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Sample records for technical appendix volume

  1. 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.

  2. 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).

  3. 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

  4. 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.

  5. 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

  6. 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...

  7. 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...

  8. 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…

  9. 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)

  10. 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

  11. 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.

  12. 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...

  13. 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...

  14. 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...

  15. 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...

  16. 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...

  17. 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...

  18. 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...

  19. 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...

  20. 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...

  1. 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...

  2. 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...

  3. 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...

  4. 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...

  5. 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...

  6. 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...

  7. 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...

  8. 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.

  9. 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. 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.

  11. 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.

  12. 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

  13. 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...

  14. 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

  15. 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).

  16. 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

  17. 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)

  18. 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.

  19. 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)

  20. 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.

  1. 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.

  2. 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

  3. 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.

  4. 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.

  5. 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.

  6. 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."

  7. 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

  8. 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)

  9. 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.

  10. 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.

  11. 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.

  12. 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

  13. 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

  14. 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.

  15. 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

  16. 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.

  17. 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...

  18. 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...

  19. 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.

  20. 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.

  1. 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…

  2. 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...

  3. 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.

  4. 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.

  5. 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

  6. 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

  7. 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

  8. 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…

  9. 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…

  10. 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

  11. 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)

  12. 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.

  13. 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.

  14. 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…

  15. 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

  16. 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.

  17. 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...

  18. 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

  19. 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

  20. 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

  1. 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

  2. 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

  3. 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.

  4. 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.

  5. 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.

  6. 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.

  7. 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

  8. 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

  9. 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.

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

    Science.gov (United States)

    1988-01-01

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

  11. 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

  12. 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

  13. 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

  14. Final Technical Report - Kotzebue Wind Power Project - Volume II

    Energy Technology Data Exchange (ETDEWEB)

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

    2007-10-31

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

  15. Subsurface contamination focus area technical requirements. Volume II

    International Nuclear Information System (INIS)

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

    1996-10-01

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

  16. Subsurface contamination focus area technical requirements. Volume II

    Energy Technology Data Exchange (ETDEWEB)

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

    1996-10-01

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

  17. 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

  18. Resource Conservation and Recovery Act: Part B Permit application. Volume 2, Chapter C, Appendix C1-Appendix C8

    International Nuclear Information System (INIS)

    1995-01-01

    Volume 2 contains appendices for the following: chemical compatibility analysis of waste forms and container materials; data accumulated from headspace-gas analyses; totals analysis versus toxicity characteristic leaching procedure; waste characterization sampling methods; applicability of real-time radiography; quality assurance objectives for waste characterization sampling and analytical methods; quality assurance project plan requirements; and Waste Isolation Pilot Plant generator/storage site waste screening and acceptance audit program

  19. 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

  20. 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

  1. 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

  2. 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;…

  3. 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…

  4. 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).

  5. 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.

  6. 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

  7. 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.

  8. 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

  9. 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…

  10. 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.

  11. 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

  12. 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)

  13. 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 ...

  14. 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

  15. 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

  16. 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

  17. Canadian energy supply and demand 1993 - 2010: Appendix to the technical report

    International Nuclear Information System (INIS)

    1994-12-01

    The National Energy Board has since 1959 prepared and maintained projections of energy supply requirements and has from tine to time published reports on them. The objectives of this report are to provide a comprehensive 'all energy' market analysis and outlook to service as a standard of reference for all parties interested in Canadian energy issues; to provide a framework for public discussion on emerging energy issues of national importance and to monitor the prospects for the supply, demand and price of natural gas in Canada pursuant to the Market-Based Procedure for regulating. The focus of the technical report provides detailed descriptions of the analytical methods used and the quantitative results. The quantitative analysis will be of value to users who wish to develop their own views of prospects or to have a detailed assessment of the impact of alternative assumptions. 93 tabs., 13 figs

  18. Canadian energy supply and demand 1993 - 2010: Appendix to the technical report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1994-12-01

    The National Energy Board has since 1959 prepared and maintained projections of energy supply requirements and has from tine to time published reports on them. The objectives of this report are to provide a comprehensive `all energy` market analysis and outlook to service as a standard of reference for all parties interested in Canadian energy issues; to provide a framework for public discussion on emerging energy issues of national importance and to monitor the prospects for the supply, demand and price of natural gas in Canada pursuant to the Market-Based Procedure for regulating. The focus of the technical report provides detailed descriptions of the analytical methods used and the quantitative results. The quantitative analysis will be of value to users who wish to develop their own views of prospects or to have a detailed assessment of the impact of alternative assumptions. 93 tabs., 13 figs.

  19. 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.

  20. 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.

  1. 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

  2. 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...

  3. 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 )

  4. 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

  5. Draft Title 40 CFR 191 compliance certification application for the Waste Isolation Pilot Plant. Volume 3: Appendix BIR Volume 1

    International Nuclear Information System (INIS)

    1995-01-01

    The Waste Isolation Pilot Plant (WIPP) Transuranic Waste Baseline Inventory Report (WTWBIR) establishes a methodology for grouping wastes of similar physical and chemical properties, from across the US Department of Energy (DOE) transuranic (TRU) waste system, into a series of ''waste profiles'' that can be used as the basis for waste form discussions with regulatory agencies. The majority of this document reports TRU waste inventories of DOE defense sites. An appendix is included which provides estimates of commercial TRU waste from the West Valley Demonstration Project. The WIPP baseline inventory is estimated using waste streams identified by the DOE TRU waste generator/storage sites, supplemented by information from the Mixed Waste Inventory Report (MWIR) and the 1994 Integrated Data Base (IDB). The sites provided and/or authorized all information in the Waste Stream Profiles except the EPA (hazardous waste) codes for the mixed inventories. These codes were taken from the MWIR (if a WTWBIR mixed waste stream was not in MWIR, the sites were consulted). The IDB was used to generate the WIPP radionuclide inventory. Each waste stream is defined in a waste stream profile and has been assigned a waste matrix code (WMC) by the DOE TRU waste generator/storage site. Waste stream profiles with WMCs that have similar physical and chemical properties can be combined into a waste matrix code group (WMCG), which is then documented in a site-specific waste profile for each TRU waste generator/storage site that contains waste streams in that particular WMCG

  6. 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.

  7. 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.

  8. 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)

  9. 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

  10. 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.

  11. Surrogate Plant Data Base : Volume 4. Appendix E : Medium and Heavy Truck Manufacturing

    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 ...

  12. 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 ...

  13. 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.

  14. 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.

  15. Data summary of municipal solid waste management alternatives. Volume 5, Appendix C, Fluidized-bed combustion

    Energy Technology Data Exchange (ETDEWEB)

    None

    1992-10-01

    This appendix provides information on fluidized-bed combustion (FBC) technology as it has been applied to municipal waste combustion (MWC). A review of the literature was conducted to determine: (1) to what extent FBC technology has been applied to MWC, in terms of number and size of units was well as technology configuration; (2) the operating history of facilities employing FBC technology; and (3) the cost of these facilities as compared to conventional MSW installations. Where available in the literature, data on operating and performance characteristics are presented. Tabular comparisons of facility operating/cost data and emissions data have been complied and are presented. The literature review shows that FBC technology shows considerable promise in terms of providing improvements over conventional technology in areas such as NOx and acid gas control, and ash leachability. In addition, the most likely configuration to be applied to the first large scale FBC dedicated to municipal solid waste (MSW) will employ circulating bed (CFB) technology. Projected capital costs for the Robbins, Illinois 1600 ton per day CFB-based waste-to-energy facility are competitive with conventional systems, in the range of $125,000 per ton per day of MSW receiving capacity.

  16. 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.

  17. 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.

  18. 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

  19. 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.

  20. 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

  1. 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

  2. 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

  3. 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.

  4. Draft Waste Management Programmatic Environmental Impact Statement for managing treatment, storage, and disposal of radioactive and hazardous waste. Volume 3, Appendix A: Public response to revised NOI, Appendix B: Environmental restoration, Appendix C, Environmental impact analysis methods, Appendix D, Risk

    International Nuclear Information System (INIS)

    1995-08-01

    Volume three contains appendices for the following: Public comments do DOE's proposed revisions to the scope of the waste management programmatic environmental impact statement; Environmental restoration sensitivity analysis; Environmental impacts analysis methods; and Waste management facility human health risk estimates

  5. An evaluation of known remaining oil resources in the United States: Appendix. Volume 10

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1993-11-01

    Volume ten contains the following appendices: overview of improved oil recovery methods which covers enhanced oil recovery methods and advanced secondary recovery methods; the benefits of improved oil recovery, selected data for the analyzed states; and list of TORIS fields and reservoirs.

  6. Hybrid Vehicle Technology Constraints and Application Assessment Study : Volume 4. Sections 10, 11, and Appendix.

    Science.gov (United States)

    1977-01-01

    This four-volume report presents analyses and assessments of both heat engine/battery- and heat engine/flywheel-powered hybrid vehicles to determine if they could contribute to near-term (1980-1990) reductions in transportation energy consumption und...

  7. Space shuttle/food system study. Volume 2, Appendix F: Flight food and primary packaging

    Science.gov (United States)

    1974-01-01

    The analysis and selection of food items and primary packaging, the development of menus, the nutritional analysis of diet, and the analyses of alternate food mixes and contingency foods is reported in terms of the overall food system design for space shuttle flight. Stowage weights and cubic volumes associated with each alternate mix were also evaluated.

  8. 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

  9. 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.

  10. 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

  11. Space shuttle/food system study. Volume 2, appendix E: Alternate flight systems analysis

    Science.gov (United States)

    1974-01-01

    The functional requirements of stowage, preparation, serving, consumption, and cleanup were applied to each of the five food mixes selected for study in terms of the overall design of the space shuttle food system. The analysis led to a definition of performance requirements for each food mix, along with a definition of equipment to meet those requirements. Weight and volume data for all five systems, in terms of food and packaging, support equipment, and galley installation penalties, are presented.

  12. Army Synthetic Validity Project Report of Phase 2 Results. Volume 2. Appendixes

    Science.gov (United States)

    1990-10-01

    to Equipment & Food o Personal Hygine - Field & Garrison (4) o Kitchen Equipment - Garrison o Field Preparation of Foods & Equipment o Food, Field...Results: Volume II: Appendi i 12. PERSONAL AUTHOR(S) Wise, Lauress L. (AIR); Peterson, Norman G.; Houston, Janis (PDRI); Hoffman, R. Gene Campbell, John...o Handling KIA o Personal Hygiene & Preventive Medicine Numbers in parentheses indicate the number of participants that identified the task as

  13. Draft Waste Management Programmatic Environmental Impact Statement for managing treatment, storage, and disposal of radioactive and hazardous waste. Volume 3, Appendix A: Public response to revised NOI, Appendix B: Environmental restoration, Appendix C, Environmental impact analysis methods, Appendix D, Risk

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-08-01

    Volume three contains appendices for the following: Public comments do DOE`s proposed revisions to the scope of the waste management programmatic environmental impact statement; Environmental restoration sensitivity analysis; Environmental impacts analysis methods; and Waste management facility human health risk estimates.

  14. Operation, Maintenance and Performance Evaluation of the Potomac Estuary Experimental Water Treatment Plant. Appendix. Volume 2.

    Science.gov (United States)

    1983-09-01

    TO 16 MARCH 1983 VIRUS ASSAY (Continued) Lower Volume Detect ion v Samw lno Filtered CeIll Limit Concentration Date (Gallons) Line (MPNCU/Gallon...through a glass fiber filter which has been prepared with 100 ml of Milli-Q. 11. Collect samples of and/or analyze filtrate for the parameters listed below...constant for each jar test at 50 mg/L k 2. 200 ml of supernatant filtered through a Gelman glass fiber filter Discussion. The results summarized above

  15. 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

  16. 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.

  17. 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. 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.

  19. 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.

  20. 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.

  1. 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.

  2. 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...

  3. County-Level Climate Uncertainty for Risk Assessments: Volume 25 Appendix X - Forecast Sea Ice Age.

    Energy Technology Data Exchange (ETDEWEB)

    Backus, George A. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Lowry, Thomas Stephen [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Jones, Shannon M. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Walker, La Tonya Nicole [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Roberts, Barry L. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Malczynski, Leonard A. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2017-05-01

    This report uses the CMIP5 series of climate model simulations to produce country- level uncertainty distributions for use in socioeconomic risk assessments of climate change impacts. It provides appropriate probability distributions, by month, for 169 countries and autonomous-areas on temperature, precipitation, maximum temperature, maximum wind speed, humidity, runoff, soil moisture and evaporation for the historical period (1976-2005), and for decadal time periods to 2100. It also provides historical and future distributions for the Arctic region on ice concentration, ice thickness, age of ice, and ice ridging in 15-degree longitude arc segments from the Arctic Circle to 80 degrees latitude, plus two polar semicircular regions from 80 to 90 degrees latitude. The uncertainty is meant to describe the lack of knowledge rather than imprecision in the physical simulation because the emphasis is on unfalsified risk and its use to determine potential socioeconomic impacts. The full report is contained in 27 volumes.

  4. County-Level Climate Uncertainty for Risk Assessments: Volume 26 Appendix Y - Historical Ridging Rate.

    Energy Technology Data Exchange (ETDEWEB)

    Backus, George A. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Lowry, Thomas Stephen [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Jones, Shannon M. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Walker, La Tonya Nicole [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Roberts, Barry L. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Malczynski, Leonard A. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2017-05-01

    This report uses the CMIP5 series of climate model simulations to produce country- level uncertainty distributions for use in socioeconomic risk assessments of climate change impacts. It provides appropriate probability distributions, by month, for 169 countries and autonomous-areas on temperature, precipitation, maximum temperature, maximum wind speed, humidity, runoff, soil moisture and evaporation for the historical period (1976-2005), and for decadal time periods to 2100. It also provides historical and future distributions for the Arctic region on ice concentration, ice thickness, age of ice, and ice ridging in 15-degree longitude arc segments from the Arctic Circle to 80 degrees latitude, plus two polar semicircular regions from 80 to 90 degrees latitude. The uncertainty is meant to describe the lack of knowledge rather than imprecision in the physical simulation because the emphasis is on unfalsified risk and its use to determine potential socioeconomic impacts. The full report is contained in 27 volumes.

  5. County-Level Climate Uncertainty for Risk Assessments: Volume 23 Appendix V - Forecast Sea Ice Thickness

    Energy Technology Data Exchange (ETDEWEB)

    Backus, George A.; Lowry, Thomas Stephen; Jones, Shannon M; Walker, La Tonya Nicole; Roberts, Barry L; Malczynski, Leonard A.

    2017-04-01

    This report uses the CMIP5 series of climate model simulations to produce country- level uncertainty distributions for use in socioeconomic risk assessments of climate change impacts. It provides appropriate probability distributions, by month, for 169 countries and autonomous-areas on temperature, precipitation, maximum temperature, maximum wind speed, humidity, runoff, soil moisture and evaporation for the historical period (1976-2005), and for decadal time periods to 2100. It also provides historical and future distributions for the Arctic region on ice concentration, ice thickness, age of ice, and ice ridging in 15-degree longitude arc segments from the Arctic Circle to 80 degrees latitude, plus two polar semicircular regions from 80 to 90 degrees latitude. The uncertainty is meant to describe the lack of knowledge rather than imprecision in the physical simulation because the emphasis is on unfalsified risk and its use to determine potential socioeconomic impacts. The full report is contained in 27 volumes.

  6. County-Level Climate Uncertainty for Risk Assessments: Volume 27 Appendix Z - Forecast Ridging Rate.

    Energy Technology Data Exchange (ETDEWEB)

    Backus, George A.; Lowry, Thomas Stephen; Jones, Shannon M; Walker, La Tonya Nicole; Roberts, Barry L; Malczynski, Leonard A.

    2017-06-01

    This report uses the CMIP5 series of climate model simulations to produce country- level uncertainty distributions for use in socioeconomic risk assessments of climate change impacts. It provides appropriate probability distributions, by month, for 169 countries and autonomous-areas on temperature, precipitation, maximum temperature, maximum wind speed, humidity, runoff, soil moisture and evaporation for the historical period (1976-2005), and for decadal time periods to 2100. It also provides historical and future distributions for the Arctic region on ice concentration, ice thickness, age of ice, and ice ridging in 15-degree longitude arc segments from the Arctic Circle to 80 degrees latitude, plus two polar semicircular regions from 80 to 90 degrees latitude. The uncertainty is meant to describe the lack of knowledge rather than imprecision in the physical simulation because the emphasis is on unfalsified risk and its use to determine potential socioeconomic impacts. The full report is contained in 27 volumes.

  7. County-Level Climate Uncertainty for Risk Assessments: Volume 24 Appendix W - Historical Sea Ice Age.

    Energy Technology Data Exchange (ETDEWEB)

    Backus, George A. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Lowry, Thomas Stephen [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Jones, Shannon M [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Walker, La Tonya Nicole [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Roberts, Barry L [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Malczynski, Leonard A. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2017-05-01

    This report uses the CMIP5 series of climate model simulations to produce country- level uncertainty distributions for use in socioeconomic risk assessments of climate change impacts. It provides appropriate probability distributions, by month, for 169 countries and autonomous-areas on temperature, precipitation, maximum temperature, maximum wind speed, humidity, runoff, soil moisture and evaporation for the historical period (1976-2005), and for decadal time periods to 2100. It also provides historical and future distributions for the Arctic region on ice concentration, ice thickness, age of ice, and ice ridging in 15-degree longitude arc segments from the Arctic Circle to 80 degrees latitude, plus two polar semicircular regions from 80 to 90 degrees latitude. The uncertainty is meant to describe the lack of knowledge rather than imprecision in the physical simulation because the emphasis is on unfalsified risk and its use to determine potential socioeconomic impacts. The full report is contained in 27 volumes.

  8. Heater test planning for the Near Surface Test Facility at the Hanford reservation. Volume II. Appendix

    International Nuclear Information System (INIS)

    DuBois, A.; Binnall, E.; Chan, T.; McEvoy, M.; Nelson, P.; Remer, J.

    1979-04-01

    Volume II contains the following information: theoretical support for radioactive waste storage projects - development of data analysis methods and numerical models; injectivity temperature profiling as a means of permeability characterization; geophysical holes at the Near Surface Test Facility (NSTF), Hanford; proposed geophysical and hydrological measurements at NSTF; suggestions for characterization of the discontinuity system at NSTF; monitoring rock property changes caused by radioactive waste storage using the electrical resistivity method; microseismic detection system for heated rock; Pasco Basin groundwater contamination study; a letter to Mark Board on Gable Mountain Faulting; report on hydrofracturing tests for in-situ stress measurement, NSTF, Hole DC-11, Hanford Reservation; and borehole instrumentation layout for Hanford Near Surface Test Facility

  9. County-Level Climate Uncertainty for Risk Assessments: Volume 17 Appendix P - Forecast Soil Moisture

    Energy Technology Data Exchange (ETDEWEB)

    Backus, George A.; Lowry, Thomas Stephen; Jones, Shannon M; Walker, La Tonya Nicole; Roberts, Barry L; Malczynski, Leonard A.

    2017-04-01

    This report uses the CMIP5 series of climate model simulations to produce country- level uncertainty distributions for use in socioeconomic risk assessments of climate change impacts. It provides appropriate probability distributions, by month, for 169 countries and autonomous-areas on temperature, precipitation, maximum temperature, maximum wind speed, humidity, runoff, soil moisture and evaporation for the historical period (1976-2005), and for decadal time periods to 2100. It also provides historical and future distributions for the Arctic region on ice concentration, ice thickness, age of ice, and ice ridging in 15-degree longitude arc segments from the Arctic Circle to 80 degrees latitude, plus two polar semicircular regions from 80 to 90 degrees latitude. The uncertainty is meant to describe the lack of knowledge rather than imprecision in the physical simulation because the emphasis is on unfalsified risk and its use to determine potential socioeconomic impacts. The full report is contained in 27 volumes.

  10. County-Level Climate Uncertainty for Risk Assessments: Volume 15 Appendix N - Forecast Surface Runoff.

    Energy Technology Data Exchange (ETDEWEB)

    Backus, George A. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Lowry, Thomas Stephen [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Jones, Shannon M. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Walker, La Tonya Nicole [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Roberts, Barry L. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Malczynski, Leonard A. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2017-05-01

    This report uses the CMIP5 series of climate model simulations to produce country- level uncertainty distributions for use in socioeconomic risk assessments of climate change impacts. It provides appropriate probability distributions, by month, for 169 countries and autonomous-areas on temperature, precipitation, maximum temperature, maximum wind speed, humidity, runoff, soil moisture and evaporation for the historical period (1976-2005), and for decadal time periods to 2100. It also provides historical and future distributions for the Arctic region on ice concentration, ice thickness, age of ice, and ice ridging in 15-degree longitude arc segments from the Arctic Circle to 80 degrees latitude, plus two polar semicircular regions from 80 to 90 degrees latitude. The uncertainty is meant to describe the lack of knowledge rather than imprecision in the physical simulation because the emphasis is on unfalsified risk and its use to determine potential socioeconomic impacts. The full report is contained in 27 volumes.

  11. County-Level Climate Uncertainty for Risk Assessments: Volume 10 Appendix I - Historical Evaporation.

    Energy Technology Data Exchange (ETDEWEB)

    Backus, George A.; Lowry, Thomas Stephen; Jones, Shannon M; Walker, La Tonya Nicole; Roberts, Barry L; Malczynski, Leonard A.

    2017-06-01

    This report uses the CMIP5 series of climate model simulations to produce country- level uncertainty distributions for use in socioeconomic risk assessments of climate change impacts. It provides appropriate probability distributions, by month, for 169 countries and autonomous-areas on temperature, precipitation, maximum temperature, maximum wind speed, humidity, runoff, soil moisture and evaporation for the historical period (1976-2005), and for decadal time periods to 2100. It also provides historical and future distributions for the Arctic region on ice concentration, ice thickness, age of ice, and ice ridging in 15-degree longitude arc segments from the Arctic Circle to 80 degrees latitude, plus two polar semicircular regions from 80 to 90 degrees latitude. The uncertainty is meant to describe the lack of knowledge rather than imprecision in the physical simulation because the emphasis is on unfalsified risk and its use to determine potential socioeconomic impacts. The full report is contained in 27 volumes.

  12. County-Level Climate Uncertainty for Risk Assessments: Volume 14 Appendix M - Historical Surface Runoff.

    Energy Technology Data Exchange (ETDEWEB)

    Backus, George A.; Lowry, Thomas Stephen; Jones, Shannon M; Walker, La Tonya Nicole; Roberts, Barry L; Malczynski, Leonard A.

    2017-06-01

    This report uses the CMIP5 series of climate model simulations to produce country- level uncertainty distributions for use in socioeconomic risk assessments of climate change impacts. It provides appropriate probability distributions, by month, for 169 countries and autonomous-areas on temperature, precipitation, maximum temperature, maximum wind speed, humidity, runoff, soil moisture and evaporation for the historical period (1976-2005), and for decadal time periods to 2100. It also provides historical and future distributions for the Arctic region on ice concentration, ice thickness, age of ice, and ice ridging in 15-degree longitude arc segments from the Arctic Circle to 80 degrees latitude, plus two polar semicircular regions from 80 to 90 degrees latitude. The uncertainty is meant to describe the lack of knowledge rather than imprecision in the physical simulation because the emphasis is on unfalsified risk and its use to determine potential socioeconomic impacts. The full report is contained in 27 volumes.

  13. County-Level Climate Uncertainty for Risk Assessments: Volume 8 Appendix G - Historical Precipitation.

    Energy Technology Data Exchange (ETDEWEB)

    Backus, George A.; Lowry, Thomas Stephen; Jones, Shannon M; Walker, La Tonya Nicole; Roberts, Barry L; Malczynski, Leonard A.

    2017-06-01

    This report uses the CMIP5 series of climate model simulations to produce country- level uncertainty distributions for use in socioeconomic risk assessments of climate change impacts. It provides appropriate probability distributions, by month, for 169 countries and autonomous-areas on temperature, precipitation, maximum temperature, maximum wind speed, humidity, runoff, soil moisture and evaporation for the historical period (1976-2005), and for decadal time periods to 2100. It also provides historical and future distributions for the Arctic region on ice concentration, ice thickness, age of ice, and ice ridging in 15-degree longitude arc segments from the Arctic Circle to 80 degrees latitude, plus two polar semicircular regions from 80 to 90 degrees latitude. The uncertainty is meant to describe the lack of knowledge rather than imprecision in the physical simulation because the emphasis is on unfalsified risk and its use to determine potential socioeconomic impacts. The full report is contained in 27 volumes.

  14. County-Level Climate Uncertainty for Risk Assessments: Volume 12 Appendix K - Historical Rel. Humidity.

    Energy Technology Data Exchange (ETDEWEB)

    Backus, George A.; Lowry, Thomas Stephen; Jones, Shannon M; Walker, La Tonya Nicole; Roberts, Barry L; Malczynski, Leonard A.

    2017-06-01

    This report uses the CMIP5 series of climate model simulations to produce country- level uncertainty distributions for use in socioeconomic risk assessments of climate change impacts. It provides appropriate probability distributions, by month, for 169 countries and autonomous-areas on temperature, precipitation, maximum temperature, maximum wind speed, humidity, runoff, soil moisture and evaporation for the historical period (1976-2005), and for decadal time periods to 2100. It also provides historical and future distributions for the Arctic region on ice concentration, ice thickness, age of ice, and ice ridging in 15-degree longitude arc segments from the Arctic Circle to 80 degrees latitude, plus two polar semicircular regions from 80 to 90 degrees latitude. The uncertainty is meant to describe the lack of knowledge rather than imprecision in the physical simulation because the emphasis is on unfalsified risk and its use to determine potential socioeconomic impacts. The full report is contained in 27 volumes.

  15. County-Level Climate Uncertainty for Risk Assessments: Volume 16 Appendix O - Historical Soil Moisture.

    Energy Technology Data Exchange (ETDEWEB)

    Backus, George A.; Lowry, Thomas Stephen; Jones, Shannon M; Walker, La Tonya Nicole; Roberts, Barry L; Malczynski, Leonard A.

    2017-06-01

    This report uses the CMIP5 series of climate model simulations to produce country- level uncertainty distributions for use in socioeconomic risk assessments of climate change impacts. It provides appropriate probability distributions, by month, for 169 countries and autonomous-areas on temperature, precipitation, maximum temperature, maximum wind speed, humidity, runoff, soil moisture and evaporation for the historical period (1976-2005), and for decadal time periods to 2100. It also provides historical and future distributions for the Arctic region on ice concentration, ice thickness, age of ice, and ice ridging in 15-degree longitude arc segments from the Arctic Circle to 80 degrees latitude, plus two polar semicircular regions from 80 to 90 degrees latitude. The uncertainty is meant to describe the lack of knowledge rather than imprecision in the physical simulation because the emphasis is on unfalsified risk and its use to determine potential socioeconomic impacts. The full report is contained in 27 volumes.

  16. County-Level Climate Uncertainty for Risk Assessments: Volume 22 Appendix U - Historical Sea Ice Thickness

    Energy Technology Data Exchange (ETDEWEB)

    Backus, George A.; Lowry, Thomas Stephen; Jones, Shannon M; Walker, La Tonya Nicole; Roberts, Barry L; Malczynski, Leonard A.

    2017-06-01

    This report uses the CMIP5 series of climate model simulations to produce country- level uncertainty distributions for use in socioeconomic risk assessments of climate change impacts. It provides appropriate probability distributions, by month, for 169 countries and autonomous-areas on temperature, precipitation, maximum temperature, maximum wind speed, humidity, runoff, soil moisture and evaporation for the historical period (1976-2005), and for decadal time periods to 2100. It also provides historical and future distributions for the Arctic region on ice concentration, ice thickness, age of ice, and ice ridging in 15-degree longitude arc segments from the Arctic Circle to 80 degrees latitude, plus two polar semicircular regions from 80 to 90 degrees latitude. The uncertainty is meant to describe the lack of knowledge rather than imprecision in the physical simulation because the emphasis is on unfalsified risk and its use to determine potential socioeconomic impacts. The full report is contained in 27 volumes.

  17. 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

  18. 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

  19. 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

  20. 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

  1. 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

  2. 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.

  3. 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

  4. Foothills Parkway Section 8B Final Environmental Report, Volume 6, Appendix N

    Energy Technology Data Exchange (ETDEWEB)

    Blasing, T.J.; Cada, G.F.; Carer, M.; Chin, S.M.; Dickerman, J.A.; Etnier, D.A.; Gibson, R.; Harvey, M.; Hatcher, B.; Lietzske, D.; Mann, L.K.; Mulholland, P.J.; Petrich, C.H.; Pounds, L.; Ranney, J.; Reed, R.M.; Ryan, P.F.; Schweitzer, M.; Smith, D.; Thomason, P.; Wade, M.C.

    1999-07-01

    In 1994, Oak Ridge National Laboratory (ORNL) was tasked by the National Park Service (NPS) to prepare an Environmental Report (ER) for Section 8B of the Foothills Parkway in the Great Smoky Mountains National Park (GSMNP). Section 8B represents 27.7 km (14.2 miles) of a total of 115 km (72 miles) of the planned Foothills Parkway and would connect the Cosby community on the east to the incorporated town of Pittman Center to the west. The major deliverables for the project are listed. From August 1995 through October 1996, NPS, GSMNP, and ORNL staff interacted with Federal Highway Administration staff to develop a conceptual design plan for Section 8B with the intent of protecting critical resources identified during the ER process to the extent possible. In addition, ORNL arranged for bioengineering experts to discuss techniques that might be employed on Section 8B with NPS, GSMNP, and ORNL staff during September 1996. For the purposes of this ER, there are two basic alternatives under consideration: (1) a build alternative and (2) a no-build alternative. Within the build alternative are a number of options including constructing Section 8B with no interchanges, constructing Section 8B with an interchange at SR 416 or U.S. 321, constructing Section 8B with a spur road on Webb Mountain, and considering operation of Section 8B both before and after the operation of Section 8C. The no-build alternative is considered the no-action alternative and is not to construct Section 8B. This volume of the ER documents the results of the architectural, historical, and cultural resources assessment for the entire Section 8B ROW that was completed in May 1995 to document the architectural, historical, and cultural resources located within the project area. The assessment included evaluation of the potential for cultural (i.e., rural historic) landscapes in the area of the ROW. The assessment showed that one National Register-listed property is located 0.3 mile south of the ROW

  5. Foothills Parkway Section 8B Final Environmental Report, Volume 3, Appendix D

    Energy Technology Data Exchange (ETDEWEB)

    Blasing, T.J.; Cada, G.F.; Carer, M.; Chin, S.M.; Dickerman, J.A.; Etnier, D.A.; Gibson, R.; Harvey, M.; Hatcher, B.; Lietzske, D.; Mann, L.K.; Mulholland, P.J.; Petrich, C.H.; Pounds, L.; Ranney, J.; Reed, R.M.; Ryan, P.F.; Schweitzer, M.; Smith, D.; Thomason, P.; Wade, M.C.

    1999-07-01

    In 1994, Oak Ridge National Laboratory (ORNL) was tasked by the National Park Service (NPS) to prepare an Environmental Report (ER) for Section 8B of the Foothills Parkway in the Great Smoky Mountains National Park (GSMNP). Section 8B represents 27.7 km (14.2 miles) of a total of 115 km (72 miles) of the planned Foothills Parkway and would connect the Cosby community on the east to the incorporated town of Pittman Center to the west. The major deliverables for the project are listed. From August 1995 through October 1996, NPS, GSMNP, and ORNL staff interacted with Federal Highway Administration staff to develop a conceptual design plan for Section 8B with the intent of protecting critical resources identified during the ER process to the extent possible. In addition, ORNL arranged for bioengineering experts to discuss techniques that might be employed on Section 8B with NPS, GSMNP, and ORNL staff during September 1996. For the purposes of this ER, there are two basic alternatives under consideration: (1) a build alternative and (2) a no-build alternative. Within the build alternative are a number of options including constructing Section 8B with no interchanges, constructing Section 8B with an interchange at SR416 or U.S. 321, constructing Section 8B with a spur road on Webb Mountain, and considering operation of Section 8B both before and after the operation of Section 8C. The no-build alternative is considered the no-action alternative and is not to construct Section 8B. This volume of the ER inventories the fishes and benthic macroinvertebrates inhabiting the aquatic ecosystems potentially affected by the proposed construction of Section 8B. Stream biological surveys were completed at 31 stream sites during the Fall of 1994. The sampling strategy for both invertebrates and fish was to survey the different taxa from all available habitats. For benthic invertebrates, a standardized qualitative manual collection technique was employed for all 31 stations. For fish

  6. 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

  7. 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

  8. 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.

  9. 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

  10. 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

  11. 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

  12. Technical Specifications, Clinton Power Station, Unit No. 1 (Docket No. 50-461). Appendix ''A'' to License No. NPF-55

    International Nuclear Information System (INIS)

    1986-09-01

    This report presents information on the technical specifications of the Clinton Unit No. 1 Reactor in the areas of: safety limits and limiting safety system settings; limiting conditions for operation and surveillance requirements; design features; and administrative controls

  13. 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

  14. 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

  15. 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

  16. 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.

  17. 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.

  18. 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

  19. 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

  20. 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

  1. Technical specifications, Callaway Plant, Unit No. 1. Appendix A to license No. NPF-25 (Docket No. STN 50-483)

    International Nuclear Information System (INIS)

    Anderson, F.D.

    1984-06-01

    Technical specifications are presented for the limiting conditions for operation and surveillance requirements for the reactor core, reactivity control systems, power distribution limits, instrumentation, reactor coolant system, emergency core cooling systems, containment systems, plant systems, electrical power systems, refueling operations, special test exceptions, radioactive effluents, radiological environmental monitoring; design features of the site, containment, core, coolant system, and fuel storage; and plant staff organization

  2. Technical Specifications: Clinton Power Station, Unit No. 1 (Docket No. 50-461): Appendix ''A'' to License No. NPF-62

    International Nuclear Information System (INIS)

    1987-04-01

    The Clinton Power Station, Unit No. 1 Technical Specifications were prepared by the US Nuclear Regulatory Commission to set forth 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

  3. Technical Specifications, Seabrook Station, Unit 1 (Docket No. 50-443): Appendix ''A'' to License No. NPF-67

    International Nuclear Information System (INIS)

    1989-05-01

    The Seabrook Station, Unit 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 Part 50 for the protection of the health and safety of the public

  4. Technical specifications: Hope Creek Generating Station (Docket No. 50-354). Appendix A to License No. NPF-50

    International Nuclear Information System (INIS)

    1986-04-01

    Information is provided on the technical specifications for the Hope Creek Nuclear Power Station. Areas of interest discussed in this report include: safety limits and limiting safety system settings; limiting conditions for operation and surveillance requirements; design features; and administrative controls

  5. 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

  6. 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)

  7. 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.

  8. 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).

  9. 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

  10. 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.

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

    International Nuclear Information System (INIS)

    1995-01-01

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

  12. 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.

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

    Science.gov (United States)

    1975-12-01

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

  14. Space shuttle/food system. Volume 2, Appendix C: Food cooling techniques analysis. Appendix D: Package and stowage: Alternate concepts analysis

    Science.gov (United States)

    1974-01-01

    The relative penalties associated with various techniques for providing an onboard cold environment for storage of perishable food items, and for the development of packaging and vehicle stowage parameters were investigated in terms of the overall food system design analysis of space shuttle. The degrees of capability for maintaining both a 40 F to 45 F refrigerated temperature and a 0 F and 20 F frozen environment were assessed for the following cooling techniques: (1) phase change (heat sink) concept; (2) thermoelectric concept; (3) vapor cycle concept; and (4) expendable ammonia concept. The parameters considered in the analysis were weight, volume, and spacecraft power restrictions. Data were also produced for packaging and vehicle stowage parameters which are compatible with vehicle weight and volume specifications. Certain assumptions were made for food packaging sizes based on previously generated space shuttle menus. The results of the study are shown, along with the range of meal choices considered.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1991-05-31

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

  16. 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.

  17. 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.

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

    International Nuclear Information System (INIS)

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

    1983-12-01

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

  19. 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...

  20. 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...

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2015-06-15

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

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

    International Nuclear Information System (INIS)

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

    2015-01-01

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

  3. Space shuttle/food system study. Volume 2, Appendix A: Active heating system-screening analysis. Appendix B: Reconstituted food heating techniques analysis

    Science.gov (United States)

    1974-01-01

    Technical data are presented which were used to evaluate active heating methods to be incorporated into the space shuttle food system design, and also to evaluate the relative merits and penalties associated with various approaches to the heating of rehydrated food during space flight. Equipment heating candidates were subject to a preliminary screening performed by a selection rationale process which considered the following parameters; (1) gravitational effect; (2) safety; (3) operability; (4) system compatibility; (5) serviceability; (6) crew acceptability; (7) crew time; (8) development risk; and (9) operating cost. A hot air oven, electrically heated food tray, and microwave oven were selected for further consideration and analysis. Passive, semi-active, and active food preparation approaches were also studied in an effort to determine the optimum method for heating rehydrated food. Potential complexity, cost, vehicle impact penalties, and palatability were considered in the analysis. A summary of the study results is provided along with cost estimates for each of the potential sytems

  4. 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

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

    Energy Technology Data Exchange (ETDEWEB)

    Sheehan, M.A.

    1997-04-01

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

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

    International Nuclear Information System (INIS)

    Sheehan, M.A.

    1997-04-01

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

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

    Science.gov (United States)

    1989-09-01

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

  8. 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)

  9. The San Francisco Bay - Delta Wastewater and Residual Solids Management Study. Volume III. Technical Appendix. Wastewater Residual Solids Management Study

    Science.gov (United States)

    1972-08-01

    wI. I’- D;~ U0! IS 0 U)- 00oa u (D0 ILL z In wi Ug iu U)0ii - __ U) w m w0: - -x x xr -j4 COd 0 cr. (0 0 0) 0 ~0 0-I 0 0> I- Zc w 0 -j I I to- 0n / I...sludge ("phosphate calcium", calcium hydroxyapatite - Ca5O1-l(PO4) 3 ) from 0aC03. (Ref. 15.) The CaCO 3 can then be rocalcined while the phosphate sludge

  10. Telegraph Canyon Creek, City of Chula Vista, San Diego County, California. Detailed Report for Flood Control. Volume 2. Technical Appendixes.

    Science.gov (United States)

    1983-07-01

    occurred within 40 miles of’ the site. Most of these earthquakes appear to be related to activity on the Elsinore, Agua Caliente, and offshore faults. The...device would be required by the Sweetwater Authority to prevent contamination of potable water lines. TELEGRAPH CANYON CREEK - - Recommended Plant List A

  11. Development of flight experiment task requirements. Volume 2: Technical Report. Part 2: Appendix H: Tasks-skills data series

    Science.gov (United States)

    Hatterick, G. R.

    1972-01-01

    The data sheets presented contain the results of the task analysis portion of the study to identify skill requirements of space shuttle crew personnel. A comprehensive data base is provided of crew functions, operating environments, task dependencies, and task-skills applicable to a representative cross section of earth orbital research experiments.

  12. GREAT I Study of the Upper Mississippi River. Technical Appendixes. Volume 5. Fish and Wildlife. Part II.

    Science.gov (United States)

    1980-09-01

    of saplings standing calm and into the reeds that fringed the edges of solid as the Sphinx, with one forefoot little ponds, our sport continued, the...line of bluffs lay darkly blue, while he stops halfway and stands with up- on the Wisconsin side they retained a raised forefoot and rigid tail. As...the tree-tops in coming up, it strikes an unnoticed and then spin away on a straight line; branch or twig; and frequently when some whisk away so close

  13. Review Report for Flood Control and Recreational Development, Little Colorado River at Holbrook, Arizona. Volume 2. Technical Appendix.

    Science.gov (United States)

    1980-09-01

    Anasasi culture (Wendorf�: .160). Pueblo I s it is possible that the Kayenta people end thea inhabi- taints of the central Little Colorado shared...the -same Kayenta - type structure during aseakrIII,* Pueblo 1, and early Pueblo It time (Oumerman and Skimner 1968: 139). Anasazi- Mogollon contacts...entity within this area (see Fig. 4). Five early Pueblo II sites, A.D. 900 to 107S, recorded in the Hopi Buttes area are almost pure Kayenta sites

  14. Grand Lake Saint Marys, Ohio, Survey Report for Flood Control and Allied Purposes. Volume 2. Technical Appendix.

    Science.gov (United States)

    1981-08-01

    and nettle . Site 2. Adjacent to the west end of Grand Lake St. Marys between Brown and Monroe Streets, trees in the canopy in this wooded area...or in iieu of, tile drainage in attempts to combat standing water problems in affected fields. Within more recent years, an inczeasing number of farm...further reduce soil erosion since crop rotation is widely practiced to control pest insects and vary nutrient withdrawal. D-86 S . mnuu The remaining

  15. General Reevaluation and Environmental Impact Statement for Flood Control and Related Purposes, Sheyenne River, North Dakota. Volume 2. Technical Appendixes.

    Science.gov (United States)

    1984-01-01

    such as earthen embankments, butchering areas, rock align- nents, depressions, or pictographs. Most of these site-type identifica- tions art tentative...424 1280-1300 Historic Homestead & Prehistoric Lithic Scatter 425 1260-1280 427 1270-1280 428 1280-1300 Butchering Area(? 32BE3 Village & Trenchwork...Includes land damage from scour and gully erosion and deposition of undesirable material; livestock and poultry losses; damages to equipment, fences

  16. 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

  17. 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

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

    NARCIS (Netherlands)

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

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

  19. 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

  20. 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.''

  1. 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.''

  2. 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.

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

    International Nuclear Information System (INIS)

    Roberts, B.B.; Bland, D.

    1988-12-01

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

  4. 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

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

    International Nuclear Information System (INIS)

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

    1979-03-01

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

  6. Gulf Coast Salt Domes geologic Area Characterization Report, East Texas Study Area. Volume II. Technical report

    International Nuclear Information System (INIS)

    1982-07-01

    The East Texas Area Characterization Report (ACR) is a compilation of data gathered during the Area Characterization phase of the Department of Energy's National Waste Terminal Storage program in salt. The characterization of Gulf Coast Salt Domes as a potential site for storage of nuclear waste is an ongoing process. This report summarizes investigations covering an area of approximately 2590 km 2 (1000 mi 2 ). Data on Oakwood, Keechi, and Palestine Domes are given. Subsequent phases of the program will focus on smaller land areas and fewer specific salt domes, with progressively more detailed investigations, possibly culminating with a license application to the Nuclear Regulatory Commission. The data in this report are a result of drilling and sampling, geophysical and geologic field work, and intensive literature review. The ACR contains text discussing data usage, interpretations, results and conclusions based on available geologic and hydrologic data, and figures including diagrams showing data point locations, geologic and hydrologic maps, geologic cross sections, and other geologic and hydrologic information. An appendix contains raw data gathered during this phase of the project and used in the preparation of these reports

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

    International Nuclear Information System (INIS)

    1985-01-01

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

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

    Science.gov (United States)

    Consumer Product Safety Commission, Washington, DC.

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

  9. 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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1993-08-01

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

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

    International Nuclear Information System (INIS)

    BARCOT, R.A.

    2001-01-01

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

  12. 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.

  13. 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

  14. 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

  15. 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

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

    Energy Technology Data Exchange (ETDEWEB)

    Easton, C. R.

    1978-08-01

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

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

    Science.gov (United States)

    Levak, Daniel

    1993-01-01

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

  18. Global Spent Fuel Logistics Systems Study (GSFLS). Volume 3. GSFLS technical and financial analysis. Interim report

    International Nuclear Information System (INIS)

    1978-01-01

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

  19. Surrogate Plant Data Base : Volume 3. Appendix D : Facilities Planning Data ; Operating Manpower, Manufacturing Budgets and Pre-Production Launch ...

    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 ...

  20. Exxon Nuclear Company WREM-based generic PWR ECCS evaluation model. Appendix C to Volume II. Yankee Rowe example problem

    International Nuclear Information System (INIS)

    1975-01-01

    Core 12, of the Yankee Rowe (YR), plant is to be licensed with the Exxon Nuclear Co. PWR Evaluation Model. This appendix presents methodology and results of an example calculation for the YR plant using the ENC Evaluation Model. This example problem is for the double-ended guillotine cold leg break with a discharge coefficient of 0.6 assuming loss of one emergency diesel. The NSSS supplier has determined this case to give the highest peak cladding temperature (PCT) for Core 11. The YR example problem was performed to determine the maximum acceptable local peak heating rate (Kw/ft). The blowdown was performed with beginning-of-cycle (BOC) ENC fuel at full power with the hot assembly power corresponding to the design peak rod heating rate of 12.9 Kw/ft. The HOT CHANNEL, TOODEE2, and RELAP4-FLOOD runs were made at several reduced hot assembly radial peaks, holding axial peaking constant, until an acceptable PCT was achieved. This procedure results in a PCT of 1834 0 F at a reduced peak linear heating rate of 10.5 Kw/ft for the ENC fuel at BOC. (auth)

  1. Data summary of municipal solid waste management alternatives. Volume 7, Appendix E -- Material recovery/material recycling technologies

    Energy Technology Data Exchange (ETDEWEB)

    None

    1992-10-01

    The enthusiasm for and commitment to recycling of municipal solid wastes is based on several intuitive benefits: Conservation of landfill capacity; Conservation of non-renewable natural resources and energy sources; Minimization of the perceived potential environmental impacts of MSW combustion and landfilling; Minimization of disposal costs, both directly and through material resale credits. In this discussion, ``recycling`` refers to materials recovered from the waste stream. It excludes scrap materials that are recovered and reused during industrial manufacturing processes and prompt industrial scrap. Materials recycling is an integral part of several solid waste management options. For example, in the preparation of refuse-derived fuel (RDF), ferrous metals are typically removed from the waste stream both before and after shredding. Similarly, composting facilities, often include processes for recovering inert recyclable materials such as ferrous and nonferrous metals, glass, Plastics, and paper. While these two technologies have as their primary objectives the production of RDF and compost, respectively, the demonstrated recovery of recyclables emphasizes the inherent compatibility of recycling with these MSW management strategies. This appendix discusses several technology options with regard to separating recyclables at the source of generation, the methods available for collecting and transporting these materials to a MRF, the market requirements for post-consumer recycled materials, and the process unit operations. Mixed waste MRFs associated with mass bum plants are also presented.

  2. SSI response of a typical shear wall structure. Appendix B. In-structure response spectra comparisons. Volume 2

    International Nuclear Information System (INIS)

    Johnson, J.J.; Schewe, E.C.; Maslenikov, O.R.

    1984-04-01

    The objectives of this study were two-fold: (1) develop building response calibration factors, i.e., factors which relate best estimate or median level response to responses calculated by selected design procedures. Soil-structure interaction was the phenomenon of interest because significant simplifications are frequently introduced in its treatment; and (2) the second objective can be viewed in the context of a question: what effect does placing an identical structure on different sites and with different foundation conditions have on structure response. The structure selected for this study is a part of the Zion AFT complex. Only the auxiliary, fuel-handling, and diesel generator buildings were studied. This structure is a connected group of shear-wall buildings constructed of reinforced concrete, typical of nuclear power plant structures. The bases of comparison for this study were structure responses: peak in-structure accelerations (27 components), and peak wall forces and moments (111 components). In-structure response spectra were also considered. This appendix contains in-structure response spectra comparisons in detail

  3. Technical evaluation of Aerojet Energy Conversion Company's topical report on a mobile volume reduction system

    International Nuclear Information System (INIS)

    Henscheid, J.W.

    1984-01-01

    This report summarizes EG and G Idaho's review of Aerojet Energy Conversion Company's (AECC's) topical report on a Mobile Volume Reduction System. The review evaluated compliance with pertinent codes, standards and regulations. The initial review was discussed with AECC by EG and G Idaho and the NRC, and all outstanding issues resolved before this final evaluation was made

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

    Energy Technology Data Exchange (ETDEWEB)

    None

    1979-11-01

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

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

    Science.gov (United States)

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

  6. Technical Assistance in Evaluating Career Education Projects. Final Report. Volume II: Final Career Education Evaluation Report.

    Science.gov (United States)

    Stenner, A. Jackson; And Others

    This document contains the second 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…

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

    International Nuclear Information System (INIS)

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

    1985-01-01

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

  8. Crew appliance concepts. Volume 2, appendix B: Shuttle orbiter appliances supporting engineering data. [food management and personal hygiene

    Science.gov (United States)

    Proctor, B. W.; Reysa, R. P.; Russell, D. J.

    1975-01-01

    Technical data collected for the food management and personal hygiene appliances considered for the shuttle orbiter are presented as well as plotted and tabulated trade study results for each appliance. Food storage, food operation, galley cleanup, waste collection/transfer, body cleansing, and personal grooming were analyzed.

  9. 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.

  10. 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

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

    International Nuclear Information System (INIS)

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

    1992-11-01

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

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

    International Nuclear Information System (INIS)

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

    1983-08-01

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

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

    International Nuclear Information System (INIS)

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

    1995-01-01

    This document is a revision to WHC-SD-SNF-SD-002, and is issued to support the individual projects that make up the Spent Nuclear Fuel Project in the lower-tier functions, requirements, interfaces, and technical baseline items. It presents results of engineering analyses since Sept. 1994. The mission of the SNFP on the Hanford site is to provide safety, economic, environmentally sound management of Hanford SNF in a manner that stages it to final disposition. This particularly involves K Basin fuel, although other SNF is involved also

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

    Science.gov (United States)

    1978-01-01

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

  15. Regulatory and technical reports (abstract index journal): Annual compilation for 1994. Volume 19, Number 4

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-03-01

    This compilation consists of bibliographic data and abstracts for the formal regulatory and technical reports issued by the US Nuclear Regulatory Commission (NRC) Staff and its contractors. It is NRC`s intention to publish this compilation quarterly and to cumulate it annually. The main citations and abstracts in this compilation are listed in NUREG number order. These precede the following indexes: secondary report number index, personal author index, subject index, NRC originating organization index (staff reports), NRC originating organization index (international agreements), NRC contract sponsor index (contractor reports), contractor index, international organization index, and licensed facility index. A detailed explanation of the entries precedes each index.

  16. Regulatory and technical reports, compilation for 1979. Volume 4. Bibliographical report Jan-Dec 79

    International Nuclear Information System (INIS)

    Oliu, W.E.; McKenzie, L.; Aragon, R.

    1980-07-01

    The compilation lists formal regulatory and technical reports issued in 1979 by the U.S. Nuclear Regulatory Commission (NRC) staff and by NRC contractors. The compilation is divided into three major sections. The first major section consists of a sequential listing of all NRC reports in report-number order. The first portion of this sequential section lists staff reports, the second portion lists NRC-sponsored conference proceedings, and the third lists contractor reports. Each report citation in the sequential section contains full bibliographic information

  17. Fate and effects of nearshore discharges of OCS produced waters. Volume 2. Technical report (Final)

    International Nuclear Information System (INIS)

    Rabalais, N.N.; McKee, B.A.; Reed, D.J.; Means, J.C.

    1991-06-01

    While the number of facilities that discharge OCS produced waters into coastal environments of Louisiana are few in number, they account for large volumes, individually and collectively. Of the 15 facilities which discharge OCS-generated produced water into coastal environments of Louisiana (as of February 1990), 10 discharges in seven areas were studied. The discharge volumes of the study areas range from 3,000 to 106,000/bbl.d. The receiving environments for these effluents are varied, but include the shallow, nearshore continental shelf; high energy, freshwater distributaries of the Mississippi River delta; and brackish and saline coastal environments with moderately to poorly flushed waters. All study areas are within the Mississippi River Deltaic Plain. The study expanded on the initial assessment of Boesch and Rabalais (1989a) with increased temporal and spatial studies of three areas, additional study sites including an abandoned discharge, and additional analytical and field observations

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

    International Nuclear Information System (INIS)

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

    1988-01-01

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

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

    International Nuclear Information System (INIS)

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

    1985-05-01

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

  20. Technical Reviews and Audits for Systems, Equipment and Computer Software. Volume 1

    Science.gov (United States)

    2009-09-15

    acquisitions and technology developments. 2. This new-issue SMC standard comprises the text of The Aerospace Corporation report number TOR-2007( 8583 )-6414...TRA) Deskbook – DUSD(S&T) (May 2005) 17. IMP & IMS Preparation and Use Guide Version 0.9 (21 October 2005) 18. ISO /IEC STD 15939 Software...1521B, TOR-2007( 8583 )-6414_Volume 1. 110.2 Purpose A. The guidelines contained herein implement the Department of Defense Directive 4120.21

  1. Remedial investigation/feasibility study for the Clinch River/Poplar Creek operable unit. Volume 3. Appendix E

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-09-01

    This document contains Appendix E: Toxicity Information and Uncertainty Analysis, description of methods, from the combined Remedial Investigation/Feasibility Study Report for the Clinch River/Poplar Crack (CR/PC) Operable Unit (OU). The CR/PC OU is located in Anderson and Roane Counties, Tennessee and consists of the Clinch River and several of its embayments in Melton Hill and Watts Bar Reservoirs. These waters have received hazardous substances released over a period of 50 years from the US Department of Energy`s Oak Ridge Reservation (ORR), a National Priority List site established under the Comprehensive Environmental Response, Compensation, and Liability Act. A remedial investigation has been conducted to determine the current nature and extent of any contamination and to assess the resulting risk to human health and the environment. The feasibility study evaluates remedial action alternatives to identify any that are feasible for implementation and that would effectively reduce risk. Historical studies had indicated that current problems would likely include {sup 137}Cs in sediment of the Clinch River, mercury in sediment and fish of Poplar Creek and PCBs and pesticides in fish from throughout the OU. Peak releases of mercury and {sup 137}Cs occurred over 35 years ago, and current releases are low. Past releases of PCBs from the ORR are poorly quantified, and current releases are difficult to quantify because levels are so low. The site characterization focused on contaminants in surface water, sediment, and biota. Contaminants in surface water were all found to be below Ambient Water Quality Criteria. Other findings included the following: elevated metals including cesium 137 and mercury in McCoy Branch sediments; PCBs and chlordane elevated in several fish species, presenting the only major human health risk, significant ecological risks in Poplar Creek but not in the Clinch River.

  2. Remedial investigation/feasibility study for the Clinch River/Poplar Creek operable unit. Volume 3. Appendix E

    International Nuclear Information System (INIS)

    1995-09-01

    This document contains Appendix E: Toxicity Information and Uncertainty Analysis, description of methods, from the combined Remedial Investigation/Feasibility Study Report for the Clinch River/Poplar Crack (CR/PC) Operable Unit (OU). The CR/PC OU is located in Anderson and Roane Counties, Tennessee and consists of the Clinch River and several of its embayments in Melton Hill and Watts Bar Reservoirs. These waters have received hazardous substances released over a period of 50 years from the US Department of Energy's Oak Ridge Reservation (ORR), a National Priority List site established under the Comprehensive Environmental Response, Compensation, and Liability Act. A remedial investigation has been conducted to determine the current nature and extent of any contamination and to assess the resulting risk to human health and the environment. The feasibility study evaluates remedial action alternatives to identify any that are feasible for implementation and that would effectively reduce risk. Historical studies had indicated that current problems would likely include 137 Cs in sediment of the Clinch River, mercury in sediment and fish of Poplar Creek and PCBs and pesticides in fish from throughout the OU. Peak releases of mercury and 137 Cs occurred over 35 years ago, and current releases are low. Past releases of PCBs from the ORR are poorly quantified, and current releases are difficult to quantify because levels are so low. The site characterization focused on contaminants in surface water, sediment, and biota. Contaminants in surface water were all found to be below Ambient Water Quality Criteria. Other findings included the following: elevated metals including cesium 137 and mercury in McCoy Branch sediments; PCBs and chlordane elevated in several fish species, presenting the only major human health risk, significant ecological risks in Poplar Creek but not in the Clinch River

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

    International Nuclear Information System (INIS)

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

    2001-01-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2001-07-01

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

  5. Data Base Development of Automobile and Light Truck Maintenance : Volume I. Test and Appendixes A-D

    Science.gov (United States)

    1978-08-01

    The volume describes the development of the life cycle maintenance costs for 212 sales-leading 1970 through 1975 passenger cars and light trucks. These costs provide a data base for the Department of Transportation, which describes the costs for part...

  6. 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.

  7. Simulation model for wind energy storage systems. Volume I. Technical report. [SIMWEST code

    Energy Technology Data Exchange (ETDEWEB)

    Warren, A.W.; Edsinger, R.W.; Chan, Y.K.

    1977-08-01

    The effort developed a comprehensive computer program for the modeling of wind energy/storage systems utilizing any combination of five types of storage (pumped hydro, battery, thermal, flywheel and pneumatic). An acronym for the program is SIMWEST (Simulation Model for Wind Energy Storage). The level of detail of SIMWEST is consistent with a role of evaluating the economic feasibility as well as the general performance of wind energy systems. The software package consists of two basic programs and a library of system, environmental, and load components. Volume I gives a brief overview of the SIMWEST program and describes the two NASA defined simulation studies.

  8. Technical Note: Influence of Compton currents on profile measurements in small-volume ion chambers

    Energy Technology Data Exchange (ETDEWEB)

    Tanny, Sean; Sperling, Nicholas; Parsai, E. Ishmael, E-mail: e.parsai@utoledo.edu [Department of Radiation Oncology, University of Toledo Medical Center, 1325 Conference Drive, Toledo, Ohio 43614 (United States); Holmes, Shannon [Standard Imaging, 3120 Deming Way, Middleton, Wisconsin 53562 (United States)

    2015-10-15

    Purpose: This work is to evaluate the effects of Compton current generation in three small-volume ionization chambers on measured beam characteristics for electron fields. Methods: Beam scans were performed using Exradin A16, A26, and PTW 31014 microchambers. Scans with varying chamber components shielded were performed. Static point measurements, output factors, and cable only irradiations were performed to determine the contribution of Compton currents to various components of the chamber. Monte Carlo simulations were performed to evaluate why one microchamber showed a significant reduction in Compton current generation. Results: Beam profiles demonstrated significant distortion for two of the three chambers when scanned parallel to the chamber axis, produced by electron deposition within the wire. Measurements of ionization produced within the cable identified Compton current generation as the cause of these distortions. The size of the central collecting wire was found to have the greatest influence on the magnitude of Compton current generation. Conclusions: Microchambers can demonstrate significant (>5%) deviations from properties as measured with larger volume chambers (0.125 cm{sup 3} and above). These deviations can be substantially reduced by averaging measurements conducted at opposite polarities.

  9. 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

  10. 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

  11. 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

  12. Proceedings of the sixth international conference on fluidized bed combustion. Volume II. Technical sessions

    Energy Technology Data Exchange (ETDEWEB)

    None

    1980-08-01

    The Sixth International Conference on Fluidized Bed Combustion was held April 9-11, 1980, at the Atlanta Hilton, Atlanta, Georgia. It was sponsored by the US Department of Energy, the Electric Power Research Institute, the US Environmental Protection Agency, and the Tennessee Valley Authority. The papers covered recent developments in atmospheric and pressurized fluidized-bed combustion, especially the design, operation and control of pilot and demonstration plants. The cleanup of combustion products and the erosion, corrosion and fouling of gas turbines was emphasized also. Fifty-five papers from Volume 2 of the proceedings have been entered individually into EDB and ERA; five papers had been entered previously from other sources. (LTN)

  13. ASHRAE transactions 1999: Technical and symposium papers. Volume 105, Part 1

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-07-01

    This book contains 50 technical papers and 83 symposium papers. The symposium papers are divided into the following sections: Computer Models for Fire and Smoke Control; Thermal Properties and Estimation Techniques of Ground-Coupled Heat Pump Boreholes, Grouts, and Fills; Advances in Thermal and Fluid Characteristics in HVAC and Refrigeration Processes; Effects of Controlling Humidity on Energy Consumption of Supermarkets; Fault Detection and Diagnostics -- Learning from Building Operations; Innovative Methods for Room Air Distribution; Laboratory Exhaust Fans and Stacks; Full Scale Tests in Very Large Spaces and CFD Modeling; Laboratory Verification and Testing; Absorption/Sorption Heat Pumps and Refrigeration Systems; Attic and Cathedral Ceilings II; Health Care Issues Update; Computers in HVAC Education; Multizone Modeling of Ventilation and Infiltration in Residential Buildings; Documenting the Value of a Facility of Corporate Energy Manager; Water Heating systems Information and Design Tools; Snow Melting: System Assessment; Fault Detection and Diagnostics (FDD) Methods and Evaluation Techniques; The Effects of Commissioning and O and M on IAQ; Energy Efficiency in Commercial Food Service Facilities; Historical Views of Steam, Ice and Refrigerants; Low Total Equivalent Warming Impact (TWEI) Unitary Air Conditioners and Heat Pump Systems; and Second Law Studies of Systems and Processes. Separate abstracts were prepared for most papers in this book.

  14. 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)

  15. 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

  16. Characteristics of potential repository wastes: Volume 4, Appendix 4A, Nuclear reactors at educational institutions of the United States; Appendix 4B, Data sheets for nuclear reactors at educational institutions; Appendix 4C, Supplemental data for Fort St. Vrain spent fuel; Appendix 4D, Supplemental data for Peach Bottom 1 spent fuel; Appendix 4E, Supplemental data for Fast Flux Test Facility

    International Nuclear Information System (INIS)

    1992-07-01

    Volume 4 contains the following appendices: nuclear reactors at educational institutions in the United States; data sheets for nuclear reactors at educational institutions in the United States(operational reactors and shut-down reactors); supplemental data for Fort St. Vrain spent fuel; supplemental data for Peach Bottom 1 spent fuel; and supplemental data for Fast Flux Test Facility

  17. 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

  18. 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.

  19. Technical Note: Harmonic analysis applied to MR image distortion fields specific to arbitrarily shaped volumes.

    Science.gov (United States)

    Stanescu, T; Jaffray, D

    2018-05-25

    Magnetic resonance imaging is expected to play a more important role in radiation therapy given the recent developments in MR-guided technologies. MR images need to consistently show high spatial accuracy to facilitate RT specific tasks such as treatment planning and in-room guidance. The present study investigates a new harmonic analysis method for the characterization of complex 3D fields derived from MR images affected by system-related distortions. An interior Dirichlet problem based on solving the Laplace equation with boundary conditions (BCs) was formulated for the case of a 3D distortion field. The second-order boundary value problem (BVP) was solved using a finite elements method (FEM) for several quadratic geometries - i.e., sphere, cylinder, cuboid, D-shaped, and ellipsoid. To stress-test the method and generalize it, the BVP was also solved for more complex surfaces such as a Reuleaux 9-gon and the MR imaging volume of a scanner featuring a high degree of surface irregularities. The BCs were formatted from reference experimental data collected with a linearity phantom featuring a volumetric grid structure. The method was validated by comparing the harmonic analysis results with the corresponding experimental reference fields. The harmonic fields were found to be in good agreement with the baseline experimental data for all geometries investigated. In the case of quadratic domains, the percentage of sampling points with residual values larger than 1 mm were 0.5% and 0.2% for the axial components and vector magnitude, respectively. For the general case of a domain defined by the available MR imaging field of view, the reference data showed a peak distortion of about 12 mm and 79% of the sampling points carried a distortion magnitude larger than 1 mm (tolerance intrinsic to the experimental data). The upper limits of the residual values after comparison with the harmonic fields showed max and mean of 1.4 mm and 0.25 mm, respectively, with only 1.5% of

  20. Emissions of greenhouse gases from the use of transportation fuels and electricity. Volume 2: Appendixes A--S

    Energy Technology Data Exchange (ETDEWEB)

    DeLuchi, M.A. [Argonne National Lab., IL (United States)]|[Univ. of California, Davis, CA (United States). Inst. of Transportation Studies

    1993-11-01

    This volume contains the appendices to the report on Emission of Greenhouse Gases from the Use of Transportation Fuels and Electricity. Emissions of methane, nitrous oxide, carbon monoxide, and other greenhouse gases are discussed. Sources of emission including vehicles, natural gas operations, oil production, coal mines, and power plants are covered. The various energy industries are examined in terms of greenhouse gas production and emissions. Those industries include electricity generation, transport of goods via trains, trucks, ships and pipelines, coal, natural gas and natural gas liquids, petroleum, nuclear energy, and biofuels.

  1. Advanced Flue Gas Desulfurization (AFGD) demonstration project: Volume 2, Project performance and economics. Final technical report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-04-30

    The project objective is to demonstrate removal of 90--95% or more of the SO{sub 2} at approximately one-half the cost of conventional scrubbing technology; and to demonstrate significant reduction of space requirements. In this project, Pure Air has built a single SO{sub 2} absorber for a 528-MWe power plant. The absorber performs three functions in a single vessel: prequencher, absorber, and oxidation of sludge to gypsum. Additionally, the absorber is of a co- current design, in which the flue gas and scrubbing slurry move in the same direction and at a relatively high velocity compared to conventional scrubbers. These features all combine to yield a state- of-the-art SO{sub 2} absorber that is more compact and less expensive than conventional scrubbers. The project incorporated a number of technical features including the injection of pulverized limestone directly into the absorber, a device called an air rotary sparger located within the base of the absorber, and a novel wastewater evaporation system. The air rotary sparger combines the functions of agitation and air distribution into one piece of equipment to facilitate the oxidation of calcium sulfite to gypsum. Additionally, wastewater treatment is being demonstrated to minimize water disposal problems inherent in many high-chloride coals. Bituminous coals primarily from the Indiana, Illinois coal basin containing 2--4.5% sulfur were tested during the demonstration. The Advanced Flue Gas Desulfurization (AFGD) process has demonstrated removal of 95% or more of the SO{sub 2} while providing a commercial gypsum by-product in lieu of solid waste. A portion of the commercial gypsum is being agglomerated into a product known as PowerChip{reg_sign} gypsum which exhibits improved physical properties, easier flowability and more user friendly handling characteristics to enhance its transportation and marketability to gypsum end-users.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1979-12-01

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

  3. Preliminary risk assessment for nuclear waste disposal in space. Volume I. Executive summary of technical report

    International Nuclear Information System (INIS)

    Rice, E.E.; Denning, R.S.; Friedlander, A.L.

    1982-01-01

    Three major conclusions come from this preliminary risk assessment of nuclear waste disposal in space. Preliminary estimates of space disposal risk are low, even with the estimated uncertainty bounds. If calculated mined geologic repository (MGR) release risks remain low, and the EPA requirements continue to be met, then no additional space disposal study effort is warranted. If risks perceived by the public are significant in the acceptance of mined geologic repositories, then consideration of space disposal as an MGR complement is warranted. As a result of this study, the following recommendations are made to NASA and the US DOE: During the continued evaluation of the mined geologic repository risk over the years ahead by DOE, if any significant increase in the calculated health risk is predicted for the MGR, then space disposal should be reevaluated at that time. The risks perceived by the public for the MGR should be evaluated on a broad basis by an independent organization to evaluate acceptance. If, in the future, MGR risks are found to be significant due to some presently unknown technical or social factor, and space disposal is selected as an alternative that may be useful in mitigating the risks, then the following space disposal study activities are recommended: improvement in chemical processing technology for wastes; payload accident response analysis; risk uncertainty analysis for both MGR and space disposal; health risk modeling that includes pathway and dose estimates; space disposal cost modeling; assessment of space disposal perceived (by public) risk benefit; and space systems analysis supporting risk and cost modeling

  4. International Best Practice Basis for Assessing Recovery Operations. Annex II of Technical Volume 5

    International Nuclear Information System (INIS)

    2015-01-01

    This volume seeks to identify lessons learned related to post-accident recovery that may further improve preparedness worldwide. This objective assessment of the recovery programme is made according to international best practice. In the practice and assessment of radiation and nuclear safety, international best practice is a process or technique that is likely to consistently produce superior results. An important principle is that a ‘best’ practice can evolve to become better as improvements are discovered and lessons are learned from past experience. The lessons to be learned from the recovery programme as it unfolds in Japan will feed back into improving international best practice in post-accident recovery worldwide. Best practice is used to maintain quality and is a component of quality management systems and standards, such as ISO 9000. It is generally regarded as being the most efficient and effective way to accomplish desired outcomes. The body of best practice is used as a benchmark and for self assessment

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

    Directory of Open Access Journals (Sweden)

    V. H. Kuznetsov

    2007-08-01

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

  6. Technical Note: New methodology for measuring viscosities in small volumes characteristic of environmental chamber particle samples

    Directory of Open Access Journals (Sweden)

    L. Renbaum-Wolff

    2013-01-01

    Full Text Available Herein, a method for the determination of viscosities of small sample volumes is introduced, with important implications for the viscosity determination of particle samples from environmental chambers (used to simulate atmospheric conditions. The amount of sample needed is < 1 μl, and the technique is capable of determining viscosities (η ranging between 10−3 and 103 Pascal seconds (Pa s in samples that cover a range of chemical properties and with real-time relative humidity and temperature control; hence, the technique should be well-suited for determining the viscosities, under atmospherically relevant conditions, of particles collected from environmental chambers. In this technique, supermicron particles are first deposited on an inert hydrophobic substrate. Then, insoluble beads (~1 μm in diameter are embedded in the particles. Next, a flow of gas is introduced over the particles, which generates a shear stress on the particle surfaces. The sample responds to this shear stress by generating internal circulations, which are quantified with an optical microscope by monitoring the movement of the beads. The rate of internal circulation is shown to be a function of particle viscosity but independent of the particle material for a wide range of organic and organic-water samples. A calibration curve is constructed from the experimental data that relates the rate of internal circulation to particle viscosity, and this calibration curve is successfully used to predict viscosities in multicomponent organic mixtures.

  7. Advanced Transportation System Studies. Technical Area 3: Alternate Propulsion Subsystem Concepts. Volume 1; Executive Summary

    Science.gov (United States)

    Levack, Daniel J. H.

    2000-01-01

    SSTO mission This volume overviews each of the tasks giving its objectives, main results. and conclusions. More detailed Final Task Reports are available on each individual task.

  8. Draft site-wide environmental impact statement for Sandia National Laboratories/New Mexico. Volume 2: Appendixes

    International Nuclear Information System (INIS)

    1999-04-01

    The DOE proposes to continue operating the Sandia National Laboratories/New Mexico (SNL/NM) located in central New Mexico. The DOE has identified and assessed three alternatives for the operation of SNL/NM: (1) No Action, (2) Expanded Operations, and (3) Reduced Operations. In the No Action Alternative, the DOE would continue the historical mission support activities SNL/NM has conducted at planned operational levels. In the Expanded Operations Alternative, the DOE would operate SNL/NM at the highest reasonable levels of activity currently foreseeable. Under the Reduced Operations Alternative, the DOE would operate SNL/NM at the minimum levels of activity necessary to maintain the capabilities to support the DOE mission in the near term. Under all of the alternatives, the affected environment is primarily within 50 miles (80 kilometers) of SNL/NM. Analyses indicate little difference in the environmental impacts among alternatives. This volume contains Appendices A--H

  9. County-Level Climate Uncertainty for Risk Assessments: Volume 4 Appendix C - Historical Maximum Near-Surface Air Temperature.

    Energy Technology Data Exchange (ETDEWEB)

    Backus, George A.; Lowry, Thomas Stephen; Jones, Shannon M; Walker, La Tonya Nicole; Roberts, Barry L; Malczynski, Leonard A.

    2017-06-01

    This report uses the CMIP5 series of climate model simulations to produce country- level uncertainty distributions for use in socioeconomic risk assessments of climate change impacts. It provides appropriate probability distributions, by month, for 169 countries and autonomous-areas on temperature, precipitation, maximum temperature, maximum wind speed, humidity, runoff, soil moisture and evaporation for the historical period (1976-2005), and for decadal time periods to 2100. It also provides historical and future distributions for the Arctic region on ice concentration, ice thickness, age of ice, and ice ridging in 15-degree longitude arc segments from the Arctic Circle to 80 degrees latitude, plus two polar semicircular regions from 80 to 90 degrees latitude. The uncertainty is meant to describe the lack of knowledge rather than imprecision in the physical simulation because the emphasis is on unfalsified risk and its use to determine potential socioeconomic impacts. The full report is contained in 27 volumes.

  10. County-Level Climate Uncertainty for Risk Assessments: Volume 6 Appendix E - Historical Minimum Near-Surface Air Temperature.

    Energy Technology Data Exchange (ETDEWEB)

    Backus, George A.; Lowry, Thomas Stephen; Jones, Shannon M; Walker, La Tonya Nicole; Roberts, Barry L; Malczynski, Leonard A.

    2017-06-01

    This report uses the CMIP5 series of climate model simulations to produce country- level uncertainty distributions for use in socioeconomic risk assessments of climate change impacts. It provides appropriate probability distributions, by month, for 169 countries and autonomous-areas on temperature, precipitation, maximum temperature, maximum wind speed, humidity, runoff, soil moisture and evaporation for the historical period (1976-2005), and for decadal time periods to 2100. It also provides historical and future distributions for the Arctic region on ice concentration, ice thickness, age of ice, and ice ridging in 15-degree longitude arc segments from the Arctic Circle to 80 degrees latitude, plus two polar semicircular regions from 80 to 90 degrees latitude. The uncertainty is meant to describe the lack of knowledge rather than imprecision in the physical simulation because the emphasis is on unfalsified risk and its use to determine potential socioeconomic impacts. The full report is contained in 27 volumes.

  11. County-Level Climate Uncertainty for Risk Assessments: Volume 18 Appendix Q - Historical Maximum Near-Surface Wind Speed.

    Energy Technology Data Exchange (ETDEWEB)

    Backus, George A.; Lowry, Thomas Stephen; Jones, Shannon M; Walker, La Tonya Nicole; Roberts, Barry L; Malczynski, Leonard A.

    2017-06-01

    This report uses the CMIP5 series of climate model simulations to produce country- level uncertainty distributions for use in socioeconomic risk assessments of climate change impacts. It provides appropriate probability distributions, by month, for 169 countries and autonomous-areas on temperature, precipitation, maximum temperature, maximum wind speed, humidity, runoff, soil moisture and evaporation for the historical period (1976-2005), and for decadal time periods to 2100. It also provides historical and future distributions for the Arctic region on ice concentration, ice thickness, age of ice, and ice ridging in 15-degree longitude arc segments from the Arctic Circle to 80 degrees latitude, plus two polar semicircular regions from 80 to 90 degrees latitude. The uncertainty is meant to describe the lack of knowledge rather than imprecision in the physical simulation because the emphasis is on unfalsified risk and its use to determine potential socioeconom ic impacts. The full report is contained in 27 volumes.

  12. County-Level Climate Uncertainty for Risk Assessments: Volume 2 Appendix A - Historical Near-Surface Air Temperature.

    Energy Technology Data Exchange (ETDEWEB)

    Backus, George A.; Lowry, Thomas Stephen; Jones, Shannon M; Walker, La Tonya Nicole; Roberts, Barry L; Malczynski, Leonard A.

    2017-06-01

    This report uses the CMIP5 series of climate model simulations to produce country- level uncertainty distributions for use in socioeconomic risk assessments of climate change impacts. It provides appropriate probability distributions, by month, for 169 countries and autonomous-areas on temperature, precipitation, maximum temperature, maximum wind speed, humidity, runoff, soil moisture and evaporation for the historical period (1976-2005), and for decadal time periods to 2100. It also provides historical and future distributions for the Arctic region on ice concentration, ice thickness, age of ice, and ice ridging in 15-degree longitude arc segments from the Arctic Circle to 80 degrees latitude, plus two polar semicircular regions from 80 to 90 degrees latitude. The uncertainty is meant to describe the lack of knowledge rather than imprecision in the physical simulation because the emphasis is on unfalsified risk and its use to determine potential socioeconomic impacts. The full report is contained in 27 volumes.

  13. County-Level Climate Uncertainty for Risk Assessments: Volume 21 Appendix T - Forecast Sea Ice Area Fraction.

    Energy Technology Data Exchange (ETDEWEB)

    Backus, George A.; Lowry, Thomas Stephen; Jones, Shannon M; Walker, La Tonya Nicole; Roberts, Barry L; Malczynski, Leonard A.

    2017-06-01

    This report uses the CMIP5 series of climate model simulations to produce country- level uncertainty distributions for use in socioeconomic risk assessments of climate change impacts. It provides appropriate probability distributions, by month, for 169 countries and autonomous-areas on temperature, precipitation, maximum temperature, maximum wind speed, humidity, runoff, soil moisture and evaporation for the historical period (1976-2005), and for decadal time periods to 2100. It also provides historical and future distributions for the Arctic region on ice concentration, ice thickness, age of ice, and ice ridging in 15-degree longitude arc segments from the Arctic Circle to 80 degrees latitude, plus two polar semicircular regions from 80 to 90 degrees latitude. The uncertainty is meant to describe the lack of knowledge rather than imprecision in the physical simulation because the emphasis is on unfalsified risk and its use to determine potential socioeconomic impacts. The full report is contained in 27 volumes.

  14. County-Level Climate Uncertainty for Risk Assessments: Volume 20 Appendix S - Historical Sea Ice Area Fraction

    Energy Technology Data Exchange (ETDEWEB)

    Backus, George A.; Lowry, Thomas Stephen; Jones, Shannon M; Walker, La Tonya Nicole; Roberts, Barry L; Malczynski, Leonard A.

    2017-06-01

    This report uses the CMIP5 series of climate model simulations to produce country- level uncertainty distributions for use in socioeconomic risk assessments of climate change impacts. It provides appropriate probability distributions, by month, for 169 countries and autonomous-areas on temperature, precipitation, maximum temperature, maximum wind speed, humidity, runoff, soil moisture and evaporation for the historical period (1976-2005), and for decadal time periods to 2100. It also provides historical and future distributions for the Arctic region on ice concentration, ice thickness, age of ice, and ice ridging in 15-degree longitude arc segments from the Arctic Circle to 80 degrees latitude, plus two polar semicircular regions from 80 to 90 degrees latitude. The uncertainty is meant to describe the lack of knowledge rather than imprecision in the physical simulation because the emphasis is on unfalsified risk and its use to determine potential socioeconomic impacts. The full report is contained in 27 volumes.

  15. 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

  16. 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.

  17. 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

  18. 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

  19. A safeguards case study of the Nuclear Materials and equipment corporation uranium processing plant Apollo, Pennsylvania. Appendix B with proprietary information removed. Staff technical report

    International Nuclear Information System (INIS)

    Altman, W.; Hockert, J.; Quinn, E.

    1980-04-01

    The report characterizes the Atomic Energy Commission safeguards requirements and the safeguards systems and procedures in place at the Nuclear Materials and Equipment (NUMEC) uranium processing plant in Apollo, Pennsylvania during the spring of 1964. Based upon this characterization, a list of safeguards weaknesses which would be considered deficiencies under 1979 requirements is developed. Appendixes A and B to the report provide a detailed characterization of AEC safeguards requirements as well as a side by side comparison of NUMEC's safeguards program in 1964 with the safeguards program currently required of a comparable licensed facility

  20. 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.

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

    International Nuclear Information System (INIS)

    Post, R.G.

    1984-01-01

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

  2. 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)

  3. 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

  4. Proposed nuclear weapons nonproliferation policy concerning foreign research reactor spent nuclear fuel: Appendix B, foreign research reactor spent nuclear fuel characteristics and transportation casks. Volume 2

    International Nuclear Information System (INIS)

    1995-03-01

    This is Appendix B of a draft Environmental Impact Statement (EIS) on a Proposed Nuclear Weapons Nonproliferation Policy Concerning Foreign Research Reactor Spent Nuclear Fuel. It discusses relevant characterization and other information of foreign research reactor spent nuclear fuel that could be managed under the proposed action. It also discusses regulations for the transport of radioactive materials and the design of spent fuel casks

  5. Technical specifications: Perry Nuclear Power Plant, unit no. 1 (Docket no. 50-440): Appendix ''A'' to license no. NPF-58

    International Nuclear Information System (INIS)

    1986-11-01

    This report presents technical specifications for the Perry-1 Reactor in the areas of: safety limits and limiting safety system settings; limiting conditions for operation and surveillance requirements; design features; and administrative controls

  6. Technical specifications, Vogtle Electric Generating Plant, Unit No. 1 (Docket No. 50-424): Appendix ''A'' to license No. NPF-61

    International Nuclear Information System (INIS)

    1987-01-01

    This technical specifications report presents information concerning the Vogtle Electric Generating Plant in the following areas: safety limits and limiting safety system settings; limiting conditions for operation and surveillance requirements; design features; and administrative controls

  7. 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)

  8. 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)

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

    International Nuclear Information System (INIS)

    BARCOT, R.A.

    2005-01-01

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

  10. 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 ...

  11. 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...

  12. 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...

  13. Technical specifications: Susquehanna Steam Electric Station, Unit No. 2 (Docket No. 50-388). Appendix A to License No. NPF-22

    International Nuclear Information System (INIS)

    1984-03-01

    Susquehanna Steam Electric Station, Unit 2 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 Part 50 for the protection of the health and safety of the public

  14. Technical specifications, Shoreham Nuclear Power Station, Unit No. 1 (Docket No. 50-322): Appendix ''A'' to License No. NPF-82

    International Nuclear Information System (INIS)

    1989-04-01

    The Shoreham, Unit 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 facility as set forth in Section 50.36 of 10 CFR Part 50 for the protection of the health and safety of the public. 20 figs., 75 tabs

  15. Technical specifications, Palo Verde Nuclear Generating Station, Unit No. 2 (Docket No. 50-529). Appendix A to License No. NPF-51

    International Nuclear Information System (INIS)

    1986-04-01

    Information is presented concerning the technical specifications for the Palo Verde-2 Reactor. Areas of interest discussed in this report include: safety limits and limiting safety system settings; limiting conditions for operation and surveillance requirements; design features; and administrative controls. 19 figs., 62 tabs

  16. Technical specifications, Palo Verde Nuclear Generating Station, Unit No. 1 (Docket No. 50-528). Appendix A to License No. NPF-34

    International Nuclear Information System (INIS)

    1984-12-01

    Technical specifications are presented concerning operating safety limits for reactivity control systems, power distribution, instrumentation, coolant system, emergency core cooling system, containment systems, plant systems, electrical power systems, refueling operations, radioactive effluents, and radiological environmental monitoring; design features of the reactor site, containment, reactor core, coolant system, and fuel storage; and administrative controls

  17. Technical specifications: Grand Gulf Nuclear Station, Unit No. 1. Docket No. 50-416, Appendix A to License No. NPF-13

    International Nuclear Information System (INIS)

    1982-06-01

    Technical specifications are presented concerning safety limits; limiting safety system settings; reactivity control systems; power distribution limits; instrumentation; reactor coolant system; emergency core cooling systems; containment systems; plant systems; electrical power systems; refueling operations; radioactive effluents; radiological environmental monitoring; site; and administrative controls

  18. Technical specifications, Braidwood Station, Unit Nos. 1 and 2 (Docket Nos. STN 50-456 and STN 50-457): Appendix ''A'' to License No. NPF-70

    International Nuclear Information System (INIS)

    1987-05-01

    The Braidwood Station, Unit Nos. 1 and 2, 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 Part 50 for the protection of the health and safety of the public. 18 figs., 55 tabs

  19. Technical specifications for Grand Gulf Nuclear Station, Unit 1 (Docket No. 50-416). Appendix A to License No. NPF-13

    International Nuclear Information System (INIS)

    1984-08-01

    The Grand Gulf Nuclear Station, Unit 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 facility as set forth in Section 50.36 of 10 CFR part 50 for the protection of the health and safety of the public

  20. Regulatory and technical reports (Abstract Index Journal). Compilation for third quarter 1985, July-September. Volume 10, No. 3

    International Nuclear Information System (INIS)

    1985-10-01

    This compilation consists of bibliographic data and abstracts for the formal Regulatory and technical reports issued by the US Nuclear Regulatory Commission (NRC) Staff and its contractors. This compilation covers the period from July through September, 1985

  1. 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

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

    International Nuclear Information System (INIS)

    1995-04-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    BARCOT, R.A.

    2005-04-13

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

  4. 50 CFR Appendix A to Part 679 - Performance and Technical Requirements for Scales Used To Weigh Catch at Sea in the Groundfish...

    Science.gov (United States)

    2010-10-01

    ... Load (Lot) 3.2.4Influence Quantities 3.2.4.1Temperature 3.2.4.1.1Operating Temperature 3.2.4.2Power... 4.2.1.2Increasing and Decreasing Load and Shift Tests 4.2.2Accuracy Classes 4.2.3Minimum Load 4.2.4Influence Quantities 4.2.4.1Temperature 4.2.4.1.1Operating Temperature 4.2.4.2Power Supply 4.3Technical...

  5. 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.''

  6. 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

  7. 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.

  8. 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

  9. Direct use applications of geothermal resources at Desert Hot Springs, California. Final report, May 23, 1977--July 31, 1978. Volume II: appendixes

    Energy Technology Data Exchange (ETDEWEB)

    Christiansen, C.C.

    1978-07-01

    The following appendixes are included: Desert Hot Springs (DHS) Geothermal Project Advisory Board, Geothermal Citizens Advisory Committee, community needs assessment, geothermal resource characterization, a detailed discussion of the geothermal applications considered for DHS, space/water heating, agricultural operations, detailed analysis of a geothermal aquaculture facility, detailed discussion of proposed energy cascading systems for DHS, regulatory requirements, environmental impact assessment, resource management plan, and geothermal resources property rights and powers of cities to regulate indigenous geothermal resources and to finance construction of facilities for utilization of such resources. (MHR)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1994-06-01

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

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

    International Nuclear Information System (INIS)

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

    1994-06-01

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

  12. Technical Specifications, Byron Station, Unit Nos. 1 and 2 (Docket Nos. STN 50-454 and STN 50-455). Appendix A to license No. NPF-37

    International Nuclear Information System (INIS)

    1985-02-01

    The Byron Station, Unit No. 1 and Unit No. 2 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 Part 50 for the protection of the health and safety of the public. Specifications are presented for limiting conditions for operation for the reactor control system, power distribution limits, instrumentation, primary coolant circuit, ECCS, containment systems, plant systems, electrical power systems, refueling operations, radioactive effluents, and radiological environmental monitoring

  13. Supplemental technical information in support of Y/OWI/TM--44. Volume 9. Drawings for repository preconceptual design studies: salt

    International Nuclear Information System (INIS)

    1978-04-01

    Volume 9 contains drawings for a preconceptual design for a nuclear waste storage facility in salt. Drawings are included for three fuel cycles: fuel recycle, throwaway fuel cycle, and uranium recycle with plutonium in the high-level waste

  14. Supplemental technical information in support of Y/OWI/TM--44. Volume 15. Drawings for repository preconceptual design studies: basalt

    International Nuclear Information System (INIS)

    1978-04-01

    Volume 15 contains the drawings of a preconceptual design for a nuclear waste repository in basalt. Three fuel cycles are considered: fuel recycle, throwaway cycle, and uranium recycle with plutonium in the high-level wastes

  15. Assessment of LWR spent fuel disposal options. Volume 3. Study bases and system design considerations (Appendices). Technical report

    Energy Technology Data Exchange (ETDEWEB)

    1979-07-01

    Volume 3 (Appendices) provides a tabulation of the bases and assumptions used in the study as well as preconceptual design description and cost estimates of the facilities and transportation systems necessary to implement the various study cases.

  16. Assessment of LWR spent fuel disposal options. Volume 3. Study bases and system design considerations (Appendices). Technical report

    International Nuclear Information System (INIS)

    1979-07-01

    Volume 3 (Appendices) provides a tabulation of the bases and assumptions used in the study as well as preconceptual design description and cost estimates of the facilities and transportation systems necessary to implement the various study cases

  17. Resource Conservation and Recovery Act, Part B Permit Application [for the Waste Isolation Pilot Plant (WIPP)]. Chapter E, Appendix E1, Chapter L, Appendix L1: Volume 12, Revision 3

    Energy Technology Data Exchange (ETDEWEB)

    1993-01-01

    The Waste Isolation Pilot Plant (WIPP) Project was authorized by the US Department of Energy 5 (DOE) National Security and Military Applications of the Nuclear Energy Authorization Act of 1980 (Public Law 96-164). Its legislative mandate is to provide a research and development facility to demonstrate the safe disposal of radioactive waste resulting from national defense programs and activities. To fulfill this mandate, the WIPP facility has been designed to perform scientific investigations of the behavior of bedded salt as a repository medium and the interactions between the soft and radioactive wastes. In 1991, DOE proposed to initiate a experimental Test Phase designed to demonstrate the performance of the repository. The Test Phase activities involve experiments using transuranic (TRU) waste typical of the waste planned for future disposal at the WIPP facility. Much of this TRU waste is co-contaminated with chemical constituents which are defined as hazardous under HWMR-7, Pt. II, sec. 261. This waste is TRU mixed waste and is the subject of this application. Because geologic repositories, such as the WIPP facility, are defined under the Resource Conservation and Recovery Act (RCRA) as land disposal facilities, the groundwater monitoring requirements of HWMR-7, PLV, Subpart X, must be addressed. HWMR-7, Pt. V, Subpart X, must be addressed. This appendix demonstrates that groundwater monitoring is not needed in order to demonstrate compliance with the performance standards; therefore, HWMR-7, Pt.V, Subpart F, will not apply to the WIPP facility.

  18. Nirex 97 an assessment of the post-closure performance of a deep waste repository at Sellafield. Volume 2; hydrogeological conceptual model development - effective parameters and calibration appendix

    International Nuclear Information System (INIS)

    Jackson, C.; Watson, S.

    1997-01-01

    United Kingdom Nirex Limited ('Nirex') is responsible for providing and managing facilities for the safe disposal of intermediate and certain low-level radioactive waste (ILW and LLW respectively). Government policy is that the preferred disposal route for such wastes is a deep geological repository. The repository concept aims to use a combination of natural and engineered barriers to achieve the necessary degree of long-term isolation and containment of the radioactive wastes. Since 1987, Nirex has carried out an extensive technical programme directed at the science of safe disposal. The work comprises a research programme into the long-term performance of waste forms and the engineered and natural barriers, including the characterisation of candidate geological settings to assess their suitability to host a deep waste repository ('DWR'). Between mid-1991 and March 1997 the geological characterisation programme was concentrated on establishing the suitability, or otherwise, of a candidate site at Sellafield, West Cumbria. In July 1994, as part of a detailed site investigation programme, Nirex applied for planning permission to develop an underground Rock Characterisation Facility (RCF) at Longlands Farm near Sellafield. This application was rejected by the planning authority and Nirex's appeal against that decision led to a local planning inquiry which ran from September 1995 until February 1996. In line with the Inspector's Report, in March 1997 the Nirex appeal was dismissed by the Secretary of State for the Environment. The Company's response to that decision, and its readiness to contribute to the new government's review of the way forward, are described in the Nirex Annual Report for 1996-97. This report - Nirex 97 - is founded on the understanding developed through the Nirex technical programme. It reports the outcome of an assessment of the post-closure safety performance, over hundreds of thousands of years, of a repository system located in a potential

  19. Regulatory and technical reports (abstract index journal). Volume 20, No. 2: Compilation for second quarter April--June 1995

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-09-01

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

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

    International Nuclear Information System (INIS)

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

    1979-12-01

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

  1. Regulatory and technical reports (Abstract Index Journal). Compilation for first quarter 1986, January-March. Volume 11, No. 1

    International Nuclear Information System (INIS)

    1986-04-01

    This compilation consists of bibliographic data and abstracts for the formal regulatory and technical reports issued by the US Nuclear Regulatory Commission staff and its contractors, as well as conference proceedings. Entries are indexed by contractor report number, personal author, subject, NRC originating organization, NRC contract sponsor, contractor, and licensed facility

  2. Regulatory and technical reports (abstract index journal). Volume 20, No. 2: Compilation for second quarter April--June 1995

    International Nuclear Information System (INIS)

    1995-09-01

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

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

    International Nuclear Information System (INIS)

    1978-04-01

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

  4. Regulatory and technical reports (abstract index journal). Compilation for third quarter 1984, July-September. Volume 9, No. 3

    International Nuclear Information System (INIS)

    1984-11-01

    This compilation consists of bibliographic data and abstracts for the formal regulatory and technical reports issued by the US Nuclear Regulatory Commission (NRC) Staff and its contractors. The main citations and abstracts in this compilation are listed in NUREG number order: NUREG-XXXX, NUREG/CP-XXXX, and NUREG/CR-XXXX. These precede the following indexes: Contractor Report Number, Personal Author, Subject, NRC Originating Organization (Staff Reports), NRC Contract Sponsor (Contractor Reports), Contractor, and Licensed Facility

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

    Science.gov (United States)

    Kraus, E. F.

    1976-01-01

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

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

    Science.gov (United States)

    1992-01-01

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

  7. Louisiana Coastal Area, Louisiana. Freshwater Diversion to Barataria and Breton Sound Basins. Feasibility Study. Volume 2. Technical Appendixes A, B, C, and D.

    Science.gov (United States)

    1984-09-01

    the bullfrog, pig frog, bronze frop, leopard frog, lesser siren, gulf coast toad, preen and squirrel treefrogs, cricket frog, and several species of...geese that winter in significant numbers are lesser snow geese. Other game birds include coots, rails, gallinules, snipe, woodcock, and mourning doves...98 • . - . . . ." . . . . - " - -. - . . Simoneaux, L.F. 1979. The distribution of menhaden, genus Brevortia. with respect to salinity, in the upper

  8. Mississippi and Louisiana Estuarine Areas. Freshwater Diversion to Lake Pontchartrain Basin and Mississippi Sound. Feasibility Study. Volume 2. Technical Appendixes, A, B, C, D.

    Science.gov (United States)

    1984-04-01

    Resource Inventory, March 1979. k/Over half of the reef is within Mobile Bay with an additional 870 acres occuring within Mississippi Sound. 2 / Deegan ...13.7 to 16.2 feet per year resulting In land loss rates of 1,670 to 2,093 acres per year prior to 1960 ( Craig et al., 1978). In Mississippi, land loss...contrlhuted to the increased width of canals. The annual increase in canal width has been estimated at 2 to 5 percent per year ( Craig et al., 197A). A

  9. A survey of the Canadian public's attitudes towards the energy situation. Vol. 2. [Technical appendix included as a separate volume

    Energy Technology Data Exchange (ETDEWEB)

    Keller, G.; McDougall, D.H.G.

    1983-06-01

    Based on a telephone survey of ca 1,900 male and female heads-of-households in nine cities, a report was prepared in 1983 on the Canadian public's attitudes towards the energy situation. This report presents additional analyses of the 1983 data and provides some comparisons with the eight previous annual surveys conducted in this area. The major objective of this report is to provide an understanding of the relationship between Canadians' attitudes, behaviours, and program support with respect to the energy situation. Some conclusions were as follows. Energy shortage is not an issue, rising energy prices are. Surprisingly, in light of the perception of energy prices, self reported conservation actions and behaviours declined in 1983 compared to 1982. Awareness and participation levels in oil substitution and home insulation programs are high and continued government activity in these areas appears warranted. A detailed analysis of two conservation behaviors - adding insulation and weatherstripping/caulking - provided some interesting results. Those who had performed these behaviors tended to be knowledgeable about energy, were satisfied that the money was well spent, and planned to do mere. Those who didn't, felt they had sufficient insulation/weatherstipping and many did not plan to improve the energy efficiency of their home within the next year. There has been a modest trend towards downsizing cars between 1981 and 1983. However, multiple car households still remain as disproportionately heavy users of gasoline. 42 tabs.

  10. 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)

    1995-03-01

    This Remedial Investigation Report on Waste Area Grouping, (NVAG) 5 at Oak Ridge National Laboratory was prepared in accordance with requirements under the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) for reporting, the results of a site chacterization for public review. This work was performed under Work Breakdown Structure 1.4.12.6.1.05.40.02 (Activity Data Sheet 3305, ''WAG 5''). Publication of this document meets a Federal Facility Agreement milestone of March 31, 1995. This document provides the Environmental Restoration Program with information about the results of investigations performed at 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

  11. Remedial investigation report on Waste Area Grouping 5 at Oak Ridge National Laboratory, Oak Ridge, Tennessee. Volume 3, Appendix B, Technical findings and conclusions

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-03-01

    This Remedial Investigation Report on Waste Area Grouping, (NVAG) 5 at Oak Ridge National Laboratory was prepared in accordance with requirements under the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) for reporting, the results of a site chacterization for public review. This work was performed under Work Breakdown Structure 1.4.12.6.1.05.40.02 (Activity Data Sheet 3305, ``WAG 5``). Publication of this document meets a Federal Facility Agreement milestone of March 31, 1995. This document provides the Environmental Restoration Program with information about the results of investigations performed at 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.

  12. Mississippi and Louisiana Estuarine Areas. Freshwater Diversion to Lake Pontchartrain Basin and Mississippi Sound. Feasibility Study. Volume 3. Technical Appendixes, E, F, G, H, I, J, K.

    Science.gov (United States)

    1984-04-01

    Effects on Biota. (a) Primary Production, Photosynthesis . Some phytoplankton would be destroyed by turbidity in areas adjacent to discharge sites...These vegetation surveys would provide meaningful data on long term impacts of the proposed project. Seagrass beds in the study area would be

  13. Resource Conservation and Recovery Act, Part B Permit Application [for the Waste Isolation Pilot Plant (WIPP)]. Volume 2, Chapter C, Appendix C1--Chapter C, Appendix C3 (beginning), Revision 3

    Energy Technology Data Exchange (ETDEWEB)

    1993-03-01

    This volume contains appendices for the following: Rocky Flats Plant and Idaho National Engineering Laboratory waste process information; TRUPACT-II content codes (TRUCON); TRUPACT-II chemical list; chemical compatibility analysis for Rocky Flats Plant waste forms; chemical compatibility analysis for waste forms across all sites; TRU mixed waste characterization database; hazardous constituents of Rocky Flats Transuranic waste; summary of waste components in TRU waste sampling program at INEL; TRU waste sampling program; and waste analysis data.

  14. Report to Congress on the U.S. Department of Energy's Environmental Management Science Program. Research funded and its linkages to environmental cleanup problems. High out-year cost environmental management project descriptions. Volume 3 of 3 - Appendix C

    International Nuclear Information System (INIS)

    1998-04-01

    The Department of Energy's Environmental Management Science Program (EMSP) serves as a catalyst for the application of scientific discoveries to the development and deployment of technologies that will lead to reduction of the costs and risks associated with cleaning up the nation's nuclear complex. Appendix C provides details about each of the Department's 82 high cost projects and lists the EMSP research awards with potential to impact each of these projects. The high cost projects listed are those having costs greater than $50 million in constant 1998 dollars from the year 2007 and beyond, based on the March 1998 Accelerating Cleanup: Paths to Closure Draft data, and having costs of quantities of material associated with an environmental management problem area. The high cost project information is grouped by operations office and organized by site and project code. Each operations office section begins with a list of research needs associated with that operations office. Potentially related research awards are listed by problem area in the Index of Research Awards by Environmental Management Problem Area, which can be found at the end of appendices B and C. For projects that address high risks to the public, workers, or the environment, refer also the Health/Ecology/Risk problem area awards. Research needs are programmatic or technical challenges that may benefit from knowledge gained through basic research

  15. Low level radioactive waste disposal siting: a social and technical plan for Pennsylvania. Volume 2. Socioeconomic analyses

    International Nuclear Information System (INIS)

    Aron, G.; Bord, R.J.; Clemente, F.A.; Dornsife, W.P.; Jarrett, A.R.; Jester, W.A.; Schmalz, R.F.; Witzig, W.F.

    1984-09-01

    Volume II comprises five chapters: Socioeconomic Screening Criteria for LLRW Facility Siting and An Application to Counties in Pennsylvania; Evaluating Public Participation Options for the Case of Low Level Radioactive Waste Siting in Pennsylvania; Potential Socioeconomic Impacts of a LLRW Facility in Pennsylvania; The Role of Community Incentives in Low Level Radioactive Waste Management; and Institutional Aspects of LLRW Site Development and Operations in Pennsylvania

  16. 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 ...

  17. Evaluation of economic and technical efficiency of diesel engines operation on the basis of volume combustion rate

    Directory of Open Access Journals (Sweden)

    І. О. Берестовой

    2016-11-01

    Full Text Available The article deals with a new approach to evaluation of complex efficiency of diesel engines. Traditionally, cylinder’s capacity, rotation frequency, average efficient pressure inside cylinder, piston’s stroke, average piston’s velocity, fuel specific consumption and other indices are used as generalizing criteria, characterizing diesel engine’s efficiency, but they do not reflect interrelation between engine’s complex efficiency and a set of economic, mass-dimensional, operational and ecological efficiency. The approach applied in the article makes it possible to reveal the existing and modify the existing methods of solving the problem of improving diesel engine’s efficiency with due regard to interrelation of the parameters, characterizing efficiency of their operation. Statistic analyses were carried out, on the basis of which an assumption regarding the existence of interrelation between specific fuel consumption and the analyzed engine’s parameters was made. Processing of statistical data for various analyzed functions of diesel engines helped offer a function, illustrating the link between volume combustion rate, piston’s area and nominal theoretical specific fuel consumption. Interrelation between volume combustion rate, nominal parameters of diesel operation and efficiency indices, obtained by processing statistical data of more than 500 models of diesels of different series was evaluated, the main feature of it being a mathematical trend. The analysis of the obtained function makes it possible to establish an interrelation between economic efficiency of a diesel, its main index being specific fuel consumption and volume combustion rate and design peculiarities

  18. Assessment of technical strengths and information flow of energy conservation research in Japan. Volume 2. Background document

    Energy Technology Data Exchange (ETDEWEB)

    Hane, G.J.; Lewis, P.M.; Hutchinson, R.A.; Rubinger, B.; Willis, A.

    1985-06-01

    Purpose of this study is to explore the status of R and D in Japan and the ability of US researchers to keep abreast of Japanese technical advances. US researchers familiar with R and D activities in Japan were interviewed in ten fields that are relevant to the more efficient use of energy: amorphous metals, biotechnology, ceramics, combustion, electrochemical energy storage, heat engines, heat transfer, high-temperature sensors, thermal and chemical energy storage, and tribology. The researchers were questioned about their perceptions of the strengths of R and D in Japan, comparative aspects of US work, and the quality of available information sources describing R and D in Japan. Of the ten related fields, the researchers expressed a strong perception that significant R and D is under way in amorphous metals, biotechnology, and ceramics, and that the US competitive position in these technologies will be significantly challenged. Researchers also identified alternative emphases in Japanese R and D programs in these areas that provide Japan with stronger technical capabilities. For example, in biotechnology, researchers noted the significant Japanese emphasis on industrial-scale bioprocess engineering, which contrasts with a more meager effort in the US. In tribology, researchers also noted the strength of the chemical tribology research in Japan and commented on the effective mix of chemical and mechanical tribology research. This approach contrasts with the emphasis on mechanical tribology in the US.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1987-10-15

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

  20. 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...

  1. Greater-than-Class C low-level waste characterization. Appendix I: Impact of concentration averaging low-level radioactive waste volume projections

    International Nuclear Information System (INIS)

    Tuite, P.; Tuite, K.; O'Kelley, M.; Ely, P.

    1991-08-01

    This study provides a quantitative framework for bounding unpackaged greater-than-Class C low-level radioactive waste types as a function of concentration averaging. The study defines the three concentration averaging scenarios that lead to base, high, and low volumetric projections; identifies those waste types that could be greater-than-Class C under the high volume, or worst case, concentration averaging scenario; and quantifies the impact of these scenarios on identified waste types relative to the base case scenario. The base volume scenario was assumed to reflect current requirements at the disposal sites as well as the regulatory views. The high volume scenario was assumed to reflect the most conservative criteria as incorporated in some compact host state requirements. The low volume scenario was assumed to reflect the 10 CFR Part 61 criteria as applicable to both shallow land burial facilities and to practices that could be employed to reduce the generation of Class C waste types

  2. Feasibility planning study for a behavior database. Volume III Appendix B, Compendium of survey questions on drinking and driving and occupant restraints

    Science.gov (United States)

    1987-04-01

    The general objective of the project was to determine the feasibility of and the general requirements for a centralized database on driver behavior and attitudes related to drunk driving and occupant restraints. Volume III is a compendium of question...

  3. Resource Conservation and Recovery Act, Part B permit application [of the Waste Isolation Pilot Plant (WIPP)]. Volume 11, Chapter D, Appendix D4--Chapter D, Appendix D17: Revision 3

    Energy Technology Data Exchange (ETDEWEB)

    1993-03-01

    This volume contains appendices D4 through D17 which cover the following: Waste Isolation Pilot Plant site environmental report; ecological monitoring program at the Waste Isolation Pilot Plant; site characterization; regional and site geology and hydrology; general geology; dissolution features; ground water hydrology; typical carbon sorption bed efficiency; VOC monitoring plan for bin-room tests; chemical compatibility analysis of waste forms and container materials; probable maximum precipitation; WHIP supplementary roof support system room 1, panel 1; and corrosion risk assessment of the Waste Isolation Pilot Plant ``humid`` test bins.

  4. Solar central receiver hybrid power system, Phase I. Volume 3. Appendices. Final technical report, October 1978-August 1979

    Energy Technology Data Exchange (ETDEWEB)

    None

    1979-09-01

    A design study for a central receiver/fossil fuel hybrid power system using molten salts for heat transfer and heat storage is presented. This volume contains the appendices: (A) parametric salt piping data; (B) sample heat exchanger calculations; (C) salt chemistry and salt/materials compatibility evaluation; (D) heliostat field coordinates; (E) data lists; (F) STEAEC program input data; (G) hybrid receiver design drawings; (H) hybrid receiver absorber tube thermal math model; (I) piping stress analysis; (J) 100-MWe 18-hour storage solar central receiver hybrid power system capital cost worksheets; and (K) 500-MWe 18-hour solar central receiver hybrid power system cost breakdown. (WHK)

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1976-08-10

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

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

    Energy Technology Data Exchange (ETDEWEB)

    Schwinkendorf, W.E.

    1984-09-01

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

  7. Regulatory and technical reports (abstract index journal): Compilation for third quarter 1994, July--September. Volume 19, Number 3

    International Nuclear Information System (INIS)

    1994-12-01

    This compilation consists of bibliographic data and abstracts for the formal regulatory and technical reports issues by the U.S. Nuclear Regulatory Commission (NRC) Staff and its contractors. It is NRC's intention to publish this compilation quarterly and to cumulate it annually. The main citations and abstracts in this compilation are listed in NUREG number order: NUREG-XXXX, NUREG/CP-XXXX, NUREG/CR-XXXX, and NUREG/IA-XXXX. These precede the following indexes: Secondary Report Number Index, Personal Author Index, Subject Index, NRC Originating Organization Index (Staff Reports), NRC Originating Organization Index (International Agreements), NRC Contract Sponsor Index (Contractor Reports) Contractor Index, International Organization Index, Licensed Facility Index. A detailed explanation of the entries precedes each index

  8. Regulatory and technical reports (abstract index journal): Compilation for third quarter 1996 July--September. Volume 21, Number 3

    International Nuclear Information System (INIS)

    1997-02-01

    This compilation consists of bibliographic data and abstracts for the formal regulatory and technical reports issued by the US Nuclear Regulatory Commission (NRC) Staff and its contractors. It is NRC's intention to publish this compilation quarterly and to cumulate it annually. The main citations and abstracts in this compilation are listed in NUREG number order: NUREG-XXXX, NUREG/CP-XXXX, NUREG/CR-XXXX, and NUREG/IA-XXXX. These precede the following indexes: secondary report number index; personal author index; subject index; NRC originating organization index (staff reports); NRC originating organization index (international agreements); NRC contract sponsor index (contractor reports); contractor index; international organization index; and licensed facility index. A detailed explanation of the entries precedes each index

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

    International Nuclear Information System (INIS)

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

    1976-01-01

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

  10. Regulatory and technical reports (abstract index journal): Compilation for third quarter 1996 July--September. Volume 21, Number 3

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-02-01

    This compilation consists of bibliographic data and abstracts for the formal regulatory and technical reports issued by the US Nuclear Regulatory Commission (NRC) Staff and its contractors. It is NRC`s intention to publish this compilation quarterly and to cumulate it annually. The main citations and abstracts in this compilation are listed in NUREG number order: NUREG-XXXX, NUREG/CP-XXXX, NUREG/CR-XXXX, and NUREG/IA-XXXX. These precede the following indexes: secondary report number index; personal author index; subject index; NRC originating organization index (staff reports); NRC originating organization index (international agreements); NRC contract sponsor index (contractor reports); contractor index; international organization index; and licensed facility index. A detailed explanation of the entries precedes each index.

  11. Regulatory and technical reports (abstract index journal): Compilation for third quarter 1994, July--September. Volume 19, Number 3

    Energy Technology Data Exchange (ETDEWEB)

    None

    1994-12-01

    This compilation consists of bibliographic data and abstracts for the formal regulatory and technical reports issues by the U.S. Nuclear Regulatory Commission (NRC) Staff and its contractors. It is NRC`s intention to publish this compilation quarterly and to cumulate it annually. The main citations and abstracts in this compilation are listed in NUREG number order: NUREG-XXXX, NUREG/CP-XXXX, NUREG/CR-XXXX, and NUREG/IA-XXXX. These precede the following indexes: Secondary Report Number Index, Personal Author Index, Subject Index, NRC Originating Organization Index (Staff Reports), NRC Originating Organization Index (International Agreements), NRC Contract Sponsor Index (Contractor Reports) Contractor Index, International Organization Index, Licensed Facility Index. A detailed explanation of the entries precedes each index.

  12. Technical procedures for water resources: Volume 3, Environmental Field Program, Deaf Smith County Site, Texas: Final draft

    International Nuclear Information System (INIS)

    1987-08-01

    To ensure that the environmental field program comprehensively addresses the issues and requirements of the project, a site study plan (SSP) has been prepared for Water Resources (ONWI, 1987). This technical procedure (TP) has been developed to implement the field program described in the Water Resources Site Study Plan. This procedure provides the general method for the field collection of water and sediment samples from playa lakes using an Alpha horizontal type sampler or equivalent or a peristaltic pump for water and a KB-coring devise or ponar grab for sediments. The samples will be preserved and then shipped to a laboratory for analysis. The water quality and sediment samples will be collected as part of the surface-water quality field study described in the Site Plan for Water Resources. 15 refs., 5 figs., 3 tabs

  13. Draft Environmental Impact Statement for the Nevada Test Site and off-site locations in the State of Nevada. Volume 1, Appendix I: Transportation study

    International Nuclear Information System (INIS)

    1996-01-01

    This report has been prepared to address local issues concerning current and potential operations at the Nevada Test Site (NTS), to document the results of the NTS transportation risk analysis, and to provide information and supporting documentation for the NTS Environmental Impact Statement (EIS). Stakeholders have identified transportation, health, and safety issues as their paramount concern. In response to these concerns, the US Department of Energy, Nevada Operations Office (DOE/NV) solicited and received input from the public through public meetings and in meetings with federal, state, local, and tribal organizations; and commissioned a transportation risk analysis. The stakeholders and DOE went on to establish the Transportation Protocol Working Group and Big Group to further discuss transportation issues associated with NTS transportation activities. This study used two different models: ADROIT for Defense Program activities and a RADTRAN-like model for waste management activities. Because of national security concerns associated with special nuclear material, the DOE has developed ADROIT to assist in defining the potential risk associated with Defense Program transportation activities. RADTRAN is a computer model which analyzes data without exposing the steps taken to reach the end result. So the public could see every step in the process, a RADTRAN-like model was used. This model is composed of a combination of spreadsheet and FORTRAN codes, that can be used by the stakeholder on a personal computer. This model is available to the public upon request. A detailed discussion of the results of the model are contained in this Appendix

  14. Report on the remedial investigation of Bear Creek Valley at the Oak Ridge Y-12 Plant, Oak Ridge, Tennessee. Volume 6: Appendix G -- Baseline ecological risk assessment 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 G contains ecological risks for fish, benthic invertebrates, soil invertebrates, plants, small mammals, deer, and predator/scavengers (hawks and fox). This risk assessment identified significant ecological risks from chemicals in water, sediment, soil, and shallow ground water. Metals and PCBs are the primary contaminants of concern.

  15. Technical and economic assessment of fluidized-bed-augmented compressed-air energy-storage system. Volume I. Executive summary

    Energy Technology Data Exchange (ETDEWEB)

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

    1981-09-01

    An energy storage system which could be attractive for future electric utility peak-load applications is a modified gas turbine power system utilizing underground storage of very high pressure air. The compressed air energy storage (CAES) concept involves using off-peak electricity generated from indigenous coal or nuclear sources to compress air, storing the air in large underground facilities, and withdrawing the air during peak-load periods when it would be heated by combustion and expanded through gas turbines to generate power. The attractiveness of the CAES concept is based upon its potential to supply competitively priced peaking energy, to reduce peak-load power plant dependence on petroleum-based fuels, and to provide a means for leveling the utility system load demand. Therefore, a technical and economic assessment of coal-fired fluidized bed (FBC) combustor/compressed air energy storage (FBC/CAES) systems was performed and is described. The conclusions drawn from the FBC/CAES study program are encouraging. They indicate that pressurized FBC/CAES power plants should be technologically feasible, provide good performance, and be economically competitive. Specifically, it is concluded that: coal-fired FBC/CAES systems should be technically feasible in the near future and potentially attractive for peak-load power generation; and an open-bed PFBC/CAES configuration would provide the best candidate for early commercialization. It has relatively low risk combined with moderate cost and reasonable round-trip heat rate. It also has the potential for future growth options which tend to reduce costs and lower fuel consumption.

  16. 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.

  17. 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

  18. Department of Energy Programmatic Spent Nuclear Fuel Management and Idaho National Engineering Laboratory Environmental Restoration and Waste Management Programs. Final Environmental Impact Statement: Volume 1, Appendix L, Environmental Justice

    International Nuclear Information System (INIS)

    1995-04-01

    Appendix L provides an assessment of the areas surrounding the 10 sites under consideration for the management of spent nuclear fuels (SNF) under all programmatic alternatives considered in this volume. It is divided into two sections: (a) the five sites considered for the management of DOE naval SNF only (under the No Action and Decentralization alternatives, and (b) the five DOE sites being considered for the management of all types of DOE SNF under all alternatives. The five sites considered for the management of naval SNF only are the Norfolk Naval Shipyard, Portsmouth, Virginia; Portsmouth Naval Shipyard, Kittery, Maine; Pearl Harbor Naval Shipyard, Honolulu, Hawaii; Puget Sound Naval Shipyard, Bremerton, Washington; and Kesselring Site, West Milton, New York. The five DOE sites considered for the management of some portion or all DOE SNF are the Savannah River Site, Aiken, South Carolina; Oak Ridge Reservation, Oak Ridge, Tennessee; Idaho National Engineering Laboratory, Idaho Falls, Idaho; Hanford Site, Richland, Washington; and Nevada Test Site, Mercury, Nevada. This assessment includes potential adverse impacts resulting from both onsite activities and associated transportation of materials. Based on this assessment, it is concluded that none of the alternatives analyzed results in disproportionately high and adverse effects on minority populations or low-income communities surrounding any of the sites under consideration for the management of SNF or associated offsite transportation routes

  19. Total energy cycle assessment of electric and conventional vehicles: an energy and environmental analysis. Volume 1: technical report

    Energy Technology Data Exchange (ETDEWEB)

    Cuenca, R.; Formento, J.; Gaines, L.; Marr, B.; Santini, D.; Wang, M. [Argonne National Lab., IL (United States); Adelman, S.; Kline, D.; Mark, J.; Ohi, J.; Rau, N. [National Renewable Energy Lab., Golden, CO (United States); Freeman, S.; Humphreys, K.; Placet, M. [Pacific Northwest National Lab., Richland, WA (United States)

    1998-01-01

    This report compares the energy use, oil use and emissions of electric vehicles (EVs) with those of conventional, gasoline-powered vehicles (CVs) over the total life cycle of the vehicles. The various stages included in the vehicles` life cycles include vehicle manufacture, fuel production, and vehicle operation. Disposal is not included. An inventory of the air emissions associated with each stage of the life cycle is estimated. Water pollutants and solid wastes are reported for individual processes, but no comprehensive inventory is developed. Volume I contains the major results, a discussion of the conceptual framework of the study, and summaries of the vehicle, utility, fuel production, and manufacturing analyses. It also contains summaries of comments provided by external peer reviewers and brief responses to these comments.

  20. Technical analysis of volume-rendering algorithms: application in low-contrast structures using liver vascularisation as a model

    International Nuclear Information System (INIS)

    Cademartiri, Filippo; Luccichenti, Giacomo; Runza, Giuseppe; Bartolotta, Tommaso Vincenzo; Midiri, Massimo; Gualerzi, Massimo; Brambilla, Lorenzo; Coruzzi, Paolo; Soliani, Paolo; Sianesi, Mario

    2005-01-01

    Purpose: To assess the influence of pre-set volume rendering opacity curves (OC) on image quality and to identify which absolute parameters (density of aorta, hepatic parenchyma and portal vein) affect visualization of portal vascular structures (low-contrast structures). Materials and methods: Twenty-two patients underwent a dual-phase spiral CT with the following parameters: collimation 3 mm, pitch 2, increment 1 mm. Three scans were performed: one without contrast medium and the latter two after the injection of contrast material (conventionally identified as 'arterial' and 'portal'). The images were sent to a workstation running on an NT platform equipped with post-processing software allowing three-dimensional (3D) reconstructions to generate volume-rendered images of the vascular supply to the liver. Correlation between the absolute values of aorta, liver and portal vein density, OC parameters, and image quality were assessed. Results: 3D images generated using pre-set OC obtained a much mower overall quality score than those produced with OC set by the operator. High contrast between the liver and the portal vein, for example during the portal vascular phase, allows wider windows, thus improving image quality. Conversely, the OC in the parenchymal phase scans must have a high gradient in order to better differentiate between the vascular structures and the surrounding hepatic parenchyma. Conclusions: Image features considered to be of interest by the operator cannot be simplified by the mean of pre-set OC. Due to their strong individual variability automatic 3D algorithms cannot be universally applied: they should be adapted to both image and patient characteristics [it

  1. Industrial Sector Technology Use Model (ISTUM): industrial energy use in the United States, 1974-2000. Volume 4. Technology appendix. Final Report

    Energy Technology Data Exchange (ETDEWEB)

    1979-10-01

    Volume IV of the ISTUM documentation gives information on the individual technology specifications, but relates closely with Chapter II of Volume I. The emphasis in that chapter is on providing an overview of where each technology fits into the general-model logic. Volume IV presents the actual cost structure and specification of every technology modeled in ISTUM. The first chapter presents a general overview of the ISTUM technology data base. It includes an explanation of the data base printouts and how the separate-cost building blocks are combined to derive an aggregate-technology cost. The remaining chapters are devoted to documenting the specific-technology cost specifications. Technologies included are: conventional technologies (boiler and non-boiler conventional technologies); fossil-energy technologies (atmospheric fluidized bed combustion, low Btu coal and medium Btu coal gasification); cogeneration (steam, machine drive, and electrolytic service sectors); and solar and geothermal technologies (solar steam, solar space heat, and geothermal steam technologies), and conservation technologies.

  2. 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.

  3. 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.

  4. Critical evaluation of the nonradiological environmental technical specifications. Volume 3. Peach Bottom Atomic Power Station Units 2 and 3

    International Nuclear Information System (INIS)

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

    1976-01-01

    A comprehensive study of the data collected as part of the environmental Technical Specifications program for Units 2 and 3 of the Peach Bottom Nuclear Power Plant was conducted for the Office of Regulatory Research of the U.S. Nuclear Regulatory Commission. The program included an analysis of both the hydrothermal and ecological monitoring data collected from 1967 through 1976. Specific recommendations are made for improving both the present hydrothermal and ecological monitoring programs. Hydrothermal monitoring would be improved by more complete reporting of in-plant operating parameters. In addition, the present boat surveys could be discontinued, and monitoring efforts could be directed toward expanding the present thermograph network. Ecological monitoring programs were judged to be of high quality because standardized collection techniques, consistent reporting formats, and statistical analyses were performed on all of the data and were presented in an annual report. Sampling for all trophic groups was adequate for the purposes of assessing power plant induced perturbations. Considering the extensive period of preoperational data (six years) and operational data (three years) available for analysis, consideration could be given to reducing monitoring effort after data have been collected for a period when both units are operating at full capacity. In this way, an assessment of the potential ecological impact of the Peach Bottom facility can be made under conditions of maximum plant induced perturbations

  5. DOE standard: Integration of environment, safety, and health into facility disposition activities. Volume 1 of 2: Technical standard

    International Nuclear Information System (INIS)

    1998-05-01

    This Department of Energy (DOE) technical standard (referred to as the Standard) provides guidance for integrating and enhancing worker, public, and environmental protection during facility disposition activities. It provides environment, safety, and health (ES and H) guidance to supplement the project management requirements and associated guidelines contained within DOE O 430.1A, Life-Cycle Asset Management (LCAM), and amplified within the corresponding implementation guides. In addition, the Standard is designed to support an Integrated Safety Management System (ISMS), consistent with the guiding principles and core functions contained in DOE P 450.4, Safety Management System Policy, and discussed in DOE G 450.4-1, Integrated Safety Management System Guide. The ISMS guiding principles represent the fundamental policies that guide the safe accomplishment of work and include: (1) line management responsibility for safety; (2) clear roles and responsibilities; (3) competence commensurate with responsibilities; (4) balanced priorities; (5) identification of safety standards and requirements; (6) hazard controls tailored to work being performed; and (7) operations authorization. This Standard specifically addresses the implementation of the above ISMS principles four through seven, as applied to facility disposition activities

  6. Plutonium working group report on environmental, safety and health vulnerabilities associated with the Department's plutonium storage. Volume 2, Appendix A: Process and protocol

    International Nuclear Information System (INIS)

    1994-09-01

    This appendix contains documentation prepared by the Plutonium ES and H Vulnerability Working Group for conducting the Plutonium ES and H Vulnerability Assessment and training the assessment teams. It has the following five parts. (1) The Project Plan describes the genesis of the project, sets forth the goals, objectives and scope, provides definitions, the projected schedule, and elements of protocol. (2) The Assessment Plan provides a detailed methodology necessary to guide the many professionals who have been recruited to conduct the DOE-wide assessment. It provides guidance on which types and forms of plutonium are to be considered within the scope of the assessment, and lays out the assessment methodology to be used. (3) The memorandum from the Project to Operations Office Managers provides the protocol and direction for participation in the assessment by external stakeholders and members of the public; and the guidance for the physical inspection of plutonium materials in storage. (4) The memorandum from the Project to the assessment teams provides guidance for vulnerability screening criteria, vulnerability evaluation and prioritization process, and vulnerability quantification for prioritization. (5) The Team Training manual was used at the training session held in Colorado Springs on April 19--21, 1994 for all members of the Working Group Assessment Teams and for the leaders of the Site Assessment Teams. The goal was to provide the same training to all of the individuals who would be conducting the assessments, and thereby provide consistency in the conduct of the assessments and uniformity in reporting of the results. The training manual in Section A.5 includes supplemental material provided to the attendees after the meeting

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

    International Nuclear Information System (INIS)

    1978-04-01

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

  8. District heating and cooling systems for communities through power plant retrofit distribution network, Phase 2. Final report, March 1, 1980-January 31, 1984. Volume 5, Appendix A

    Energy Technology Data Exchange (ETDEWEB)

    1984-01-31

    This volume contains the backup data for the portion of the load and service assessment in Section 2, Volume II of this report. This includes: locations of industrial and commercial establishments, locations of high rise buildings, data from the Newark (Essex County) Directory of Business, data from the Hudson County Industrial Directory, data from the N. J. Department of Energy Inventory of Public Buildings, data on commercial and industrial establishments and new developments in the Hackensack Meadowlands, data on urban redevelopment and Operation Breakthrough, and list of streets in the potential district heating areas of Newark/Harrison and Jersey City/Hoboken.

  9. Critical evaluation of the nonradiological environmental technical specifications. Volume 2. Surry Power Plants, Units 1 and 2

    International Nuclear Information System (INIS)

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

    1976-01-01

    A comprehensive study of the data collected as part of the environmental Technical Specifications program for Units 1 and 2 of the Surry Nuclear Power Plant was carried out for the Office of Regulatory Research of the U.S. Nuclear Regulatory Commission. The program included an analysis of the hydrothermal and ecological monitoring data collected from 1973 through 1975. The hydrothermal analysis includes a discussion of models used in plume predictions prior to plant operation and an evaluation of the present hydrothermal monitoring program. The two primary methods used for temperature monitoring employ a fixed thermographs network and boat measurements. Review of data indicates that both the application and formulation of the hydrothermal monitoring program are inadequate to fully characterize the operation of the plant and the behavior of the thermal plume. Furthermore, there are no existing data that can be used to adequately verify or disprove the validity of the various Surry plume predictions. The ecological analysis includes validation of impacts predicted in the Final Environmental Statement using the operational monitoring data. Phytoplankton cell concentrations, chlorophyll a, and carbon-14 measurements were used to monitor changes in the primary producers. Densities of consumers (i.e., zooplankton, benthos, and fish) were sed to monitor changes in the primary producers. Models based on operating data were constructed to determine whether changes were occurring at each trophic level. Analysis of the monitoring data suggests that the thermal discharges at Surry are having a negative effect on the phytoplankton and zooplankton but are enhancing the benthic and nekton populations in the discharge area

  10. Development of whole-building energy design targets for commercial buildings: Phase 1, Planning: Volume 2, Technical report

    Energy Technology Data Exchange (ETDEWEB)

    Crawley, D.B.; Briggs, R.S.; Jones, J.W.; Seaton, W.W.; Kaufman, J.E.; Deringer, J.J.; Kennett, E.W.

    1987-08-01

    This is the second volume of the Phase 1 report and discusses the 10 tasks performed in Phase 1. The objective of this research is to develop a methodology for setting energy design targets to provide voluntary guidelines for the buildings industry. The whole-building energy targets project is being conducted at the Pacific Northwest Laboratory (PNL) for the US Department of Energy (DOE) to encourage the construction of energy-efficient buildings by informing designers and owners about cost-effective goals for energy use in new commercial buildings. The outcome of this research will be a flexible methodology for setting such targets. The tasks are listed and discussed in this report as follows: Task 1 - Develop Detailed Project Goals and Objectives; Task 2 - Establish Buildings-Industry Liaison; Task 3 - Develop Approaches to the Energy Targets Model, Building Operations, and Climate; Task 4 - Develop an Approach for Treating Economic Considerations; Task 5 - Develop an Approach for Treating Energy Sources; Task 6 - Collect Energy-Use Data; Task 7 - Survey Energy Expert Opinion; Task 8 - Evaluation Procedure Specification and Integration; Task 9 - Phase 1 Report Development; and Task 10 - Phase 1 Review Planning.

  11. Analysis of space systems for the space disposal of nuclear waste follow-on study. Volume 2. Technical report

    International Nuclear Information System (INIS)

    1982-01-01

    Some of the conclusions reached as a result of this study are summarized. Waste form parameters for the reference cermet waste form are available only by analogy. Detail design of the waste payload would require determination of actual waste form properties. The billet configuration constraints for the cermet waste form limit the packing efficiency to slightly under 75% net volume. The effect of this packing inefficiency in reducing the net waste form per waste payload can be seen graphically. The cermet waste form mass per unit mass of waste payload is lower than that of the iodine waste form even though the cermet has a higher density (6.5 versus 5.5). This is because the lead iodide is cast achieving almost 100% efficiency in packing. This inefficiency in the packing of the cermet results in a 20% increase in number of flights which increases both cost and risk. Alternative systems for waste mixes requiring low flight rates (technetium-99, iodine-129) can make effective use of the existing 65K space transportation system in either single- or dual-launch scenarios. A comprehensive trade study would be required to select the optimum orbit transfer system for low-launch-rate systems. This study was not conducted as part of the present effort due to selection of the cermet waste form as the reference for the study. Several candidates look attractive for both single- and dual-launch systems (see sec. 4.4), but due to the relatively small number of missions, a comprehensive comparison of life cycle costs including DDT and E would be required to select the best system. The reference system described in sections 5.0, 6.0, 7.0, and 8.0 offers the best combination of cost, risk, and alignment with ongoing NASA technology development efforts for disposal of the reference cermet waste form

  12. Great Lakes and St. Lawrence Seaway Navigation Season Extension. Volume 3. Appendix C. Public Views and Responses on the Report and Environmental Impact Statement

    Science.gov (United States)

    1979-08-01

    current economic conditions; - The use of a ship trafflc volume projection and a cargo wix that may possibly result in an overstatement of beneftzs-due...34 Web r’ecommend "no action" as the program to adopt; i.e., halting ice breaking activities writil environmental baseline data can be collected...spawning sites and aquatic food webs During 1976, we were all made painfully aware of the problem shipping can bring to the enviornmrent of The River

  13. 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)

  14. Supplement to the Final Environmental Statement related to the decommissioning of the Rare Earths Facility, West Chicago, Illinois (Docket No. 40-2061): Volume 2, Appendix H

    International Nuclear Information System (INIS)

    1989-04-01

    This Supplement to the Final Environmental Statement is issued by the US Nuclear Regulatory Commission in response to the Atomic Safety and Licensing Board's ruling that the staff must supplement the Final Environmental Statement in order to evaluate the impact of permanent disposal of the Kerr-McGee Rare Earths Facility wastes located at West Chicago, Illinois. The statement considers the Kerr-McGee preferred plan and various alternatives to the plan. The action proposed by the Commission is the renewal of the Kerr-McGee license to allow disposal of wastes onsite and for possession of the wastes under license for an indeterminate time. The license could be terminated at a later date if certain specified requirements were met. NUREG-0904 was published in draft for comment in June 1987. Comments have been received and are published with their responses in this report. Volume 1 contains the main text and Appendices A thru G. Volume 2 contains the comments received and their responses

  15. Field grouting summary report on the WAG 4 seeps 4 and 6 removal action project, Oak Ridge National Laboratory, Oak Ridge, Tennessee. Volume 2: Appendixes A--D

    International Nuclear Information System (INIS)

    1997-05-01

    During the summer of 1996, a unique multi-phase, multi-stage, low-pressure permeation grouting pilot program was performed inside portions of four unlined waste disposal trenches at Waste Area Grouping (WAG) 4 at Oak Ridge National Laboratory (ORNL) in Oak Ridge, Tennessee. The project was deemed a non-time-critical removal action under the Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA); however, due to a history of heavy precipitation in the fall, the schedule was fast-tracked to meet an October 31, 1996 grouting completion data. The technical objective of the removal action was to reduce the off-site transport of Strontium 90 ( 90 Sr) by grouting portions of four waste disposal trenches believed to be responsible for over 70% of the 90 Sr leaving the site. A goal of the grouting operation was to reduce the average in situ hydraulic conductivity of the grouted waste materials to a value equal to or less than 1 X 10 -6 cm/sec. This target hydraulic conductivity value was established to be at least two orders of magnitude lower than that of the surrounding natural ground. The main report describes brief background to the project, describes and analyzes the grouting operations, draws conclusions from the work performed, and presents some of the lessons learned. Appendices contain: (A) pipe driving records; (B) casing grout injection records; (C) in-situ hydraulic conductivity testing records; and (D) grout quality control testing records

  16. Field grouting summary report on the WAG 4 seeps 4 and 6 removal action project, Oak Ridge National Laboratory, Oak Ridge, Tennessee. Volume 3. Appendixes E and F

    International Nuclear Information System (INIS)

    1997-05-01

    During the summer of 1996, a unique multi-phase, multi-stage, low-pressure permeation grouting pilot program was performed inside portions of four unlined waste disposal trenches at Waste Area Grouping (WAG) 4 at Oak Ridge National Laboratory (ORNL) in Oak Ridge, Tennessee. The project was deemed a non-time-critical removal action under the Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA); however, due to a history of heavy precipitation in the fall, the schedule was fast-tracked to meet an October 31, 1996 grouting completion date. The technical objective of the removal action was to reduce the off-site transport of j Strontium 90 ( 90 Sr) by grouting portions of four waste disposal trenches believed to be responsible for over 70 percent of the 90 Sr leaving the site. A goal of the grouting operation was to reduce the average in situ hydraulic conductivity of the grouted waste materials to a value equal to or less than 1 x 10 -6 cm/sec. This target hydraulic conductivity value was established to be at least two orders of magnitude lower than that of the surrounding natural ground

  17. Field grouting summary report on the WAG 4 seeps 4 and 6 removal action project, Oak Ridge National Laboratory, Oak Ridge, Tennessee. Volume 3. Appendixes E and F

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-05-01

    During the summer of 1996, a unique multi-phase, multi-stage, low-pressure permeation grouting pilot program was performed inside portions of four unlined waste disposal trenches at Waste Area Grouping (WAG) 4 at Oak Ridge National Laboratory (ORNL) in Oak Ridge, Tennessee. The project was deemed a non-time-critical removal action under the Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA); however, due to a history of heavy precipitation in the fall, the schedule was fast-tracked to meet an October 31, 1996 grouting completion date. The technical objective of the removal action was to reduce the off-site transport of j Strontium 90 ({sup 90}Sr) by grouting portions of four waste disposal trenches believed to be responsible for over 70 percent of the {sup 90}Sr leaving the site. A goal of the grouting operation was to reduce the average in situ hydraulic conductivity of the grouted waste materials to a value equal to or less than 1 x 10{sup -6} cm/sec. This target hydraulic conductivity value was established to be at least two orders of magnitude lower than that of the surrounding natural ground.

  18. 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)

  19. Ocean thermal energy conversion power system development-I. Preliminary design report. Volume 3. Appendixes D, E, and F. Phase I. Final report

    Energy Technology Data Exchange (ETDEWEB)

    1978-12-18

    The conceptual design of a 40 to 50 MW closed cycle ammonia OTEC commercial plant, the preliminary design of a 10 MW OTEC module analogous to the 50 MW module, and the preliminary design of heat exchanger test articles (evaporator and condenser) representative of the 50 MW heat exchangers for testing in OTEC-1 are presented. This volume includes the appendices: D) system equipment (hardware breakdown structure; 10-MW hardware listing; list of support and maintenance equipment, tools and spare parts; sacrificial anodes; M.A.N. brush; and Alclad 3004 data); E) heat exchanger supporting data (analyses/configuration, contract tooling, manufacturing plan, specification, and evaporator ammonia liquid distribution system); and F) rotating machinery (performance characteristics, radial inflow turbine; item descriptions; weight calculation-rotor; producibility analysis; long lead-time items; spares; support equipment; non recurring costs; performance characteristics-axial flow turbine; Worthington pump data; and American M.A.N. Corporation data). Also included is attachment 1 to the phase I final report which presents details of the system modeling; design, materials considerations, and systems analysis of the baseline module; system cost analysis; and supporting data. (WHK)

  20. Remedial investigation/feasibility study of the Clinch River/Poplar Creek Operable Unit. Volume 3. Risk assessment information. Appendixes E, F

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-03-01

    This report presents the findings of an investigation into contamination of the Clinch River and Poplar Creek near the U.S. Department of Energy`s (DOE`s) Oak Ridge Reservation (ORR) in eastern Tennessee. For more than 50 years, various hazardous and radioactive substances have been released to the environment as a result of operations and waste management activities at the ORR. In 1989, the ORR was placed on the National Priorities List (NPL), established and maintained under the federal Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA). Under CERCLA, NPL sites must be investigated to determine the nature and extent of contamination at the site, assess the risk to human health and the environment posed by the site, and, if necessary, identify feasible remedial alternatives that could be used to clean the site and reduce risk. To facilitate the overall environmental restoration effort at the ORR, CERCLA activities are being implemented individually as distinct operable units (OUs). This document is Volume 3 of the combined Remedial Investigation and Feasibility Study Report for the Clinch River/Poplar Creek OU.

  1. Remedial investigation/feasibility study of the Clinch River/Poplar Creek Operable Unit. Volume 5. Appendixes J, K, L, M, and N-other supporting information

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-06-01

    This report presents the findings of an investigation into contamination of the Clinch River and Poplar Creek near the U.S. Department of Energy`s (DOE`s) Oak Ridge Reservation (ORR) in eastern Tennessee. For more than 50 years, various hazardous and radioactive substances have been released to the environment as a result of operations and waste management activities at the ORR. In 1989, the ORR was placed on the National Priorities List (NPL), established and maintained under the federal Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA). Under CERCLA, NPL sites must be investigated to determine the nature and extent of contamination at the site, assess the risk to human health and the environment posed by the site, and, if necessary, identify feasible remedial alternatives that could be used to clean the site and reduce risk. To facilitate the overall environmental restoration effort at the ORR, CERCLA activities are being implemented individually as distinct operable units (OUs). This document is Volume 5 of the combined Remedial Investigation and Feasibility Study Report for the Clinch River/Poplar Creek OU.

  2. 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

  3. 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.

  4. 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.

  5. 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

  6. 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...

  7. 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...

  8. 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)

  9. SOLID WASTE INTEGRATED FORECAST TECHNICAL (SWIFT) REPORT FY2003 THRU FY2046 VERSION 2003.1 VOLUME 1 [SECTION 1 and 2

    International Nuclear Information System (INIS)

    BARCOT, R.A.

    2003-01-01

    The SWIFT Report provides up-to-date life cycle information about the radioactive solid waste expected to be managed by Hanford's Waste Management (WM) Project from onsite and offsite generators. This SWIFT report is a mid-year update to the SWIFT 2003.0 report that was published in January 2003. The SWIFT Report is published in two volumes. SWIFT Volume II provides detailed analyses of the data, graphical representation, comparison to previous years, and waste generator specific information. The data contained in this report are the official data for solid waste forecasting. In this revision, the volume numbers have been switched to reflect the timing of their release. This particular volume provides the following data reports: Summary volume data by DOE Office, company, and location; Annual volume data by waste generator; Annual waste specification record and physical waste form volume; Radionuclide activities and dose-equivalent curies; and Annual container type data by volume and count

  10. 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)

  11. Tritium Systems Test Facility. Volume II. Appendixes

    International Nuclear Information System (INIS)

    Anderson, G.W.; Battleson, K.W.; Bauer, W.

    1976-10-01

    This document includes the following appendices: (1) vacuum pumping, (2) tritium migration into the power cycle, (3) separation of hydrogen isotopes, (4) tritium research laboratory, (5) TSTF containment and cleanup, (6) instrumentation and control, (7) gas heating in torus, and (8) TSTF fuel loop operating procedures

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

    Science.gov (United States)

    1984-11-01

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

  13. Draft environmental impact statement on a proposed nuclear weapons nonproliferation policy concerning foreign research reactor spent nuclear fuel: Volume 2, Appendix E, Evaluation of human health effects of overland transportation

    International Nuclear Information System (INIS)

    1995-03-01

    This Appendix provides an overview of the approach used to assess the human health risks that may result from the overland transportation of foreign research reactor spent nuclear fuel. The Appendix includes discussion of the scope of the assessment, analytical methods used for the risk assessment (i.e., computer models), important assessment assumptions, determination of potential transportation routes, and presents the results of the assessment. In addition, to aid in the understanding and interpretation of the results, specific arm of uncertainty are described, with an emphasis an how the uncertainties may affect comparisons of the alternatives. he approach used in this Appendix is modeled after that used in the Programmatic Spent Nuclear Fuel Management and Idaho National Engineering Laboratory Draft Environmental Impact Statement (SNF ampersand INEL Draft EIS) (DOE, 1994b). The SNF ampersand INEL Draft EIS did not perform as detailed an analysis on the specific actions taken for foreign research reactor spent nuclear fuel because of the breadth necessary to analyze the entire spent fuel management program. However, the fundamental assumptions used in this analysis are consistent with those used in the SNF ampersand INEL Draft EIS (DOE, 1994b), and the same computer codes and generic release and accident data are used. The risk assessment results are presented in this Appendix in terms of ''Per-shipment'' risk factors, as well as for the total risks associated with each alternative. Per-shipment risk factors provide an estimate of the risk from a single spent nuclear fuel shipment between a specific origin and destination. They are calculated for all possible origin and destination pairs for each spent nuclear fuel type. The total risks for a given alternative are found by multiplying the expected number of shipments by the appropriate per-shipment risk factors. This approach provides maximum flexibility for determining the risks for a large number of potential

  14. Comparison of different application systems and CT- assisted treatment planning procedures in primary endometrium cancer: Is it technically possible to include the whole uterus volume in the volume treated by brachytherapy

    International Nuclear Information System (INIS)

    Mock, U.; Knocke, Th.; Fellner, C.; Poetter, R.

    1996-01-01

    Purpose: Brachytherapy is regarded as the definitive component of treatment for inoperable patients with endometrium cancer. In published series the whole uterus has been claimed to represent the target volume independently of the individual tumor spread. The purpose of this work is to compare different planning and application procedures and to analyze the target volumes (whole uterus), treatment volumes and their respective relation for the given various conditions. Material and Methods: In ten patients with primary endometrium cancer the correlation between target- and treatment volume was analysed based on standard one-channel applicators or individual Heyman applicators. A comparative analysis of target volumes resulting from two different planning procedures of Heyman applications was performed. CT was carried out after insertion of the Heyman ovoids. Target volume was estimated by measuring the uterus size at different cross sections of the CT images. Dose calculation was performed with (PLATO-system) or without (NPS-system) transferring these data directly to the planning system. We report on the differences in treatment volumes resulting from the two application and planning systems. Results: The mean value of the uterus volume was 180 ccm (range 57 ccm to 316 ccm). Four out of 10 patients had an asymmetric uterus configuration with a side-difference (in longitudinal or transversal direction) of more than 1 cm. On average 70% (range 48-95%) of the uterus volume was included by the treatment volume when Heymann applicators were used compared to 45 % (range 25-89%) when standard one channel applicators were used. This represents an improvement of 25% (range from 11%-35%). By utilizing the more sophisticated way of treatment planning a more adequate coverage of the uterus volume was achieved in five out of ten patients. The treated volume increased on the average by 20 % (range 11 %-32%). In three cases changes in the irradiation volume were less than 5%. In

  15. Supplemental technical information in support of Y/OWI/TM--44. Volume 17. Drawings for repository preconceptual design studies: BPNL waste forms in salt

    International Nuclear Information System (INIS)

    1978-04-01

    Volume 17 contains drawings of a preconceptual design for a nuclear waste storage facility in salt. Three full cycles are considered: full recycle, throwaway cycle, and uranium recycle with plutonium in high-level waste

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

    International Nuclear Information System (INIS)

    Monteleone, S.

    1998-03-01

    This three-volume report contains papers presented at the conference. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included papers presented by researchers from France, Japan, Norway, and Russia. The titles of the papers and the names of the authors have been updated and may differ from those that appeared in the final program of the meeting. This volume contains the following: (1) human reliability analysis and human performance evaluation; (2) technical issues related to rulemakings; (3) risk-informed, performance-based initiatives; and (4) high burn-up fuel research

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1998-03-01

    This three-volume report contains papers presented at the conference. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included papers presented by researchers from France, Japan, Norway, and Russia. The titles of the papers and the names of the authors have been updated and may differ from those that appeared in the final program of the meeting. This volume contains the following: (1) human reliability analysis and human performance evaluation; (2) technical issues related to rulemakings; (3) risk-informed, performance-based initiatives; and (4) high burn-up fuel research. Selected papers have been indexed separately for inclusion in the Energy Science and Technology Database.

  18. Technical Specifications: Vogtle Electric Generating Plant, Unit Nos. 1 and 2 (Docket Nos. 50-424 and 50-425): Appendix ''A'' to License Nos. NPF-68 and NPF-79

    International Nuclear Information System (INIS)

    1989-02-01

    The Vogtle Electric Generating Plant, Unit Nos. 1 and 2, Technical Specifications were prepared by the US Nuclear Regulatory Commission to set forth the limits, operating conditions, and other requirements applicable to a nuclear facility as set forth in Section 50.36 of 10 CFR 50 for the protection of the health and safety of the public

  19. Technical Specifications, Vogtle Electric Generating Plant, Unit Nos. 1 and 2 (Docket Nos. 50-424 and 50-425): Appendix ''A'' to License Nos. NPF-68 and NPF-81

    International Nuclear Information System (INIS)

    1989-03-01

    The Vogtle Electric Generating Plant, Unit Nos. 1 and 2, Technical Specifications were prepared by the US Nuclear Regulatory Commission to set forth the limits, operating conditions, and other requirements applicable to a nuclear facility as set forth in Section 50.36 of 10 CFR 50 for the protection of the health and safety of the public

  20. Technical specifications, Braidwood Station Unit Nos. 1 and 2 (Docket Nos. STN 50-456 and STN 50-457): Appendix ''A'' to License No. NPF-72, [October 1986-July 1987

    International Nuclear Information System (INIS)

    1987-07-01

    The Braidwood Station, Units 1 and 2, 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 Part 50 for the protection of the health and safety of the public

  1. Technical Specifications, South Texas Project, Unit Nos. 1 and 2 (Docket Nos. 50-498 and 50-499): Appendix ''A'' to License Nos. NPF-76 and NPF-80

    International Nuclear Information System (INIS)

    1989-03-01

    The South Texas Project, Unit Nos. 1 and 2, 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 Part 50 for the protection of the health and safety of the public

  2. Technical specifications, South Texas Project, Unit Nos. 1 and 2 (Docket Nos. 50-498 and 50-499): Appendix ''A'' to License Nos. NPF-76 and NPF-78

    International Nuclear Information System (INIS)

    1989-01-01

    The South Texas Project, Unit Nos. 1 and 2, 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 Part 50 for the protection of the health and safety of the public

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1994-11-01

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

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

    International Nuclear Information System (INIS)

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

    1994-11-01

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

  5. 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

  6. 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.

  7. 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

  8. Magnetic fusion energy plasma interactive and high heat flux components. Volume I. Technical assessment of the critical issues and problem areas in the plasma materials interaction field

    International Nuclear Information System (INIS)

    Conn, R.W.; Gauster, W.B.; Heifetz, D.; Marmar, E.; Wilson, K.L.

    1984-01-01

    A technical assessment of the critical issues and problem areas in the field of plasma materials interactions (PMI) in magnetic fusion devices shows these problems to be central for near-term experiments, for intermediate-range reactor devices including D-T burning physics experiments, and for long-term reactor machines. Critical technical issues are ones central to understanding and successful operation of existing and near-term experiments/reactors or devices of great importance for the long run, i.e., ones which will require an extensive, long-term development effort and thus should receive attention now. Four subgroups were formed to assess the critical PMI issues along four major lines: (1) PMI and plasma confinement physics experiments; (2) plasma-edge modelling and theory; (3) surface physics; and (4) materials technology for in-vessel components and the first wall. The report which follows is divided into four major sections, one for each of these topics

  9. A shuttle and space station manipulator system for assembly, docking, maintenance, cargo handling and spacecraft retrieval (preliminary design). Volume 3: Concept analysis. Part 1: Technical

    Science.gov (United States)

    1972-01-01

    Information backing up the key features of the manipulator system concept and detailed technical information on the subsystems are presented. Space station assembly and shuttle cargo handling tasks are emphasized in the concept analysis because they involve shuttle berthing, transferring the manipulator boom between shuttle and station, station assembly, and cargo handling. Emphasis is also placed on maximizing commonality in the system areas of manipulator booms, general purpose end effectors, control and display, data processing, telemetry, dedicated computers, and control station design.

  10. Greater-than-Class C low-level radioactive waste characterization. Appendix E-5: Impact of the 1993 NRC draft Branch Technical Position on concentration averaging of greater-than-Class C low-level radioactive waste

    International Nuclear Information System (INIS)

    Tuite, P.; Tuite, K.; Harris, G.

    1994-09-01

    This report evaluates the effects of concentration averaging practices on the disposal of greater-than-Class C low-level radioactive waste (GTCC LLW) generated by the nuclear utility industry and sealed sources. Using estimates of the number of waste components that individually exceed Class C limits, this report calculates the proportion that would be classified as GTCC LLW after applying concentration averaging; this proportion is called the concentration averaging factor. The report uses the guidance outlined in the 1993 Nuclear Regulatory Commission (NRC) draft Branch Technical Position on concentration averaging, as well as waste disposal experience at nuclear utilities, to calculate the concentration averaging factors for nuclear utility wastes. The report uses the 1993 NRC draft Branch Technical Position and the criteria from the Barnwell, South Carolina, LLW disposal site to calculate concentration averaging factors for sealed sources. The report addresses three waste groups: activated metals from light water reactors, process wastes from light-water reactors, and sealed sources. For each waste group, three concentration averaging cases are considered: high, base, and low. The base case, which is the most likely case to occur, assumes using the specific guidance given in the 1993 NRC draft Branch Technical Position on concentration averaging. To project future GTCC LLW generation, each waste category is assigned a concentration averaging factor for the high, base, and low cases

  11. TECHNICAL REPORT ON TECHNOLOGICALLY ENHANCED NATURALLY OCCURRING RADIOACTIVE MATERIALS FROM URANIUM MINING, VOLUME II: INVESTIGATION OF POTENTIAL HEALTH, GEOGRAPHIC, AND ENVIRONMENTAL ISSUES OF ABANDONED URANIUM MINES

    Science.gov (United States)

    Volume II investigates the potential radiogenic risks from abandoned uranium mines and evaluates which may pose the greatest hazards to members of the public and to the environment. The intent of this report is to identify who may be most likely to be exposed to wastes at small a...

  12. Technical writing versus technical writing

    Science.gov (United States)

    Dillingham, J. W.

    1981-01-01

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

  13. 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.

  14. Program plan for the DOE Office of Fusion Energy First Wall/Blanket/Shield Engineering Technology Program. Volume II. Detailed technical plan. Revision 2

    International Nuclear Information System (INIS)

    1982-08-01

    The four sections which comprise Part II describe in detail the technical basis for each of the four Program Elements (PE's) of the FWBS Engineering Technology Program (ETP). Each PE is planned to be executed in a number of phases. The purpose of the DTP's is to delineate detailed near-term research, development, and testing required to establish a FWBS engineering data base. Optimum testing strategies and construction of test facilities where needed are identified. The DTP's are based on guidelines given by Argonne National Laboratory which included the basic programmatic goals and the requirements for the types of tests and test conditions

  15. 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)

  16. 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)

  17. Report to Congress on the U.S. Department of Energy`s Environmental Management Science Program: Research funded and its linkages to environmental cleanup problems, and Environmental Management Science Program research award abstracts. Volume 2 of 3 -- Appendix B

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-04-01

    The Department of Energy`s Environmental Management Science Program (EMSP) serves as a catalyst for the application of scientific discoveries to the development and deployment of technologies that will lead to reduction of the costs and risks associated with cleaning up the nation`s nuclear complex. Appendix B provides details about each of the 202 research awards funded by the EMSP. This information may prove useful to researchers who are attempting to address the Department`s environmental management challenges in their work, program managers who are planning, integrating, and prioritizing Environmental Management projects, and stakeholders and regulators who are interested in the Department`s environmental challenges. The research award information is organized by the state and institution in which the lead principal investigator is located. In many cases, the lead principal investigator is one of several investigators at a number of different institutions. In these cases, the lead investigator (major collaborator) at each of the additional institutions is listed. Each research award abstract is followed by a list of high cost projects that can potentially be impacted by the research results. High cost projects are Environmental Management projects that have total costs greater than $50 million from the year 2007 and beyond, based on the March 1998 Accelerating Cleanup: Paths to Closure Draft data, and have costs or quantities of material associated with an Environmental Management problem area. High cost projects which must remain active in the year 2007 and beyond to manage high risk are also identified. Descriptions of these potentially related high cost Environmental Management projects can be found in Appendix C. Additional projects in the same problem area as a research award can be located using the Index of High Cost Environmental Management Projects by Problem Area, at the end of Appendices B and C.

  18. Report to Congress on the U.S. Department of Energy's Environmental Management Science Program: Research funded and its linkages to environmental cleanup problems, and Environmental Management Science Program research award abstracts. Volume 2 of 3 -- Appendix B

    International Nuclear Information System (INIS)

    1998-04-01

    The Department of Energy's Environmental Management Science Program (EMSP) serves as a catalyst for the application of scientific discoveries to the development and deployment of technologies that will lead to reduction of the costs and risks associated with cleaning up the nation's nuclear complex. Appendix B provides details about each of the 202 research awards funded by the EMSP. This information may prove useful to researchers who are attempting to address the Department's environmental management challenges in their work, program managers who are planning, integrating, and prioritizing Environmental Management projects, and stakeholders and regulators who are interested in the Department's environmental challenges. The research award information is organized by the state and institution in which the lead principal investigator is located. In many cases, the lead principal investigator is one of several investigators at a number of different institutions. In these cases, the lead investigator (major collaborator) at each of the additional institutions is listed. Each research award abstract is followed by a list of high cost projects that can potentially be impacted by the research results. High cost projects are Environmental Management projects that have total costs greater than $50 million from the year 2007 and beyond, based on the March 1998 Accelerating Cleanup: Paths to Closure Draft data, and have costs or quantities of material associated with an Environmental Management problem area. High cost projects which must remain active in the year 2007 and beyond to manage high risk are also identified. Descriptions of these potentially related high cost Environmental Management projects can be found in Appendix C. Additional projects in the same problem area as a research award can be located using the Index of High Cost Environmental Management Projects by Problem Area, at the end of Appendices B and C

  19. 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

  20. Technology, safety and costs of decommissioning a reference boiling water reactor power station. Volume 2. Appendices. Technical report, September 1977-October 1979

    International Nuclear Information System (INIS)

    Oak, H.D.; Holter, G.M.; Kennedy, W.E. Jr.; Konzek, G.J.

    1980-06-01

    Technology, safety and cost information is given for the conceptual decommissioning of a large (1100MWe) boiling water reactor (BWR) power station. Three approaches to decommissioning, immediate dismantlement, safe storage with deferred dismantlement and entombment, were studied to obtain comparisons between costs, occupational radiation doses, potential dose to the public and other safety impacts. It also shows the sensitivity of decommissioning safety and costs to the power rating of a BWR in the range of 200 to 1100 MWE. This volume contains the appendices

  1. Total energy cycle assessment of electric and conventional vehicles: an energy and environmental analysis. Volume 2: appendices A-D to technical report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-01-01

    This report compares the energy use, oil use and emissions of electric vehicles (EVs) with those of conventional, gasoline- powered vehicles (CVs) over the total life cycle of the vehicles. The various stages included in the vehicles` life cycles include vehicle manufacture, fuel production, and vehicle operation. Disposal is not included. An inventory of the air emissions associated with each stage of the life cycle is estimated. Water pollutants and solid wastes are reported for individual processes, but no comprehensive inventory is developed. Volume II contains additional details on the vehicle, utility, and materials analyses and discusses several details of the methodology.

  2. Advanced training course on state systems of accounting for and control of nuclear materials. Volume I. Program for technical assistance to IAEA safeguards

    International Nuclear Information System (INIS)

    Sorenson, R.J.; Schneider, R.A.

    1979-01-01

    Purpose of the course was to provide practical training in the implementation and operation of a national system of accounting for and control of nuclear materials in a bulk processing facility, in the context of international safeguards. This course extends the training received in the basic course on State Systems of Accounting for and Control of Nuclear Materials to a practical, illustrative example utilizing the Exxon Nuclear low enriched uranium fabrication plant. Volume I of this manual contains the text of the presentations following the outline of the syllabus. Sample problems and answers are also included, along with some visual aids

  3. SeaWiFS Technical Report Series. Volume 42; Satellite Primary Productivity Data and Algorithm Development: A Science Plan for Mission to Planet Earth

    Science.gov (United States)

    Falkowski, Paul G.; Behrenfeld, Michael J.; Esaias, Wayne E.; Balch, William; Campbell, Janet W.; Iverson, Richard L.; Kiefer, Dale A.; Morel, Andre; Yoder, James A.; Hooker, Stanford B. (Editor); hide

    1998-01-01

    Two issues regarding primary productivity, as it pertains to the Sea-viewing Wide Field-of-view Sensor (SeaWiFS) Program and the National Aeronautics and Space Administration (NASA) Mission to Planet Earth (MTPE) are presented in this volume. Chapter 1 describes the development of a science plan for deriving primary production for the world ocean using satellite measurements, by the Ocean Primary Productivity Working Group (OPPWG). Chapter 2 presents discussions by the same group, of algorithm classification, algorithm parameterization and data availability, algorithm testing and validation, and the benefits of a consensus primary productivity algorithm.

  4. Technology, safety and costs of decommissioning a reference boiling water reactor power station. Volume 2. Appendices. Technical report, September 1977-October 1979

    Energy Technology Data Exchange (ETDEWEB)

    Oak, H.D.; Holter, G.M.; Kennedy, W.E. Jr.; Konzek, G.J.

    1980-06-01

    Technology, safety and cost information is given for the conceptual decommissioning of a large (1100MWe) boiling water reactor (BWR) power station. Three approaches to decommissioning, immediate dismantlement, safe storage with deferred dismantlement and entombment, were studied to obtain comparisons between costs, occupational radiation doses, potential dose to the public and other safety impacts. It also shows the sensitivity of decommissioning safety and costs to the power rating of a BWR in the range of 200 to 1100 MWE. This volume contains the appendices.

  5. Total energy cycle assessment of electric and conventional vehicles: an energy and environmental analysis. Volume 4: peer review comments on technical report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-01-01

    This report compares the energy use, oil use and emissions of electric vehicles (EVs) with those of conventional, gasoline-powered vehicles (CVs) over the total life cycle of the vehicles. The various stages included in the vehicles` life cycles include vehicle manufacture, fuel production, and vehicle operation. Disposal is not included. An inventory of the air emissions associated with each stage of the life cycle is estimated. Water pollutants and solid wastes are reported for individual processes, but no comprehensive inventory is developed. Volume IV includes copies of all the external peer review comments on the report distributed for review in July 1997.

  6. Technical support of standards for high-level radioactive waste management. Volume B. Engineering controls. Task b report Mar-Aug 77

    International Nuclear Information System (INIS)

    1979-01-01

    This report is the result of work performed under the second part (Task B) of a four-part contract to gather technical information to evaluate enviornmental acceptablity of various options for disposing high-level wastes. The other tasks are: A-Source Term Characterization; C-Assessment of Migration Pathways; D-Assessment of Accidental Pathways. The scope of work for Task B was divided into 2 major steps: analysis of technology for engineering control of high-level wastes, and projections of costs for various alternative disposal technologies. Primary emphasis has been placed in non-reprocessed spent fuel. Brief consideration has been given to lower-level transuranic contaminated wastes which arise primarily from plutonium fuel fabrication and reprocessing plants. The objective of this limited review is to provide some insight into the state of the art for applying engineering controls to such wastes, including, where necessary, direct burial with high-level wastes in a geologic disposal facility

  7. Research on the characterization and conditioning of uranium mill tailings. II. Thermal stabilization of uranium mill tailings: technical and economic evaluation. Volume 2

    International Nuclear Information System (INIS)

    Dreesen, D.R.; Cokal, E.J.; Thode, E.F.; Wangen, L.E.; Williams, J.M.

    1983-06-01

    A method of conditioning uranium mill tailings has been devised to greatly reduce radon emanation and contaminant leachability by using high-temperature treatments, i.e., thermal stabilization. The thermally stabilized products appear resistant to weathering as measured by the effects of grinding and water leaching. The technical feasibility of the process has been partially verified in pilot-scale experiments. A conceptual thermal stabilization process has been designed and the economics of the process show that the thermal stabilization of tailings can be cost competitive compared with relocation of tailings during remedial action. The alteration of morphology, structure, and composition during thermal treatment would indicate that this stabilization method may be a long-lasting solution to uranium mill tailings disposal problems

  8. Technical support document: Energy efficiency standards for consumer products: Room air conditioners, water heaters, direct heating equipment, mobile home furnaces, kitchen ranges and ovens, pool heaters, fluorescent lamp ballasts and television sets. Volume 1, Methodology

    Energy Technology Data Exchange (ETDEWEB)

    1993-11-01

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

  9. 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

  10. The Appendix on CT

    Energy Technology Data Exchange (ETDEWEB)

    Whitley, S. [Sunnybrook Health Sciences Center, Toronto, Ontario (Canada); Barts and the Royal London, Royal London Hospital, Whitechapel, London (United Kingdom)], E-mail: siobhanwhitley@yahoo.co.uk; Sookur, P.; McLean, A.; Power, N. [Barts and the Royal London, Royal London Hospital, Whitechapel, London (United Kingdom)

    2009-02-15

    Appendicitis can be a difficult clinical diagnosis to make. A negative appendicectomy rate of 20% has traditionally been accepted as the consequences of appendiceal perforation can be grave. Cross-sectional imaging is increasingly being employed in the investigation of adults with suspected appendicitis. This review will demonstrate the appearance of the normal appendix on computed tomography (CT) and its appearance in a range of inflammatory and neoplastic processes including appendicitis, Crohn's disease, infections, and benign and malignant tumour000.

  11. 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

  12. 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.

  13. Report to Congress on the U.S. Department of Energy`s Environmental Management Science Program: Research funded and its linkages to environmental cleanup problems, and high out-year cost environmental management project descriptions. Volume 3 of 3 -- Appendix C

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-04-01

    The Department of Energy`s Environmental Management Science Program (EMSP) serves as a catalyst for the application of scientific discoveries to the development and deployment of technologies that will lead to reduction of the costs and risks associated with cleaning up the nation`s nuclear complex. Appendix C provides details about each of the Department`s 82 high cost projects and lists the EMSP research awards with potential to impact each of these projects. The high cost projects listed are those having costs greater than $50 million in constant 1998 dollars from the year 2007 and beyond, based on the March 1998 Accelerating Cleanup: Paths to Closure Draft data, and having costs of quantities of material associated with an environmental management problem area. The high cost project information is grouped by operations office and organized by site and project code. Each operations office section begins with a list of research needs associated with that operations office. Potentially related research awards are listed by problem area in the Index of Research Awards by Environmental Management Problem Area, which can be found at the end of appendices B and C. For projects that address high risks to the public, workers, or the environment, refer also the Health/Ecology/Risk problem area awards. Research needs are programmatic or technical challenges that may benefit from knowledge gained through basic research.

  14. 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.

  15. Technical analysis of volume-rendering algorithms: application in low-contrast structures using liver vascularisation as a model; Analisi tecnica degli algoritmi di volume rendering: applicazione alle strutture a basso contrsto usando come modello la vascolarizzazione epatica

    Energy Technology Data Exchange (ETDEWEB)

    Cademartiri, Filippo [Erasmus Medical Center, Rotterdam (Netherlands); Luccichenti, Giacomo [Fondazione Biomedica Europea ONLUS, Roma (Italy); Runza, Giuseppe; Bartolotta, Tommaso Vincenzo; Midiri, Massimo [Palermo Univ., Palermo (Italy). Sezione di scienze radiologiche; Gualerzi, Massimo; Brambilla, Lorenzo; Coruzzi, Paolo [Parma Univ., Parma (Italy). UO di prevenzione e riabilitazione vascolare, Fondazione Don C. Gnocchi ONLUS; Soliani, Paolo; Sianesi, Mario [Parma Univ., Parma (Italy). Dipartimento di chirurgia

    2005-04-01

    Purpose: To assess the influence of pre-set volume rendering opacity curves (OC) on image quality and to identify which absolute parameters (density of aorta, hepatic parenchyma and portal vein) affect visualization of portal vascular structures (low-contrast structures). Materials and methods: Twenty-two patients underwent a dual-phase spiral CT with the following parameters: collimation 3 mm, pitch 2, increment 1 mm. Three scans were performed: one without contrast medium and the latter two after the injection of contrast material (conventionally identified as 'arterial' and 'portal'). The images were sent to a workstation running on an NT platform equipped with post-processing software allowing three-dimensional (3D) reconstructions to generate volume-rendered images of the vascular supply to the liver. Correlation between the absolute values of aorta, liver and portal vein density, OC parameters, and image quality were assessed. Results: 3D images generated using pre-set OC obtained a much mower overall quality score than those produced with OC set by the operator. High contrast between the liver and the portal vein, for example during the portal vascular phase, allows wider windows, thus improving image quality. Conversely, the OC in the parenchymal phase scans must have a high gradient in order to better differentiate between the vascular structures and the surrounding hepatic parenchyma. Conclusions: Image features considered to be of interest by the operator cannot be simplified by the mean of pre-set OC. Due to their strong individual variability automatic 3D algorithms cannot be universally applied: they should be adapted to both image and patient characteristics. [Italian] Scopo: Valutare l'influenza delle curve di opacit� (CO) preimpostate del volume-rendering sulla qualit� delle immagini, ed identificare quali parametri assoluti (attenzione dell'aorta, del parenchima epatico e della vena porta) influenzano la

  16. 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.

  17. Magnetic Fusion Energy Plasma Interactive and High Heat Flux Components: Volume 5, Technical assessment of critical issues in the steady state operation of fusion confinement devices

    Energy Technology Data Exchange (ETDEWEB)

    1988-01-01

    Critical issues for the steady state operation of plasma confinement devices exist in both the physics and technology fields of fusion research. Due to the wide range and number of these issues, this technical assessment has focused on the crucial issues associated with the plasma physics and the plasma interactive components. The document provides information on the problem areas that affect the design and operation of a steady state ETR or ITER type confinement device. It discusses both tokamaks and alternative concepts, and provides a survey of existing and planned confinement machines and laboratory facilities that can address the identified issues. A universal definition of steady state operation is difficult to obtain. From a physics point of view, steady state is generally achieved when the time derivatives approach zero and the operation time greatly exceeds the characteristic time constants of the device. Steady state operation for materials depends on whether thermal stress, creep, fatigue, radiation damage, or power removal are being discussed. For erosion issues, the fluence and availability of the machine for continuous operation are important, assuming that transient events such as disruptions do not limit the component lifetimes. The panel suggests, in general terms, that steady state requires plasma operation from 100 to 1000 seconds and an availability of more than a few percent, which is similar to the expectations for an ETR type device. The assessment of critical issues for steady state operation is divided into four sections: physics issues; technology issues; issues in alternative concepts; and devices and laboratory facilities that can address these problems.

  18. Magnetic Fusion Energy Plasma Interactive and High Heat Flux Components: Volume 5, Technical assessment of critical issues in the steady state operation of fusion confinement devices

    International Nuclear Information System (INIS)

    1988-01-01

    Critical issues for the steady state operation of plasma confinement devices exist in both the physics and technology fields of fusion research. Due to the wide range and number of these issues, this technical assessment has focused on the crucial issues associated with the plasma physics and the plasma interactive components. The document provides information on the problem areas that affect the design and operation of a steady state ETR or ITER type confinement device. It discusses both tokamaks and alternative concepts, and provides a survey of existing and planned confinement machines and laboratory facilities that can address the identified issues. A universal definition of steady state operation is difficult to obtain. From a physics point of view, steady state is generally achieved when the time derivatives approach zero and the operation time greatly exceeds the characteristic time constants of the device. Steady state operation for materials depends on whether thermal stress, creep, fatigue, radiation damage, or power removal are being discussed. For erosion issues, the fluence and availability of the machine for continuous operation are important, assuming that transient events such as disruptions do not limit the component lifetimes. The panel suggests, in general terms, that steady state requires plasma operation from 100 to 1000 seconds and an availability of more than a few percent, which is similar to the expectations for an ETR type device. The assessment of critical issues for steady state operation is divided into four sections: physics issues; technology issues; issues in alternative concepts; and devices and laboratory facilities that can address these problems

  19. 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...

  20. Report on the remedial investigation of Bear Creek Valley at the Oak Ridge Y-12 Plant, Oak Ridge, Tennessee. Volume 3: Appendix D -- Nature and extent of contamination 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 D describes the nature and extent of contamination in environmental media and wastes

  1. Report on the remedial investigation of Bear Creek Valley at the Oak Ridge Y-12 Plant, Oak Ridge, Tennessee. Volume 4: Appendix E -- Valley-wide fate and transport 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 E addresses contaminant releases and migration pathways from a valley-wide perspective and provides estimates of changes in contaminant fluxes in BCV

  2. Report to Congress on the U.S. Department of Energy`s Environmental Management Science Program: Research funded and its linkages to environmental cleanup problems. Volume 1 of 3 -- Report and Appendix A

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-04-01

    This report is submitted in response to a Congressional request and is intended to communicate the nature, content, goals, and accomplishments of the Environmental Management Science Program (EMSP) to interested and affected parties in the Department and its contractors, at Federal agencies, in the scientific community, and in the general public. The EMSP was started in response to a request to mount an effort in longer term basic science research to seek new and innovative cleanup methods to replace current conventional approaches which are often costly and ineffective. Section 1, ``Background of the Program,`` provides information on the evolution of the EMSP and how it is managed, and summarizes recent accomplishments. Section 2, ``Research Award Selection Process,`` provides an overview of the ongoing needs identification process, solicitation development, and application review for scientific merit and programmatic relevance. Section 3, ``Linkages to Environmental Cleanup Problems,`` provides an overview of the major interrelationships (linkages) among EMSP basic research awards, Environmental Management problem areas, and high cost projects. Section 4, ``Capitalizing on Science Investments,`` discusses the steps the EMSP plans to use to facilitate the application of research results in Environmental Management strategies through effective communication and collaboration. Appendix A contains four program notices published by the EMSP inviting applications for grants.

  3. Report to Congress on the U.S. Department of Energy's Environmental Management Science Program: Research funded and its linkages to environmental cleanup problems. Volume 1 of 3 - Report and Appendix A

    International Nuclear Information System (INIS)

    1998-04-01

    This report is submitted in response to a Congressional request and is intended to communicate the nature, content, goals, and accomplishments of the Environmental Management Science Program (EMSP) to interested and affected parties in the Department and its contractors, at Federal agencies, in the scientific community, and in the general public. The EMSP was started in response to a request to mount an effort in longer term basic science research to seek new and innovative cleanup methods to replace current conventional approaches which are often costly and ineffective. Section 1, ''Background of the Program,'' provides information on the evolution of the EMSP and how it is managed, and summarizes recent accomplishments. Section 2, ''Research Award Selection Process,'' provides an overview of the ongoing needs identification process, solicitation development, and application review for scientific merit and programmatic relevance. Section 3, ''Linkages to Environmental Cleanup Problems,'' provides an overview of the major interrelationships (linkages) among EMSP basic research awards, Environmental Management problem areas, and high cost projects. Section 4, ''Capitalizing on Science Investments,'' discusses the steps the EMSP plans to use to facilitate the application of research results in Environmental Management strategies through effective communication and collaboration. Appendix A contains four program notices published by the EMSP inviting applications for grants

  4. Report on the remedial investigation of Bear Creek Valley at the Oak Ridge Y-12 Plant, Oak Ridge, Tennessee. Volume 5: Appendix F - Baseline human health risk assessment 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 F documents potential risks and provides information necessary for making remediation decisions. A quantitative analysis of the inorganic, organic, and radiological site-related contaminants found in various media is used to characterize the potential risks to human health associated with exposure to these contaminants

  5. Report on the remedial investigation of Bear Creek Valley at the Oak Ridge Y-12 Plant, Oak Ridge, Tennessee. Volume 5: Appendix F -- Baseline human health risk assessment 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 F documents potential risks and provides information necessary for making remediation decisions. A quantitative analysis of the inorganic, organic, and radiological site-related contaminants found in various media is used to characterize the potential risks to human health associated with exposure to these contaminants.

  6. Report on the remedial investigation of Bear Creek Valley at the Oak Ridge Y-12 Plant, Oak Ridge, Tennessee. Volume 3: Appendix D -- Nature and extent of contamination 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 D describes the nature and extent of contamination in environmental media and wastes.

  7. Imagining Technicities

    DEFF Research Database (Denmark)

    Liboriussen, Bjarke; Plesner, Ursula

    2011-01-01

    to the elements of taste and skill. In the final analysis those references were synthesized as five imagined technicities: the architect, the engineer, the client, the Chinese, and the Virtual World native. Because technicities are often assumed and rarely discussed as actants who influence practice, their role......, this article focuses on innovative uses of virtual worlds in architecture. We interviewed architects, industrial designers and other practitioners. Conceptually supported by an understanding of technicity found in Cultural Studies, the interviews were then coded with a focus on interviewees’ references...... in cooperation and development of ICTs seems to pass unnoticed. However, since they are aligned into ICTs, technicities impact innovation....

  8. 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)

  9. 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.

  10. Technical Note: Impact of the geometry dependence of the ion chamber detector response function on a convolution-based method to address the volume averaging effect

    Energy Technology Data Exchange (ETDEWEB)

    Barraclough, Brendan; Lebron, Sharon [Department of Radiation Oncology, University of Florida, Gainesville, Florida 32608 and J. Crayton Pruitt Family Department of Biomedical Engineering, University of Florida, Gainesville, Florida 32611 (United States); Li, Jonathan G.; Fan, Qiyong; Liu, Chihray; Yan, Guanghua, E-mail: yangua@shands.ufl.edu [Department of Radiation Oncology, University of Florida, Gainesville, Florida 32608 (United States)

    2016-05-15

    Purpose: To investigate the geometry dependence of the detector response function (DRF) of three commonly used scanning ionization chambers and its impact on a convolution-based method to address the volume averaging effect (VAE). Methods: A convolution-based approach has been proposed recently to address the ionization chamber VAE. It simulates the VAE in the treatment planning system (TPS) by iteratively convolving the calculated beam profiles with the DRF while optimizing the beam model. Since the convolved and the measured profiles are subject to the same VAE, the calculated profiles match the implicit “real” ones when the optimization converges. Three DRFs (Gaussian, Lorentzian, and parabolic function) were used for three ionization chambers (CC04, CC13, and SNC125c) in this study. Geometry dependent/independent DRFs were obtained by minimizing the difference between the ionization chamber-measured profiles and the diode-measured profiles convolved with the DRFs. These DRFs were used to obtain eighteen beam models for a commercial TPS. Accuracy of the beam models were evaluated by assessing the 20%–80% penumbra width difference (PWD) between the computed and diode-measured beam profiles. Results: The convolution-based approach was found to be effective for all three ionization chambers with significant improvement for all beam models. Up to 17% geometry dependence of the three DRFs was observed for the studied ionization chambers. With geometry dependent DRFs, the PWD was within 0.80 mm for the parabolic function and CC04 combination and within 0.50 mm for other combinations; with geometry independent DRFs, the PWD was within 1.00 mm for all cases. When using the Gaussian function as the DRF, accounting for geometry dependence led to marginal improvement (PWD < 0.20 mm) for CC04; the improvement ranged from 0.38 to 0.65 mm for CC13; for SNC125c, the improvement was slightly above 0.50 mm. Conclusions: Although all three DRFs were found adequate to

  11. 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

  12. 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).

  13. 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 C, Savannah River Site Spent Nuclear Fuel Mangement Program

    Energy Technology Data Exchange (ETDEWEB)

    1994-06-01

    The US Department of Energy (DOE) is engaged in two related decision making processes concerning: (1) the transportation, receipt, processing, and storage of spent nuclear fuel (SNF) at the DOE Idaho National Engineering Laboratory (INEL) which will focus on the next 10 years; and (2) programmatic decisions on future spent nuclear fuel management which will emphasize the next 40 years. DOE is analyzing the environmental consequences of these spent nuclear fuel management actions in this two-volume Environmental Impact Statement (EIS). Volume 1 supports broad programmatic decisions that will have applicability across the DOE complex and describes in detail the purpose and need for this DOE action. Volume 2 is specific to actions at the INEL. This document, which limits its discussion to the Savannah River Site (SRS) spent nuclear fuel management program, supports Volume 1 of the EIS. Following the introduction, Chapter 2 contains background information related to the SRS and the framework of environmental regulations pertinent to spent nuclear fuel management. Chapter 3 identifies spent nuclear fuel management alternatives that DOE could implement at the SRS, and summarizes their potential environmental consequences. Chapter 4 describes the existing environmental resources of the SRS that spent nuclear fuel activities could affect. Chapter 5 analyzes in detail the environmental consequences of each spent nuclear fuel management alternative and describes cumulative impacts. The chapter also contains information on unavoidable adverse impacts, commitment of resources, short-term use of the environment and mitigation measures.

  14. 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

  15. Technical Network

    CERN Multimedia

    2007-01-01

    In order to optimize the management of the Technical Network (TN), to ease the understanding and purpose of devices connected to the TN, and to improve security incident handling, the Technical Network Administrators and the CNIC WG have asked IT/CS to verify the "description" and "tag" fields of devices connected to the TN. Therefore, persons responsible for systems connected to the TN will receive email notifications from IT/CS asking them to add the corresponding information in the network database. Thank you very much for your cooperation. The Technical Network Administrators & the CNIC WG

  16. Technical Network

    CERN Multimedia

    2007-01-01

    In order to optimise the management of the Technical Network (TN), to facilitate understanding of the purpose of devices connected to the TN and to improve security incident handling, the Technical Network Administrators and the CNIC WG have asked IT/CS to verify the "description" and "tag" fields of devices connected to the TN. Therefore, persons responsible for systems connected to the TN will receive e-mails from IT/CS asking them to add the corresponding information in the network database at "network-cern-ch". Thank you very much for your cooperation. The Technical Network Administrators & the CNIC WG

  17. 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).

  18. 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 F, Nevada Test Site and Oak Ridge Reservation Spent Nuclear Fuel Management Programs

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1994-06-01

    This volume addresses the interim storage of spent nuclear fuel (SNF) at two US Department of Energy sites, the Nevada Test Site (NTS) and the Oak Ridge Reservation (ORR). These sites are being considered to provide a reasonable range of alternative settings at which future SNF management activities could be conducted. These locations are not currently involved in management of large quantities of SNF; NTS has none, and ORR has only small quantities. But NTS and ORR do offer experience and infrastructure for the handling, processing and storage of radioactive materials, and they do exemplify a broad spectrum of environmental parameters. This broad spectrum of environmental parameters will provide, a perspective on whether and how such location attributes may relate to potential environmental impacts. Consideration of these two sites will permit a programmatic decision to be based upon an assessment of the feasible options without bias, to the current storage sites. This volume is divided into four parts. Part One is the volume introduction. Part Two contains chapters one through five for the NTS, as well as references contained in chapter six. Part Three contains chapters one through five for the ORR, as well as references contained in chapter six. Part Four is summary information including the list of preparers, organizations contacted, acronyms, and abbreviations for both the NTS and the ORR. A Table of Contents, List of Figures, and List of Tables are included in parts Two, Three, and Four. This approach permitted the inclusion of both sites in one volume while maintaining consistent chapter numbering.

  19. 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.

  20. 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