2 technical baseline and the activities, activity outcomes, outcome probabilities, and the input parameters for SPM-2 analysis
12 CFR Appendix D to Part 41 - [Reserved

Science.gov (United States)

2010-01-01

... 12 Banks and Banking 1 2010-01-01 2010-01-01 false [Reserved] D Appendix D to Part 41 Banks and Banking COMPTROLLER OF THE CURRENCY, DEPARTMENT OF THE TREASURY FAIR CREDIT REPORTING Appendix D to Part 41[Reserved] ...
Radon-safe new buildings, documentation and technology development. Appendix; Radonsikring i nybyggeri, documentation og teknologiudvikling. Bilag

Energy Technology Data Exchange (ETDEWEB)

Breddam Overgaard, L.; Bruun Petersen, J.; Neerup Jeppesen, M.

2011-07-01

The project is carried out as three separate subprojects, with subproject 1 as the principal project. Subproject 1 deals with field tests of radon penetration of different floor design (1A) and the effect of passive sub slab ventilation (1B). Subproject 2 deals with laboratory tests of material and design permeability, and subproject 3 deals with mapping of the radon potential and variation of a defined area. The appendix volume presents the detailed data for the results achieved in the project. (ln)
Development of SRC-I product analysis. Volume 3. Documentation of procedures

Energy Technology Data Exchange (ETDEWEB)

Schweighardt, F.K.; Kingsley, I.S.; Cooper, F.E.; Kamzelski, A.Z.; Parees, D.M.

1983-09-01

This section documents the BASIC computer program written to simulate Wilsonville's GC-simulated distillation (GCSD) results at APCI-CRSD Trexlertown. The GC conditions used at APCI for the Wilsonville GCSD analysis of coal-derived liquid samples were described in the SRC-I Quarterly Technical Report, April-June 1981. The approach used to simulate the Wilsonville GCSD results is also from an SRC-I Quarterly Technical Report and is reproduced in Appendix VII-A. The BASIC computer program is described in the attached Appendix VII-B. Analysis of gases produced during coal liquefaction generates key information needed to determine product yields for material balance and process control. Gas samples from the coal process development unit (CPDU) and tubing bombs are the primary samples analyzed. A Carle gas chromatographic system was used to analyze coal liquefaction gas samples. A BASIC computer program was written to calculate the gas chromatographic peak area results into mole percent results. ICRC has employed several analytical workup procedures to determine the amount of distillate, oils, asphaltenes, preasphaltenes, and residue in SRC-I process streams. The ASE procedure was developed using Conoco's liquid column fractionation (LC/F) method as a model. In developing the ASE procedure, ICRC was able to eliminate distillation, and therefore quantify the oils fraction in one extraction step. ASE results were shown to be reproducible within +- 2 wt %, and to yield acceptable material balances. Finally, the ASE method proved to be the least affected by sample composition.
Leiomyoma of the appendix: a case report

Energy Technology Data Exchange (ETDEWEB)

Kim, Seong Hoon; Cho, Hyun Cheol; Son, Mi Young [Dae-Gu Veterans Hospital, Daegu (Korea, Republic of)

2007-05-15

Leiomyomas of the appendix are rare and most are encountered incidentally during exploration of the abdomen for some other disease, during postmortem examination, or in the course of routine pathologic examinations of surgical specimens. We report here the findings of ultrasonography, CT and surgery of a case of leiomyoma that arose from the appendix; this lesion was pathologically confirmed.
Alternatives for managing wastes from reactors and post-fission operations in the LWR fuel cycle. Volume 5. Appendices

International Nuclear Information System (INIS)

1976-05-01

Volume V of the five-volume report consists of appendices, which provide supplementary information, with emphasis on characteristics of geologic formations that might be used for final storage or disposal. Appendix titles are: selected glossary; conversion factors; geologic isolation, including, (a) site selection factors for repositories of wastes in geologic media, (b) rock types--geologic occurrence, (c) glossary of geohydrologic terms, and (d) 217 references; the ocean floor; and, government regulations pertaining to the management of radioactive materials
Alternatives for managing wastes from reactors and post-fission operations in the LWR fuel cycle. Volume 5. Appendices

Energy Technology Data Exchange (ETDEWEB)

1976-05-01

Volume V of the five-volume report consists of appendices, which provide supplementary information, with emphasis on characteristics of geologic formations that might be used for final storage or disposal. Appendix titles are: selected glossary; conversion factors; geologic isolation, including, (a) site selection factors for repositories of wastes in geologic media, (b) rock types--geologic occurrence, (c) glossary of geohydrologic terms, and (d) 217 references; the ocean floor; and, government regulations pertaining to the management of radioactive materials. (JGB)
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)
FY 1995 Scientific and Technical Reports, Articles, Papers, and Presentations, Volume 1

Science.gov (United States)

Turner, Joyce E. (Compiler)

1995-01-01

This document presents formal NASA technical reports, papers published in technical journals, and presentations by MSFC personnel in FY95. It also includes papers of MSFC contractors. The information in this report may be of value to the scientific and engineering community in determining what information has been published and what is available.
Volume 2. Probabilistic analysis of HTGR application studies. Supporting data

International Nuclear Information System (INIS)

1980-09-01

Volume II, Probabilistic Analysis of HTGR Application Studies - Supporting Data, gives the detail data, both deterministic and probabilistic, employed in the calculation presented in Volume I. The HTGR plants and the fossil plants considered in the study are listed. GCRA provided the technical experts from which the data were obtained by MAC personnel. The names of the technical experts (interviewee) and the analysts (interviewer) are given for the probabilistic data
The System 80+ Standard Plant design control document. Volume 18

International Nuclear Information System (INIS)

1997-01-01

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

International Nuclear Information System (INIS)

1982-03-01

Part F of the Safeguards Technical Manual is being issued in three volumes. Volume 1 was published in 1977 and revised slightly in 1979. Volume 1 discusses basic probability concepts, statistical inference, models and measurement errors, estimation of measurement variances, and calibration. These topics of general interest in a number of application areas, are presented with examples drawn from nuclear materials safeguards. The final two chapters in Volume 1 deal with problem areas unique to safeguards: calculating the variance of MUF and of D respectively. Volume 2 continues where Volume 1 left off with a presentation of topics of specific interest to Agency safeguards. These topics include inspection planning from a design and effectiveness evaluation viewpoint, on-facility site inspection activities, variables data analysis as applied to inspection data, preparation of inspection reports with respect to statistical aspects of the inspection, and the distribution of inspection samples to more than one analytical laboratory. Volume 3 covers generally the same material as Volumes 1 and 2 but with much greater unity and cohesiveness. Further, the cook-book style of the previous two volumes has been replaced by one that makes use of equations and formulas as opposed to computational steps, and that also provides the bases for the statistical procedures discussed. Hopefully, this will help minimize the frequency of misapplications of the techniques
14 CFR Appendix D to Part 25 - Appendix D to Part 25

Science.gov (United States)

2010-01-01

... AIRWORTHINESS STANDARDS: TRANSPORT CATEGORY AIRPLANES Pt. 25, App. D Appendix D to Part 25 Criteria for... any compartment. (7) The degree of automation provided in the aircraft systems to afford (after...
Visualization of the normal appendix with MR enterography in children

Energy Technology Data Exchange (ETDEWEB)

Kovanlikaya, Arzu; Rosenbaum, Daniel; Brill, Paula W. [Weill Cornell Medical College, New York Presbyterian Hospital, Department of Radiology, New York, NY (United States); Mazumdar, Madhu; Dunning, Allison [Division of Biostatistics and Epidemiology, Weill Cornell Medical College, Department of Public Health, New York, NY (United States)

2012-08-15

Magnetic resonance (MR) imaging may provide a radiation-sparing alternative to CT in diagnosing appendicitis in children in whom US is equivocal. However, comparability with CT in the detection of the appendix remains to be established. To determine the detection rate of the normal appendix in children on oral and IV contrast-enhanced MRI. MR imaging of 58 patients who had previously undergone MR enterography was retrospectively reviewed. Detection rate, body mass index, age and gender were recorded. The normal appendix was detected in 28 cases (48 %), with greatest detection rate on the axial fast imaging employing steady-state acquisition (FIESTA) sequence. Children in whom the appendix was detected had significantly higher BMI compared to children in whom the appendix was not seen. Neither age nor gender demonstrated a significant association with detection rate. The detection rate of the normal appendix in children on oral and IV contrast-enhanced MRI was 48 %, which is comparable to detection rates on CT, as well as to previously reported detection rates on MR imaging with neither oral nor IV contrast agents. These findings may serve to guide the development of MRI protocols for pediatric appendicitis. (orig.)
Bonneville Purchasing Instructions. Appendix 14A, Contracting Officer`s Technical Representatives` Guide for Services Contracts.

Energy Technology Data Exchange (ETDEWEB)

United States. Bonneville Power Administration.

1993-07-01

This guide outlines the duties of BPA personnel designated as Contracting Officers Technical Representatives (COTRs). The BPA Administrator gives contracting officers (COs) in BPA responsibility and authority for awarding and administering contracts. COs are authorized to designate other BPA employees to act as their representatives for purposes of contract administration, from the time of contract award until final receipt and acceptance of the contracted services. COTRs are the individuals primarily relied upon to perform technical contract administration functions. Similar functions for supply and construction contracts are performed by engineering representatives, construction inspectors, and inspectors. Although this Guide is written primarily with the COTR in mind, the concept and operation of teamwork is essential throughout the entire process of contract administration. The CO administers the contract during performance, but rarely has expertise in all of the relevant technical areas. Therefore, CO decisions rely on input from a team. The COTR is an indispensable member of that team. The instructions in this Guide are designed to facilitate this essential CO-COTR cooperation. COTR duties are usually additional to those required of the COTR in his or her assigned line organization. The COTR is still accountable to the line supervisor for performance of regularly-assigned duties. These duties are to be reflected appropriately in performance appraisals and job descriptions. For contract administration duties, however, the COTR reports directly to, and is accountable only to, the CO. The COTR`s supervisor must allow sufficient time to ensure that the COTR can adequately monitor the contract for technical compliance. This Guide is designed for COTRs who are performing service contract (including intergovernmental contract) administration functions as an adjunct to their normal technical duties.
Georgetown University Integrated Community Energy System (GU-ICES). Phase III, Stage I. Feasibility analysis. Final report. Volume 1

Energy Technology Data Exchange (ETDEWEB)

None

1980-10-01

This Feasibility Analysis covers a wide range of studies and evaluations. The Report is divided into five parts. Section 1 contains all material relating to the Institutional Assessment including consideration of the requirements and position of the Potomac Electric Co. as they relate to cogeneration at Georgetown in parallel with the utility (Task 1). Sections 2 through 7 contain all technical information relating to the Alternative Subsystems Analysis (Task 4). This includes the energy demand profiles upon which the evaluations were based (Task 3). It further includes the results of the Life-Cycle-Cost Analyses (Task 5) which are developed in detail in the Appendix for evaluation in the Technical Report. Also included is the material relating to Incremental Savings and Optimization (Task 6) and the Conceptual Design for candidate alternate subsystems (Task 7). Section 8 contains all material relating to the Environmental Impact Assessment (Task 2). The Appendix contains supplementary material including the budget cost estimates used in the life-cycle-cost analyses, the basic assumptions upon which the life-cycle analyses were developed, and the detailed life-cycle-cost anlysis for each subsystem considered in detail.
29 CFR Appendix F to Part 825 - [Reserved

Science.gov (United States)

2010-07-01

... 29 Labor 3 2010-07-01 2010-07-01 false [Reserved] F Appendix F to Part 825 Labor Regulations Relating to Labor (Continued) WAGE AND HOUR DIVISION, DEPARTMENT OF LABOR OTHER LAWS THE FAMILY AND MEDICAL LEAVE ACT OF 1993 Appendix F to Part 825 [Reserved] ...
Lengths and Positions of the Vermiform Appendix among Sudanese Cadavers

Directory of Open Access Journals (Sweden)

Ehab I. El-Amin

2015-08-01

Full Text Available Background/objective: The anatomy of vermiform appendix displays great variations in length and position between different populations. The reports relating these variations to a specific etiological factor are few. This study aims to describe the positions and lengths of vermiform appendix among Sudanese cadavers. Methods: This descriptive study was carried out in Omdurman Teaching Hospital Morgue and Omdurman Islamic University-Sudan. Sixty Sudanese cadavers (30 male and 30 female, were dissected in the period from June 2013 to June 2014. The positions and the lengths of vermiform appendix were measured in millimeters. The data was analyzed by SPSS version 20. Results: The cadavers’ age ranged between 20 to 80 years according to their medico-legal reports. Retrocaecal position was mainly observed in 60%, pelvic in 35%, post-ileal in 3.3%, and pre-ileal in 1.7%. The lengths of the appendix was found < 69 mm in 23.3%, 70-110 mm in 60%, and > 110 mm in 16.7%, also the study showed insignificant difference between the lengths and ages (p < 0.08, and between males and females (p = 0.23. Age was the influencing factor for the positions of vermiform appendixes (p = 0.04. Conclusion: The study showed that the commonest lengths of the appendix were 70-110 mm while the common position was retrocaecal regardless to age or gender. This data should be considered in surgical removal of the inflamed appendix.
ENDOMETRIOSIS OF APPENDIX IN WOMEN PRESENTING WITH RIGHT LOWER ABDOMINAL PAIN

Directory of Open Access Journals (Sweden)

Radha Bai Prabhu T, Velayudam DA, Jayalakshmi M

2015-07-01

Full Text Available Endometriosis is a well known gynaecological condition associated with infertility and chronic pelvic pain. Review of literature shows that endometriosis can affect any tissue in the body, including the appendix. Here we report a case of pelvic endometriosis involving the vermiform appendix in a 45 years old multiparous woman. When women of the reproductive age present with recurrent lower abdominal pain on the right side, endometriosis of the appendix should also be considered. At the time of surgery appendix should be inspected and removed; especially in the presence of pelvic endometriosis.
48 CFR Appendix to Part 1252 - Tar Matrix

Science.gov (United States)

2010-10-01

... 48 Federal Acquisition Regulations System 5 2010-10-01 2010-10-01 false Tar Matrix Appendix to Part 1252 Federal Acquisition Regulations System DEPARTMENT OF TRANSPORTATION CLAUSES AND FORMS SOLICITATION PROVISIONS AND CONTRACT CLAUSES Pt. 1252, App. Appendix to Part 1252—Tar Matrix ER27DE05.000...

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

Science.gov (United States)

Larsen, Ronald L.; Wallgren, Kenneth

1985-01-01

Progress reports and technical updates of programs being performed by NASA centers are covered. Presentations in viewgraph form are included for topics in three categories: computer science, data systems and space station applications.
Fiscal year 1985 Department of Energy authorization (high-energy and nuclear physics). Volume II-B. Hearing before the Subcommittee on Energy Development and Applications of the Committee on Science and Technology, US House of Representatives, Ninety-Eighth Congress, Second Session, February 22, 1984

International Nuclear Information System (INIS)

Anon.

1984-01-01

Volume II-B of the DOE authorization hearings for fiscal year 1985 covers testimony on high-energy and nuclear physics programs. The volume opens with a continuation of Appendix I, which contains questions directed at Dr. Alvin Trivelpiece and his responses on research at several laboratories and four construction projects. The latter include general plant projects, the Continuous Electron Beam Accelerator Facility, the Tandem/AGS Heavy Ion Transfer Line, and the University Accelerator Upgrade at the University of Washington and Yale. Two 1983 DOE/National Science Foundation reports make up Appendix II. The volume concludes with the text of the 1985 budget request for $746,105,000 and a breakdown of line item expenditures
Proceedings: Computer Science and Data Systems Technical Symposium, volume 2

Science.gov (United States)

Larsen, Ronald L.; Wallgren, Kenneth

1985-01-01

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

Science.gov (United States)

Schou-Jensen, Katrine; Antipina, Elena Nikolaevna; Brisling, Steffen Kirstein; Azawi, Nessn

2014-12-15

A nine-year-old girl was admitted to the paediatric ward due to fever and lower abdomen pain through a day. Acute laparoscopic exploration showed a large necrotic perforation at the distal end of the appendix. During the appendectomy multiple small, live Enterobius vermicularis (pinworms) were observed. The patient was admitted for three days of observation and received relevant treatment with intravenous antibiotics and antihelminthic treatment. The histology showed numerous pinworms in the lumen of the appendix and invasion of the pinworms of the submucosal layer and the wall of the appendix.
MORPHOLOGIC CHARACTERISTICS OF THE VERMIFORM APPENDIX DURING THE PRENATAL PERIOD IN MAN

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Vladimir Živković

2012-01-01

Full Text Available In the literature, there are different data about the morphologic characteristics and variations of the appendix during the postnatal period in man, but the information about its characteristics in the prenatal period is scarce. In our study, the characteristics of the appendix in prenatal period of development were studied on the fetal material. We used the fetuses from the collection of the Institute of Anatomy, Faculty of Medicine in Niš, 100 of them in total, formalin-fixed, of both genders, in their second and third trimester of intrauterine development. Regarding anatomical variations, we found a missing appendix in one case and a double appendix in another. The appendical opening into the cecum was located on the inner, posterior, outer, and anterior walls of the cecum, always below the ileal opening. The origin from the inferior, lowest part of the cecum was also observed. The appendix ran in preileal, retroileal, prececal, retrocecal, and retrocolic directions. The appendix had tubular shape, with one or two bends, being rarely straight. The length of the appendix varied from very short to very long, descending from the inferior edge of the liver to the right iliac fossa. The morphologic characteristics of the appendix in fetus, observed in our study, in the literature have been described to exist in the postnatal human life as well.
12 CFR Appendixes A-B to Part 41 - [Reserved

Science.gov (United States)

2010-01-01

... 12 Banks and Banking 1 2010-01-01 2010-01-01 false [Reserved] A Appendixes A-B to Part 41 Banks and Banking COMPTROLLER OF THE CURRENCY, DEPARTMENT OF THE TREASURY FAIR CREDIT REPORTING Appendixes A-B to Part 41 [Reserved] ...
Computational needs survey of NASA automation and robotics missions. Volume 2: Appendixes

Science.gov (United States)

Davis, Gloria J.

1991-01-01

NASA's operational use of advanced processor technology in space systems lags behind its commercial development by more than eight years. One of the factors contributing to this is the fact that mission computing requirements are frequency unknown, unstated, misrepresented, or simply not available in a timely manner. NASA must provide clear common requirements to make better use of available technology, to cut development lead time on deployable architectures, and to increase the utilization of new technology. Here, NASA, industry and academic communities are provided with a preliminary set of advanced mission computational processing requirements of automation and robotics (A and R) systems. The results were obtained in an assessment of the computational needs of current projects throughout NASA. The high percent of responses indicated a general need for enhanced computational capabilities beyond the currently available 80386 and 68020 processor technology. Because of the need for faster processors and more memory, 90 percent of the polled automation projects have reduced or will reduce the scope of their implemented capabilities. The requirements are presented with respect to their targeted environment, identifying the applications required, system performance levels necessary to support them, and the degree to which they are met with typical programmatic constraints. Here, appendixes are provided.
Technical Assistance in Evaluating Career Education Projects. Final Report. Volume I: Summary Volume.

Science.gov (United States)

Stenner, A. Jackson; And Others

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

International Nuclear Information System (INIS)

Trubatch, S.L.

1987-01-01

This paper describes and discusses non-technical policy considerations which may improperly influence decisions on the solidification of low-level radioactive wastes (''LLW''). These policy considerations are contained principally in several State and Federal statutes which regulate various aspects of LLW disposal. One policy consideration in particular, the unqualified bias in favor of volume reduction, is shown to present a substantial potential for leading to technically suboptimal decisions on the appropriate processes for solidifying LLW. To avoid the unintended skewing of technical decisions by non-technical policy considerations, certain current policies may need to be revised to ensure that the choices of waste treatment, including decisions on solidification, are based primarily on reasonable assurance of adequate protection of public health and safety. This goal may be realized in part by basing any disposal fee structure on more than just LLW volume to include consideration of the waste's activity and its difficulty of confinement
36 CFR Appendix A to Part 14 - Appendix A to Part 14

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2010-07-01

... obtain the benefits of _____(Cite statute); and I further certify that the right-of-way herein described... RIGHTS-OF-WAY Pt. 14, App. A Appendix A to Part 14 Where necessary, these forms should be modified so as...
Survey and Analysis of Environmental Requirements for Shipboard Electronic Equipment Applications. Appendix A. Volume 2.

Science.gov (United States)

1991-07-31

ADDRESS: 35 South Service Road Plainview NY 11803 MARKETING: Clint Brown TECHNICAL: PHONE: (516) 694 6700 FAX: (516) 694 6771I I I I I VMEbus VENDOR...DISTRIBUTOR ADDRESS: 17032 Murphy Avenue I Irvine CA 92714 I MARKETING: John Sutherland TECHNICAL: Tim Elsmore PHONE: (714) 261 0606 FAX: (714) 261 0894 I I
Bio-aggregates based building materials state-of-the-art report of the RILEM Technical Committee 236-BBM

CERN Document Server

Collet, Florence

2017-01-01

The work of the RILEM Technical Committee (TC -236 BBM) was dedicated to the study of construction materials made from plant particles. It considered the question whether building materials containing as main raw material recyclable and easily available plant particles are renewable. This book includes a state-of-the-art report and an appendix. The state-of-the-art report relates to the description of vegetal aggregates. Then, hygrothermal properties, fire resistance, durability and finally the impact of the variability of the method of production of bio-based concrete are assessed. The appendix is a TC report which presents the experience of a working group. The goal was to define testing methods for the measurement of water absorption, bulk density, particle size distribution, and thermal conductivity of bio aggregates. The work is based on a first round robin test of the TC-BBM where the protocols in use by the different laboratories (labs) are compared. .
47 CFR Appendix I to Subpart E of... - A Procedure for Calculating PCS Signal Levels at Microwave Receivers (Appendix E of the...

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2010-10-01

... 47 Telecommunication 2 2010-10-01 2010-10-01 false A Procedure for Calculating PCS Signal Levels...—A Procedure for Calculating PCS Signal Levels at Microwave Receivers (Appendix E of the Memorandum... receiver from the PCS operation. This appendix describes a procedure for computing this PCS level. In...
Feasibility of developing a portable driver performance data acquisition system for human factors research: Technical tasks. Volume 1

Energy Technology Data Exchange (ETDEWEB)

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

1998-01-01

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

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Kasukurthy Ashalatha

2016-07-01

Full Text Available BACKGROUND Appendix is derived from a Latin word (Pendere meaning at the end. It is a narrow worm-like tubular diverticulum, which arises from the posteromedial wall of caecum about 2 cms below the ileocaecal junction and is suspended by a peritoneal fold known as mesoappendix. The body of appendix is kinked on itself where the free border of mesoappendix ends. Hence, it is coiled like a worm and so is named the ‘Vermiform Appendix’. The appendix is taken up for study in view of its different positions, varying anatomical relations, and the clinical complications when pathologically affected. The relations, measurements, positions, and arterial supply were studied by gross dissection in 61 specimens (Adults – 33 and foetuses – 28 from the population of Krishna and Warangal districts of Andhra Pradesh. MATERIALS AND METHODS The present study was done on 31 adult specimens, out the length of the appendix, the diameter of the appendix at base, length of the caecum, length of ascending colon were measured. The position of the appendix was classified as per Datta’s classification. Mesenteric attachment to the vermiform appendix were noted. Even arterial supply of the appendix was studied. RESULTS Length of the appendix in adults varied from 2.00 to 25.00 cm as described by different authors, the average being 3.00 to 12.50 cm. The length of the caecum in adults were ranging from 5 to 8 cm. In the present study, the length of appendix was 14.4 cm The origin of the appendicular artery was from inferior division of ileocolic artery. A single appendicular artery is observed in all the specimens almost coinciding with studies of Michels et al. In the present study, in adults, the mesoappendix was extending to the tip in 19 specimens and extending to a variable extent in 14 specimens. Regarding the positions, in adults, they were retrocaecal, retrocolic, and subcaecal positions were 21.21% and splenic, promontory, and pelvic positions were 78
Autoamputation of the Appendix in a Chronic Adnexal Abscess

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C. Michele Markey

2018-01-01

Full Text Available Autoamputation of the appendix has rarely been described in the literature. We present a case of a pelvic mass, thought to be a dermoid cyst based on preoperative imaging. After surgical removal and pathological examination, the mass was found to be a chronic pelvic abscess containing the right adnexa as well as an autoamputated vermiform appendix. Differentiating between gynecologic and gastrointestinal disease preoperatively can be difficult and often a definitive diagnosis cannot be made until surgical exploration and pathological review. However, to our knowledge, this is the first described case of a chronic pelvic abscess containing an autoamputated vermiform appendix.
Incorporating technical analysis in undergraduate curricula

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Michael R. Melton

2017-11-01

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

DEFF Research Database (Denmark)

Liu, Wei; Nannarelli, Alberto

This document is an appendix to the paper: Wei Liu and Alberto Nannarelli, ”Power Dissipation in Division”, Proc. of 42nd Asilomar Conference on Signals, Systems, and Computers, October 2008. The purpose of the document is to provide the necessary information for the implementation of the archite......This document is an appendix to the paper: Wei Liu and Alberto Nannarelli, ”Power Dissipation in Division”, Proc. of 42nd Asilomar Conference on Signals, Systems, and Computers, October 2008. The purpose of the document is to provide the necessary information for the implementation...
In vivo location of the vermiform appendix in multidetector CT

Energy Technology Data Exchange (ETDEWEB)

Lee, Su Lim; Ku, Young Mi [Dept. of Radiology, Uijeongbu St. Mary' s Hospital, College of Medicine, The Catholic University of Korea, Uijeongbu (Korea, Republic of); Choi, Byung Gil; Byun, Jae Young [Dept. of Radiology, Seoul St. Mary' s Hospital, College of Medicine, The Catholic University of Korea, Seoul (Korea, Republic of)

2014-04-15

To provide a more detailed classification system regarding the position of the vermiform appendix within the right lower quadrant, as seen on multidetector computed tomography (MDCT) and to investigate the relative differences in frequency of appendiceal position according to patient gender and the pathologic state of appendix. Between January 2008 and December 2010, 1157 patients were included in our final analysis: 542 patients with preoperative MDCT and subsequent appendectomy and 615 patients with visible appendix seen on MDCT performed as part of a health checkup. We classified the appendix according to its position relative to the cecum, the terminal ileum, and the external iliac vessels: type 1: antececal; type 2: preileal; type 3: postileal; type 4: subileal; type 5: subcecal; type 6: deep pelvic; type 7: retrocecal; and type 8: paracecal. The relative incidence of various positions of the appendix found in all of our study patients was: type 1: 3.5%; type 2: 1.7%; type 3: 9.0%; type 4: 12.9%; type 5: 42.3%; type 6: 16.2%; type 7: 10.9%; and type 8: 3.0%. According to patient gender, type 1 (male: 3.7% vs. female: 3.3%), type 3 (8.6% vs. 9.8%), type 4 (14.3% vs. 9.8%), type 5 (47.5% vs. 32.7%), type 7 (9.2% vs. 14.4%), and type 8 (3.4% vs. 2.2%) positions showed a statistically significant male predominance. In terms of the inflamed state, type 2 preileal (normal: 0.8% vs. inflamed: 2.8%), type 3 (10.2% vs. 7.6%), type 4 (14.0% vs. 11.6%), and type 5 (14.1% vs. 18.5%) positions showed a statistically significant difference. Contrary to the common assumption that the retrocecal appendix is the most common position, the in vivo appendix is seen more often on MDCT in the subcecal and deep pelvic positions. The relative frequency of various positions of the appendix can also differ according to patient gender and the pathologic state.
Mucinous Cystadenoma of the Appendix in a Patient with Systemic Lupus Erthematosus

Directory of Open Access Journals (Sweden)

Debrah A Wirtzfeld

1998-01-01

Full Text Available A 38-year-old female with systemic lupus erythematosus presented with abdominal pain, diarrhea and iron-deficient anemia. Computed tomogram showed a 2x4 cm inhomogeneous lesion of the right adnexa. An unusual mass was identified extending from the appendiceal orifice at colonoscopy, and an 8 cm tubular appendix, apparently prolapsed into the cecum, was identified at celiotomy. An appendectomy with cecectomy was performed. On cut section, mucin was extruded from the lumen of the appendix. A mucinous neoplasm of the appendix with mucinous dissection to the serosal surface was reported at the time of frozen section. No gross ovarian pathology or peritoneal implants were noted. Cystadenoma with associated mucocele formation was verified by permanent histology. Mucocele of the vermiform appendix is a rare condition associated with neoplastic transformation in approximately 75% of all cases. Benign mucinous cystadenoma of the appendix should be differentiated from cystadenocarcinoma by frozen section at the time of celiotomy to ensure appropriate treatment. While systemic lupus erythematosus can lead to cutaneous mucinosis, an association with mucinous cystadenoma of the appendix has not been previously reported. Surveillance for metachronous colonic neoplasms is warranted in patients diagnosed with a mucinous neoplasm of the appendix.

12 CFR Appendix B to Part 716 - SAMPLE CLAUSES

Science.gov (United States)

2010-01-01

...-dealers, and insurance agents”]; • Non-financial companies, such as [provide illustrative examples, such... CONSUMER FINANCIAL INFORMATION Pt. 716, App. B Appendix B to Part 716—SAMPLE CLAUSES This appendix only... disclose nonpublic personal information about you to the following types of third parties: • Financial...
Gender Research in Africa into ICTs for Empowerment (GRACE ...

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

Reports. Final technical report - appendix D / citations of African women and ICTs : investigating technology, gender and empowerment (2009), as of 24 February 2012. Download PDF. Reports. Final technical report - appendix B / publications, presentations and reports. Download PDF. Reports. Final technical report ...
Mixed Waste Focus Area integrated technical baseline report, Phase 1: Volume 1

International Nuclear Information System (INIS)

1996-01-01

The Department of Energy (DOE) established the Mixed Waste Characterization, Treatment, and Disposal Focus Area (MWFA) to develop and facilitate implementation of technologies required to meet the Department's commitments for treatment of mixed low-level and transuranic wastes. The mission of the MWFA is to provide acceptable treatment systems, developed in partnership with users and with participation of stakeholders, tribal governments, and regulators, that are capable of treating DOE's mixed waste. These treatment systems include all necessary steps such as characterization, pretreatment, and disposal. To accomplish this mission, a technical baseline is being established that forms the basis for determining which technology development activities will be supported by the MWFA. The technical baseline is the prioritized list of deficiencies, and the resulting technology development activities needed to overcome these deficiencies. This document presents Phase I of the technical baseline development process, which resulted in the prioritized list of deficiencies that the MWFA will address. A summary of the data and the assumptions upon which this work was based is included, as well as information concerning the DOE Office of Environmental Management (EM) mixed waste technology development needs. The next phase in the technical baseline development process, Phase II, will result in the identification of technology development activities that will be conducted through the MWFA to resolve the identified deficiencies
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.
Draft Title 40 CFR 191 compliance certification application for the Waste Isolation Pilot Plant. Volume 4: Appendix BIR Volume 2

International Nuclear Information System (INIS)

1995-01-01

This report consists of the waste stream profile for the WIPP transuranic waste baseline inventory at Lawrence Livermore National Laboratory. The following assumptions/modifications were made by the WTWBIR team in developing the LL waste stream profiles: since only current volumes were provided by LL, the final form volumes were assumed to be the same as the current volumes; the WTWBIR team had to assign identification numbers (IDs) to those LL waste streams not given an identifier by the site, the assigned identification numbers are consistent with the site reported numbers; LL Final Waste Form Groups were modified to be consistent with the nomenclature used in the WTWBID, these changes included word and spelling changes, the assigned Final Waste Form Groups are consistent with the information provided by LL; the volumes for the year 1993 were changed from an annual rate of generation (m 3 /year) to a cumulative value (m 3 )
Influence of technical parameters on epicardial fat volume quantification at cardiac CT.

Science.gov (United States)

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

2015-06-01

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

Science.gov (United States)

Gladis, Sister Mary Paulette

The second of two volumes, the document contains the appendixes to a study which investigated the influence of typewriting on selected language arts skills and motor development of educable mentally retarded students. The academic achievement of such students in reading, vocabulary, spelling, and in motor skill development, after completing…
Vandenberg Air Force Base integrated resource assessment. Volume 3, Resource assessment

Energy Technology Data Exchange (ETDEWEB)

Daellenbach, K.K.; Dagle, J.E.; Dittmer, A.L.; Elliott, D.B.; Halverson, M.A.; Hickman, B.J.; Parker, G.B.; Richman, E.E.; Shankle, S.A.

1993-06-01

The US Air Force Space Command (SPACECOM) has tasked the Pacific Northwest Laboratory (PNL), as the lead laboratory supporting the US Department of Energy (DOE) Federal Energy Management Program (FEMP), to identify, evaluate, and assist in acquiring all cost-effective energy projects at Vandenberg Air Force Base (VAFB). This is part of a model program that PNL is designing to support energy-use decisions in the federal sector. This report provides the results of the fossil fuel and electric energy resource opportunity (ERO) assessments performed by PNL at the SPACECOM VAFB facility located approximately 50 miles northwest of Santa Barbara, California. It is a companion report to Volume 1, Executive Summary, and Volume 2, Baseline Detail. The results of the analysis of EROs are presented in ten common energy end-use categories (e.g., boilers and furnaces, service hot water, and building lighting). In addition, a case study of process loads at Space Launch Complex-4 (SLC-4) is included. A narrative description of each ERO is provided, including information on the installed cost, energy and dollar savings; impacts on operation and maintenance (O and M); and, when applicable, a discussion of energy supply and demand, energy security, and environmental issues. A description of the evaluation methodologies and technical and cost assumptions is also provided for each ERO. Summary tables present the cost-effectiveness of energy end-use equipment before and after the implementation of each ERO and present the results of the life-cycle cost (LCC) analysis indicating the net present value (NPV) and value index (VI) of each ERO. Finally, an appendix includes a summary of an economic analysis case study of the South Vandenberg Power Plant (SVPP) operating scenarios.
17 CFR Appendix B to Part 160 - Sample Clauses

Science.gov (United States)

2010-04-01

... as [provide illustrative examples, such as “mortgage bankers”]; • Non-financial companies, such as... FINANCIAL INFORMATION Pt. 160, App. B Appendix B to Part 160—Sample Clauses This appendix only applies to privacy notices provided before January 1, 2011. Financial institutions, including a group of financial...
29 CFR Appendix A to Part 825-Index - [Reserved

Science.gov (United States)

2010-07-01

... 29 Labor 3 2010-07-01 2010-07-01 false [Reserved] A Appendix A to Part 825-Index Labor Regulations Relating to Labor (Continued) WAGE AND HOUR DIVISION, DEPARTMENT OF LABOR OTHER LAWS THE FAMILY AND MEDICAL LEAVE ACT OF 1993 Appendix A to Part 825—Index [Reserved] ...
'Nuclex 75'. Preview of the technical fair

International Nuclear Information System (INIS)

Anon.

1975-01-01

The 'Nuclex 75' - fourth international technical fair and specialist meetings for the nuclear industry - takes place from the 7th to the 11th October 1975 in the halls of the Schweizer Mustermesse in Basel. The meeting, which has taken place at three-yearly intervals since 1966, is divided into a technical fair and a congress. 422 exhibitors from 25 countries take part in the 'Nuclex 75'. Several industrial countries are again represented by communal exhibitions. The editorial office of 'Atom and Electricity' gives a few hints on the technical fair to follow which are based on the papers of the exhibitor sent in up to the editor's closing date. A detailed report on the technical fair as well as on important topics of the congress will appear in volume 11/12 1975. (orig./LH) [de
Alligator Rivers Analogue Project. Final Report - Volume 1

Energy Technology Data Exchange (ETDEWEB)

Duerden, P [Australian Nuclear Science and Technology Organisation (ANSTO), Lucas Heights, NSW (Australia); Lever, D A [AEA Technology, Harwell (United Kingdom); Sverjensky, D A [Johns Hopkins Univ., Baltimore, MD (United States); Townley, L R [Commonwealth Scientific and Industrial Research Organisation (CSIRO), Wembley, WA (Australia). Div. of Water Resources

1992-07-01

This summary report, which highlights the work and findings of the Alligator Rivers Analogue Project (ARAP) is one of a series of 16 volumes, listed below. Detailed descriptions and results are provided in Volumes 2 to 16. Full acknowledgment to individual contributions is provided in the individual reports, and in Appendix I of this report. The findings from the technical studies are discussed in the context of assessments of the long-term performance of geological repositories for radioactive wastes, which are being undertaken in many countries. They are also considered in an integrated 'Scenario Development' approach, aimed to understand the formation of the ore deposit. Despite their inherent uncertainties, the findings provide a basis for assessing the way in which radionuclides will migrate in environments with a variety of geologic settings and over a range of different geologic timescales. Thus, section 2 of this report discusses the concept of using uranium deposits as natural analogues and refers to a number of such studies, including those at the Koongarra deposit in the Alligator Rivers Region of the Northern Territory of Australia. Section 3 reviews early scientific work in the Alligator Rivers Region and summarises the results of the analogue studies undertaken between 1981 and 1987 that were funded by the US Nuclear Regulatory Commission (USNRC) and the UK Department of the Environment (UKDoE). Section 4 describes the objectives of ARAP and the manner in which the study was conducted and provides a general outline of the project and a summary of the findings. A general description of the Koongarra ore deposit, the focus of ARAP, is provided in Section 5, with Sections 6-13 providing summaries of the work carried out to characterise the site in detail and provide data for modelling. Sections 14-18 discuss how this data was used in modelling and how the results may be applied for performance assessment studies. Finally, Section 19 considers the
Alligator Rivers Analogue Project. Final Report - Volume 1

International Nuclear Information System (INIS)

Duerden, P.; Lever, D.A.; Sverjensky, D.A.; Townley, L.R.

1992-01-01

This summary report, which highlights the work and findings of the Alligator Rivers Analogue Project (ARAP) is one of a series of 16 volumes, listed below. Detailed descriptions and results are provided in Volumes 2 to 16. Full acknowledgment to individual contributions is provided in the individual reports, and in Appendix I of this report. The findings from the technical studies are discussed in the context of assessments of the long-term performance of geological repositories for radioactive wastes, which are being undertaken in many countries. They are also considered in an integrated 'Scenario Development' approach, aimed to understand the formation of the ore deposit. Despite their inherent uncertainties, the findings provide a basis for assessing the way in which radionuclides will migrate in environments with a variety of geologic settings and over a range of different geologic timescales. Thus, section 2 of this report discusses the concept of using uranium deposits as natural analogues and refers to a number of such studies, including those at the Koongarra deposit in the Alligator Rivers Region of the Northern Territory of Australia. Section 3 reviews early scientific work in the Alligator Rivers Region and summarises the results of the analogue studies undertaken between 1981 and 1987 that were funded by the US Nuclear Regulatory Commission (USNRC) and the UK Department of the Environment (UKDoE). Section 4 describes the objectives of ARAP and the manner in which the study was conducted and provides a general outline of the project and a summary of the findings. A general description of the Koongarra ore deposit, the focus of ARAP, is provided in Section 5, with Sections 6-13 providing summaries of the work carried out to characterise the site in detail and provide data for modelling. Sections 14-18 discuss how this data was used in modelling and how the results may be applied for performance assessment studies. Finally, Section 19 considers the
German (GRS) approach to accident analysis (part I). German licensing basis for accident analyses. Applicants accident analyses in second part license for Konvoi-plants. Appendix 1. Assessor accident analyses in second part license for Konvoi-plants. Appendix 2. Reference list of DBA to be considered in the safety status analysis of a PSR. Appendix 3a. Reference list of special very rare and BDB plant conditions to be considered in the safety status analysis of a PSE. Appendix 3b

International Nuclear Information System (INIS)

Velkov, K.

2002-01-01

Appendix 1: The Safety Analysis Report (S.A.R.) is presented from 3 Handbooks - ECC Handbook (LOCA), Plant Dynamics Handbook (Transients incl. ATWS), and Core Design Handbook. The first one Conceived as Living handbook, Basis for design, catalogue of transients, specifications and licensing. Handbook contains LOCA in primary system, it contains also core damage analysis, and description of codes, description of essential plant data and code input data. The second one consists of Basis for design, commissioning, operation, and catalogue of transients, specifications and licensing, as well as specified operation, disturbed operation, incidents, non-LOCA, SS-procedures and Code description. The third book consists of Reactivity balance and reactivity coefficients, efficiency of shutdown systems. Calculation of burn up cycle, power density distribution, and critical boron concentration. Also Codes used, as SAV79A standard analysis methodology including FASER for nuclear data generation, MEDIUM and PANBOX for static and transient core calculations. Appendix 2: The three TUEV (Technical Inspection Agencies) responsible for the three individual plants of type KONVOI: TUEV Bayern for ISAR-2, TUV-Hanover for KKE, TUEV-Stuttgart for GKN-2 and GRS performed the safety assessment. TUV-Bayern for disturbance and failure of secondary heat sink without loss of coolant (failure of main heat sink, erroneous operation of valves in MS and in FW system, failure of MFW supply), long term LONOP, performance of selected SBLOCA analyses. TUV Hanover for disturbances due to failure of MCPs, short term LONOP, damages of SG tubes incl. SGTR, performance of selected LOCA analyses (blowdown phase of LBLOCA). TUV-Stuttgart for breaks and leaks in MS and FW system with and without leaks in SG tubes. GRS for ATWS, sub-cooling transients due to disturbances on secondary side, initial and boundary conditions for transients with opening of pressurizer valves with and without stuck-open, most of the
32 CFR Appendix to Part 395 - Delegations of Authority

Science.gov (United States)

2010-07-01

... 32 National Defense 2 2010-07-01 2010-07-01 false Delegations of Authority Appendix to Part 395...) ORGANIZATIONAL CHARTERS DEFENSE LEGAL SERVICES AGENCY Pt. 395, App. Appendix to Part 395—Delegations of Authority... terminate the service, of an employee in the interest of national security. 2. Authorize and approve...
Significance of acquired diverticular disease of the vermiform appendix

DEFF Research Database (Denmark)

Kallenbach, Klaus; Hjorth, Sofie Vetli; Engel, Ulla

2012-01-01

To assess the prevalence of acquired diverticulum of the appendix (DA), including incipient forms and its possible significance as a marker of local/regional neoplasms.......To assess the prevalence of acquired diverticulum of the appendix (DA), including incipient forms and its possible significance as a marker of local/regional neoplasms....
KBS Technical report 1-120 (1977-1978). Summaries

International Nuclear Information System (INIS)

1979-05-01

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

International Nuclear Information System (INIS)

1995-11-01

The System Operation Review (SOR) is a study and environmental compliance process being used by the three Federal agencies to analyze future operations of the system and river use issues. The goal of the SOR is to achieve a coordinated system operation strategy for the river that better meets the needs of all river users. This technical appendix addresses only the effects of alternative system operating strategies for managing the Columbia River system. Analysis of water quality begins with an account of the planning and evaluation process, and continues with a description of existing water quality conditions in the Columbia River Basin. This is followed by an explanation how the analysis was conducted. The analysis concludes with an assessment of the effects of SOR alternatives on water quality and a comparison of alternatives
12 CFR Appendix A to Part 233 - Model Notice

Science.gov (United States)

2010-01-01

... FUNDING OF UNLAWFUL INTERNET GAMBLING (REGULATION GG) Part 233, App. A Appendix A to Part 233—Model Notice... 12 Banks and Banking 3 2010-01-01 2010-01-01 false Model Notice A Appendix A to Part 233 Banks and... that your institution processed payments through our facilities for Internet gambling transactions...
Report on the remedial investigation of Bear Creek Valley at the Oak Ridge Y-12 Plant, Oak Ridge, Tennessee. Volume 2: Appendix A - Waste sites, source terms, and waste inventory report; Appendix B - Description of the field activities and report database; Appendix C - Characterization of hydrogeologic setting report

International Nuclear Information System (INIS)

1996-01-01

This Remedial Investigation (RI) Report characterizes the nature and extent of contamination, evaluates the fate and transport of contaminants, and assesses risk to human health and the environment resulting from waste disposal and other US Department of Energy (DOE) operations in Bear Creek Valley (BCV). BCV, which is located within the DOE Oak Ridge Reservation (ORR) encompasses multiple waste units containing hazardous and radioactive wastes arising from operations at the adjacent Oak Ridge Y-12 Plant. The primary waste units discussed in this RI Report are the S-3 Site, Oil Landfarm (OLF), Boneyard/Burnyard (BYBY), Sanitary Landfill 1 (SL 1), and Bear Creek Burial Grounds (BCBG). These waste units, plus the contaminated media resulting from environmental transport of the wastes from these units, are the subject of this RI. This BCV RI Report represents the first major step in the decision-making process for the BCV watershed. The RI results, in concert with the follow-on FS will form the basis for the Proposed Plan and Record of Decision for all BCV sites. This comprehensive decision document process will meet the objectives of the watershed approach for BCV. Appendix A includes descriptions of waste areas and estimates of the current compositions of the wastes. Appendix B contains an extensive database of environmental data for the Bear Creek Valley Characterization Area. Information is also presented about the number and location of samples collected, the analytes examined, and the extent of data validation. Appendix C describes the hydrogeologic conceptual model for Bear Creek Valley. This model is one of the principal components of the conceptual site models for contaminant transport in BCV

Report on the remedial investigation of Bear Creek Valley at the Oak Ridge Y-12 Plant, Oak Ridge, Tennessee. Volume 2: Appendix A -- Waste sites, source terms, and waste inventory report; Appendix B -- Description of the field activities and report database; Appendix C -- Characterization of hydrogeologic setting report

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-09-01

This Remedial Investigation (RI) Report characterizes the nature and extent of contamination, evaluates the fate and transport of contaminants, and assesses risk to human health and the environment resulting from waste disposal and other US Department of Energy (DOE) operations in Bear Creek Valley (BCV). BCV, which is located within the DOE Oak Ridge Reservation (ORR) encompasses multiple waste units containing hazardous and radioactive wastes arising from operations at the adjacent Oak Ridge Y-12 Plant. The primary waste units discussed in this RI Report are the S-3 Site, Oil Landfarm (OLF), Boneyard/Burnyard (BYBY), Sanitary Landfill 1 (SL 1), and Bear Creek Burial Grounds (BCBG). These waste units, plus the contaminated media resulting from environmental transport of the wastes from these units, are the subject of this RI. This BCV RI Report represents the first major step in the decision-making process for the BCV watershed. The RI results, in concert with the follow-on FS will form the basis for the Proposed Plan and Record of Decision for all BCV sites. This comprehensive decision document process will meet the objectives of the watershed approach for BCV. Appendix A includes descriptions of waste areas and estimates of the current compositions of the wastes. Appendix B contains an extensive database of environmental data for the Bear Creek Valley Characterization Area. Information is also presented about the number and location of samples collected, the analytes examined, and the extent of data validation. Appendix C describes the hydrogeologic conceptual model for Bear Creek Valley. This model is one of the principal components of the conceptual site models for contaminant transport in BCV.
Crohn's disease limited to the vermiform appendix

DEFF Research Database (Denmark)

Bak, Martin; Andersen, J C

1987-01-01

Thirteen cases of Crohn's disease confined to the vermiform appendix were seen during a 12-year period. They constituted 16.9% of patients with primary resection of the bowel for Crohn's disease in the same period, but only 0.4% of the cases of acute appendicitis. In 10 of the 13 cases there was ......Thirteen cases of Crohn's disease confined to the vermiform appendix were seen during a 12-year period. They constituted 16.9% of patients with primary resection of the bowel for Crohn's disease in the same period, but only 0.4% of the cases of acute appendicitis. In 10 of the 13 cases...... to approach that of recurrence after resection in other parts of the intestines. Collective review of this and three other relatively large case series gave an estimated recurrence rate of 3.5%. We conclude that in Crohn's disease initially confined to the appendix the course appears to be indolent....
The facts on file dictionary of environmental science

Energy Technology Data Exchange (ETDEWEB)

Stevenson, L.H.; Wyman, B. (eds.)

1991-01-01

More than 3000 entries of terms related to environmental science are included in this volume. The terms are defined in words meant to be understood by the nonexpert, for use in reporting to the general public. Definitions are one to two sentences in length and are accurate without being highly technical. The Appendix lists over 500 commonly used environmental science acronyms and abbreviations as well as a table of standard human factors.
47 CFR Appendix - Technical Appendix 2

Science.gov (United States)

2010-10-01

.... Outputs (General) S-Video Digital Video Interface (DVI);Component video (YPbPr); High-Definition... and other existing video and audio equipmentRemote control may have dedicated keys to provide direct...
47 CFR Appendix - Technical Appendix 1

Science.gov (United States)

2010-10-01

... auditory systems as the primary measuring “instrument.” These methods may incorporate viewing active video..., measured in the 6 MHZ channel under test, referenced to the average power of the DTV signal. The input DTV... 47 CFR § 11.11 of the FCC Rules; (2) parental control information as required by the FCC Rules in 47...
HARNESSING BIG DATA VOLUMES

Directory of Open Access Journals (Sweden)

Bogdan DINU

2014-04-01

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

Science.gov (United States)

2010-07-01

... 31 Money and Finance: Treasury 1 2010-07-01 2010-07-01 false Examples A Appendix A to Subpart C of... A to Subpart C of Part 29—Examples This appendix contains sample calculations of Federal Benefit Payments in a variety of situations. Optional Retirement Examples Example 1: No Unused Sick Leave A. In...
System analysis of shallow land burial. Volume 2: technical background. Technical report, 26 November 1979-23 January 1981

International Nuclear Information System (INIS)

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

1981-03-01

This is volume two of a three volume set detailing the activities and results of the System Analysis of Shallow Land Burial Project. Activities under four project tasks are described: Task 1 - Identify Potential Radionuclide Release Pathways, Task 2 - Systems Model for Shallow Land Burial of Low-Level Waste, Task 3 - Sensitivity and Optimization Study and Task 4 - Reference Facility Dose Assessment
GREAT I Study of the Upper Mississippi River. Technical Appendixes. Volume 6. Recreation.

Science.gov (United States)

1980-09-01

Engineers, St. Paul District 1s. NUMBER OF PAGES * 1135 USPO & Custom House, St. Paul, MN 55101 , I4. MONITORING AGENCY NAME & ADDRESS(I different hrm ...the purpose of this proposal that the viewer would either be the highway traveler ( automobile ) or the river traveler (recreational craft). An attempt...P.S. - Parking spaces; automobile and boat trailer L.L. - Boat launching lanes B.A. - Beach area, acres * -163-- GREAT I Recreation Needs
Urban Data Book : Volume 2. Urban Data - Milwaukee-Washington, Notes and Technical Appendixes

Science.gov (United States)

1975-11-01

A quick reference compilation of certain population, socio-economic, employment, and modal split characteristics of the 35 largest Standard Metropolitan Statistical Areas (SMSA) in the United States is presented. The three basic groups of urban data ...
Standard Technical Specifications, Babcock and Wilcox Plants

International Nuclear Information System (INIS)

1992-09-01

This NUREG contains improved Standard Technical Specifications (STS) for Babcock and Wilcox (B ampersand W) plants and documents the positions of the Nuclear Regulatory Commission (NRC) based on the B ampersand W Owners Group's proposed STS. This document is the result of extensive technical meetings and discussions among the NRC staff, the Nuclear Steam Supply System (NSSS) Owners Groups, the NSSS vendors, and the Nuclear Management and Resources Council. The improved STS were developed based on the criteria in the interim Commission Policy Statement on Technical Specification Improvements for Nuclear Power Reactors, dated February 6, 1987. The improved STS will be used as the basis for developing improved plant-specific technical specifications by individual nuclear power plant licensees. This volume contains sections 3.4--3.9 which cover: Reactor coolant systems, emergency core cooling systems, containment systems, plant systems, electrical power systems, refueling operations
Savannah River Site Approved Site Treatment Plan, 2001 Annual Update (Volumes I and II)

Energy Technology Data Exchange (ETDEWEB)

Lawrence, B.

2001-04-30

The Compliance Plan Volume (Volume I) identifies project activity scheduled milestones for achieving compliance with Land Disposal Restrictions. Information regarding the technical evaluation of treatment options for SRS mixed wastes is contained in the Background Volume (Volume II) and is provided for information.
12 CFR Appendix A to Part 563e - Ratings

Science.gov (United States)

2010-01-01

... 12 Banks and Banking 5 2010-01-01 2010-01-01 false Ratings A Appendix A to Part 563e Banks and Banking OFFICE OF THRIFT SUPERVISION, DEPARTMENT OF THE TREASURY COMMUNITY REINVESTMENT Pt. 563e, App. A Appendix A to Part 563e—Ratings (a) Ratings in general. (1) In assigning a rating, the OTS evaluates a...
31 CFR Appendix A to Part 132 - Model Notice

Science.gov (United States)

2010-07-01

... 31 Money and Finance: Treasury 1 2010-07-01 2010-07-01 false Model Notice A Appendix A to Part 132 Money and Finance: Treasury Regulations Relating to Money and Finance PROHIBITION ON FUNDING OF UNLAWFUL INTERNET GAMBLING Pt. 132, App. A Appendix A to Part 132—Model Notice [Date] [Name of foreign sender or...
12 CFR Appendix B to Part 345 - CRA Notice

Science.gov (United States)

2010-01-01

... 12 Banks and Banking 4 2010-01-01 2010-01-01 false CRA Notice B Appendix B to Part 345 Banks and... REINVESTMENT Pt. 345, App. B Appendix B to Part 345—CRA Notice (a) Notice for main offices and, if an... Community Reinvestment Act (CRA), the Federal Deposit Insurance Corporation (FDIC) evaluates our record of...
12 CFR Appendix B to Part 228 - CRA Notice

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2010-01-01

... 12 Banks and Banking 3 2010-01-01 2010-01-01 false CRA Notice B Appendix B to Part 228 Banks and... REINVESTMENT (REGULATION BB) Pt. 228, App. B Appendix B to Part 228—CRA Notice (a) Notice for main offices and... Federal Community Reinvestment Act (CRA), the Federal Reserve Board (Board) evaluates our record of...
12 CFR Appendix B to Part 25 - CRA Notice

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2010-01-01

... 12 Banks and Banking 1 2010-01-01 2010-01-01 false CRA Notice B Appendix B to Part 25 Banks and... DEPOSIT PRODUCTION REGULATIONS Pt. 25, App. B Appendix B to Part 25—CRA Notice (a) Notice for main offices... the Federal Community Reinvestment Act (CRA), the Comptroller of the Currency evaluates our record of...
43 CFR Appendix A to Part 10 - Sample Summary

Science.gov (United States)

2010-10-01

... 43 Public Lands: Interior 1 2010-10-01 2010-10-01 false Sample Summary A Appendix A to Part 10... REPATRIATION REGULATIONS Pt. 10, App. A Appendix A to Part 10—Sample Summary The following is a generic sample and should be used as a guideline for preparation of summaries tailoring the information to the...
41 CFR Appendix A to Subpart B of... - 3-Key Points and Principles

Science.gov (United States)

2010-07-01

... Principles A Appendix A to Subpart B of Part 102 Public Contracts and Property Management Federal Property.... B, App. A Appendix A to Subpart B of Part 102-3—Key Points and Principles This appendix provides... principles that may be applied to situations not covered elsewhere in this subpart. The guidance follows: Key...
41 CFR Appendix A to Subpart A of... - 3-Key Points and Principles

Science.gov (United States)

2010-07-01

... Principles A Appendix A to Subpart A of Part 102 Public Contracts and Property Management Federal Property..., Subpt. A, App. A Appendix A to Subpart A of Part 102-3—Key Points and Principles This appendix provides... principles that may be applied to situations not covered elsewhere in this subpart. The guidance follows: Key...

Technical innovation and industrial change

Energy Technology Data Exchange (ETDEWEB)

Krupp, H

1982-10-01

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

International Nuclear Information System (INIS)

1980-04-01

A review is made of the state of the art of volume reduction techniques for low level liquid and solid radioactive wastes produced as a result of: (1) operation of commercial nuclear power plants, (2) storage of spent fuel in away-from-reactor facilities, and (3) decontamination/decommissioning of commercial nuclear power plants. The types of wastes and their chemical, physical, and radiological characteristics are identified. Methods used by industry for processing radioactive wastes are reviewed and compared to the new techniques for processing and reducing the volume of radioactive wastes. A detailed system description and report on operating experiences follow for each of the new volume reduction techniques. In addition, descriptions of volume reduction methods presently under development are provided. The Appendix records data collected during site surveys of vendor facilities and operating power plants. A Bibliography is provided for each of the various volume reduction techniques discussed in the report
Final report from VFL technologies for the pilot-scale thermal treatment of Lower East Fork Poplar Creek floodplain soils: LEFPC appendices, volume 1, appendix I-IV

International Nuclear Information System (INIS)

1994-09-01

This document contains Appendix I-IV for the pilot-scale thermal treatment of lower East Fork Poplar Creek floodplain soils. Included are calibration records; quality assurance; soils characterization; pilot scale trial runs
Optimizing US examination to detect the normal and abnormal appendix in children

International Nuclear Information System (INIS)

Peletti, Adriana B.; Baldisserotto, Matteo

2006-01-01

US detection of a normal appendix can safely rule out appendicitis. However, there is a wide range of accuracy in detection of a normal appendix. To optimize US examination to detect the normal and the abnormal appendix according to the potential positions of the appendix. This prospective study included 107 children who underwent gray-scale US scanning. Noncompressive and compressive graded sonography was performed to detect normal and abnormal appendices according to their potential positions. The maximum transverse diameter of the appendices was measured. Of the 107 children examined, 56 had a histologic diagnosis of acute appendicitis. Sonography had a sensitivity of 100% and specificity of 98% for the diagnosis of appendicitis. A normal appendix was visualized in 44 (86.2%) of the 51 patients without acute appendicitis, and of these 44, 43 were true-negative and 1 was false-positive. Normal and abnormal appendices, respectively, were positioned as follows: 54.4% and 39.3% were mid-pelvic; 27.2% and 28.6% were retrocecal; 11.4% and 17.8% were deep pelvic; and 6.8% and 14.3% were abdominal. US scanning according to the potential positions of the appendix was useful in the detection of normal appendices in children suspected of having appendicitis. (orig.)
49 CFR Appendix B to Part 222 - Alternative Safety Measures

Science.gov (United States)

2010-10-01

.... 222, App. B Appendix B to Part 222—Alternative Safety Measures Introduction A public authority seeking... requirements associated with an SSM as listed in appendix A is revised or deleted, data or analysis supporting...); d. Photographic or video equipment deployed to capture images sufficient to document the violation...
16 CFR Appendix E to Part 305 - Room Air Conditioners

Science.gov (United States)

2010-01-01

... 16 Commercial Practices 1 2010-01-01 2010-01-01 false Room Air Conditioners E Appendix E to Part 305 Commercial Practices FEDERAL TRADE COMMISSION REGULATIONS UNDER SPECIFIC ACTS OF CONGRESS RULE... Appendix E to Part 305—Room Air Conditioners Range Information Manufacturer's rated cooling capacity in Btu...
19 CFR Appendix A to Part 210 - Adjudication and Enforcement

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2010-04-01

... 19 Customs Duties 3 2010-04-01 2010-04-01 false Adjudication and Enforcement A Appendix A to Part 210 Customs Duties UNITED STATES INTERNATIONAL TRADE COMMISSION INVESTIGATIONS OF UNFAIR PRACTICES IN IMPORT TRADE ADJUDICATION AND ENFORCEMENT Pt. 210, App. A Appendix A to Part 210—Adjudication and...
Torsion of the vermiform appendix: A case report | Wani | Internet ...

African Journals Online (AJOL)

Torsion of the vermiform appendix is a rare condition with few cases reported in the literature. Various factors predispose to torsion. Various factors predispose to torsion. We report a case of primary torsion of the vermiform appendix. The clinical presentation was indistinguishable from acute appendicitis and the diagnosis ...
10 CFR Appendix B to Part 600 - Audit Report Distributees

Science.gov (United States)

2010-01-01

... 10 Energy 4 2010-01-01 2010-01-01 false Audit Report Distributees B Appendix B to Part 600 Energy DEPARTMENT OF ENERGY (CONTINUED) ASSISTANCE REGULATIONS FINANCIAL ASSISTANCE RULES Pt. 600, App. B Appendix B to Part 600—Audit Report Distributees Distributee: Manager, Eastern Region, Office of Inspector...
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.
Primary Adenocarcinoma of the Vermiform Appendix. A Case Report

Directory of Open Access Journals (Sweden)

Luis Antonio Revuelta Pérez

2014-11-01

Full Text Available Primary adenocarcinoma of the vermiform appendix is the least common carcinoma of this organ; its exact frequency is unknown. Primary malignant tumors of the appendix are rare; they are generally found in 1 to 2% of all appendices examined. Most appendiceal malignancies arise from a primary tumor in the adjacent organs, and in some cases, may be metastases from distant tumors. The case of a 43-year-old patient with a history of emergency surgery who was presumptively diagnosed with acute appendicitis is presented. The presence of an adenocarcinoma at the base of the appendix was reported by the pathology department. Because of the rarity of the condition, the publication of this case is considered scientifically important.
Fusion Engineering Device. Volume 1. Mission and program summary

International Nuclear Information System (INIS)

1981-10-01

This volume presents, in summary form, a recommended approach to implementing the Magnetic Fusion Energy Engineering Act of 1980. These recommendations constitute the findings of the FED Technical Management Board (TMB). The TMB and the affiliated technical managers gave particular scrutiny to elucidating the role of FED in fusion development and to defining the device mission
Standard technical specifications, Westinghouse Plants: Bases (Sections 3.4--3.9). Volume 3, Revision 1

International Nuclear Information System (INIS)

1995-04-01

This NUREG contains the improved Standard Technical Specifications (STS) for Westinghouse plants. Revision 1 incorporates the cumulative changes to Revision 0, which was published in September 1992. The changes reflected in Revision 1 resulted from the experience gained from license amendment applications to convert to these improved STS or to adopt partial improvements to existing technical specifications. This NUREG is the result of extensive public technical meetings and discussions between the Nuclear Regulatory Commission (NRC) staff and various nuclear power plant licensees, Nuclear Steam Supply System (NSSS) Owners Groups, specifically the Westinghouse Owners Group (WOG), NSSS vendors, and the Nuclear Energy Institute (NEI). The improved STS were developed based on the criteria in the Final Commission Policy Statement on Technical Specifications Improvements for Nuclear Power Reactors, dated July 22, 1993 (58 FR 39132). Licensees are encouraged to upgrade their technical specifications consistent with those criteria and conforming, to the extent practical and consistent with the licensing basis for the facility, to Revision 1 to the improved STS. The Commission continues to place the highest priority on requests for complete conversions to the improved STS. Licensees adopting portions of the improved STS to existing technical specifications should adopt all related requirements, as applicable, to achieve a high degree of standardization and consistency
Standard technical specifications, Westinghouse Plants: Bases (Sections 2.0--3.3). Volume 2, Revision 1

International Nuclear Information System (INIS)

1995-04-01

This NUREG contains the improved Standard Technical Specifications (STS) for Westinghouse plants. Revision 1 incorporates the cumulative changes to Revision 0, which was published in September 1992. The changes reflected in Revision 1 resulted from the experience gained from license amendment applications to convert to these improved STS or to adopt partial improvements to existing technical specifications. This NUREG is the result of extensive public technical meetings and discussions between the Nuclear Regulatory Commission (NRC) staff and various nuclear power plant licensees, Nuclear Steam Supply System (NSSS) Owners Groups, specifically the Westinghouse Owners Group (WOG), NSSS vendors, and the Nuclear Energy Institute (NEI). The improved STS were developed based on the criteria in the Final Commission Policy Statement on Technical Specifications Improvements for Nuclear Power Reactors, dated July 22, 1993 (58 FR 39132). Licensees are encouraged to upgrade their technical specifications consistent with those criteria and conforming, to the extent practical and consistent with the licensing basis for the facility, to Revision 1 to the improved STS. The Commission continues to place the highest priority on requests for complete conversions to the improved STS. Licensees adopting portions of the improved STS to existing technical specifications should adopt all related requirements, as applicable, to achieve a high degree of standardization and consistency
Productivity and technical efficiency of suckler beef production systems: trends for the period 1990 to 2012.

Science.gov (United States)

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

2015-12-01

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

Energy Technology Data Exchange (ETDEWEB)

Grayson Heffner, Charles Goldman, Kintner-Meyer, M; Kirby, Brendan

2007-05-01

In this study, we examine the arrangements for andexperiences of end-use loads providing ancillary services (AS) in fiveelectricity markets: Australia, the United Kingdom (UK), the Nordicmarket, and the ERCOT and PJM markets in the United States. Our objectivein undertaking this review of international experience was to identifyspecific approaches or market designs that have enabled customer loads toeffectively deliver various ancillary services (AS) products. We hopethat this report will contribute to the ongoing discussion in the U.S.and elsewhere regarding what institutional and technical developments areneeded to ensure that customer loads can meaningfully participate in allwholesale electricity markets.
Comments on H- volume production in Cs-seeded ion sources. Appendix I

International Nuclear Information System (INIS)

Peterson, J.R.

1986-01-01

Considerable interest was generated at the IAEA Negative Ion Beam Workshop in Grenoble, France, in March, 1985, by a report from the Kurchatov Institute on the development of a 2-ampere steady-state H - ion source, in which the ions were volume-produced in a discharge in H 2 , seeded with Cs vapor. The mechanism primarily responsible for this remarkably high current from a volume production source was not yet understood, but it was tentatively presumed to involve the collisional energy transfer from electronically excited Cs 6p atoms into H 2 vibrations. In any case, it was apparently different from the surface-plasma interactions that have been assumed to control the H - production in the Dudnikov-Dimov type sources
Technical issues associated with in situ vitrification of the INEL Subsurface Disposal Area

International Nuclear Information System (INIS)

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

1991-12-01

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

International Nuclear Information System (INIS)

Ashby, J.P.; Rawlings, G.E.; Soto, C.A.; Wood, D.F.; Chorley, D.W.

1979-12-01

The method of selection of parameters to be considered in the selection of a site for underground disposal of radioactive wastes is reported in volume 1. This volume contains the appendix to that report. The topics include: specific rock mechanics tests; drilling investigation techniques and equipment; geophysical surveying; theoretical study of a well text in a nonhomogeneous aquifer; and basic statistical and probability theory that may be used in the derivation of input parameters
12 CFR Appendix A to Part 411 - Certification Regarding Lobbying

Science.gov (United States)

2010-01-01

... 12 Banks and Banking 4 2010-01-01 2010-01-01 false Certification Regarding Lobbying A Appendix A to Part 411 Banks and Banking EXPORT-IMPORT BANK OF THE UNITED STATES NEW RESTRICTIONS ON LOBBYING Pt. 411, App. A Appendix A to Part 411—Certification Regarding Lobbying Certification for Contracts...

49 CFR Appendix B to Part 37 - FTA Regional Offices

Science.gov (United States)

2010-10-01

... 49 Transportation 1 2010-10-01 2010-10-01 false FTA Regional Offices B Appendix B to Part 37 Transportation Office of the Secretary of Transportation TRANSPORTATION SERVICES FOR INDIVIDUALS WITH DISABILITIES (ADA) Pt. 37, App. B Appendix B to Part 37—FTA Regional Offices Region I, Federal Transit...
25 CFR Appendix B to Part 276 - Financial Reporting Requirements

Science.gov (United States)

2010-04-01

... 25 Indians 1 2010-04-01 2010-04-01 false Financial Reporting Requirements B Appendix B to Part 276...—Financial Reporting Requirements A. Purpose and scope. This appendix prescribes requirements for grantee to report financial information to the Bureau and to request advances and reimbursement when a letter-of...
A comprehensive inventory of radiological and nonradiological contaminants in waste buried or projected to be buried in the subsurface disposal area of the INEL RWMC during the years 1984-2003, Volume 2

International Nuclear Information System (INIS)

1995-05-01

This is the second volume of this comprehensive report of the inventory of radiological and nonradiological contaminants in waste buried or projected to be buried in the subsurface disposal area of the Idaho National Engineering Laboratory. Appendix B contains a complete printout of contaminant inventory and other information from the CIDRA Database and is presented in volumes 2 and 3 of the report
Endolymphatic Thoracic Duct Stent-Graft Reconstruction for Chylothorax: Approach, Technical Success, Safety, and Short-term Outcomes.

Science.gov (United States)

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

2018-04-01

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

International Nuclear Information System (INIS)

Krupp, H.

1982-01-01

Technical development is leading by rationalization at economical stagnation to a decrease in the working volume. The economical difficulties are based on the discrepancy between the offer of goods and services as well as the actual demand. The demand of common goods is growing compared to the consumption goods, which will decrease. The therefore necessary structure change requires a high standard of governmental efforts and social consensus. (orig.) [de
14 CFR Appendix J to Part 23 - HIRF Environments and Equipment HIRF Test Levels

Science.gov (United States)

2010-01-01

... 14 Aeronautics and Space 1 2010-01-01 2010-01-01 false HIRF Environments and Equipment HIRF Test Levels J Appendix J to Part 23 Aeronautics and Space FEDERAL AVIATION ADMINISTRATION, DEPARTMENT OF.... 23, App. J Appendix J to Part 23—HIRF Environments and Equipment HIRF Test Levels This appendix...
Computed tomography of the normal appendix and acute appendicitis

International Nuclear Information System (INIS)

Ghiatas, A.A.; Chopra, S.; Chintapalli, K.N.; Esola, C.C.; Daskalogiannaki, M.; Dodd, G.D. III; Gourtsoyiannis, N.

1997-01-01

The aim of this article is to present pictorially the spectrum of appearances of the appendix and appendicitis on CT. The images presented were selected from the database of our hospitals. The various appearances of the normal appendix on CT are shown. Appendicitis can be divided into four categories on the basis of CT findings. Examples of each category are shown. (orig.). With 14 figs
31 CFR Appendix to Part 341 - Tables of Redemption Values

Science.gov (United States)

2010-07-01

... 31 Money and Finance: Treasury 2 2010-07-01 2010-07-01 false Tables of Redemption Values Appendix... RETIREMENT PLAN BONDS Pt. 341, App. Appendix to Part 341—Tables of Redemption Values Table of Redemption Values Providing an Investment Yield of 33/4 Percent per Annum for Bonds Bearing Issue Dates Beginning...
22 CFR Appendix A to Part 311 - Certification Regarding Lobbying

Science.gov (United States)

2010-04-01

... 22 Foreign Relations 2 2010-04-01 2010-04-01 true Certification Regarding Lobbying A Appendix A to Part 311 Foreign Relations PEACE CORPS NEW RESTRICTIONS ON LOBBYING Pt. 311, App. A Appendix A to Part...,” in accordance with its instructions. (3) The undersigned shall require that the language of this...
32 CFR Appendix C to Part 45 - DD Form 215

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2010-07-01

... 32 National Defense 1 2010-07-01 2010-07-01 false DD Form 215 C Appendix C to Part 45 National... CERTIFICATE OF RELEASE OR DISCHARGE FROM ACTIVE DUTY (DD FORM 214/5 SERIES) Pt. 45, App. C Appendix C to Part 45—DD Form 215 EC21OC91.050 ...
12 CFR Appendix A to Part 343 - Consumer Grievance Process

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2010-01-01

... POLICY CONSUMER PROTECTION IN SALES OF INSURANCE Pt. 343, App. A Appendix A to Part 343—Consumer... Consumer Protection (DSC), Federal Deposit Insurance Corporation, at the following address: 550 17th Street... 12 Banks and Banking 4 2010-01-01 2010-01-01 false Consumer Grievance Process A Appendix A to Part...
49 CFR Appendix D to Part 599 - CARS Purchaser Survey

Science.gov (United States)

2010-10-01

... 49 Transportation 7 2010-10-01 2010-10-01 false CARS Purchaser Survey D Appendix D to Part 599 Transportation Other Regulations Relating to Transportation (Continued) NATIONAL HIGHWAY TRAFFIC SAFETY... RECYCLE AND SAVE ACT PROGRAM Pt. 599, App. D Appendix D to Part 599—CARS Purchaser Survey ER29JY09.008 ...
Decommissioning of eight surplus production reactors at the Hanford Site, Richland, Washington. Addendum (Final Environmental Impact Statement)

Energy Technology Data Exchange (ETDEWEB)

1992-12-01

The first section of this volume summarizes the content of the draft environmental impact statement (DEIS) and this Addendum, which together constitute the final environmental impact statement (FEIS) prepared on the decommissioning of eight surplus plutonium production reactors at Hanford. The FEIS consists of two volumes. The first volume is the DEIS as written. The second volume (this Addendum) consists of a summary; Chapter 9, which contains comments on the DEIS and provides DOE`s responses to the comments; Appendix F, which provides additional health effects information; Appendix K, which contains costs of decommissioning in 1990 dollars; Appendix L, which contains additional graphite leaching data; Appendix M, which contains a discussion of accident scenarios; Appendix N, which contains errata; and Appendix 0, which contains reproductions of the letters, transcripts, and exhibits that constitute the record for the public comment period.
Decommissioning of eight surplus production reactors at the Hanford Site, Richland, Washington

International Nuclear Information System (INIS)

1992-12-01

The first section of this volume summarizes the content of the draft environmental impact statement (DEIS) and this Addendum, which together constitute the final environmental impact statement (FEIS) prepared on the decommissioning of eight surplus plutonium production reactors at Hanford. The FEIS consists of two volumes. The first volume is the DEIS as written. The second volume (this Addendum) consists of a summary; Chapter 9, which contains comments on the DEIS and provides DOE's responses to the comments; Appendix F, which provides additional health effects information; Appendix K, which contains costs of decommissioning in 1990 dollars; Appendix L, which contains additional graphite leaching data; Appendix M, which contains a discussion of accident scenarios; Appendix N, which contains errata; and Appendix 0, which contains reproductions of the letters, transcripts, and exhibits that constitute the record for the public comment period
Appendix F - Sample Contingency Plan

Science.gov (United States)

This sample Contingency Plan in Appendix F is intended to provide examples of contingency planning as a reference when a facility determines that the required secondary containment is impracticable, pursuant to 40 CFR §112.7(d).
ASEAN--USAID Buildings Energy Conservation Project final report. Volume 2, Technology

Energy Technology Data Exchange (ETDEWEB)

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

1992-06-01

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

Science.gov (United States)

Cherepanov, Anatoly P.; Lyapustin, Pavel K.

2017-10-01

The article shows a method of increasing the safe operation of technical devices at various stages of the life cycle according to the proposed classification parameters of the resource by applying the model of resource prediction. The model takes into account the presence of defects, the rate of corrosion and corrosion resistance of the material, the volume of technical diagnosis, the degree of risk in case of failure or damage of technical devices. The article shows the application of the model resource of the technical device from the manufacture to the end of its service life.
12 CFR Appendix A to Part 536 - Consumer Grievance Process

Science.gov (United States)

2010-01-01

... 12 Banks and Banking 5 2010-01-01 2010-01-01 false Consumer Grievance Process A Appendix A to Part 536 Banks and Banking OFFICE OF THRIFT SUPERVISION, DEPARTMENT OF THE TREASURY CONSUMER PROTECTION IN SALES OF INSURANCE Pt. 536, App. A Appendix A to Part 536—Consumer Grievance Process Any consumer who...
12 CFR Appendix A to Part 14 - Consumer Grievance Process

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2010-01-01

... 12 Banks and Banking 1 2010-01-01 2010-01-01 false Consumer Grievance Process A Appendix A to Part 14 Banks and Banking COMPTROLLER OF THE CURRENCY, DEPARTMENT OF THE TREASURY CONSUMER PROTECTION IN SALES OF INSURANCE Pt. 14, App. A Appendix A to Part 14—Consumer Grievance Process Any consumer who...
32 CFR Appendix B to Part 231 - In-Store Banking

Science.gov (United States)

2010-07-01

... 32 National Defense 2 2010-07-01 2010-07-01 false In-Store Banking B Appendix B to Part 231.... 231, App. B Appendix B to Part 231—In-Store Banking A. Selection Process. The purpose of this guidance... provide in-store banking services when such services are desired and approved by the installation...

Reducing surgery of volume for the pulmonary emphysema

International Nuclear Information System (INIS)

Ramirez, Juan Camilo

1997-01-01

The paper includes aspects as selection approaches, functional evaluation, imagenologic evaluation, cardiovascular evaluation, technical aspects and results among other topics related with the reducing surgery of volume of the pulmonary emphysema
Surrogate Plant Data Base : Volume 2. Appendix C : Facilities Planning Baseline Data

Science.gov (United States)

1983-05-01

This four volume report consists of a data base describing "surrogate" automobile and truck manufacturing plants developed as part of a methodology for evaluating capital investment requirements in new manufacturing facilities to build new fleets of ...
Evaluation of Upland Disposal of Oakland Harbor, California, Sediment. Volume 2: Inner and Outer Harbor Sediments

Science.gov (United States)

1993-08-01

the drop size and terminal velocities of natural rain- fall, factors which are critical in erosion and infiltration studies ( Westerdahl and Skogerboe... Westerdahl and Skogerboe 1982; Lee and Skogerboe 1984; Skogerboe et al. 1987). The WES Rainfall Simulator/ Lysimeter System proved to be an effective...Waters (Phase IIIA of -42-Foot Project); Volume 2: Appendixes," iNL-83-2, Vol 2, Battelle/Marine Science Laboratory, Sequim, WA. Westerdahl , H. E., and
Measurement exercise at the Fort de Vaujours on 25 February 2014. Reading of measurements performed by the ACRO according to the requirements of the IRSN PRP-CRI/SIAR 14-00093 technical protocol

International Nuclear Information System (INIS)

Pigree, G.; Josset, M.; Barbey, P.

2014-01-01

This document reports radiological measurements performed on the request of the ASN Paris department on some singular points and according to a specific technical protocol elaborated by the IRSN. After a discussion of results, the report presents instruments used for radiological measurements, reference values issued from other sites, reference values at a point of entrance of the site and at the vicinity of singular points, and then measurements on singular points. Additional measurements have been performed on a radioactive fragment at the origin of some offsets. The text of the IRSN technical protocol for this specific study (scope, areas to be controlled, expected radioactive elements, technical protocol, result presentation) is provided in appendix
40 CFR Appendix F to Part 75 - Conversion Procedures

Science.gov (United States)

2010-07-01

... procedures of section 5.5.3 of this appendix shall not be used to determine heat input from a coal unit that... 5.5.3.1-5.5.3.3 of this appendix to determine the heat input from coal for each 24-hour period. (All... equivalent to the applicable ASTM methods under §§ 75.23 and 75.66. 5.5.3.3Calculate the heat input from coal...
12 CFR Appendix C to Part 360 - Deposit File Structure

Science.gov (United States)

2010-01-01

.... • STATE = State government. • COMM = Commercial. • CORP = Corporate. • BANK = Bank Owned. • DUE TO = Other... 12 Banks and Banking 4 2010-01-01 2010-01-01 false Deposit File Structure C Appendix C to Part 360... RESOLUTION AND RECEIVERSHIP RULES Pt. 360, App. C Appendix C to Part 360—Deposit File Structure This is the...
12 CFR Appendix F to Part 360 - Customer File Structure

Science.gov (United States)

2010-01-01

... 12 Banks and Banking 4 2010-01-01 2010-01-01 false Customer File Structure F Appendix F to Part... POLICY RESOLUTION AND RECEIVERSHIP RULES Pt. 360, App. F Appendix F to Part 360—Customer File Structure This is the structure of the data file to provide to the FDIC information related to each customer who...
Reduced waste generation technical work plan

International Nuclear Information System (INIS)

1987-05-01

The United States Department of Energy has established policies for avoiding plutonium losses to the waste streams and minimizing the generation of wastes produced at its nuclear facilities. This policy is evidenced in DOE Order 5820.2, which states ''Technical and administrative controls shall be directed towards reducing the gross volume of TRU waste generated and the amount of radioactivity in such waste.'' To comply with the DOE directive, the Defense Transuranic Waste Program (DTWP) supports and provides funding for specific research and development tasks at the various DOE sites to reduce the generation of waste. This document has been prepared to give an overview of current and past Reduced Waste Generation task activities which are to be based on technical and cost/benefit factors. The document is updated annually, or as needed, to reflect the status of program direction. Reduced Waste Generation (RWG) tasks encompass a wide range of goals which are basically oriented toward (1) avoiding the generation of waste, (2) changing processes or operations to reduce waste, (3) converting TRU waste into LLW by sorting or decontamination, and (4) reducing volumes through operations such as incineration or compaction
Spent nuclear fuel technical baseline description, Fiscal Year 1996: Volume II, supporting data

International Nuclear Information System (INIS)

Womack, J.C.

1995-11-01

The Technical Baseline Description documents the Project-Level functions and requirements, along with associated enabling assumptions, issues, trade studies, interfaces, and products. It is a snapshot in time of the baseline at the beginning of September 1995. It supports the individual subprojects in the development of lower-tier functions, requirements, and specifications in FY 1996. It also supports the need for Hanford site planning to be based on an integrated Hanford site systems engineering technical baseline; and is traceable to that baseline. This document replaces and supercedes WHC-SD-SNF-SD-003
41 CFR Appendix A to Part 102 - 37-Miscellaneous Donation Statutes

Science.gov (United States)

2010-07-01

... Donation Statutes A Appendix A to Part 102 Public Contracts and Property Management Federal Property Management Regulations System (Continued) FEDERAL MANAGEMENT REGULATION PERSONAL PROPERTY 37-DONATION OF SURPLUS PERSONAL PROPERTY Pt. 102-37, App. A Appendix A to Part 102-37—Miscellaneous Donation Statutes The...
40 CFR Appendix B to Part 425 - Modified Monier-Williams Method

Science.gov (United States)

2010-07-01

... 40 Protection of Environment 29 2010-07-01 2010-07-01 false Modified Monier-Williams Method B Appendix B to Part 425 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) EFFLUENT GUIDELINES AND STANDARDS LEATHER TANNING AND FINISHING POINT SOURCE CATEGORY Pt. 425, App. B Appendix B to...
14 CFR Appendix E to Part 91 - Airplane Flight Recorder Specifications

Science.gov (United States)

2010-01-01

... 14 Aeronautics and Space 2 2010-01-01 2010-01-01 false Airplane Flight Recorder Specifications E Appendix E to Part 91 Aeronautics and Space FEDERAL AVIATION ADMINISTRATION, DEPARTMENT OF TRANSPORTATION... Appendix E to Part 91—Airplane Flight Recorder Specifications Parameters Range Installed system 1 minimum...
14 CFR Appendix B to Part 135 - Airplane Flight Recorder Specifications

Science.gov (United States)

2010-01-01

... 14 Aeronautics and Space 3 2010-01-01 2010-01-01 false Airplane Flight Recorder Specifications B Appendix B to Part 135 Aeronautics and Space FEDERAL AVIATION ADMINISTRATION, DEPARTMENT OF TRANSPORTATION.... B Appendix B to Part 135—Airplane Flight Recorder Specifications Parameters Range Installed system 1...
The System 80+ Standard Plant design control document. Volume 19

International Nuclear Information System (INIS)

1997-01-01

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

Directory of Open Access Journals (Sweden)

Jason Cui

Full Text Available Introduction: Foreign body ingestion is a common clinical presentation with less than 1% of the cases requiring surgical intervention. In this report, we present a rare case of razor blades lodged in the appendix as a result of intentional ingestion. Presentation of case: A 25 year old male prisoner presented to our hospital with persistent right iliac fossa pain after razor blade ingestion. After 5 days of conservative management, there was no sign of transition on serial X-Rays. Laparoscopy with intraoperative image intensification confirmed the presence of the razor blades in the appendix and appendicectomy was subsequently performed without complications. Discussion: Most ingested objected with diameter less than 2.5 cm and length less than 6 cm can pass through the gastrointestinal tract spontaneously in less than one week. The entry of foreign objects into the appendix is thought to be due to relative low motility of the caecum, the dependent position of the appendix and the size of the appendiceal orifice. Radiographic localisation to the appendiceal lumen was complicated by metallic artefact, but was consistent with failure to transit. Appendicectomy was felt to be the safest mode of retrieval. Conclusion: Ingested foreign body lodged in the appendix is a rare event. Once the exact location is confirmed, a simple laparoscopic appendicectomy can be performed to facilitate the removal. Keywords: Appendicitis, Laparoscopy, Appendicectomy, Foreign body ingestion, Razor blades, Case report
Secondary Torsion of Vermiform Appendix with Mucinous Cystadenoma

Directory of Open Access Journals (Sweden)

Maki Kitagawa

2007-06-01

Full Text Available Torsion of the vermiform appendix is a rare disorder, which causes abdominal symptoms indistinguishable from acute appendicitis. We report a case (a 34-year-old male of secondary torsion of the vermiform appendix with mucinous cystadenoma. This case was characterized by mild inflammatory responses, pentazocine-resistant abdominal pain, and appendiceal tumor, which was not enhanced by the contrast medium on computed tomography presumably because of reduced blood flow by the torsion. These findings may be helpful for the preoperative diagnosis of secondary appendiceal torsion.
Characteristic sonographic appearance of normal appendix in children: inner hypoechoic band without folding

International Nuclear Information System (INIS)

Park, Noh Hyuck; Song, Soon Young; Lee, En Ja; Kim, Mi Sung; Park, Chan Sup; Oh, Hwa En; Yang, Geun Seok

2004-01-01

To identify the characteristic ultrasonographic findings of the normal appendix in children in order to detect it more easily and so to exclude acute appendicitis from a diagnosis with more confidence. Among 64 patients presenting with right lower quadrant pain, 44 patients, excluding 15 patients diagnosed as acute appendicitis and 5 patients with non-visualization of the appendix due to severe ileus and obesity, were evaluated for the point of incidence, the thickness and the presence of folding of the inner hypoechoic band of the normal appendix. The age of the patients ranged from 3 to 15 years with a mean age of 6.5 years. Two patients were operated on and we correlated the preoperative ultrasonographic findings with the histologic findings. In all the cases of the 44 patients with normal appendix, the inner hypoechoic band was discovered, which was seen as a linear structure without folding along the whole length of appendix. This measured as 0.75 mm (0.3-1.5 mm) for the mean thickness. The inner hypoechoic band corresponded to the mucosal layer that had abundant lymphoid tissue on the histologic examination. For the pediatric normal appendix, the inner hypoechoic band without folding is present, and this corresponds to the mucosal layer with abundant lymphoid tissue
Characteristic sonographic appearance of normal appendix in children: inner hypoechoic band without folding

Energy Technology Data Exchange (ETDEWEB)

Park, Noh Hyuck; Song, Soon Young; Lee, En Ja; Kim, Mi Sung; Park, Chan Sup; Oh, Hwa En [College of Medicine, Kwandong Univ., Koyang (Korea, Republic of); Yang, Geun Seok [College of Medicine, Dongkook Univ., Gyeongju (Korea, Republic of)

2004-12-01

To identify the characteristic ultrasonographic findings of the normal appendix in children in order to detect it more easily and so to exclude acute appendicitis from a diagnosis with more confidence. Among 64 patients presenting with right lower quadrant pain, 44 patients, excluding 15 patients diagnosed as acute appendicitis and 5 patients with non-visualization of the appendix due to severe ileus and obesity, were evaluated for the point of incidence, the thickness and the presence of folding of the inner hypoechoic band of the normal appendix. The age of the patients ranged from 3 to 15 years with a mean age of 6.5 years. Two patients were operated on and we correlated the preoperative ultrasonographic findings with the histologic findings. In all the cases of the 44 patients with normal appendix, the inner hypoechoic band was discovered, which was seen as a linear structure without folding along the whole length of appendix. This measured as 0.75 mm (0.3-1.5 mm) for the mean thickness. The inner hypoechoic band corresponded to the mucosal layer that had abundant lymphoid tissue on the histologic examination. For the pediatric normal appendix, the inner hypoechoic band without folding is present, and this corresponds to the mucosal layer with abundant lymphoid tissue.
Waste acceptance criteria study: Volume 2, Appendixes: Final report

International Nuclear Information System (INIS)

Johnson, E.R.; McLeod, N.B.; McBride, J.A.

1988-09-01

These appendices to the report on Waste Acceptance Criteria have been published as a separate volume for the convenience of the reader. They consist of the text of the 10CFR961 Contract for disposal of spent fuel, estimates of the cost (savings) to the DOE system of accepting different forms of spent fuel, estimates of costs of acceptance testing/inspection of spent fuel, illustrative specifications and procedures, and the resolution of comments received on a preliminary draft of the report. These estimates of costs contained herein preliminary and are intended only to demonstrate the trends in costs, the order of magnitude involved, and the methodology used to develop the costs. The illustrative specifications and procedures included herein have been developed for the purpose of providing a starting point for the development of a consensus on such matters between utilities and DOE
EUV mask defect inspection and defect review strategies for EUV pilot line and high volume manufacturing

Science.gov (United States)

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

2010-04-01

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

Acute torsion and ischemia of the appendix in a young child

Directory of Open Access Journals (Sweden)

Dhruvin H. Hirpara

2018-04-01

Full Text Available Torsion of the vermiform appendix is a rare diagnosis; its clinical and radiographic presentation can mimic that of acute appendicitis. We report the case of a two-year-old boy presenting with a one day history of lower abdominal pain and serial ultrasound examinations suspicious for atypical acute appendicitis. Operative findings revealed a necrotic and engorged appendix with a 720° clockwise torsion at its base. Final pathology was consistent with ischemic necrosis in the setting of lymphoid hyperplasia. A brief update on the current body of literature regarding pediatric torsion of the vermiform appendix is provided. Keywords: Appendicitis, Volvulus, Torsion
2 CFR Appendix B to Part 230 - Selected Items of Cost

Science.gov (United States)

2010-01-01

... PRINCIPLES FOR NON-PROFIT ORGANIZATIONS (OMB CIRCULAR A-122) Pt. 230, App. B Appendix B to Part 230—Selected... use of patents and copyrights 45. Selling and marketing 46. Specialized service facilities 47. Taxes... of this appendix provide principles to be applied in establishing the allowability of certain items...
30 CFR Appendix I to Subpart M of... - National Consensus Standards

Science.gov (United States)

2010-07-01

... 30 Mineral Resources 1 2010-07-01 2010-07-01 false National Consensus Standards I Appendix I to... Machinery and Equipment Pt. 56, Subpt. M, App. I Appendix I to Subpart M of Part 56—National Consensus... object protective structures (FOPS) may consult the following national consensus standards, as applicable...
29 CFR Appendix B to Subpart L of... - National Consensus Standards

Science.gov (United States)

2010-07-01

... 29 Labor 5 2010-07-01 2010-07-01 false National Consensus Standards B Appendix B to Subpart L of... Appendix B to Subpart L of Part 1910—National Consensus Standards The following table contains a cross-reference listing of those current national consensus standards which contains information and guidelines...
40 CFR Appendix E to Subpart A of... - Article 5 Parties

Science.gov (United States)

2010-07-01

... 40 Protection of Environment 17 2010-07-01 2010-07-01 false Article 5 Parties E Appendix E to Subpart A of Part 82 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) AIR PROGRAMS... Appendix E to Subpart A of Part 82—Article 5 Parties Afghanistan, Albania, Algeria, Angola, Antigua...
49 CFR Appendix B to Part 178 - Alternative Leakproofness Test Methods

Science.gov (United States)

2010-10-01

... 49 Transportation 2 2010-10-01 2010-10-01 false Alternative Leakproofness Test Methods B Appendix... FOR PACKAGINGS Pt. 178, App. B Appendix B to Part 178—Alternative Leakproofness Test Methods In addition to the method prescribed in § 178.604 of this subchapter, the following leakproofness test methods...
XML: Solution for the integration of nuclear power plant data and technical documents

International Nuclear Information System (INIS)

Gordillo, F.

2000-01-01

Assuring proper operation of the systems that make up a nuclear power plant requires handling a massive amount of technical documents. This technical documentation, consisting mainly of system descriptions, operating and maintenance procedures, safety procedures, etc, presents particular characteristics, mainly: Great volume of information. High contents in figures and graphics. High reliability required. Multiple cross-references among documents. (Author)
Technical realization of the VISA-2 Project, contract: 2.01/ I phase, Volume No. I

International Nuclear Information System (INIS)

1963-12-01

Cooperation between the Institutes in Vinca and Saclay has started by carrying out the task 'Technical realization of the VISA-2 project' which should enable: obtaining new experimental spaces in the RA reactor with high fast neutron flux for sample irradiation; obtaining experience in reactor continual operation for few months at nominal power of 6.5 MW and increase of RA reactor utilization; solving the problem of activated channels and samples transport, problems of working in hot cells; obtaining irradiated samples for examining radiation effects first in Saclay and later in Vinca. The project is divided in three phases. Phase one covers the reconstruction of the RA reactor fuel channels according to the VISA-2 project demands. The second phase includes the activities related to measuring devices for measuring the temperatures at the incoming and outgoing heavy water in 5 VISA-2 channels, as well as temperature of the samples (55 thermocouples) and testing the channels and capsules after their insertion in the reactor. The third phase includes activities are related to problems of transport of radioactive channels and VISA-2 capsules, problems of cutting as well as packing and transporting of irradiated samples from Vinca to Saclay. This volume includes all the relevant documents for completing the task including contracts, needed preliminary calculations as well as safety analysis [sr
Istra district heating system. General technical report. Appendix 1 to the master plan

Energy Technology Data Exchange (ETDEWEB)

NONE

2001-09-01

The objective of the master plan project is to improve the heat supply in Istra. The considerable system losses from the fuel supplied to the end-users are one issue for improvement. At the same time, the current system operation results in poor quality heat for the consumers. Due to the inflexibility of the system the dwellings/premises of the consumers are either overheated or insufficiently heated. The financial situation in Istra, the legal ownership of the district heating system and consumers' lacking ability to pay limit the possibilities for system improvements. The Master Plan and Feasibility Study evaluates four different development scenarios. Each of the scenarios is compared to the current situation in Istra, where nothing is done to change the system, but only to operate the present system in a sustainable way. The sustainable operation of the district heating system includes all necessary renovations and component replacements necessary. The project does not take into account the present financial situation in Istra, which has resulted in less maintenance than necessary. This situation is not a comparable parameter, as it is not sustainable and will lead to a breakdown of the heat supply within a short time horizon. The General Technical Report evaluates the technical situation and describes system improvements at a general level. The intention with this report is to provide important information useful to other district heating companies in Russia. (au)
Primary minute mucinous adenocarcinoma of vermiform appendix arising from appendiceal diverticulosis

Directory of Open Access Journals (Sweden)

Tadashi Terada, MD, PhD

2015-03-01

Full Text Available Primary mucinous adenocarcinoma (MA of vermiform appendix is extremely rare; only three cases have been reported in the English literature. A 77-year-old man presented with abdominal pain, and was diagnosed with acute appendicitis. Appendectomy was performed. The resected appendix showed submucosal swelling measuring 0.7×0.6×0.6 cm in the tip of appendix. The appendix showed inflammation and numerous diverticuloses. Microscopically, the submucosal swelling was a mucin lake in which adenocarcinoma cells were floating. The adenocarcinoma cells were MA in 80% and signet-ring cell carcinoma in 20%. The carcinoma cells were located in the submucosa, muscular layer and subserosa, sparing the mucosa. No apparent lymphovascular permeation was seen. The surgical margins were negative for tumor cells. The non-tumorous appendix shows numerous diverticulosis, diverticulitis, and appendicitis. Immunohistochemically, the tumor cells were positive for CK CAM5.2, CK AE1/3, CK8, CK18, CK19, CK20, EMA, CEA, CA19-9, MUC1, MUC2, MUC5AC, MUC6, NCAM, p53 and Ki-67 (labeling index = 23%. The tumor cells were negative for CK34BE12, CD5, CK6, CK7, NSE, chromogranin, synaptophysin, CA125, KIT, and PDGFRA. No metastasis has been seen 2.5 years after the operation.
Columbia River System Operation Review : Final Environmental Impact Statement, Appendix N: Wildlife.

Energy Technology Data Exchange (ETDEWEB)

Columbia River System Operation Review (U.S.)

1995-11-01

The Columbia River System is a vast and complex combination of Federal and non-Federal facilities used for many purposes including power production, irrigation, navigation, flood control, recreation, fish and wildlife habitat and municipal and industrial water supply. Each river use competes for the limited water resources in the Columbia River Basin. This technical appendix addresses only the effects of alternative system operating strategies for managing the Columbia River system. The environmental impact statement (EIS) itself and some of the other appendices present analyses of the alternative approaches to the other three decisions considered as part of the SOR. This document is the product of the Wildlife Work Group, focusing on wildlife impacts but not including fishes. Topics covered include the following: scope and process; existing and affected environment, including specific discussion of 18 projects in the Columbia river basin. Analysis, evaluation, and alternatives are presented for all projects. System wide impacts to wildlife are also included.
Columbia River system operation review: Final environmental impact statement. Appendix N, wildlife

International Nuclear Information System (INIS)

1995-11-01

The Columbia River System is a vast and complex combination of Federal and non-Federal facilities used for many purposes including power production, irrigation, navigation, flood control, recreation, fish and wildlife habitat and municipal and industrial water supply. Each river use competes for the limited water resources in the Columbia River Basin. This technical appendix addresses only the effects of alternative system operating strategies for managing the Columbia River system. The environmental impact statement (EIS) itself and some of the other appendices present analyses of the alternative approaches to the other three decisions considered as part of the SOR. This document is the product of the Wildlife Work Group, focusing on wildlife impacts but not including fishes. Topics covered include the following: scope and process; existing and affected environment, including specific discussion of 18 projects in the Columbia river basin. Analysis, evaluation, and alternatives are presented for all projects. System wide impacts to wildlife are also included
Study of the Utah uranium-milling industry. Volume I. A policy analysis

International Nuclear Information System (INIS)

Turley, R.E.

1980-05-01

This is the first volume of a two volume study of the Utah Uranium Milling Industry. The study was precipitated by a 1977 report issued by the Western Interstate Nuclear Board entitled Policy Recommendations on Financing Stabilization. Perpetual Surveillance and Maintenance of Uranium Mill Tailings. Volume I of this study is a policy analysis or technology assessment of the uranium milling industry in the state of Utah; specifically, the study addresses issues that deal with the perpetual surveillance, monitoring, and maintenance of uranium tailings piles at the end of uranium milling operations, i.e., following shutdown and decommissioning. Volume II of this report serves somewhat as an appendix. It represents a full description of the uranium industry in the state of Utah, including its history and statements regarding its future. The topics covered in volume I are as follows: today's uranium industry in Utah; management of the industry's characteristic nuclear radiation; uranium mill licensing and regulation; state licensing and regulation of uranium mills; forecast of future milling operations; policy needs relative to perpetual surveillance, monitoring, and maintenance of tailings; policy needs relative to perpetual oversight; economic aspects; state revenue from uranium; and summary with conclusions and recommendations. Appendices, figures and tables are also presented
Heliophysics 3 Volume Set

Science.gov (United States)

Schrijver, Carolus J.; Siscoe, George L.

2010-11-01

Volume 1: Preface; 1. Prologue Carolus J. Schrijver and George L. Siscoe; 2. Introduction to heliophysics Thomas J. Bogdan; 3. Creation and destruction of magnetic field Matthias Rempel; 4. Magnetic field topology Dana W. Longcope; 5. Magnetic reconnection Terry G. Forbes; 6. Structures of the magnetic field Mark B. Moldwin, George L. Siscoe and Carolus J. Schrijver; 7. Turbulence in space plasmas Charles W. Smith; 8. The solar atmosphere Viggo H. Hansteen; 9. Stellar winds and magnetic fields Viggo H. Hansteen; 10. Fundamentals of planetary magnetospheres Vytenis M. Vasyliūnas; 11. Solar-wind magnetosphere coupling: an MHD perspective Frank R. Toffoletto and George L. Siscoe; 12. On the ionosphere and chromosphere Tim Fuller-Rowell and Carolus J. Schrijver; 13. Comparative planetary environments Frances Bagenal; Bibliography; Index. Volume 2: Preface; 1. Perspective on heliophysics George L. Siscoe and Carolus J. Schrijver; 2. Introduction to space storms and radiation Sten Odenwald; 3. In-situ detection of energetic particles George Gloeckler; 4. Radiative signatures of energetic particles Tim Bastian; 5. Observations of solar and stellar eruptions, flares, and jets Hugh Hudson; 6. Models of coronal mass ejections and flares Terry Forbes; 7. Shocks in heliophysics Merav Opher; 8. Particle acceleration in shocks Dietmar Krauss-Varban; 9. Energetic particle transport Joe Giacalone; 10. Energy conversion in planetary magnetospheres Vytenis Vasyliūnas; 11. Energization of trapped particles Janet Green; 12. Flares, CMEs, and atmospheric responses Tim Fuller-Rowell and Stanley C. Solomon; 13. Energetic particles and manned spaceflight 358 Stephen Guetersloh and Neal Zapp; 14. Energetic particles and technology Alan Tribble; Appendix I. Authors and editors; List of illustrations; List of tables; Bibliography; Index. Volume 3: Preface; 1. Interconnectedness in heliophysics Carolus J. Schrijver and George L. Siscoe; 2. Long-term evolution of magnetic activity of Sun
Technical description - interim storage, encapsulation and disposal of spent nuclear fuel; Teknisk beskrivning - mellanlagring, inkapsling och slutfoervaring av anvaent kaernbraensle

Energy Technology Data Exchange (ETDEWEB)

2010-07-15

The purpose of the annex Technical description is, in accordance with Chapter 22 paragraph 1 Environmental Code to describe the candidate operations and facilities. In particular, things that are important for their environmental impact are described. SKB's goal of the appendix is to describe the facilities, activities, pollution sources, land usage and more during construction, operation and decommissioning, to the extent and on a level of detail, so that the Environment Court without requiring additions can prepare the matter for the government's admissibility test
32 CFR Appendix G to Part 623 - Continental US Army Boundaries

Science.gov (United States)

2010-07-01

... 32 National Defense 3 2010-07-01 2010-07-01 true Continental US Army Boundaries G Appendix G to Part 623 National Defense Department of Defense (Continued) DEPARTMENT OF THE ARMY SUPPLIES AND EQUIPMENT LOAN OF ARMY MATERIEL Pt. 623, App. G Appendix G to Part 623—Continental US Army Boundaries...
16 CFR Appendix G6 to Part 305 - Boilers-Gas (Steam)

Science.gov (United States)

2010-01-01

... 16 Commercial Practices 1 2010-01-01 2010-01-01 false Boilers-Gas (Steam) G6 Appendix G6 to Part 305 Commercial Practices FEDERAL TRADE COMMISSION REGULATIONS UNDER SPECIFIC ACTS OF CONGRESS RULE... Appendix G6 to Part 305—Boilers—Gas (Steam) Manufacturer's rated heating capacities (Btu's/hr.) Range of...
29 CFR Appendix A to Part 4022 - Lump Sum Mortality Rates

Science.gov (United States)

2010-07-01

... 29 Labor 9 2010-07-01 2010-07-01 false Lump Sum Mortality Rates A Appendix A to Part 4022 Labor Regulations Relating to Labor (Continued) PENSION BENEFIT GUARANTY CORPORATION COVERAGE AND BENEFITS BENEFITS PAYABLE IN TERMINATED SINGLE-EMPLOYER PLANS Pt. 4022, App. A Appendix A to Part 4022—Lump Sum Mortality...
Laboratory Evaluation of In Situ Chemical Oxidation for Groundwater Remediation, Test Area North, Operable Unit 1-07B, Idaho National Engineering and Environmental Laboratory, Volume Two, Appendices C, D, and E

Energy Technology Data Exchange (ETDEWEB)

Cline, S.R.; Denton, D.L.; Giaquinto, J.M.; McCracken, M.K.; Starr, R.C.

1999-04-01

These appendices support the results and discussion of the laboratory work performed to evaluate the feasibility of in situ chemical oxidation for Idaho National Environmental and Engineering Laboratory's (INEEL) Test Area North (TAN) which is contained in ORNL/TM-1371 l/Vol. This volume contains Appendices C-E. Appendix C is a compilation of all recorded data and mathematical calculations made to interpret the data. For the Task 3 and Task 4 work, the spreadsheet column definitions are included immediately before the actual spreadsheet pages and are listed as ''Sample Calculations/Column Definitions'' in the table of contents. Appendix D includes the chronological order in which the experiments were conducted and the final project costs through October 1998. Appendix E is a compilation of the monthly progress reports submitted to INEEL during the course of the project.
Ocean Thermal Energy Conservation (OTEC) power system development (PDS) II. Preliminary design report

Energy Technology Data Exchange (ETDEWEB)

1979-08-10

This report documents the results and conclusions of the PDS II, Phase I, preliminary design of a 10 MWe OTEC power system, using enhanced plate type heat exchangers, and of representative 0.2 MWe test articles. It further provides the documentation (specifications, drawings, trade studies, etc.) resulting from the design activities. The data and discussions of the technical concepts are organized to respond to the PDS II, Phase II proposal evaluation criteria. This volume, which specifically addresses the three evaluation categories (heat exchangers, rotating machinery, and power system configuration and performance) is an integral part of the Phase II plans (proposal) which describe the technical approach to delivering test articles to OTEC-1. In addition, there is a section which addresses power system cost and net energy analysis and another which discusses the results of stainless steel feasibility studies. Supporting documentation is contained in two appendix volumes.

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