WorldWideScience

Sample records for project technical requirements

  1. 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)

  2. 75 FR 41875 - Technical Processing Requirements for Multifamily Project Mortgage Insurance

    Science.gov (United States)

    2010-07-19

    ... is used to determine if key principals are acceptable and have the ability to manage the development... principals are acceptable and have the ability to manage the development, construction, completion, and... Requirements for Multifamily Project Mortgage Insurance AGENCY: Office of the Chief Information Officer, HUD...

  3. Financing biotechnology projects: lender due diligence requirements and the role of independent technical consultants.

    Science.gov (United States)

    Keller, J B; Plath, P B

    1999-01-01

    An increasing number of biotechnology projects are being brought to commercialization using conventional structured finance sources, which have traditionally only been available to proven technologies and primary industries. Attracting and securing competitive cost financing from mainstream lenders, however, will require the sponsor of a new technology or process to undergo a greater level of due diligence. The specific areas and intensity of investigation, which are typically required by lenders in order to secure long-term financing for biotechnology-based manufacturing systems, is reviewed. The processes for evaluating the adequacy of prior laboratory testing and pilot plant demonstrations is discussed. Particular emphasis is given to scale-up considerations and the ability of the proposed facility design to accommodate significant modifications, in the event that scale-up problems are encountered.

  4. Technical safety requirements for the South Tank Farm remediation project, Oak Ridge National Laboratory, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    Platfoot, J.H.

    1999-01-01

    The South Tank Farm (STF) is a series of six, 170,000-gal underground, domed storage tanks that were placed into service in 1943. The tanks were constructed of a concrete mixture known as gunite. They were used as a portion of the Liquid LOW-LEVEL WASTE (LLW) System for the collection, neutralization, storage, and transfer of the aqueous portion of the radioactive and/or hazardous chemical wastes produced as part of normal facility operations at Oak Ridge National Laboratory (ORNL). Although the last of the tanks was taken out of service in 1986, they have been shown by structural analysis to continue to be structurally sound. An attempt was made in 1983 to empty the tanks; however, removal of all the sludge from the tanks was not possible with the equipment and schedule available. Since removal of the liquid waste in 1983, liquid continues to accumulate within the tanks. The in-leakage is believed to be the result of groundwater dripping into the tanks around penetrations in the domes. The tanks are currently being maintained under a Surveillance and Maintenance Program, which includes activities such as level monitoring, vegetation control, High Efficiency Particulate Air filter leakage requirement testing/replacement, sign erection/repair, pump-out of excess liquids, and instrument calibration/maintenance. A technique known as confined sluicing, which uses a high-pressure, low-volume water jet integrated with a jet pump, will be used to remove the sludge. The Technical Safety Requirements (TSRs) are those operational requirements that specify the operating limits and surveillance requirements, the basis thereof, safety boundaries, and the management of administrative controls necessary to ensure the safe operation of the STF remediation project. Effective implementation of TSRs will limit to acceptable levels the risks to the public and workers from uncontrolled releases of radioactive or other hazardous material

  5. Waste management project technical baseline description

    International Nuclear Information System (INIS)

    Sederburg, J.P.

    1997-01-01

    A systems engineering approach has been taken to describe the technical baseline under which the Waste Management Project is currently operating. The document contains a mission analysis, function analysis, requirement analysis, interface definitions, alternative analysis, system definition, documentation requirements, implementation definitions, and discussion of uncertainties facing the Project

  6. Trojan technical specification verification project

    International Nuclear Information System (INIS)

    Bates, L.; Rickenback, M.

    1991-01-01

    The Trojan Technical Specification Verification (TTSV) project at the Trojan plant of Portland General Electric Company was motivated by the recognition that many numbers in the Trojan technical specifications (TTS) potentially lacked the consideration of instrument- and/or process-related errors. The plant setpoints were known to consider such errors, but many of the values associated with the limiting conditions for operation (LCO) did not. In addition, the existing plant instrument error analyses were based on industry values that do not reflect the Trojan plant-specific experience. The purpose of this project is to ensure that the Trojan plant setpoint and LCO values include plant-specific instrument error

  7. Spent nuclear fuel project technical databook

    International Nuclear Information System (INIS)

    Reilly, M.A.

    1998-01-01

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

  8. Spent nuclear fuel project technical databook

    Energy Technology Data Exchange (ETDEWEB)

    Reilly, M.A.

    1998-07-22

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

  9. 75 FR 6683 - Notice of Proposed Information Collection: Comment Request; Technical Processing Requirements for...

    Science.gov (United States)

    2010-02-10

    ... Information Collection: Comment Request; Technical Processing Requirements for Multifamily Project Mortgage... information: Title of Proposal: Technical Processing Requirements for Multifamily Project Mortgage Insurance... information collection requirement described below will be submitted to the Office of Management and Budget...

  10. Technical safety requirments for the South Tank Farm Remediation Project, Oak Ridge National Laboratory, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    Platfoot, J.H.

    1998-02-01

    The South Tank Farm (STF) is a series of six, 170,000-gal underground, domed storage tanks that were placed into service in 1943. The tanks were constructed of a concrete mixture known as gunite. They were used as a portion of the Liquid LOW-LEVEL WASTE (LLLW) System for the collection, neutralization, storage, and transfer of the aqueous portion of the radioactive and/or hazardous chemical wastes produced as part of normal facility operations at Oak Ridge National Laboratory (ORNL). Although the last of the tanks was taken out of service in 1986, they have been shown by structural analysis to continue to be structurally sound. An attempt was made in 1983 to empty the tanks; however, removal of all the sludge from the tanks was not possible with the equipment and schedule available. Since removal of the liquid waste in 1983, liquid continues to accumulate within the tanks. The in-leakage is believed to be the result of groundwater dripping into the tanks around penetrations in the domes. The tanks are currently being maintained under a Surveillance and Maintenance Program, which includes activities such as level monitoring, vegetation control, High Efficiency Particulate Air filter leakage requirement testing/replacement, sign erection/repair, pump-out of excessive liquids, and instrument calibration/maintenance

  11. 15 CFR 911.8 - Technical requirements.

    Science.gov (United States)

    2010-01-01

    ... PROCEDURES CONCERNING USE OF THE NOAA SPACE-BASED DATA COLLECTION SYSTEMS § 911.8 Technical requirements. (a) All platform operators of the NOAA DCS must use a data collection platform radio set whose technical... 15 Commerce and Foreign Trade 3 2010-01-01 2010-01-01 false Technical requirements. 911.8 Section...

  12. 78 FR 65695 - 30-Day Notice of Proposed Information Collection: Technical Processing Requirements for...

    Science.gov (United States)

    2013-11-01

    ... Information Collection: Technical Processing Requirements for Multifamily Project Mortgage Insurance AGENCY: Office of the Chief Information Officer, HUD. ACTION: Correction, notice. SUMMARY: On October 25, 2013 at... Collection Title of Information Collection: Technical Processing Requirements for Multifamily Project...

  13. Requirements in engineering projects

    CERN Document Server

    Fernandes, João M

    2016-01-01

    This book focuses on various topics related to engineering and management of requirements, in particular elicitation, negotiation, prioritisation, and documentation (whether with natural languages or with graphical models). The book provides methods and techniques that help to characterise, in a systematic manner, the requirements of the intended engineering system.  It was written with the goal of being adopted as the main text for courses on requirements engineering, or as a strong reference to the topics of requirements in courses with a broader scope. It can also be used in vocational courses, for professionals interested in the software and information systems domain.   Readers who have finished this book will be able to: - establish and plan a requirements engineering process within the development of complex engineering systems; - define and identify the types of relevant requirements in engineering projects; - choose and apply the most appropriate techniques to elicit the requirements of a giv...

  14. When Serious Project Management is a Critical Business Requirement

    Science.gov (United States)

    Jansma, P. A.; Gibby, L.; Chambers, C.; Joines, J.; Egger, R.

    2000-01-01

    When serious project management is a critical business requirement, project managers need to integrate cost, schedule and technical scope of work across the project, and apply earned value management (EVM).

  15. 78 FR 64146 - 30-Day Notice of Proposed Information Collection: Technical Processing Requirements for...

    Science.gov (United States)

    2013-10-25

    ... Information Collection: Technical Processing Requirements for Multifamily Project Mortgage Insurance AGENCY: Office of the Chief Information Officer, HUD. ACTION: Notice. SUMMARY: HUD has submitted the proposed... Information Collection Title of Information Collection: Technical Processing Requirements for Multifamily...

  16. Improvements to Technical Specifications surveillance requirements

    International Nuclear Information System (INIS)

    Lobel, R.; Tjader, T.R.

    1992-12-01

    In August 1983 an NRC task group was formed to investigate problems with surveillance testing required by Technical Specifications, and to recommend approaches to effect improvements. NUREG-1024 (''Technical Specifications-Enhancing Safety Impact'') resulted, and it contained recommendations to review the basis for test frequencies; to ensure that the tests promote safety and do not degrade equipment; and to review surveillance tests so that they do not unnecessarily burden personnel. The Technical Specifications Improvement Program (TSIP) was established in December 1984 to provide the framework for rewriting and improving the Technical Specifications. As an element of the TSIP, all Technical Specifications surveillance requirements were comprehensively examined as recommended in NUREG-1024. The results of that effort are presented in this report. The study found that while some testing at power is essential to verify equipment and system operability, safety can be improved, equipment degradation decreased, and unnecessary personnel burden relaxed by reducing the amount of testing at power

  17. Canister Storage Building (CSB) Technical Safety Requirements

    International Nuclear Information System (INIS)

    KRAHN, D.E.

    2000-01-01

    The purpose of this section is to explain the meaning of logical connectors with specific examples. Logical connectors are used in Technical Safety Requirements (TSRs) to discriminate between, and yet connect, discrete Conditions, Required Actions, Completion Times, Surveillances, and Frequencies. The only logical connectors that appear in TSRs are AND and OR. The physical arrangement of these connectors constitutes logical conventions with specific meanings

  18. Technical safety requirements control level verification

    International Nuclear Information System (INIS)

    STEWART, J.L.

    1999-01-01

    A Technical Safety Requirement (TSR) control level verification process was developed for the Tank Waste Remediation System (TWRS) TSRs at the Hanford Site in Richland, WA, at the direction of the US. Department of Energy, Richland Operations Office (RL). The objective of the effort was to develop a process to ensure that the TWRS TSR controls are designated and managed at the appropriate levels as Safety Limits (SLs), Limiting Control Settings (LCSs), Limiting Conditions for Operation (LCOs), Administrative Controls (ACs), or Design Features. The TSR control level verification process was developed and implemented by a team of contractor personnel with the participation of Fluor Daniel Hanford, Inc. (FDH), the Project Hanford Management Contract (PHMC) integrating contractor, and RL representatives. The team was composed of individuals with the following experience base: nuclear safety analysis; licensing; nuclear industry and DOE-complex TSR preparation/review experience; tank farm operations; FDH policy and compliance; and RL-TWRS oversight. Each TSR control level designation was completed utilizing TSR control logic diagrams and TSR criteria checklists based on DOE Orders, Standards, Contractor TSR policy, and other guidance. The control logic diagrams and criteria checklists were reviewed and modified by team members during team meetings. The TSR control level verification process was used to systematically evaluate 12 LCOs, 22 AC programs, and approximately 100 program key elements identified in the TWRS TSR document. The verification of each TSR control required a team consensus. Based on the results of the process, refinements were identified and the TWRS TSRs were modified as appropriate. A final report documenting key assumptions and the control level designation for each TSR control was prepared and is maintained on file for future reference. The results of the process were used as a reference in the RL review of the final TWRS TSRs and control suite. RL

  19. Technical safety requirements control level verification; TOPICAL

    International Nuclear Information System (INIS)

    STEWART, J.L.

    1999-01-01

    A Technical Safety Requirement (TSR) control level verification process was developed for the Tank Waste Remediation System (TWRS) TSRs at the Hanford Site in Richland, WA, at the direction of the US. Department of Energy, Richland Operations Office (RL). The objective of the effort was to develop a process to ensure that the TWRS TSR controls are designated and managed at the appropriate levels as Safety Limits (SLs), Limiting Control Settings (LCSs), Limiting Conditions for Operation (LCOs), Administrative Controls (ACs), or Design Features. The TSR control level verification process was developed and implemented by a team of contractor personnel with the participation of Fluor Daniel Hanford, Inc. (FDH), the Project Hanford Management Contract (PHMC) integrating contractor, and RL representatives. The team was composed of individuals with the following experience base: nuclear safety analysis; licensing; nuclear industry and DOE-complex TSR preparation/review experience; tank farm operations; FDH policy and compliance; and RL-TWRS oversight. Each TSR control level designation was completed utilizing TSR control logic diagrams and TSR criteria checklists based on DOE Orders, Standards, Contractor TSR policy, and other guidance. The control logic diagrams and criteria checklists were reviewed and modified by team members during team meetings. The TSR control level verification process was used to systematically evaluate 12 LCOs, 22 AC programs, and approximately 100 program key elements identified in the TWRS TSR document. The verification of each TSR control required a team consensus. Based on the results of the process, refinements were identified and the TWRS TSRs were modified as appropriate. A final report documenting key assumptions and the control level designation for each TSR control was prepared and is maintained on file for future reference. The results of the process were used as a reference in the RL review of the final TWRS TSRs and control suite. RL

  20. UMTRA project technical assistance contractor quality assurance implementation plan

    International Nuclear Information System (INIS)

    1994-03-01

    The Uranium Mill Tailings Remedial Action (UMTRA) Project Technical Assistance contractor (TAC) Quality Assurance Implementation Plan (QAIP) outlines the primary requirements for integrating quality functions for TAC technical activities applied to the surface and ground water phases of the UMTRA Project. The QAIP is subordinate to the latest issue of the UMTRA Project TAC Quality Assurance Program Plan (QAPP) (DOE, 1993a), which was developed using US Department of Energy (DOE) Order 5700.6C quality assurance (QA) criteria. The QAIP addresses technical aspects of the TAC UMTRA Project surface and ground water programs. All QA issues in the QAIP shall comply with requirements contained in the TAC QAPP (DOE, 1933a). Because industry standards for data acquisition and data control are not addressed in DOE Order 5700.6C, the QAIP has been formatted to the 14 US Environmental Protection Agency (EPA) Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) QA requirements. DOE Order 5700.6C criteria that are not contained in the CERCLA requirements are added to the QAIP as additional requirements in Sections 15.0 through 18.0. Project documents that contain CERCLA requirements and 5700.6 criteria shall be referenced in this document to avoid duplication. Referenced documents are not included in this QAIP but are available through the UMTRA Project Document Control Center

  1. 47 CFR 80.659 - Technical requirements.

    Science.gov (United States)

    2010-10-01

    ... Telecommunication FEDERAL COMMUNICATIONS COMMISSION (CONTINUED) SAFETY AND SPECIAL RADIO SERVICES STATIONS IN THE MARITIME SERVICES Maritime Support Stations § 80.659 Technical requirements. The authorized frequency tolerance, class of emission, bandwidth, and transmitter power for maritime support stations are contained...

  2. Extension agents' technical knowledge requirements for effective ...

    African Journals Online (AJOL)

    Technical knowledge requirements of extension agents were investigated in this study. Data for the study was collected with the aid of structured questionnaire administered to the 78 respondents. It was found that respondents were mainly males, were married, were in the middle age category, had BSc/HND, made ...

  3. Gas Test Loop Functional and Technical Requirements

    International Nuclear Information System (INIS)

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

    2004-01-01

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

  4. Gas Test Loop Functional and Technical Requirements

    Energy Technology Data Exchange (ETDEWEB)

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

    2004-09-01

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

  5. Should Project Managers Buy Technical Data

    Science.gov (United States)

    2017-04-06

    the future. The research also exposed perspective organizational viewpoints on what technical data rights are needed and what analysis is available...DAU professor Dr. John Larson. To conclude, this research project was completed with tremendous love and support from my family . Address any...Study ........................................................................................................... 2 Significance of This Research

  6. Technical specifications requirements: Automated reasoning applications

    International Nuclear Information System (INIS)

    Lidsky, L.M.; Dobrzeniecki, A.B.

    1990-03-01

    Several software systems were developed and tested to determine what advantages could be gained from explicitly translating complicated regulatory requirements into computerized relationships. The Technical Specifications for US nuclear power plants were chosen as the test-bed application domain, and two analysis systems were developed to monitor plant compliance with operational limits, and track and schedule equipment test and maintenance activities mandated by Technical Specifications. Choosing PROLOG as the computer language to represent these regulatory requirements resulted in a natural match between the semantic structure of the written specifications and the corollary coded rules. Additional research results affirmed the utility of declarative programming styles, explicit management of problem complexity, and attention to the robustness and flexibility of the overall software systems. 5 refs., 2 figs

  7. Virginia Solar Pathways Project Final Technical Report

    Energy Technology Data Exchange (ETDEWEB)

    Bond, Katharine; Cosby, Sarah

    2018-03-28

    This Report provides a technical review of the final results of a funding award to Virginia Electric and Power Company (Dominion Energy Virginia (DEV) or the Company) for a project under the U.S. Department of Energy’s Solar Energy Technologies Office. The three-year project was formally known as the Virginia Solar Pathways Project (VSPP or the Project). The purpose of the VSPP was to develop a collaborative utility-administered solar strategy (Solar Strategy) for DEV’s service territory in the Commonwealth that could serve as a replicable model for other states with similar policy environments. The U.S. Department of Energy (DOE) funding award enabled DEV to take a focused approach to developing the Solar Strategy for its Virginia service territory. The structure and funding from the DOE award also facilitated valuable input from a formal stakeholder team convened to serve as advisors (Advisory Team) to the VSPP and contribute their perspectives and expertise to both the analysis and strategy development aspects of the Project. The development of the Solar Strategy involved three main goals: • Establish a policy and program framework that would integrate existing solar programs with new options appropriate for the Commonwealth’s policy environment and broader economic development objectives; • Promote wider deployment of solar within a low retail electric rate environment; and • Serve as a sustainable, utility-administered solar model that could be replicated in other states with similar policy environments, including, but not limited to, the entire Southeast region. In support of the VSPP goals, the Project Team commissioned four studies to support the Solar Strategy development. Two studies, completed by Navigant Consulting, focused on the integration of solar into the electric grid. The first solar integration study focused on integration of solar into the distribution grid where the utility system directly connects to and serves end-use customers

  8. Salt Repository Project: FY 85 technical project plan

    International Nuclear Information System (INIS)

    1985-07-01

    The FY 85 technical plan for the Salt Repository Project is briefly presented. The objectives of the project in relation to the Civilian Radioactive Waste Management Program are discussed, and the technical activities directed toward accomplishing these objectives are detailed. A budget is presented for each of the Level 2 work breakdown structure tasks (Systems, Waste Package, Site, Repository, Regulatory and Institutional, Exploratory Shaft, Test Facilities, Land Acquisition, and Project Management) in the various sections. An overall description, current status, and planned activities are presented for each of the subtasks which make up the above-mentioned Level 2 tasks. A strategy diagram and a master schedule are included and each of the milestones is also listed chronologically in the sections

  9. The CANTEACH project: preserving CANDU technical knowledge

    International Nuclear Information System (INIS)

    Garland, B.; Kosarenko, Y.; Meneley, D.

    2003-01-01

    Almost sixty years have passed since the nuclear energy venture began in Canada. Fifty years have passed since the founding of AECL. Tens of thousands of dedicated people have forged a new and successful primary energy supply. CANDU technology is well into its second century. This specialty within the world's fission technology community is quite unique, first because it was established as a separate effort very early in the history of world fission energy, and second because it grew in an isolated environment, with tight security requirements, in its early years. Commercial security rules later sustained a considerable degree of isolation. The pioneers of CANDU development have finished their work. Most of the second generation also has moved on. As yet, we cannot point to a consistent and complete record of this remarkable achievement. We, as a nuclear enterprise, have not captured the design legacy in a form that is readily accessible to the current and future generation of professionals involved with CANDU reactors, be they students, designers, operations staff, regulators, consultants or clients. This is a serious failure. Young people entering our field of study must make do with one or two textbooks and a huge collection of diverse technical papers augmented by limited-scope education and training materials. Those employed in the various parts of the nuclear industry rely mostly on a smaller set of CANDU- related documents available within their own organization; documents that sometimes are rather limited in scope. University professors often have even more limited access to in-depth and up to date information. In fact, they often depend on literature published in other countries when preparing lectures, enhanced by guest lecturers from various parts of the industry. Because CANDU was developed mostly inside Canada, few of these text materials contain useful data describing processes important to the CANDU system. For many years it has been recognized that

  10. Salt Repository Project. FY-84 technical project plan

    International Nuclear Information System (INIS)

    1984-08-01

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

  11. Technical Specification action statements requiring shutdown

    International Nuclear Information System (INIS)

    Mankamo, T.; Kim, I.S.; Samanta, P.K.

    1993-11-01

    When safety systems fail during power operation, the limiting conditions for operation (LCOs) and associated action statements of technical specifications typically require that the plant be shut down within the limits of allowed outage time (AOT). However, when a system needed to remove decay heat, such as the residual heat removal (RHR) system, is inoperable or degraded, shutting down the plant may not necessarily be preferable, from a risk perspective, to continuing power operation over a usual repair time, giving priority to the repairs. The risk impact of the basic operational alternatives, i.e., continued operation or shutdown, was evaluated for failures in the RHR and standby service water (SSW) systems of a boiling-water reactor (BWR) nuclear power plant. A complete or partial failure of the SSW system fails or degrades not only the RHR system but other front-line safety systems supported by the SSW system. This report presents the methodology to evaluate the risk impact of LCOs and associated AOT; the results of risk evaluation from its application to the RHR and SSW systems of a BWR; the findings from the risk-sensitivity analyses to identify alternative operational policies; and the major insights and recommendations to improve the technical specifications action statements

  12. Project Interface Requirements Process Including Shuttle Lessons Learned

    Science.gov (United States)

    Bauch, Garland T.

    2010-01-01

    Most failures occur at interfaces between organizations and hardware. Processing interface requirements at the start of a project life cycle will reduce the likelihood of costly interface changes/failures later. This can be done by adding Interface Control Documents (ICDs) to the Project top level drawing tree, providing technical direction to the Projects for interface requirements, and by funding the interface requirements function directly from the Project Manager's office. The interface requirements function within the Project Systems Engineering and Integration (SE&I) Office would work in-line with the project element design engineers early in the life cycle to enhance communications and negotiate technical issues between the elements. This function would work as the technical arm of the Project Manager to help ensure that the Project cost, schedule, and risk objectives can be met during the Life Cycle. Some ICD Lessons Learned during the Space Shuttle Program (SSP) Life Cycle will include the use of hardware interface photos in the ICD, progressive life cycle design certification by analysis, test, & operations experience, assigning interface design engineers to Element Interface (EI) and Project technical panels, and linking interface design drawings with project build drawings

  13. The Future of Project Management in Technical Communication

    DEFF Research Database (Denmark)

    Kampf, Constance

    2006-01-01

    Project Management increasing shapes workplace communication, especially when technical commuicators participate in cross-disciplinary development teams. This paper looks at the future of project management in technical communication and argues for a communicative approach to project management...... for technical communication students. The Project Management course in the International Bachelor Program of Marketing and Management Communication at the Aarhus School of Business is described, and the implications fortechnical communication curricula are discussed....

  14. Yucca Mountain Site Characterization Project: Technical Data Catalog quarterly supplement

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1994-03-31

    The March 21, 1993, Department of Energy (DOE)/Nuclear Regulatory Commission (NRC) Site-Specific Procedural Agreement for Geologic Repository Site Investigation and Characterization Program requires the DOE to develop and maintain a catalog of data which will be updated and provided to the NRC at least quarterly. This catalog is to include a description of the data; the time (date), place, and method of acquisition; and where it may be examined. The Yucca Mountain Site Characterization Project (YMP) Technical Data Catalog is published and distributed in accordance with the requirements of the Site-Specific Agreement. The YMP Technical Data Catalog is a report based on reference information contained in the YMP Automated Technical Data Tracking System (ATDT). The reference information is provided by Participants for data acquired or developed in support of the YMP. The Technical Data Catalog is updated quarterly and published in the month following the end of each quarter. A complete revision to the Catalog is published at the end of each fiscal year. Supplements to the end-of-year edition are published each quarter. These supplements provide information related to new data items not included in previous quarterly updates and data items affected by changes to previously published reference information. The Technical Data Catalog, dated September 30, 1993, should be retained as the baseline document for the supplements until the end-of-year revision is published and distributed in October 1994.

  15. Yucca Mountain Site Characterization Project Technical Data Catalog (quarterly supplement)

    International Nuclear Information System (INIS)

    1993-01-01

    The June 1, 1985, Department of Energy (DOE)/Nuclear Regulatory Commission (NRC) Site-Specific Procedural Agreement for Geologic Repository Site Investigation and Characterization Program requires the DOE to develop and maintain a catalog of data which will be updated and provided to the NRC at least quarterly. This catalog is to include a description of the data; the time (date), place, and method of acquisition; and where it may be examined. The Yucca Mountain Site Characterization Project (YMP) Technical Data Catalog is published and distributed in accordance with the requirements of the Site-Specific Agreement. The YMP Technical Data Catalog is a report based on reference information contained in the YMP Automated Technical Data Tracking System (ATDT). The reference information is provided by Participants for data acquired or developed in support of the YMP. The Technical Data Catalog is updated quarterly and published in the month following the end of each quarter. A complete revision to the Catalog is published at the end of each fiscal year. Supplements to the end-of-year edition are published each quarter. These supplements provide information related to new data items not included in previous quarterly updates and data items affected by changes to previously published reference information. The Technical Data Catalog, dated December 31, 1992, should be retained as the baseline document for the supplements until the end-of-year revision is published and distributed in October 1993

  16. Yucca Mountain Site Characterization Project Technical Data Catalog

    International Nuclear Information System (INIS)

    1992-01-01

    The June 1, 1985, Department of Energy (DOE)/Nuclear, Regulatory Commission (NRC) Site-Specific Procedural Agreement for Geologic Repository Site Investigation and Characterization Program requires the DOE to develop and maintain a catalog of data which will be updated and provided to the NRC at least quarterly. This catalog is to include a description of the data; the time (date), place, and method of acquisition; and where it may be examined. The Yucca Mountain Site Characterization Project (YMP) Technical Data Catalog is published and distributed in accordance with the requirements of the Site-Specific Agreement. The YMP Technical Data Catalog is a report based on reference information contained in the YMP Automated Technical Data Tracking System (ATDT). The reference information is provided by Participants for data acquired or developed in support of the YMP. The Technical Data Catalog is updated quarterly and published in the month following the end of each quarter. Each new publication of the Technical Data Catalog supersedes the previous edition

  17. Yucca Mountain Site Characterization Project technical data catalog

    International Nuclear Information System (INIS)

    1992-01-01

    The June 1, 1985, Department of Energy (DOE)/Nuclear Regulatory Commission (NRC) Site-Specific Procedural Agreement for Geologic Repository Site Investigation and Characterization Program requires the DOE to develop and maintain a catalog of data which will be updated and provided to the NRC at least quarterly. This catalog is to include a description of the data; the time (date), place, and method of acquisition; and where it may be examined. The Yucca Mountain Site Characterization Project (YMP) Technical Data Catalog is published and distributed in accordance with the requirements of the Site-Specific Agreement. The YMP Technical Data Catalog is a report based on reference information contained in the YMP Automated Technical Data Tracking System (ATDT). The reference information is provided by Participants for data acquired or developed in support of the YMP. The Technical Data Catalog is updated quarterly and published in the month following the end of each quarter. Each new publication of the Technical Data Catalog supersedes the previous edition

  18. Yucca Mountain Site Characterization Project technical data catalog: Quarterly supplement

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1994-12-31

    The Department of Energy (DOE)/Nuclear Regulatory Commission (NRC) Site-Specific Procedural Agreement for Geologic Repository Site Investigation and Characterization Program requires the DOE to develop and maintain a catalog of data which will be updated and provided to the NRC at least quarterly. This catalog is to include a description of the data; the time (date), place, and method of acquisition; and where the data may be examined. The Yucca Mountain Site Characterization Project (YMP) Technical Data Catalog is published and distributed-in accordance with the requirements of the Site-Specific Agreement. The YMP Technical Data Catalog is a report based on reference information contained in the YMP Automated Technical Data Tracking System (ATDT). The reference information is provided by Participants for data acquired or developed in support of the YMP. The Technical Data Catalog is updated quarterly and distributed in the month following the end of each quarter. A complete revision to the catalog is published at the end of each fiscal year. Supplements to the end-of-year edition are published each quarter. These supplements provide information related to new data items not included in previous quarterly updates and data items affected by changes to previously published reference information. The Technical Data Catalog, dated September 30, 1994, should be retained as the baseline document for the supplements until the end-of-year revision is published and distributed in October 1995.

  19. Technical management of difference in CEPR nuclear power project

    International Nuclear Information System (INIS)

    Guo Ruiting

    2014-01-01

    The Thesis dissertate the application of technical management of difference in CEPR Nuclear Power Project from EPR technical bases, condition of a nuclear power plant site, engineering and procurement, construction, quality management, schedule management and experience feedback aspects. (author)

  20. The technical status of the supersara project at its termination

    International Nuclear Information System (INIS)

    Markovina, A.; Randles, J.

    1987-01-01

    On March 10th 1983 the Council of Ministers of the European Community adopted the decision to abandon the SuperSARA project. In the frame of this decision, the Management of the SuperSARA project formulated the guidelines to close the project, which included the preparation of the present final report. This report presents the final status of the project, which means that it reflects the situation in March 1983, with a few updates introduced shortly afterwards in conformity with the safety requirements which were being revised at that time. The aim of this report is to give a general description of activities which were carried on to implement the experimental programme and to illustrate some important achievements reached in specific areas. In addition, it is also intended to provide the access key to the documentation which was produced in the past years, so as to make the most significant technical material easily available for any possible future use

  1. The NIOSH Radiation Dose Reconstruction Project: managing technical challenges.

    Science.gov (United States)

    Moeller, Matthew P; Townsend, Ronald D; Dooley, David A

    2008-07-01

    Approximately two years after promulgation of the Energy Employees Occupational Illness Compensation Program Act, the National Institute for Occupational Safety and Health Office of Compensation and Analysis Support selected a contractor team to perform many aspects of the radiation dose reconstruction process. The project scope and schedule necessitated the development of an organization involving a comparatively large number of health physicists. From the initial stages, there were many technical and managerial challenges that required continuous planning, integration, and conflict resolution. This paper identifies those challenges and describes the resolutions and lessons learned. These insights are hopefully useful to managers of similar scientific projects, especially those requiring significant data, technical methods, and calculations. The most complex challenge has been to complete defensible, individualized dose reconstructions that support timely compensation decisions at an acceptable production level. Adherence to applying claimant-favorable and transparent science consistent with the requirements of the Act has been the key to establishing credibility, which is essential to this large and complex project involving tens of thousands of individual stakeholders. The initial challenges included garnering sufficient and capable scientific staff, developing an effective infrastructure, establishing necessary methods and procedures, and integrating activities to ensure consistent, quality products. The continuing challenges include maintaining the project focus on recommending a compensation determination (rather than generating an accurate dose reconstruction), managing the associated very large data and information management challenges, and ensuring quality control and assurance in the presence of an evolving infrastructure. The lessons learned concern project credibility, claimant favorability, project priorities, quality and consistency, and critical

  2. Office of Crystalline Repository Development FY 83 technical project plan

    International Nuclear Information System (INIS)

    1983-03-01

    The technical plan for FY 83 activities of the Office of Crystalline Repository Development is presented in detail. Crystalline Rock Project objectives are discussed in relation to the National Waste Terminal storage (NWTS) program. The plan is in full compliance with requirements mandated by the Nuclear Waste Policy Act of 1982. Implementation will comply with the requirements and criteria set forth in the Nuclear Regulatory Commission regulations (10 CFR 60) and the Environmental Protection Agency standard (40 CFR 191). Technical approaches and the related milestones and schedules are presented for each of the Level 3 NWTS work Breakdown Structure Tasks. These are: Systems, Waste Package, Site, Repository, Regulatory and Institutional, Test Facilities and Excavations, Land Acquisition, and Program Management

  3. Understanding the technical content of requirements in specification document

    DEFF Research Database (Denmark)

    Sudin, Mohd Nizam Bin; Ahmed-Kristensen, Saeema

    2011-01-01

    development process, is essential to be devised in advance. To achieve this aim, understanding how to formulate a good requirement is necessary and it is only possible if design engineers understand the technical content of a requirement. In aiming to understand the technical content of a requirement...

  4. 19 CFR 115.40 - Technical requirements for containers.

    Science.gov (United States)

    2010-04-01

    ... 19 Customs Duties 1 2010-04-01 2010-04-01 false Technical requirements for containers. 115.40...; DEPARTMENT OF THE TREASURY CARGO CONTAINER AND ROAD VEHICLE CERTIFICATION PURSUANT TO INTERNATIONAL CUSTOMS CONVENTIONS Procedures for Approval of Containers After Manufacture § 115.40 Technical requirements for...

  5. Technical assistance for Meharry Medical College Energy Efficiency Project. Final project status and technical report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-05-08

    This report presents the results of a program to provide technical assistance to Meharry Medical College. The purpose of the program is to facilitate Meharry`s effort to finance a campus-wide facility retrofit. The US Department of Energy (USDOE) funded the program through a grant to the Tennessee Department of Economic and Community Development (TECD). The University of Memphis-Technology and Energy Services (UM-TES), under contract to TECD, performed program services. The report has three sections: (1) introduction; (2) project definition, financing, and participants; and (3) opportunities for federal participation.

  6. UMTRA project technical assistance contractor quality assurance implementation plan for surface and ground water

    International Nuclear Information System (INIS)

    1994-09-01

    The Uranium Mill Tailings Remedial Action (UMTRA) Project Technical Assistance Contractor (TAC) Quality Assurance Implementation Plan (QAIP) outlines the primary requirements for integrating quality functions for TAC technical activities applied to the surface and ground water phases of the UMTRA Project. The QAIP is subordinate to the latest issue of the UMTRA Project TAC Quality Assurance Program Plan (QAPP). The QAIP addresses technical aspects of the TAC UMTRA Project surface and ground water programs. The QAIP is authorized and approved by the TAC Project Manager and QA manager. The QA program is designed to use monitoring, audit, and surveillance functions as management tools to ensure that all Project organization activities are carried out in a manner that will protect public health and safety, promote the success of the UMTRA Project and meet or exceed contract requirements

  7. Ice Load Project Final Technical Report

    Energy Technology Data Exchange (ETDEWEB)

    McCoy, Timothy J. [DNV GL, Seattle, WA (United States); Brown, Thomas [IFC Engineering, Calgary, AB (Canada); Byrne, Alex [DNV GL, Seattle, WA (United States)

    2014-10-30

    As interest and investment in offshore wind projects increase worldwide, some turbines will be installed in locations where ice of significant thickness forms on the water surface. This ice moves under the driving forces of wind, current, and thermal effects and may result in substantial forces on bottom-fixed support structures. The North and Baltic Seas in Europe have begun to see significant wind energy development and the Great Lakes of the United States and Canada may host wind energy development in the near future. Design of the support structures for these projects is best performed through the use of an integrated tool that can calculate the cumulative effects of forces due to turbine operations, wind, waves, and floating ice. The dynamic nature of ice forces requires that these forces be included in the design simulations, rather than added as static forces to simulation results. The International Electrotechnical Commission (IEC) standard[2] for offshore wind turbine design and the International Organization for Standardization (ISO) standard[3] for offshore structures provide requirements and algorithms for the calculation of forces induced by surface ice; however, currently none of the major wind turbine dynamic simulation codes provides the ability to model ice loads. The scope of work of the project described in this report includes the development of a suite of subroutines, collectively named IceFloe, that meet the requirements of the IEC and ISO standards and couples with four of the major wind turbine dynamic simulation codes. The mechanisms by which ice forces impinge on offshore structures generally include the forces required for crushing of the ice against vertical-sided structures and the forces required to fracture the ice as it rides up on conical-sided structures. Within these two broad categories, the dynamic character of the forces with respect to time is also dependent on other factors such as the velocity and thickness of the moving ice

  8. TECHNICAL RISK RATING OF DOE ENVIRONMENTAL PROJECTS - 9153

    International Nuclear Information System (INIS)

    Cercy, M.; Fayfich, Ronald; Schneider, Steven P.

    2008-01-01

    The U.S. Department of Energy's Office of Environmental Management (DOE-EM) was established to achieve the safe and compliant disposition of legacy wastes and facilities from defense nuclear applications. The scope of work is diverse, with projects ranging from single acquisitions to collections of projects and operations that span several decades and costs from hundreds of millions to billions US$. The need to be able to manage and understand the technical risks from the project to senior management level has been recognized as an enabler to successfully completing the mission. In 2008, DOE-EM developed the Technical Risk Rating as a new method to assist in managing technical risk based on specific criteria. The Technical Risk Rating, and the criteria used to determine the rating, provides a mechanism to foster open, meaningful communication between the Federal Project Directors and DOE-EM management concerning project technical risks. Four indicators (technical maturity, risk urgency, handling difficulty and resolution path) are used to focus attention on the issues and key aspects related to the risks. Pressing risk issues are brought to the forefront, keeping DOE-EM management informed and engaged such that they fully understand risk impact. Use of the Technical Risk Rating and criteria during reviews provides the Federal Project Directors the opportunity to openly discuss the most significant risks and assists in the management of technical risks across the portfolio of DOE-EM projects. Technical Risk Ratings can be applied to all projects in government and private industry. This paper will present the methodology and criteria for Technical Risk Ratings, and provide specific examples from DOE-EM projects

  9. Stability in licensing requirements: a technical perspective

    International Nuclear Information System (INIS)

    Szalay, R.A.

    1978-01-01

    The serious difficulties encountered in the licensing procedure for nuclear power plants in the United States have resulted in the elaboration of a Bill on the siting and licensing of nuclear installations for the purpose of reforming the present system. The author fears, however, that this Bill will not reduce the complexity of present regulations and will be unable to reach the object sought which is to reduce the length of the procedure; he analyses the technical and political reasons underlying this situation, and in particular the role of the staff of the Nuclear Regulatory Commission. (NEA) [fr

  10. River Protection Project waste feed delivery program technical performance measurement assessment plan

    International Nuclear Information System (INIS)

    O'TOOLE, S.M.

    1999-01-01

    This plan establishes a formal technical performance-monitoring program. Technical performance is assessed by establishing requirements based performance goals at the beginning of a program and routinely evaluating progress in meeting these goals at predetermined milestones throughout the project life cycle

  11. UMTRA project technical assistance contractor quality assurance implementation plan for surface and ground water, Revision 2

    International Nuclear Information System (INIS)

    1995-11-01

    This document contains the Technical Assistance Contractor (TAC) Quality Assurance Implementation Plan (QAIP) for the Uranium Mill Tailings Remedial Action (UMTRA) Project. The QAIP outlines the primary requirements for integrating quality functions for TAC technical activities applied to the surface and ground water phases of the UMTRA Project. The QA program is designed to use monitoring, audit, and surveillance activities as management tools to ensure that UMTRA Project activities are carried out in amanner to protect public health and safety, promote the success of the UMTRA Project, and meet or exceed contract requirements

  12. VGB-requirements regarding technical data for power plants

    International Nuclear Information System (INIS)

    Richnow, Joerg

    2009-01-01

    Much of the technical plant data resulting from the planning, construction and start-up of power plants is needed for subsequent management and maintenance. Because of this, VGB has taken the initiative and has defined standard minimum requirements from power plant operators for technical plant data. They relate to the details and structure of this data, the definition of material classes and characteristics for the main power plant components and IT implementation for delivery of the technical plant data. (orig.)

  13. Conjoint utility analysis of technical maturity and project progress of construction project

    Directory of Open Access Journals (Sweden)

    Ma Wei

    2016-01-01

    Full Text Available In this paper, taking construction project as the research object, the relationship between the project maturity index calculated by the construction project technical risks with different fine degree and the project progress index is studied, and the equilibrium relationship between the Party A’s utility curve and the Party B’s cost curve of using project maturity index and project progress index as the research variables is analyzed. The results show that, when the construction project technical risk division is more precise, the conjoint utility of the project's technical maturity index and the project progress is higher, and the project’s Party A and Party B two sides are closer to the optimal equilibrium. This shows that the construction project technical risk must be finely divided, and managed and controlled respectively, which will help to improve the conjoint utility of the project Party A and Party B two sides.

  14. 30 CFR 7.98 - Technical requirements.

    Science.gov (United States)

    2010-07-01

    ... this part with the following additional requirements: (1) A hydraulic, pneumatic, or other mechanically...) Pistons to piston rings; (2) Pistons to cylinder walls; (3) Piston rings to cylinder walls; (4) Cylinder head to cylinder block; (5) Valve stem to valve guide; or (6) Injector body to cylinder head. (m) Each...

  15. Plutonium immobilization project development and testing technical project office quality assurance program description

    International Nuclear Information System (INIS)

    Gould, T.H.; MacLean, L.M.; Ziemba, J.M.

    1999-01-01

    The Plutonium Immobilization Project (PIP) is one of several fissile materials disposition projects managed by the Department of Energy (DOE) Office of Fissile Materials Disposition (OFMD). The PIP is expected to evolve from the current Development and Testing (D and T) effort, to design, to construction, and finally to operations. Overall management and technical management of the D and T effort resides at the Lead Laboratory, Lawrence Livermore National Laboratory (LLNL), through the LLNL Manager, Fissile Materials Disposition Program (FMDP). Day to day project activities are managed by the D and T Technical Project Office (TPO), which reports to the LLNL Manager, FMDP. The D and T TPO consists of the Technical Manager, the TPO Quality Assurance (QA) Program Manager, and TPO Planning and Support Staff. This Quality Assurance Program Description (QAPD) defines the QA policies and controls that will be implemented by these TPO personnel in their management of D and T activities. This QAPD is consistent with and responsive to the Department of Energy Fissile Materials Disposition Program Quality Assurance Requirements Document (FMDP QARD). As the Project and upper level requirement's documents evolve, this QAPD will be updated as necessary to accurately define and describe the QA Program and Management of the PIP. The TPO has a policy that all development and testing activities be planned, performed and assessed in accordance with its customer's requirements, needs and expectations, and with a commitment to excellence and continuous improvement. The TPO QAPD describes implementation requirements which, when completed, will ensure that the project development and testing activities conform to the appropriate QA requirements. For the program to be effective, the TPO QA Program Manager will ensure that each site participating in D and T activities has developed a QAPD, which meets the customer's requirements, and has a designated quality leader in place. These customer

  16. Project structure plan requirements for the deconstruction projects

    International Nuclear Information System (INIS)

    Petrasch, Peter; Schmitt, Christian; Stapf, Meike

    2011-01-01

    The deconstruction of nuclear facilities requires due to the particular conditions and the size of the project a special project planning. The authors analyze the possible requirements to be fulfilled by a project structure plan for nuclear facilities, including personnel resources, organization structure, budget questions, operation and project oriented measures, possibility of modifications and supplements. Further topics include controlling and project realization procedures, documentation, third party activities (authorities, consultants, surveyors), logistics and transport, and radiation protection issues. Several questions remain for plants-specific planning, including the integration of the plant personnel, administrative work, project management, economic and financial issues, radioactive waste management issues.

  17. Technical program plan, Basalt Waste Isolation Project

    International Nuclear Information System (INIS)

    1979-12-01

    The Basalt Waste Isolation Project (BWIP) program as administered by the DOE's Richland Operations Office and Rockwell Hanford Operations is described. The objectives, scope and scientific technologies are discussed. The work breakdown structure of the project includes: project management and support, systems integration, geosciences, hydrology, engineered barriers, test facility design and construction, engineering testing, repository studies, and schedules. The budget of the program including operating and capital cost control is also included

  18. Technical requirements document for the waste flow analysis

    International Nuclear Information System (INIS)

    Shropshire, D.E.

    1996-05-01

    Purpose of this Technical Requirements Document is to define the top level customer requirements for the Waste Flow Analysis task. These requirements, once agreed upon with DOE, will be used to flow down subsequent development requirements to the model specifications. This document is intended to be a ''living document'' which will be modified over the course of the execution of this work element. Initial concurrence with the technical functional requirements from Environmental Management (EM)-50 is needed before the work plan can be developed

  19. 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)

  20. 47 CFR 15.407 - General technical requirements.

    Science.gov (United States)

    2010-10-01

    ... National Information Infrastructure Devices § 15.407 General technical requirements. (a) Power limits: (1... information or the use of repetitive codes used by certain digital technologies to complete frame or burst...

  1. 47 CFR 18.109 - General technical requirements.

    Science.gov (United States)

    2010-10-01

    ... MEDICAL EQUIPMENT General Information § 18.109 General technical requirements. ISM equipment shall be... filtering to provide adequate suppression of emissions on frequencies outside the frequency bands specified...

  2. Tank Farms Technical Safety Requirements [VOL 1 and 2

    Energy Technology Data Exchange (ETDEWEB)

    CASH, R.J.

    2000-12-28

    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).

  3. Technical report on comparative analysis of ASME QA requirements and ISO series

    International Nuclear Information System (INIS)

    Kim, Kwan Hyun

    2000-06-01

    This technical report provides the differences on the QA requirement ASME and ISO in nuclear fields. This report applies to the quality assurance(QA) programmes of the design of two requirement. The organization having overall responsibility for the nuclear design, preservation, fabrication shall be described in this report in each stage of design project

  4. Technical data management at the Yucca Mountain Site Characterization Project

    International Nuclear Information System (INIS)

    Statler, J.; Newbury, C.M.; Heitland, G.W.

    1992-01-01

    The Department of Energy/Office of Civilian Radioactive waste Management (DOE/OCRWM) is responsible for the characterization of Yucca Mountain, Nevada, to determine its potential as a site of a high-level radioactive waste repository. The characterization of Yucca Mountain encompasses many diverse investigations, both onsite and in laboratories across the country. Investigations are being conducted of the geology, hydrology, mineralogy, paleoclimate, geotechnical properties, and archeology of the area, to name a few. Effective program management requires that data from site investigations be processed, interpreted and disseminated in a timely manner to support model development and validation, repository design, and performance assessment. The Program must also meet regulatory requirements for making the technical data accessible to a variety of external users throughout the life of the Project. Finally, the DOE/OCRWM must make available the data or its description and access location available for use in support of the license application and supporting documentation. To accomplish these objectives, scientific and engineering data, generated by site characterization activities, and technical data, generated by environmental and socioeconomic impact assessment activities, must be systematically identified, cataloged, stored and disseminated in a controlled manner

  5. The Southern Forest Futures Project: technical report

    Science.gov (United States)

    David N. Wear; John G. Greis

    2013-01-01

    Please visit the Southern Forest Futures Project website for more information.The Southern Forest Futures Project provides a science-based “futuring” analysis of the forests of the 13 States of the Southeastern United States. With findings...

  6. Subsurface Contamination Focus Area technical requirements. Volume 1: Requirements summary

    International Nuclear Information System (INIS)

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

    1996-10-01

    This document summarizes functions and requirements for remediation of source term and plume sites identified by the Subsurface Contamination Focus Area. Included are detailed requirements and supporting information for source term and plume containment, stabilization, retrieval, and selective retrieval remedial activities. This information will be useful both to the decision-makers within the Subsurface Contamination Focus Area (SCFA) and to the technology providers who are developing and demonstrating technologies and systems. Requirements are often expressed as graphs or charts, which reflect the site-specific nature of the functions that must be performed. Many of the tradeoff studies associated with cost savings are identified in the text

  7. 24 CFR 234.26 - Project requirements.

    Science.gov (United States)

    2010-04-01

    ... Commissioner for the purpose of constructing or converting the project in phases or stages, any special right..., the management company, the real estate broker, and the project developer, but the lender must ensure... 24 Housing and Urban Development 2 2010-04-01 2010-04-01 false Project requirements. 234.26...

  8. The international Chernobyl project. Technical report

    International Nuclear Information System (INIS)

    1991-01-01

    This report contains the findings of the International Chernobyl Project. Separate chapters deal with the history of the accident and the Soviet emergency measures, environmental contamination, radiation exposure of the population, health impact, and protective measures. The conclusions and recommendations of the Project are presented, and an annex gives the available data on cesium 137 and strontium 90 contamination levels in populated areas of the BSSR, the RSFSR and the UkrSSR from June/July 1989: these data were used to draw up the area contamination maps. Ref, figs and tabs

  9. ALWR utility requirements - A technical basis for updated emergency planning

    International Nuclear Information System (INIS)

    Leaver, David E.W.; DeVine, John C. Jr.; Santucci, Joseph

    2004-01-01

    U.S. utilities, with substantial support from international utilities, are developing a comprehensive set of design requirements in the form of a Utility Requirements Document (URD) as part of an industry wide effort to establish a technical foundation for the next generation of light water reactors. A key aspect of the URD is a set of severe accident-related design requirements which have been developed to provide a technical basis for updated emergency planning for the ALWR. The technical basis includes design criteria for containment performance and offsite dose during severe accident conditions. An ALWR emergency planning concept is being developed which reflects this severe accident capability. The main conclusion from this work is that the likelihood and consequences of a severe accident for an ALWR are fundamentally different from that assumed in the technical basis for existing emergency planning requirements, at least in the U.S. The current technical understanding of severe accident risk is greatly improved compared to that available when the existing U.S. emergency planning requirements were established nearly 15 years ago, and the emerging ALWR designs have superior core damage prevention and severe accident mitigation capability. Thus, it is reasonable and prudent to reflect this design capability in the emergency planning requirements for the ALWR. (author)

  10. Research Projects, Technical Reports and Publications

    Science.gov (United States)

    Oliger, Joseph

    1996-01-01

    The Research Institute for Advanced Computer Science (RIACS) was established by the Universities Space Research Association (USRA) at the NASA Ames Research Center (ARC) on June 6, 1983. RIACS is privately operated by USRA, a consortium of universities with research programs in the aerospace sciences, under contract with NASA. The primary mission of RIACS is to provide research and expertise in computer science and scientific computing to support the scientific missions of NASA ARC. The research carried out at RIACS must change its emphasis from year to year in response to NASA ARC's changing needs and technological opportunities. A flexible scientific staff is provided through a university faculty visitor program, a post doctoral program, and a student visitor program. Not only does this provide appropriate expertise but it also introduces scientists outside of NASA to NASA problems. A small group of core RIACS staff provides continuity and interacts with an ARC technical monitor and scientific advisory group to determine the RIACS mission. RIACS activities are reviewed and monitored by a USRA advisory council and ARC technical monitor. Research at RIACS is currently being done in the following areas: Advanced Methods for Scientific Computing High Performance Networks During this report pefiod Professor Antony Jameson of Princeton University, Professor Wei-Pai Tang of the University of Waterloo, Professor Marsha Berger of New York University, Professor Tony Chan of UCLA, Associate Professor David Zingg of University of Toronto, Canada and Assistant Professor Andrew Sohn of New Jersey Institute of Technology have been visiting RIACS. January 1, 1996 through September 30, 1996 RIACS had three staff scientists, four visiting scientists, one post-doctoral scientist, three consultants, two research associates and one research assistant. RIACS held a joint workshop with Code 1 29-30 July 1996. The workshop was held to discuss needs and opportunities in basic research in

  11. Integrated Project Control and Technical Support

    International Nuclear Information System (INIS)

    Kim, Jun Yeon; Kim, Jun Yeon; Joo, Po Kook and others

    2005-08-01

    First, Since PEFP puts it's aim on technology innovation through collaboration and technological fusion among the sub-projects from the various fields. It has been tried to make the sub-projects consist with the goal of the whole project through building and running the integrated project control system. Also, adopting CPM(Critical Process Management), intensive process management framework has been founded. Secondly, for the every procedure, including purchase, building, installation and a trial running, license, quality control, etc., could be efficiently executed, every related task has been carried out. And, the tasks involved in international cooperative relationship and host site selection are carried out as well, so that PEFP could be firmly supported. Finally, Strategic management procedures including TRM(Technology Road Map), economic evaluation on PEFP, preliminary evaluation on company-involved R and D and TRESIS(Technology, Resources, Economic Evaluation System) are made up not only for the purpose of managing efficiency and effectiveness on the investment, but also for the purpose of life cycle management from developing stage to commercializing stage

  12. Minewater heat recovery project. Final Technical report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1992-04-01

    This report consists of three sections: (1) Design, experimental testing and performance analysis of the 20-ft long DBHE (Downhole Bundle Heat Exchanger); (2) Modified design of mine water heat exchanger; and (3) Performance tests on mine water heat exchanger. Appendices summarize design calculations, discuss the scope of the work tasks, and present a diary of the progress throughout the research and development project.

  13. Integrated Project Control and Technical Support

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Jun Yeon; Kim, Jun Yeon; Joo, Po Kook and others

    2005-08-15

    First, Since PEFP puts it's aim on technology innovation through collaboration and technological fusion among the sub-projects from the various fields. It has been tried to make the sub-projects consist with the goal of the whole project through building and running the integrated project control system. Also, adopting CPM(Critical Process Management), intensive process management framework has been founded. Secondly, for the every procedure, including purchase, building, installation and a trial running, license, quality control, etc., could be efficiently executed, every related task has been carried out. And, the tasks involved in international cooperative relationship and host site selection are carried out as well, so that PEFP could be firmly supported. Finally, Strategic management procedures including TRM(Technology Road Map), economic evaluation on PEFP, preliminary evaluation on company-involved R and D and TRESIS(Technology, Resources, Economic Evaluation System) are made up not only for the purpose of managing efficiency and effectiveness on the investment, but also for the purpose of life cycle management from developing stage to commercializing stage.

  14. Integrated Project Control and Technical Support

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Jun Yeon; Joo, Po Kook; Kim, Gye Ryung (and others)

    2003-06-15

    First, Since PEFP puts it's aim on technology innovation through collaboration and technological fusion among the subprojects from the various fields, It has been tried to make the subprojects consist with the goal of the whole project through building and running the integrated project control system. Also, adopting CPM(Critical Process Management), intensive process management framework has been founded. Secondly, for the every procedure, including purchase, building, installation and a trial running, license, quality control, etc., could be efficiently executed, every related task has been carried out. And, the tasks involved in international cooperative relationship and host site selection are carried out as well, so that PEFP could be firmly supported. Finally, TRM(Technology Road Map) is made up not only for the purpose of managing efficiency and effectiveness on the investment, but also for the purpose of life cycle management from developing stage to commercializing stage.

  15. Legal control of large technical projects

    International Nuclear Information System (INIS)

    Papier, H.J.

    1981-01-01

    More legal security, acceleration of court procedures, a fair consideration of the interests of the permission recipients, avoidance of any kind of political usurpation, as well as the attempts of judges not to present an amateuriser scientific-technical indepth-knowledge cannot be accomplished via Sporadic appeals with partially para-legal reservedness. This also goes for those frantic attempts to institute socalled ''norm selections'', and for efforts of attempting to influence objective rights by modifying grounds for contestation. What is needed is a legistation that, especially in the area of large industrial plants, exerts appropriate statuatory influence. So far, this has not been the case. It is up to the legislation to define permission standards, have them assessed and judged by experts, and harmonize them with the appropriate procedural rights. If this is done, the power of balance with regards to large industrial plants will be re-established. Curtailment of the lengthy process of official channels must also be considered. If a preliminary administrative procedure is already formalized, a second fact-establishing instance should be waived. (orig./HP) [de

  16. Radiation requirements for uranium project approvals

    International Nuclear Information System (INIS)

    Hondros, J.

    2014-01-01

    Uranium mining projects in Australia must receive approval under both state and national laws based on a wide ranging impact assessment of the project. The process may take a number of years and involves multiple levels and parts of government and public consultation and scrutiny. The impact assessment is broad and usually covers; environmental, social, health, public safety and economic aspects. Information provided in the approvals documentation needs to be presented in a credible and understandable manner for all audiences. This means making complex information simpler, while making sure that it maintains its technical integrity. Poorly communicated information, which is overly complex, overly simplified or incomplete, can result in significant delays to the project approval which can potentially impact on project timelines. For uranium projects, along with other projects involving radioactive materials, such as minerals sands and rare earths, radiation and its impacts usually draw a disproportionate amount of both government and public scrutiny compared to other potential impacts and risks. It is therefore of key importance that radiation assessments are properly performed and results clearly presented and communicated with sufficient detail for stakeholders to make informed decisions. It is also important to ensure that the radiation risk is presented in perspective with other risks of the project. This presentation outlines a structure for a radiation impact assessment based on experience from a number of projects in Australia. The structure aims to be clear and simple and ensure the right balance between scientific fact, digestible information and demonstrable competence. (author)

  17. THE RELATIONSHIP BETWEEN TECHNICAL AND SOCIAL NORMS IN ENVIRONMENTAL PROJECT

    OpenAIRE

    Jasminka Lažnjak

    1992-01-01

    In the article the relationship between system of technical and system of social norms in ecological project has been considered from constructivist standpoint in sociology of technology. For adequate solution of technological problem of enviromental pollution by hydrocarbons is necessary to define beside technical also system of social norms. Sociological analysis of accidents in transportation of hydrocarbons is suggested in purpose of clear definition of responsibilities of certain social ...

  18. Technical Requirements Analysis and Control Systems (TRACS) Initial Operating Capability (IOC) documentation

    Science.gov (United States)

    Hammond, Dana P.

    1991-01-01

    The Technical Requirements Analysis and Control Systems (TRACS) software package is described. TRACS offers supplemental tools for the analysis, control, and interchange of project requirements. This package provides the fundamental capability to analyze and control requirements, serves a focal point for project requirements, and integrates a system that supports efficient and consistent operations. TRACS uses relational data base technology (ORACLE) in a stand alone or in a distributed environment that can be used to coordinate the activities required to support a project through its entire life cycle. TRACS uses a set of keyword and mouse driven screens (HyperCard) which imposes adherence through a controlled user interface. The user interface provides an interactive capability to interrogate the data base and to display or print project requirement information. TRACS has a limited report capability, but can be extended with PostScript conventions.

  19. VIRTUAL PHILOSOPHER PROJECT: PHILOSOPHICAL, PEDAGOGICAL AND TECHNICAL ASPECTS

    Directory of Open Access Journals (Sweden)

    E. V. Kuchinov

    2017-01-01

    Full Text Available The article describes philosophical and pedagogical aspects of an idea of the ‘virtual philosopher’ project developed at creative sessions at Minin University and technically concretized during interaction with the Laboratory of Mobile Services. ‘Virtual philosopher’ is thought to deliver creative automation of routine operations; producing contingent matter for philosophical processing as well as elements of the philosophical artificial intelligence and forms of ‘artificial life’. Project implementation may lead to the creation of an unparalleled educational technology that functions on the principles of flexibility, nonlinearity, affective inclusion and gamification of the educational process. Based on specific character of problems raised, rhizomatic analysis of the philosophical communities’ requests, assessment of their technical feasibility and technical development, provisions are made on the feasibility, prospects and productivity of this project.

  20. Technical requirement of experiments and facilities for fusion nuclear technology

    International Nuclear Information System (INIS)

    Abdou, M.; Tillak, M.; Gierszwski, P.; Grover, J.; Puigh, R.; Sze, D.K.; Berwald, D.

    1986-06-01

    The technical issues and requirements of experiments and facilities for fusion nuclear technology (FNT) have been investigated. The nuclear subsystems addressed are: a) blanket, b) radiation shield, c) tritium processing system, and d) plasma interactive components. Emphasis has been placed on the important and complex development problems of the blanket. A technical planning process for FNT has been developed and applied, including four major elements: 1) characterization of issues, 2) quantification of testing requirements, 3) evaluation of facilities, and 4) development of a test plan to identify the role, timing, characteristics and costs of major experiments and facilities

  1. Spent Nuclear Fuel Project Canister Storage Building Functions and Requirements

    International Nuclear Information System (INIS)

    KLEM, M.J.

    2000-01-01

    In 1998, a major change in the technical strategy for managing Multi Canister Overpacks (MCO) while stored within the Canister Storage Building (CSB) occurred. The technical strategy is documented in Baseline Change Request (BCR) No. SNF-98-006, Simplified SNF Project Baseline (MCO Sealing) (FDH 1998). This BCR deleted the hot conditioning process initially adopted for the Spent Nuclear Fuel Project (SNF Project) as documented in WHC-SD-SNF-SP-005, Integrated Process Strategy for K Basins Spent Nuclear Fuel (WHC 199.5). In summary, MCOs containing Spent Nuclear Fuel (SNF) from K Basins would be placed in interim storage following processing through the Cold Vacuum Drying (CVD) facility. With this change, the needs for the Hot Conditioning System (HCS) and inerting/pressure retaining capabilities of the CSB storage tubes and the MCO Handling Machine (MHM) were eliminated. Mechanical seals will be used on the MCOs prior to transport to the CSB. Covers will be welded on the MCOs for the final seal at the CSB. Approval of BCR No. SNF-98-006, imposed the need to review and update the CSB functions and requirements baseline documented herein including changing the document title to ''Spent Nuclear Fuel Project Canister Storage Building Functions and Requirements.'' This revision aligns the functions and requirements baseline with the CSB Simplified SNF Project Baseline (MCO Sealing). This document represents the Canister Storage Building (CSB) Subproject technical baseline. It establishes the functions and requirements baseline for the implementation of the CSB Subproject. The document is organized in eight sections. Sections 1.0 Introduction and 2.0 Overview provide brief introductions to the document and the CSB Subproject. Sections 3.0 Functions, 4.0 Requirements, 5.0 Architecture, and 6.0 Interfaces provide the data described by their titles. Section 7.0 Glossary lists the acronyms and defines the terms used in this document. Section 8.0 References lists the

  2. Competency model for the project managers of technical projects

    Science.gov (United States)

    Duncan, William R.

    1992-05-01

    Traditional job description techniques were developed to support compensation decisions for hourly wage earners in a manufacturing environment. Their resultant focus on activities performed on the job works well in this environment where the ability to perform the activity adequately is objectively verifiable by testing and observation. Although many organizations have adapted these techniques for salaried employees and service environments, the focus on activities performed has never been satisfactory. For example, stating that a project manager `prepares regular project status reports' tells us little about what to look for in a potential project manager or how to determine if a practicing project manager is ready for additional responsibilities. The concept of a `competency model' has been developed within the last decade to address this shortcoming. Competency models focus on what skills are needed to perform the tasks defined by the job description. For example, a project manager must be able to communicate well both orally and in writing in order to `prepare regular project status reports.'

  3. AFSC Laboratory Management Information Requirements Project

    National Research Council Canada - National Science Library

    1982-01-01

    This document was developed under the auspices of the Laboratory IRM (LIRM) Management Working Group in response to AFSC Program Directive 0008-81-1, Management Information Requirement Project (23 February 1981...

  4. 78 FR 52963 - 60-Day Notice of Proposed Information Collection: Technical Processing Requirements for...

    Science.gov (United States)

    2013-08-27

    ... Information Collection: Technical Processing Requirements for Multifamily Project Mortgage Insurance AGENCY...: HUD is seeking approval from the Office of Management and Budget (OMB) for the information collection... interested parties on the proposed collection of information. The purpose of this notice is to allow for 60...

  5. Technical report of comparison in design control on R and D and industrial quality requirements

    International Nuclear Information System (INIS)

    Kim, Kwan Hyun

    2000-06-01

    This technical report provides the methods on how to establish the requirements on nuclear R and D facilities. This report applies to the quality assurance(QA) programmes of the design, fabrication in research reactor. The organization having overall responsibility for the nuclear power item design, preservation, fabrication shall be described in this report in each stage of nuclear project

  6. 24 CFR 92.612 - Project requirements.

    Science.gov (United States)

    2010-04-01

    ... 24 Housing and Urban Development 1 2010-04-01 2010-04-01 false Project requirements. 92.612 Section 92.612 Housing and Urban Development Office of the Secretary, Department of Housing and Urban Development HOME INVESTMENT PARTNERSHIPS PROGRAM American Dream Downpayment Initiative § 92.612 Project...

  7. Los Alamos National Laboratory Environmental Restoration Project quarterly technical report, April--June 1994

    Energy Technology Data Exchange (ETDEWEB)

    1994-08-18

    This quarterly report describes the technical status of activities in the Los Alamos National Laboratory Environmental Restoration (ER) Project. Each activity is identified by an activity data sheet number, a brief title describing the activity or the technical area where the activity is located, and the name of the project leader. The Hazardous and Solid Waste Amendments (HSWA) portion of the facility operating permit requires the submission of a technical progress report on a quarterly basis. This report, submitted to fulfill the permit`s requirement, summarizes the work performed and the results of sampling and analysis in the ER Project. Suspect waste found include: Radionuclides, high explosives, metals, solvents and organics. The data provided in this report have not been validated. These data are considered ``reviewed data.``

  8. Final Technical Report. Project Boeing SGS

    Energy Technology Data Exchange (ETDEWEB)

    Bell, Thomas E. [The Boeing Company, Seattle, WA (United States)

    2014-12-31

    Boeing and its partner, PJM Interconnection, teamed to bring advanced “defense-grade” technologies for cyber security to the US regional power grid through demonstration in PJM’s energy management environment. Under this cooperative project with the Department of Energy, Boeing and PJM have developed and demonstrated a host of technologies specifically tailored to the needs of PJM and the electric sector as a whole. The team has demonstrated to the energy industry a combination of processes, techniques and technologies that have been successfully implemented in the commercial, defense, and intelligence communities to identify, mitigate and continuously monitor the cyber security of critical systems. Guided by the results of a Cyber Security Risk-Based Assessment completed in Phase I, the Boeing-PJM team has completed multiple iterations through the Phase II Development and Phase III Deployment phases. Multiple cyber security solutions have been completed across a variety of controls including: Application Security, Enhanced Malware Detection, Security Incident and Event Management (SIEM) Optimization, Continuous Vulnerability Monitoring, SCADA Monitoring/Intrusion Detection, Operational Resiliency, Cyber Range simulations and hands on cyber security personnel training. All of the developed and demonstrated solutions are suitable for replication across the electric sector and/or the energy sector as a whole. Benefits identified include; Improved malware and intrusion detection capability on critical SCADA networks including behavioral-based alerts resulting in improved zero-day threat protection; Improved Security Incident and Event Management system resulting in better threat visibility, thus increasing the likelihood of detecting a serious event; Improved malware detection and zero-day threat response capability; Improved ability to systematically evaluate and secure in house and vendor sourced software applications; Improved ability to continuously monitor

  9. 78 FR 1823 - Cable Television Technical and Operational Requirements

    Science.gov (United States)

    2013-01-09

    ... FEDERAL COMMUNICATIONS COMMISSION 47 CFR Part 79 [MB Docket No. 12-217; DA 12-2081] Cable Television Technical and Operational Requirements AGENCY: Federal Communications Commission. ACTION: Proposed rule; extension of reply comment period. SUMMARY: In this document, the Commission extends the deadline...

  10. 24 CFR 511.11 - Project requirements.

    Science.gov (United States)

    2010-04-01

    ... low income occupancy or rent projections, or restrictions on return on investment or other similar policies that prevent an owner, whether for-profit or non-profit, from maximizing return or setting rent... requirements and with the affirmative marketing requirements and procedures adopted under § 511.13, for the...

  11. Digital projection radiography. Technical principles, image properties and potential applications

    International Nuclear Information System (INIS)

    Busch, H.P.

    1999-01-01

    The history of development of digital projection radiography as a diagnostic method is presented in a comprehensive survey. The various technical principles are explained in detail and illustrated by means of graphic figures and digital X-ray pictures. A comparative assessment of currently applied radiographic systems is given and the potential clinical applications of the method of digital projection radiography are discussed. (orig./CB) [de

  12. Integrating public information activities on a technical project

    International Nuclear Information System (INIS)

    Little, Sh. K.; Vecchiola, S.F.

    1984-01-01

    Through gradual evolution and successful performance, the WIPP Communications group has gained respect and recognition as a dual service organization that offers numerous benefits to a technical project. Westinghouse assembled a team that has successfully coordinated and encouraged an exchange of information not only with the public information realm but also as a project service and function. WIPP has combined educational services, external and employee communication and public information into one unit called ''Communications''

  13. Problems about the analysis of technical requirements compliance in NPPPCI systems

    International Nuclear Information System (INIS)

    Perello, M.

    1978-01-01

    The display of the problems that the analysis of the technical requirements compliance bring along is presented. In the project of nuclear power plants, above all, the influence of national and international standards in the analysis of the adjustment of requirements established by the governments of nuclear safety of the different countries. In the oral presentation greater emphasis is made on the difficulties that the PSAR evaluation brings when the lack of technical standards in the owner country makes necessary the use of other countries rules. (author)

  14. A technical description of the FlexHouse Project Testbed

    DEFF Research Database (Denmark)

    Sørensen, Jens Otto

    2000-01-01

    This paper describes the FlexHouse project testbed; a server dedicated to experiments within the FlexHouse project. The FlexHouse project is a project originating from The Business Computing Research Group at The Aarhus School of Business. The purpose of the project is to identify and develop...... methods that satisfy the following three requirements. Flexibility with respect to evolving data sources. Flexibility with respect to change of information needs. Efficiency with respect to view management....

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

    International Nuclear Information System (INIS)

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

    1947-01-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

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

    1947-03-10

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

  17. Supplemental design requirements document, Project W026

    International Nuclear Information System (INIS)

    Weidert, J.R.

    1993-01-01

    This document supplements and extends the Functional Design Criteria, SP-W026-FDC-001, for the Waste Receiving and Processing Facility (WRAP), Module 1. It provides additional detailed requirements, summarizes key Westinghouse Hanford Company design guidance, and establishes baseline technical agreements to be used in definitive design of the WRAP-1 facility. Revision 3 of the Supplemental Design Requirements Document has been assigned an Impact Level of 3ESQ based on the content of the entire revision. The actual changes made from Revision 2 have an Impact Level of 3S and the basis for these changes was previously reviewed and approved per WHC correspondence No. 9355770

  18. Iowa Hill Pumped Storage Project Investigations - Final Technical Report

    Energy Technology Data Exchange (ETDEWEB)

    Hanson, David [Sacramento Municipal Unitlity District, Sacramento, CA (United States)

    2016-07-01

    This Final Technical Report is a summary of the activities and outcome of the Department of Energy (DOE) Assistance Agreement DE-EE0005414 with the Sacramento Municipal Utility District (SMUD). The Assistance Agreement was created in 2012 to support investigations into the Iowa Hill Pumped-storage Project (Project), a new development that would add an additional 400 MW of capacity to SMUD’s existing 688MW Upper American River Hydroelectric Project (UARP) in the Sierra Nevada mountains east of Sacramento, California.

  19. Legal control of technical large-scale projects

    International Nuclear Information System (INIS)

    Kuhnt, D.

    1981-01-01

    The principle derived from experience that large projects require approval by the courts may not longer be valid. On the contrary, the courts are only entitled to real legal control according to the principle of the division of powers. If not accurately defined legal terms cannot be waived, the administration has to set the frame for review by courts by technical standards to be given in statutory ordinances, administrative provisions and administrative instructions. The average term of administrative proceedings has to be shortened considerably. The plaintiff as well as the beneficiaries of the act of licensing have a right to a prompt decision. The immediate execution of a decision can, on principle, also not be waived in future. More than up to now, the careful consideration of the interests and not an anticipated judgement on the main issue has to be the subject of legal examination according to section 80, subsection 5 of the German code of administrative procedure (Verwaltungsgerichtsordnung). (orig./HP) [de

  20. Cold Vacuum Drying (CVD) Facility Technical Safety Requirements

    International Nuclear Information System (INIS)

    KRAHN, D.E.

    2000-01-01

    The Technical Safety Requirements (TSRs) for the Cold Vacuum Drying Facility define acceptable conditions, safe boundaries, bases thereof, and management or administrative controls required to ensure safe operation during receipt of multi-canister overpacks (MCOs) containing spent nuclear fuel. removal of free water from the MCOs using the cold vacuum drying process, and inerting and testing of the MCOs before transport to the Canister Storage Building. Controls required for public safety, significant defense in depth, significant worker safety, and for maintaining radiological and toxicological consequences below risk evaluation guidelines are included

  1. Technical Safety Requirements for the Gamma Irradiation Facility (GIF)

    CERN Document Server

    Mahn, J A E M J G

    2003-01-01

    This document provides the Technical Safety Requirements (TSR) for the Sandia National Laboratories Gamma Irradiation Facility (GIF). The TSR is a compilation of requirements that define the conditions, the safe boundaries, and the administrative controls necessary to ensure the safe operation of a nuclear facility and to reduce the potential risk to the public and facility workers from uncontrolled releases of radioactive or other hazardous materials. These requirements constitute an agreement between DOE and Sandia National Laboratories management regarding the safe operation of the Gamma Irradiation Facility.

  2. Technical modifications and management innovations in exporting nuclear reactor projects

    International Nuclear Information System (INIS)

    Mao Xiaoming; Qin Xijiu; Ding Hu; Xue Zhaoqun; Wen Shengjun

    2009-01-01

    As a main channel for the foreign economic cooperation of China nuclear industry, China Zhongyuan Engineering Corporation (CZEC) has been constantly engaged in technical modifications and management innovations in its exporting nuclear reactor projects. In the implementation of heavy water research reactor contract in Algeria, CZEC had established a complete and adequate design standards system in compliance with the international standards, and made significant modifications to the reference reactor in the aspects of reactor power and reactor safety, solved quite some technical issues which-affected the reactor technical performance. The modifications and improvements enabled the technical parameters, safety features, reactor multipurpose application to attain to the advanced level in the world. In the 300 MWe PWR NPPs in Pakistan, safety features had been updated in line with upgrading regulatory requisites. The design philosophy and technology application demonstrated CZEC' s creation and innovation on basis of constant safety enhancement of nuclear power projects. Efforts had also been made by CZEC' s creation and innovation on basis of constant safety enhancement of nuclear power projects. Efforts had also been made by CZEC in promoting China made equipment items and components exportation. (authors)

  3. Technical products for radiation shielding. Shield assembled from lead blocks for radiation protection. General technical requirements

    International Nuclear Information System (INIS)

    1981-01-01

    The object of this standard description is the general technological requirements of 50 and 100 mm thick radiation protection shields assembled from lead blocks. The standard contains the definitions, types, parameters and dimensions of shields, their technical and acceptance criteria with testing methods, tagging, packaging, transportation and storage requirements, producer's liability. Some illustrated assembling examples, preferred parameters and dosimetry methods for shield inspection are given. (R.P.)

  4. NTRCI Legacy Engine Research and Development Project Final Technical Report

    Energy Technology Data Exchange (ETDEWEB)

    Smith-Holbert, Connie [National Transportation Research Center, Inc., Knoxville, TN (United States); Petrolino, Joseph [National Transportation Research Center, Inc., Knoxville, TN (United States); Watkins, Bart [Power Source Technologies Inc., Corvallis, OR (United States); Irick, David [Power Source Technologies Inc., Corvallis, OR (United States)

    2011-12-31

    The Legacy engine is a completely new design, transitional diesel engine, replacing the reciprocating engine with a rotary engine. The Legacy engine offers significant advances over conventional internal combustion engines in 1) power to weight ratio; 2) multiple fuel acceptance; 3) fuel economy; and 4) environmental compliance. These advances are achieved through a combination of innovative design geometry, rotary motion, aspiration simplicity, and manufacturing/part simplicity. The key technical challenge to the Legacy engine's commercialization, and the focus of this project, was the development of a viable roton tip seal. The PST concept for the roton tip seal was developed into a manufacturable design. The design was evaluated using a custom designed and fabricated seal test fixture and further refined. This design was incorporated into the GEN2.5A prototype and tested for achievable compression pressure. The Decision Point at the end of Phase 1 of the project (described below) was to further optimize the existing tip seal design. Enhancements to the tip seal design were incorporated into the GEN2.5B prototype and tested and evaluated using the iterative research strategy described below. Compression pressures adequate for compression ignition of diesel fuel were achieved, although not consistently in all combustion volumes. The variation in compression pressures was characterized versus design features. As the roton tip seal performance was improved, results pointed toward inadequate performance of the housing side seals. Enhancement of the housing side seal system was accomplished using a custom designed side seal test fixture. The design enhancements developed with the test fixture were also incorporated into the GEN2.5B prototype and tested and evaluated using the iterative research strategy described below. Finally, to simplify the requirements for the roton tip seals and to enhance the introduction and combustion of fuel, a flush-mount fuel injector

  5. THE RELATIONSHIP BETWEEN TECHNICAL AND SOCIAL NORMS IN ENVIRONMENTAL PROJECT

    Directory of Open Access Journals (Sweden)

    Jasminka Lažnjak

    1992-12-01

    Full Text Available In the article the relationship between system of technical and system of social norms in ecological project has been considered from constructivist standpoint in sociology of technology. For adequate solution of technological problem of enviromental pollution by hydrocarbons is necessary to define beside technical also system of social norms. Sociological analysis of accidents in transportation of hydrocarbons is suggested in purpose of clear definition of responsibilities of certain social actors and for modification of existing laws for enviromental protection (the paper is published in Croatian.

  6. Risk impact of BWR technical specifications requirements during shutdown

    International Nuclear Information System (INIS)

    Staple, B.D.; Kirk, H.K.; Yakle, J.

    1994-10-01

    This report presents an application of probabilistic models and risk based criteria for determining the risk impact of the Limiting Conditions of Operations (LCOs) in the Technical Specifications (TSs) of a boiling water reactor during shutdown. This analysis studied the risk impact of the current requirements of Allowed Outage Times (AOTs) and Surveillance Test Intervals (STIs) in eight Plant Operational States (POSs) which encompass power operations, shutdown, and refueling. This report also discusses insights concerning TS action statements

  7. Ergonomic requirements for the operation of machines and technical equipment

    Directory of Open Access Journals (Sweden)

    Górny Adam

    2017-01-01

    Full Text Available In order to operate machinery and equipment safely, it is critical for the solutions in place to conform to design-related and operating requirements. Design-related requirements are primarily the responsibility of machine designers/developers and manufacturers. Operating requirements should be satisfied by employers, who are responsible for ensuring safe working conditions for their employees. Under applicable laws, machinery and equipment should be designed, produced and then operated without placing excessive loads on workers and in keeping with machine functionality and intended use. One should also ensure that machinery and equipment can be maintained and adjusted without exposing their operators to hazards. Ergonomic criteria are an integral part of such requirements. They ensure that human users and operators of technical equipment are enabled to function properly. Design-related requirements are viewed as a priority safety consideration. While they facilitate the use of technical tools, the actual safety of employees ultimately depends on the satisfaction of specific requirements during operation.

  8. International power projections and capital requirements

    International Nuclear Information System (INIS)

    Ann, H.

    1989-01-01

    This work is related to the international power projections and capital requirements of all kinds of energy and the share of electricity. It is also related to the so-called greenhouse effect carbon dioxide concentration in atmosphere. (A.C.A.S.)

  9. 42 CFR 65.4 - Project requirements.

    Science.gov (United States)

    2010-10-01

    ... 42 Public Health 1 2010-10-01 2010-10-01 false Project requirements. 65.4 Section 65.4 Public Health PUBLIC HEALTH SERVICE, DEPARTMENT OF HEALTH AND HUMAN SERVICES FELLOWSHIPS, INTERNSHIPS, TRAINING... appropriate academic disciplines and talents. Joint applications must describe the cooperative arrangements...

  10. The Effect of Technical Assistance on Involvement and Use: The Case of a Research, Evaluation, and Technical Assistance Project

    Science.gov (United States)

    Roseland, Denise; Volkov, Boris B.; Callow-Heusser, Catherine

    2011-01-01

    In contrast to typical National Science Foundation program evaluations, the Utah State Math Science Partnership-Research, Evaluation and Technical Assistance Project (MSP-RETA) provided technical assistance (TA) in two forms: direct TA for up to 10 projects a year, and professional development sessions for a larger number of project staff. Not…

  11. Technical data base quarterly report, April--June 1992; Yucca Mountain Site Characterization Project

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1992-09-01

    The acquisition and development of technical data are activities that provide the information base from which the Yucca mountain Site will be characterized and may P-ventually be licensed as a high-level waste repository. The Project Technical Data Base (TDB) is the repository for the regional and site-specific technical data required in intermediate and license application analyses and models. The TDB Quarterly Report provides the mechanism for identifying technical data currently available from the Project TDB. Due to the variety of scientific information generated by YMP activities, the Project TDB consists of three components, each designed to store specific types of data. The Site and Engineering Properties Data Base (SEPDB) maintains technical data best stored in a tabular format. The Geographic Nodal Information Study and Evaluation System (GENISES), which is the Geographic Information System (GIS) component of the Project TDB, maintains spatial or map-like data. The Geologic and Engineering Materials Bibliography of Chemical Species (GEMBOCHS) data base maintains thermodynamic/geochemical data needed to support geochemical reaction models involving the waste package and repository geochemical environment. Each of these data bases are addressed independently within the TDB Quarterly Report.

  12. 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

  13. 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.

  14. 75 FR 18505 - International Cooperation on Harmonisation of Technical Requirements for Registration of...

    Science.gov (United States)

    2010-04-12

    ...] International Cooperation on Harmonisation of Technical Requirements for Registration of Veterinary Medicinal... veterinary use by the International Cooperation on Harmonisation of Technical Requirements for Registration... promote the international harmonization of regulatory requirements. FDA has participated in efforts to...

  15. 75 FR 18508 - International Cooperation on Harmonisation of Technical Requirements for Registration of...

    Science.gov (United States)

    2010-04-12

    ...] International Cooperation on Harmonisation of Technical Requirements for Registration of Veterinary Medicinal... use by the International Cooperation on Harmonisation of Technical Requirements for Registration of... promote the international harmonization of regulatory requirements. FDA has participated in efforts to...

  16. Projected uranium requirements of developing countries

    International Nuclear Information System (INIS)

    Anon.

    1990-01-01

    The objective of this paper is to examine the uranium requirements of developing countries both in aggregate and individually. Although the cumulative uranium requirements of these countries are expected to account for less than eight percent of total requirements, the fact that many of these countries are expressing renewed interest in nuclear is, in itself, encouraging. The countries analyzed in this paper are Argentina, Brazil, Egypt, India, Israel, Mexico, Pakistan, South Africa, South Korea and Taiwan. For each country, the existing and planned nuclear capacity levels have been identified and capacity factors have been projected. For countries with no previous nuclear power, the world weighted average capacity factor for the specific reactor type is utilized. Other factors influencing nuclear power demand and operations of these developing countries will be discussed, and finally, uranium requirements based on a calculated optimal tails assay of .30 will be provided

  17. Safety Requirements and Modern Technical Requirements in Human Information Systems in Amman Hotels

    OpenAIRE

    Farouq Ahmad Alazzam; Sattam Rakan Allahawiah; Mohammad Nayef Alsarayreh; Kafa Hmoud Abdallah al Nawaiseh

    2015-01-01

    This study aimed to demonstrate the availability of Safety requirements and modern technical requirements in human information systems in Amman hotels. an the most important results of this study is the availability of security and safety requirements in human information systems In Amman hotels and The adequacy of the information that it provided .and show that all departments are not connected by appropriate and effective communication networks in adequate form . Also sophisticated operatin...

  18. Compiling Utility Requirements For New Nuclear Power Plant Project

    International Nuclear Information System (INIS)

    Patrakka, Eero

    2002-01-01

    Teollisuuden Voima Oy (TVO) submitted in November 2000 to the Finnish Government an application for a Decision-in-Principle concerning the construction of a new nuclear power plant in Finland. The actual investment decision can be made first after a positive decision has been made by the Government and the Parliament. Parallel to the licensing process, technical preparedness has been upheld so that the procurement process can be commenced without delay, when needed. This includes the definition of requirements for the plant and preliminary preparation of bid inquiry specifications. The core of the technical requirements corresponds to the specifications presented in the European Utility Requirement (EUR) document, compiled by major European electricity producers. Quite naturally, an amount of modifications to the EUR document are needed that take into account the country- and site-specific conditions as well as the experiences gained in the operation of the existing NPP units. Along with the EUR-related requirements concerning the nuclear island and power generation plant, requirements are specified for scope of supply as well as for a variety of issues related to project implementation. (author)

  19. Admiralty Inlet Pilot Tidal Project Final Technical Report

    Energy Technology Data Exchange (ETDEWEB)

    Collar, Craig [Public Utility District No. 1 of Snohomish County, Everett, WA (United States)

    2015-09-14

    This document represents the final report for the Admiralty Inlet Pilot Tidal Project, located in Puget Sound, Washington, United States. The Project purpose was to license, permit, and install a grid-connected deep-water tidal turbine array (two turbines) to be used as a platform to gather operational and environmental data on tidal energy generation. The data could then be used to better inform the viability of commercial tidal energy generation from technical, economic, social, and environmental standpoints. This data would serve as a critical step towards the responsible advancement of commercial scale tidal energy in the United States and around the world. In late 2014, Project activities were discontinued due to escalating costs, and the DOE award was terminated in early 2015. Permitting, licensing, and engineering design activities were completed under this award. Final design, deployment, operation, and monitoring were not completed. This report discusses the results and accomplishments achieved under the subject award.

  20. Technical project for a new water purification solution

    Directory of Open Access Journals (Sweden)

    Toma Adina

    2018-01-01

    Full Text Available This research is part of the RO-BG Cross-Border Cooperation Program, project “CLEANDANUBE”, MIS-ETC 653, which has finalised by providing a common strategy to prevent the Danube’s pollution technological risks with oil and oil products. This paper presents a new sustainable water purification solution. A short introduction will be offered and an overview regarding the research and new methods to greening the waste is provided. The theoretical aspects of the centrifugal separation phenomenon are studied and the preliminary project bases were established. The paper conveys the possible constructive variations and the technological implications of those. Ultimately, the technical project for a new water purification solution and conclusions with critical points encountered during the designing phase are presented.

  1. Nuclear design and technical development required for ISER plant

    International Nuclear Information System (INIS)

    Yokoyama, Takashi; Yamano, Naoki.

    1987-01-01

    The report outlines some results of a study carried out by the ISER (intrinsically safe and economical reactor) Investigation Group. In particular, nuclear design concepts are examined in relation to the fuel cycle. Discussion is also made on technical development efforts to be made for realizing an ISER. Calculation of some basic nuclear design parameters is performed and results are used to examine the reactor core and fuel for ISER. As a result, it is indicated that a high-burnup type reactor core should be used on a 4.5-batch replacement, 15 EFPM (effective full power month) scheme to optimize an ISER. For technical development, consideration is made on various tests to be performed with an experimental reactor, called ISER-E, as well as other tests to provide basic data required for demonstrating the inherent safety of ISER. The study also deals with the possibility of the application of currently available light water reactor techniques to experiments with a critical assembly, non-nuclear test loop, and the experimental reactor ISER-E. It is revealed that many of the required experiments can be carried out by using test facilities and light water reactor techniques which are currently, or will be readily, available. It is stressed that international cooperation is necessary to accomplish these tests. (Nogami, K.)

  2. Technical skills requirement of Indonesian construction labors to work in Malaysia

    Science.gov (United States)

    Adi, Henny Pratiwi

    2017-03-01

    Labors skills is an important part of construction projects implementation. Suitability between the skills possessed by labors with the skills needed by user is required to increase employment opportunities. Malaysia is a country that using construction labors from Indonesia. This study aims to get the kind of technical skills required by users of Indonesian constructian labors in Malaysia and also the importance level of technical skills. Data collecting in this research was conducted through interviews and questionnaires on contractors in Malaysia. The next stage was determine the importance level of technical skills in work field of carpenter, bricklayer, plumber and painters. The importance level of technical skills analyzed using the Relative Importance Index (RII). The results showed that mastering the operation of both instruments either manually or electrically is the most importance in the technical skills. Therefore, an understanding of the types of equipment for work field and the manner of operation is need to had by Indonesian construction labors who will work in Malaysia.

  3. Final Technical Report, Wind Generator Project (Ann Arbor)

    Energy Technology Data Exchange (ETDEWEB)

    Geisler, Nathan [City of Ann Arbor, MI (United States)

    2017-03-20

    A Final Technical Report (57 pages) describing educational exhibits and devices focused on wind energy, and related outreach activities and programs. Project partnership includes the City of Ann Arbor, MI and the Ann Arbor Hands-on Museum, along with additional sub-recipients, and U.S. Department of Energy/Office of Energy Efficiency and Renewable Energy (EERE). Report relays key milestones and sub-tasks as well as numerous graphics and images of five (5) transportable wind energy demonstration devices and five (5) wind energy exhibits designed and constructed between 2014 and 2016 for transport and use by the Ann Arbor Hands-on Museum.

  4. 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.

  5. THE PROFESSIONAL QUALIFICATION SOLIDARY EXTENSION PROJECT AT ELECTRONICS: TECHNICAL AUXILIAR

    Directory of Open Access Journals (Sweden)

    Glaucio Lopes Ramos

    2009-10-01

    Full Text Available This paper has the objective to present the extension course “professional qualification solidary extension project at electronics: technical auxiliar” in the Electrical Engineering course in the University Center of Belo Horizonte, as a professional qualification activity that make possible to young, adults and elderly people from poor communities the social inclusion and an opportunity to improve their access to the labor market. The course is part of extension program of Uni-BH, UniTrabalho e Renda, that is offered since 2006. The responsible for the course are professors and students of the Electrical Engineering course, and an electricity project is also offered. This paper presents the results of an evaluation that is made for the students at the beginning and at the end of the course and showed that the concepts had been assimilated by the students and the expectation of them related to the insertion at labor market is also improved.

  6. Supplemental design requirements document enhanced radioactive and mixed waste storage Phase V Project W-112

    International Nuclear Information System (INIS)

    Ocampo, V.P.; Boothe, G.F.; Greager, T.M.; Johnson, K.D.; Kooiker, S.L.; Martin, J.D.

    1994-11-01

    This document provides additional and supplemental information to WHC-SD-W112-FDC-001, Project W-112 for radioactive and mixed waste storage. It provides additional requirements for the design and summarizes Westinghouse Hanford Company key design guidance and establishes the technical baseline agreements to be used for definitive design of the Project W-112 facilities

  7. 78 FR 14306 - International Cooperation on Harmonisation of Technical Requirements for Registration of...

    Science.gov (United States)

    2013-03-05

    ...]; (Formerly Docket No. 00D-1631)] International Cooperation on Harmonisation of Technical Requirements for... for veterinary use by the International Cooperation on Harmonisation of Technical Requirements for... regulatory authorities and industry associations to promote the international harmonization of regulatory...

  8. 76 FR 57060 - International Cooperation on Harmonisation of Technical Requirements for Registration of...

    Science.gov (United States)

    2011-09-15

    ...] International Cooperation on Harmonisation of Technical Requirements for Registration of Veterinary Medicinal... veterinary use by the International Cooperation on Harmonisation of Technical Requirements for Registration... regulatory authorities and industry associations to promote the international harmonization of regulatory...

  9. 77 FR 20406 - International Cooperation on Harmonisation of Technical Requirements for Registration of...

    Science.gov (United States)

    2012-04-04

    ...] International Cooperation on Harmonisation of Technical Requirements for Registration of Veterinary Medicinal... been developed for veterinary use by the International Cooperation on Harmonisation of Technical... industry associations to promote the international harmonization of regulatory requirements. FDA has...

  10. 76 FR 57054 - International Cooperation on Harmonisation of Technical Requirements for Registration of...

    Science.gov (United States)

    2011-09-15

    ...] International Cooperation on Harmonisation of Technical Requirements for Registration of Veterinary Medicinal... (MRK),'' (VICH GL46). This guidance has been developed for veterinary use by the International Cooperation on Harmonisation of Technical Requirements for Registration of Veterinary Medicinal Products (VICH...

  11. 76 FR 57057 - International Cooperation on Harmonisation of Technical Requirements for Registration of...

    Science.gov (United States)

    2011-09-15

    ...] International Cooperation on Harmonisation of Technical Requirements for Registration of Veterinary Medicinal... veterinary use by the International Cooperation on Harmonisation of Technical Requirements for Registration... undertaken by regulatory authorities and industry associations to promote the international harmonization of...

  12. 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.

  13. River Corridor Project Workplace Air Monitoring Technical Basis

    International Nuclear Information System (INIS)

    MANTOOTH, D.S.

    2001-01-01

    This document provides the technical basis by which the workplace air monitoring and sampling program is operated in the River Corridor Project (RCP). Revision 2 addresses and incorporates changes in the air monitoring program drivers and implementing documents which occurred after the previous revision was issued. This revision also includes an additional RCP project to make Revision 2 applicable to the entire RCP. These changes occurred in the following areas: (1) Changes resulting from the conversion of the Hanford Site Radiological Control Manual (HSRCM-1) into the Project Hanford Radiological Control Manual (F-5173). HNF-5173 is now the implementing document for 10CFR835. (2) Changes resulting from the issue of new and revised Hanford Site implementing procedures. (3) Changes resulting from the issue of new and revised, as well as the cancellation of RCP implementing procedures. (4) Addition of the 200 Area Accelerated Deactivation Project (ADP). (5) Modification of some air sampling/monitoring locations to better meet the needs of facility operations. (6) Changes resulting from the RCP reorganization

  14. Clarification of TMI action plan requirements. Technical report

    International Nuclear Information System (INIS)

    1980-11-01

    This document, NUREG-0737, is a letter from D.G. Eisenhut, Director of the Division of Licensing, NRR, to licensees of operating power reactors and applicants for operating licenses forwarding post-TMI requirements which have been approved for implementation. Following the accident at Three Mile Island Unit 2, the NRC staff developed the Action Plan, NUREG-0660, to provide a comprehensive and integrated plan to improve safety at power reactors. Specific items from NUREG-0660 have been approved by the Commission for implementation at reactors. In this NRC report, these specific items comprise a single document which includes additional information about schedules, applicability, method of implementation review, submittal dates, and clarification of technical positions. It should be noted that the total set of TMI-related actions have been collected in NUREG-0660, but only those items that the Commission has approved for implementation to date are included in this document, NUREG-0737

  15. Generation of recycled aggregates and technical requirements for some applications

    International Nuclear Information System (INIS)

    Martinez L, Isabel; Vazquez H, Cristina; Gonzalez F, Belen; Martinez A, Fernando

    2010-01-01

    In the present framework of sustainable construction, management of construction and demolition (C and D) waste or debris is stressed and its correct implementation requires a previous estimation of the precise quantities and detailed composition of C and D waste.This allows us to make an estimate of the production of recycled aggregate and to analyze the impact of its use in relation to the use of natural aggregate. Research of existing bibliography, the results obtained from both experimental testing and previous experience at construction works where C and D debris is used, enabled us to develop technical specifications for each application of the recycled aggregates. This includes recommendations for use, quality control specifications, and the maximum percentage of recycled aggregate that ought to substitute natural aggregate in concrete mixes in order to get admissible performances.

  16. 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

  17. National Institute of Justice (NIJ) Center Requirements Definition, Technical Assistance, and Analysis

    National Research Council Canada - National Science Library

    Frantz, Frederick

    2003-01-01

    .... The current technology thrust areas for the Northeast Region are Concealed Weapons Detection, Secure Communications, Computer Forensics, Information Management, AGILE, and various technical assistance projects...

  18. Yucca Mountain Site Characterization Project: Technical Data Catalog (quarterly supplement), June 30, 1994

    International Nuclear Information System (INIS)

    1994-01-01

    The DOE/NRC Site-Specific Procedural Agreement for Geologic Repository Site Investigation and Characterization Program requires the DOE to develop and maintain a catalog of data which will be updated and provided to the NRC at least quarterly. This catalog is to include a description of the data; the date, place, and method of acquisition; and where it may be examined. The Yucca Mountain Site Characterization Project (YMP) Technical Data Catalog is published and distributed in accordance with the requirements of the Site-Specific Agreement. The YMP Technical Data Catalog is a report based on reference information contained in the YMP Automated Technical Data Tracking System (ATDT). The reference information is provided by Participants for data acquired or developed in support of the YMP. The Technical Data Catalog is updated quarterly and published in the month following the end of each quarter. A complete revision to the catalog is published at the end of each fiscal year. Supplements to the end-of-year edition are published each quarter. These supplements provide information related to new data items not included in previous quarterly updates and data items affected by changes to previously published reference information. The Technical Data Catalog, dated September 30, 1993, should be retained as the baseline document for the supplements until the end-of-year revision is published and distributed in October 1994

  19. Understanding Project Based Production through Socio-technical Modularity

    DEFF Research Database (Denmark)

    Thuesen, Christian Langhoff

    This paper develops an approach for understanding Project Based Production. This form of production is characterized by unique deliverables, high complexity, high value, high risk, profound uncertainty and many stakeholders and is increasingly important the postmodern society. Common to the pract......This paper develops an approach for understanding Project Based Production. This form of production is characterized by unique deliverables, high complexity, high value, high risk, profound uncertainty and many stakeholders and is increasingly important the postmodern society. Common...... to the practices of PBP and other production practices is the goal of balancing the dilemma between creativity and productivity. In response to industrialized production, the concept of modularity gained popularity for addressing this dilemma by exploring product, process and organization structures. However...... with the starting point in system theory and a strong bias towards industrial production, the predominant understanding of modularity faces difficulty in explaining practices of Project Based Production in both social – technical and dynamic – stable aspects. Illustrated by a case the paper addresses this gap...

  20. Technical Safety Requirements for the Waste Storage Facilities May 2014

    Energy Technology Data Exchange (ETDEWEB)

    Laycak, D. T. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

    2014-04-16

    This document contains the Technical Safety Requirements (TSR) for the Radioactive and Hazardous Waste Management (RHWM) WASTE STORAGE FACILITIES, which include Area 625 (A625) and the Building 693 (B693) Yard Area of the Decontamination and Waste Treatment Facility (DWTF) at LLNL. The TSRs constitute requirements for safe operation of the WASTE STORAGE FACILITIES. These TSRs are derived from the Documented Safety Analyses for the Waste Storage Facilities (DSA) (LLNL 2011). The analysis presented therein concluded that the WASTE STORAGE FACILITIES are low-chemical hazard, Hazard Category 2 non-reactor nuclear facilities. The TSRs consist primarily of inventory limits and controls to preserve the underlying assumptions in the hazard and accident analyses. Further, appropriate commitments to safety programs are presented in the administrative controls sections of the TSRs. The WASTE STORAGE FACILITIES are used by RHWM to handle and store hazardous waste, TRANSURANIC (TRU) WASTE, LOW-LEVEL WASTE (LLW), mixed waste, California combined waste, nonhazardous industrial waste, and conditionally accepted waste generated at LLNL as well as small amounts of waste from other DOE facilities, as described in the DSA. In addition, several minor treatments (e.g., size reduction and decontamination) are carried out in these facilities.

  1. Technical Safety Requirements for the Waste Storage Facilities May 2014

    International Nuclear Information System (INIS)

    Laycak, D. T.

    2014-01-01

    This document contains the Technical Safety Requirements (TSR) for the Radioactive and Hazardous Waste Management (RHWM) WASTE STORAGE FACILITIES, which include Area 625 (A625) and the Building 693 (B693) Yard Area of the Decontamination and Waste Treatment Facility (DWTF) at LLNL. The TSRs constitute requirements for safe operation of the WASTE STORAGE FACILITIES. These TSRs are derived from the Documented Safety Analyses for the Waste Storage Facilities (DSA) (LLNL 2011). The analysis presented therein concluded that the WASTE STORAGE FACILITIES are low-chemical hazard, Hazard Category 2 non-reactor nuclear facilities. The TSRs consist primarily of inventory limits and controls to preserve the underlying assumptions in the hazard and accident analyses. Further, appropriate commitments to safety programs are presented in the administrative controls sections of the TSRs. The WASTE STORAGE FACILITIES are used by RHWM to handle and store hazardous waste, TRANSURANIC (TRU) WASTE, LOW-LEVEL WASTE (LLW), mixed waste, California combined waste, nonhazardous industrial waste, and conditionally accepted waste generated at LLNL as well as small amounts of waste from other DOE facilities, as described in the DSA. In addition, several minor treatments (e.g., size reduction and decontamination) are carried out in these facilities.

  2. Technical specification for the Quality Information Management System (QIMS) Pilot Project

    Energy Technology Data Exchange (ETDEWEB)

    Hall, R.C.; Claussen, L.M.; Thurston, I.

    1992-01-01

    This document contains implementation details for the Quality Information Management System (QIMS) Pilot Project, which has been released for VAX/VMS systems using the INGRES RDBMS. The INGRES Applications-By-Forms (ABF) software development tool was used to define the modules and screens which comprise the QIMS Pilot application. These specifications together with the QIMS information model and corresponding database definition constitute the QIMS technical specification and implementation description presented herein. The QIMS Pilot Project represents a completed software product which has been released for production use. Further extension projects are planned which will release new versions for QIMS. These versions will offer expanded and enhanced functionality to meet further customer requirements not accommodated by the QIMS Pilot Project.

  3. Career and Technical Education Administration: Requirements, Certification/Licensure, and Preparation

    Science.gov (United States)

    Zirkle, Christopher J.; Jeffery, Jeremy O.

    2017-01-01

    The current climate of career and technical administration requirements in all 50 states was detailed and explored. An increasing number of states are not requiring specific career-technical administration certification/licensure in order to oversee secondary career and technical education (CTE) programs, with more states moving towards a general…

  4. Status of Technical Requirements Development for Maintenance Effectiveness Management

    International Nuclear Information System (INIS)

    Ahn, Sang Kyu; Kim, Yun Il; Lee, Chang Ju; Chang, Gun Hyun

    2012-01-01

    It is well known that proper maintenance at nuclear power plant is essential to plant safety and that there is a clear link between effective maintenance and safety as it relates to such factors as the number of transients and challenges to safety systems and the associated need for operability, availability, and reliability of safety equipment. Good maintenance is also important in providing assurance that failures of non-safety related structures, systems, and components (SSCs) that could initiate, adversely affect, or mitigate a transient or an accident are also minimized. Maintenance is also important to ensure that design assumptions and margins in the original design basis are maintained and are not degraded to an unacceptable level. Therefore, good maintenance practice at nuclear power plants is of utmost importance in protecting public health and safety. This paper introduces the status of the development of regulatory technical requirements (Drafts) for utility's management of maintenance effectiveness. The process of Maintenance Effectiveness Management is shown in Figure 1

  5. Biogas Koczala. Biogas project in Koczala. Feasibility study. Technical report

    International Nuclear Information System (INIS)

    2004-08-01

    The present production of district heating in Koczala is based on coal. The district heating system is worn out technically and economically and according to the 2001 Energy Plan of Koczala the district heating plant shall be converted to a combination of a biogas fired CHP and a wood chip boiler. The overall objective of this project is to access the feasibility and viability construction an operation of a biogas plant owned by the co-operative agricultural company, Poldanor S.A. The feasibility study includes: 1) Availability of organic waste in the Koczala area, 2) Possibilities of using energy crops in the biogas plant, 3) Possibilities of receiving grants from the Polish National Fund for Environmental Protection, the new EU regional funds and through the joint implementation market (CO 2 quotas), 4) Alternative locations of the biogas plant and the CHP unit, 5) Alternative strategies for selling electricity and heat, 6) Organisational issues (ownership). This report concludes that implementing the biogas project is environmentally and financially feasible and viable. If organic waste and/or maize silage can be provided and gasified without problems, the plant can supply as well the Koczala farm as the fodder mill with steam and heat, and also supply Koczala district heating system with approx. 75% of yearly heat consumption. Furthermore, electricity is supplied to the fodder mill and the public grid. (BA)

  6. 76 FR 57058 - International Cooperation on Harmonisation of Technical Requirements for Registration of...

    Science.gov (United States)

    2011-09-15

    ...] International Cooperation on Harmonisation of Technical Requirements for Registration of Veterinary Medicinal... has been developed for veterinary use by the International Cooperation on Harmonisation of Technical... been undertaken by regulatory authorities and industry associations to promote the international...

  7. 78 FR 14308 - International Cooperation on Harmonisation of Technical Requirements for Registration of...

    Science.gov (United States)

    2013-03-05

    ...] International Cooperation on Harmonisation of Technical Requirements for Registration of Veterinary Medicinal... been developed for veterinary use by the International Cooperation on Harmonisation of Technical... regulatory authorities and industry associations to promote the international harmonization of regulatory...

  8. Yucca Mountain Site Characterization Project: Technical data catalog,(quarterly supplement)

    International Nuclear Information System (INIS)

    1993-01-01

    The June 1, 1985, Department of Energy (DOE)/Nuclear Regulatory Commission (NRC) Site-Specific Procedural Agreement for Geologic Repository Site Investigation and Characterization Program requires the DOE to develop and maintain a catalog of data which will be updated and provided to the NRC at least quarterly. This catalog is to include a description of the data; the time (date), place, and method of acquisition; and where it may be examined. The Yucca Mountain Site Characterization Project (YMP) Technical Data Catalog is published and distributed in accordance with the requirements of the Site-Specific Agreement. The YMP Technical Data Catalog is a report based on reference information contained in the YMP Automated Technical Data Tracking System (ATDT). The reference information is provided by Participants for data acquired or developed in support of the YMP. The Technical Data Catalog is updated quarterly and published in the month following the end of each quarter. A complete revision to the Catalog is published at the end of each fiscal year

  9. Technical Safety Requirements for the B695 Segment

    Energy Technology Data Exchange (ETDEWEB)

    Laycak, D

    2008-09-11

    This document contains Technical Safety Requirements (TSRs) for the Radioactive and Hazardous Waste Management (RHWM) Division's B695 Segment of the Decontamination and Waste Treatment Facility (DWTF) at Lawrence Livermore National Laboratory (LLNL). The TSRs constitute requirements regarding the safe operation of the B695 Segment. The TSRs are derived from the Documented Safety Analysis (DSA) for the B695 Segment (LLNL 2007). The analysis presented there determined that the B695 Segment is a low-chemical hazard, Hazard Category 3, nonreactor nuclear facility. The TSRs consist primarily of inventory limits as well as controls to preserve the underlying assumptions in the hazard analyses. Furthermore, appropriate commitments to safety programs are presented in the administrative controls section of the TSRs. The B695 Segment (B695 and the west portion of B696) is a waste treatment and storage facility located in the northeast quadrant of the LLNL main site. The approximate area and boundary of the B695 Segment are shown in the B695 Segment DSA. Activities typically conducted in the B695 Segment include container storage, lab-packing, repacking, overpacking, bulking, sampling, waste transfer, and waste treatment. B695 is used to store and treat radioactive, mixed, and hazardous waste, and it also contains equipment used in conjunction with waste processing operations to treat various liquid and solid wastes. The portion of the building called Building 696 Solid Waste Processing Area (SWPA), also referred to as B696S in this report, is used primarily to manage solid radioactive, mixed, and hazardous waste. Operations specific to the SWPA include sorting and segregating waste, lab-packing, sampling, and crushing empty drums that previously contained waste. Furthermore, a Waste Packaging Unit will be permitted to treat hazardous and mixed waste. RHWM generally processes LLW with no, or extremely low, concentrations of transuranics (i.e., much less than 100 n

  10. Technical Safety Requirements for the B695 Segment

    International Nuclear Information System (INIS)

    Laycak, D.

    2008-01-01

    This document contains Technical Safety Requirements (TSRs) for the Radioactive and Hazardous Waste Management (RHWM) Division's B695 Segment of the Decontamination and Waste Treatment Facility (DWTF) at Lawrence Livermore National Laboratory (LLNL). The TSRs constitute requirements regarding the safe operation of the B695 Segment. The TSRs are derived from the Documented Safety Analysis (DSA) for the B695 Segment (LLNL 2007). The analysis presented there determined that the B695 Segment is a low-chemical hazard, Hazard Category 3, nonreactor nuclear facility. The TSRs consist primarily of inventory limits as well as controls to preserve the underlying assumptions in the hazard analyses. Furthermore, appropriate commitments to safety programs are presented in the administrative controls section of the TSRs. The B695 Segment (B695 and the west portion of B696) is a waste treatment and storage facility located in the northeast quadrant of the LLNL main site. The approximate area and boundary of the B695 Segment are shown in the B695 Segment DSA. Activities typically conducted in the B695 Segment include container storage, lab-packing, repacking, overpacking, bulking, sampling, waste transfer, and waste treatment. B695 is used to store and treat radioactive, mixed, and hazardous waste, and it also contains equipment used in conjunction with waste processing operations to treat various liquid and solid wastes. The portion of the building called Building 696 Solid Waste Processing Area (SWPA), also referred to as B696S in this report, is used primarily to manage solid radioactive, mixed, and hazardous waste. Operations specific to the SWPA include sorting and segregating waste, lab-packing, sampling, and crushing empty drums that previously contained waste. Furthermore, a Waste Packaging Unit will be permitted to treat hazardous and mixed waste. RHWM generally processes LLW with no, or extremely low, concentrations of transuranics (i.e., much less than 100 n

  11. Legal requirements concerning the technical safety of nuclear installations

    International Nuclear Information System (INIS)

    Nolte, R.

    1984-01-01

    A short survey on nuclear risks and the nuclear safety conception is followed by the attempted clear definition of the semantic import of section 7, sub-section (2), No. 3 of the Atomic Energy Act. There are first beginnings of a concretization of the state-of-the-art in science and technology, i.e. all kinds of sub-legislative regulations such as the regulations of the Radiation Protection Ordinance which show scientific substance, guidelines issued by the Ministers, as well as codes for practice set up by various technical bodies and standardization associations, all of which are designed to compensate for this loop hole in the legislation. This study goes to examine to what extent administration and jurisdiction may take into account such codes of practice for the concretization of the legal requirements, and whether they are even binding on those executing the law. Only the respective regulations of the Radiation Protection Ordinance have a binding effect. All other guidelines and codes of practice are not legally binding per se, nor are they capable of being legally permitted by being referred to in terms of legal norms or by the self-commitment of those executing the law. Any attempt of using them, as the basis of a prime facie evidence or as an anticipating expertise, at least evidentarily for the concretization will have to fail owing to their evaluating character and to the fact that they may interfere in sociological conflict. An exception may be a case where a clear distinction can be made as to what extent the contents of such codes of practice is related to scientific and technological findings or to decisions based on evaluations. In such a case, a prima facil evicdence for the conformity of the regulation in question with the state-of-the-art in science and technology may be considered, which would easy the concretization of Art. 7 II Section 3 of the Atomic Law. (orig./HSCH) [de

  12. Three-dimensional digital projection in neurosurgical education: technical note.

    Science.gov (United States)

    Martins, Carolina; Ribas, Eduardo Carvalhal; Rhoton, Albert L; Ribas, Guilherme Carvalhal

    2015-10-01

    Three-dimensional images have become an important tool in teaching surgical anatomy, and its didactic power is enhanced when combined with 3D surgical images and videos. This paper describes the method used by the last author (G.C.R.) since 2002 to project 3D anatomical and surgical images using a computer source. Projecting 3D images requires the superposition of 2 similar but slightly different images of the same object. The set of images, one mimicking the view of the left eye and the other mimicking the view of the right eye, constitute the stereoscopic pair and can be processed using anaglyphic or horizontal-vertical polarization of light for individual use or presentation to larger audiences. Classically, 3D projection could be obtained by using a double set of slides, projected through 2 slide projectors, each of them equipped with complementary filters, shooting over a medium that keeps light polarized (a silver screen) and having the audience wear appropriate glasses. More recently, a digital method of 3D projection has been perfected. In this method, a personal computer is used as the source of the images, which are arranged in a Microsoft PowerPoint presentation. A beam splitter device is used to connect the computer source to 2 digital, portable projectors. Filters, a silver screen, and glasses are used, similar to the classic method. Among other advantages, this method brings flexibility to 3D presentations by allowing the combination of 3D anatomical and surgical still images and videos. It eliminates the need for using film and film developing, lowering the costs of the process. In using small, powerful digital projectors, this method substitutes for the previous technology, without incurring a loss of quality, and enhances portability.

  13. Technical safety appraisal of the West Valley Demonstration Project

    International Nuclear Information System (INIS)

    1989-09-01

    This report presents the results of one in a series of Technical Safety Appraisals (TSAs) being conducted of DOE nuclear operations by the Assistant Secretary for Environment, Safety, and Health Office of Safety Appraisals TSAs are one of the ititiatives announced by the Secretary of Energy on September 18, 1985, to enhance the DOE environment, safety and health program. This report presents the results of a TSA of the West Valley Demonstration Project (WVDP). The appraisal was conducted by a team of exerts assembled by the DOE Office of Safety Appraisal and was conducted during onsite visits of June 26-30 and July 10-21, 1989. West Valley, about 30 miles south of Buffalo, New York is the location of the only commercial nuclear fuel reprocessing facility operated in the United States. Nuclear Fuels Services, Inc. (NFS) operated the plant from 1966 to 1972 and processed about 640 metric tons of spent reactor fuel. The reprocessing operation generated about 560,000 gallons of high-level radioactive waste, which was transferred into underground tanks for storage. In 1972 NFS closed the plant and subsequently decided not to reopen it

  14. 47 CFR 25.210 - Technical requirements for space stations in the Fixed-Satellite Service.

    Science.gov (United States)

    2010-10-01

    ... 47 Telecommunication 2 2010-10-01 2010-10-01 false Technical requirements for space stations in the Fixed-Satellite Service. 25.210 Section 25.210 Telecommunication FEDERAL COMMUNICATIONS COMMISSION (CONTINUED) COMMON CARRIER SERVICES SATELLITE COMMUNICATIONS Technical Standards § 25.210 Technical...

  15. Technical Safety Requirements for the Waste Storage Facilities

    International Nuclear Information System (INIS)

    Larson, H L

    2007-01-01

    This document contains Technical Safety Requirements (TSR) for the Radioactive and Hazardous Waste Management (RHWM) WASTE STORAGE FACILITIES, which include Area 612 (A612) and the Decontamination and Waste Treatment Facility (DWTF) Storage Area at Lawrence Livermore National Laboratory (LLNL). The TSRs constitute requirements regarding the safe operation of the WASTE STORAGE FACILITIES. These TSRs are derived from the Documented Safety Analysis for the Waste Storage Facilities (DSA) (LLNL 2006). The analysis presented therein determined that the WASTE STORAGE FACILITIES are low-chemical hazard, Hazard Category 2 non-reactor nuclear facilities. The TSRs consist primarily of inventory limits and controls to preserve the underlying assumptions in the hazard and accident analyses. Further, appropriate commitments to safety programs are presented in the administrative controls sections of the TSRs. The WASTE STORAGE FACILITIES are used by RHWM to handle and store hazardous waste, TRANSURANIC (TRU) WASTE, LOW-LEVEL WASTE (LLW), mixed waste, California combined waste, nonhazardous industrial waste, and conditionally accepted waste generated at LLNL as well as small amounts from other U.S. Department of Energy (DOE) facilities, as described in the DSA. In addition, several minor treatments (e.g., drum crushing, size reduction, and decontamination) are carried out in these facilities. The WASTE STORAGE FACILITIES are located in two portions of the LLNL main site. A612 is located in the southeast quadrant of LLNL. The A612 fenceline is approximately 220 m west of Greenville Road. The DWTF Storage Area, which includes Building 693 (B693), Building 696 Radioactive Waste Storage Area (B696R), and associated yard areas and storage areas within the yard, is located in the northeast quadrant of LLNL in the DWTF complex. The DWTF Storage Area fenceline is approximately 90 m west of Greenville Road. A612 and the DWTF Storage Area are subdivided into various facilities and storage

  16. Technical Safety Requirements for the Waste Storage Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Larson, H L

    2007-09-07

    This document contains Technical Safety Requirements (TSR) for the Radioactive and Hazardous Waste Management (RHWM) WASTE STORAGE FACILITIES, which include Area 612 (A612) and the Decontamination and Waste Treatment Facility (DWTF) Storage Area at Lawrence Livermore National Laboratory (LLNL). The TSRs constitute requirements regarding the safe operation of the WASTE STORAGE FACILITIES. These TSRs are derived from the Documented Safety Analysis for the Waste Storage Facilities (DSA) (LLNL 2006). The analysis presented therein determined that the WASTE STORAGE FACILITIES are low-chemical hazard, Hazard Category 2 non-reactor nuclear facilities. The TSRs consist primarily of inventory limits and controls to preserve the underlying assumptions in the hazard and accident analyses. Further, appropriate commitments to safety programs are presented in the administrative controls sections of the TSRs. The WASTE STORAGE FACILITIES are used by RHWM to handle and store hazardous waste, TRANSURANIC (TRU) WASTE, LOW-LEVEL WASTE (LLW), mixed waste, California combined waste, nonhazardous industrial waste, and conditionally accepted waste generated at LLNL as well as small amounts from other U.S. Department of Energy (DOE) facilities, as described in the DSA. In addition, several minor treatments (e.g., drum crushing, size reduction, and decontamination) are carried out in these facilities. The WASTE STORAGE FACILITIES are located in two portions of the LLNL main site. A612 is located in the southeast quadrant of LLNL. The A612 fenceline is approximately 220 m west of Greenville Road. The DWTF Storage Area, which includes Building 693 (B693), Building 696 Radioactive Waste Storage Area (B696R), and associated yard areas and storage areas within the yard, is located in the northeast quadrant of LLNL in the DWTF complex. The DWTF Storage Area fenceline is approximately 90 m west of Greenville Road. A612 and the DWTF Storage Area are subdivided into various facilities and storage

  17. DECOVALEX II PROJECT Technical Report - Task 2C

    International Nuclear Information System (INIS)

    Jing, L.; Stephansson, O.; Chijimatzu, M.; Tsang, C.F.

    1999-05-01

    The DECOVALEX II project is an international co-operative research project supported by a number of national radioactive waste management organizations of different countries. The project studied four tasks: Task 1: numerical simulation of the RCF3 pump test at Sellafield, UK; Task 2: numerical simulation of the in situ T-H-M experiment at Kamaishi Mine, Japan; Task 3: monitoring of current development in rock fracture research; and Task 4: report on treatment of T-H-M processes in Performance Assessment works for nuclear waste repositories. The project started in 1995 and is scheduled to be finalised in March, 1999. This report concerns the Task 2 of the DECOVALEX H project. Task 2 of the DECOVALEX II project is the numerical modelling of the in-situ T-H-M experiment of a fractured rock - buffer - heater system at Kamaishi Mine, Japan. The experiment was carried out inside a test pit drilled in the floor of a 5 x 7 m alcove excavated near an existing drift at the 550 m level. The test pit has a circular cross section of diameter 1.7 m and a depth of 5 m, filled with bentonite which contains an electric heater. Four research teams studied Task 2 with different computational models. The task is divided into three sub-tasks: Task 2A, Task 2B and Task 2C. Task 2A was defined as a blind prediction to the coupled hydro-mechanical behaviour of the fractured rocks due to the excavation of the test pit. The calibration of the numerical models against measured results of pore pressures, flow rates and rock deformation before filling up of the test pit formed Task 2B. These two sub-tasks were performed to establish well calibrated fields of hydraulic conductivity and mechanical deformability of the fractured rocks at the test site. They were necessary for further simulations on interactions between the rock and buffer materials during heating experiments, as required for Task 2C, with a higher level of confidence on rock mass models. Presented in this report is the

  18. DECOVALEX II PROJECT Technical Report - Task 2C

    Energy Technology Data Exchange (ETDEWEB)

    Jing, L.; Stephansson, O. [Royal Inst. of Tech., Stockholm (Sweden). Dept. of Civil and Environmental Engineering; Boergesson, L. [Clay Technology AB, IDEON Research Center, Lund (Sweden); Chijimatzu, M. [Japan Nuclear Cycle Development Inst., Ibaraki (Japan). Waste Management and Fuel Cycle Research Center; Kautsky, F. [Swedish Nuclear Power Inspectorate (SKI), Stockholm (Sweden); Tsang, C.F. [Lawrence Berkeley National Laboratory, Berkeley, CA (United States). Earth Science Div.

    1999-05-01

    The DECOVALEX II project is an international co-operative research project supported by a number of national radioactive waste management organizations of different countries. The project studied four tasks: Task 1: numerical simulation of the RCF3 pump test at Sellafield, UK; Task 2: numerical simulation of the in situ T-H-M experiment at Kamaishi Mine, Japan; Task 3: monitoring of current development in rock fracture research; and Task 4: report on treatment ofT-H-M processes in Performance Assessment works for nuclear waste repositories. The project started in 1995 and is scheduled to be finalised in March, 1999. This report concerns the Task 2 of the DECOVALEX H project. Task 2 of the DECOVALEX II project is the numerical modelling of the in-situ T-H-M experiment of a fractured rock - buffer - heater system at Kamaishi Mine, Japan. The experiment was carried out inside a test pit drilled in the floor of a 5 x 7 m alcove excavated near an existing drift at the 550 m level. The test pit has a circular cross section of diameter 1.7 m and a depth of 5 m, filled with bentonite which contains an electric heater. Four research teams studied Task 2 with different computational models. The task is divided into three sub-tasks: Task 2A, Task 2B and Task 2C. Task 2A was defined as a blind prediction to the coupled hydro-mechanical behaviour of the fractured rocks due to the excavation of the test pit. The calibration of the numerical models against measured results of pore pressures, flow rates and rock deformation before filling up of the test pit formed Task 2B. These two sub-tasks were performed to establish well calibrated fields of hydraulic conductivity and mechanical deformability of the fractured rocks at the test site. They were necessary for further simulations on interactions between the rock and buffer materials during heating experiments, as required for Task 2C, with a higher level of confidence on rock mass models. Presented in this report is the definition

  19. Technical Safety Requirements for the Waste Storage Facilities

    International Nuclear Information System (INIS)

    Laycak, D.T.

    2010-01-01

    This document contains Technical Safety Requirements (TSR) for the Radioactive and Hazardous Waste Management (RHWM) WASTE STORAGE FACILITIES, which include Area 625 (A625) and the Decontamination and Waste Treatment Facility (DWTF) Storage Area at Lawrence Livermore National Laboratory (LLNL). The TSRs constitute requirements regarding the safe operation of the WASTE STORAGE FACILITIES. These TSRs are derived from the Documented Safety Analysis for the Waste Storage Facilities (DSA) (LLNL 2009). The analysis presented therein determined that the WASTE STORAGE FACILITIES are low-chemical hazard, Hazard Category 2 non-reactor nuclear facilities. The TSRs consist primarily of inventory limits and controls to preserve the underlying assumptions in the hazard and accident analyses. Further, appropriate commitments to safety programs are presented in the administrative controls sections of the TSRs. The WASTE STORAGE FACILITIES are used by RHWM to handle and store hazardous waste, TRANSURANIC (TRU) WASTE, LOW-LEVEL WASTE (LLW), mixed waste, California combined waste, nonhazardous industrial waste, and conditionally accepted waste generated at LLNL as well as small amounts from other U.S. Department of Energy (DOE) facilities, as described in the DSA. In addition, several minor treatments (e.g., size reduction and decontamination) are carried out in these facilities. The WASTE STORAGE FACILITIES are located in two portions of the LLNL main site. A625 is located in the southeast quadrant of LLNL. The A625 fenceline is approximately 225 m west of Greenville Road. The DWTF Storage Area, which includes Building 693 (B693), Building 696 Radioactive Waste Storage Area (B696R), and associated yard areas and storage areas within the yard, is located in the northeast quadrant of LLNL in the DWTF complex. The DWTF Storage Area fenceline is approximately 90 m west of Greenville Road. A625 and the DWTF Storage Area are subdivided into various facilities and storage areas, consisting

  20. Technical Safety Requirements for the Waste Storage Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Laycak, D T

    2008-06-16

    This document contains Technical Safety Requirements (TSR) for the Radioactive and Hazardous Waste Management (RHWM) WASTE STORAGE FACILITIES, which include Area 625 (A625) and the Decontamination and Waste Treatment Facility (DWTF) Storage Area at Lawrence Livermore National Laboratory (LLNL). The TSRs constitute requirements regarding the safe operation of the WASTE STORAGE FACILITIES. These TSRs are derived from the 'Documented Safety Analysis for the Waste Storage Facilities' (DSA) (LLNL 2008). The analysis presented therein determined that the WASTE STORAGE FACILITIES are low-chemical hazard, Hazard Category 2 non-reactor nuclear facilities. The TSRs consist primarily of inventory limits and controls to preserve the underlying assumptions in the hazard and accident analyses. Further, appropriate commitments to safety programs are presented in the administrative controls sections of the TSRs. The WASTE STORAGE FACILITIES are used by RHWM to handle and store hazardous waste, TRANSURANIC (TRU) WASTE, LOW-LEVEL WASTE (LLW), mixed waste, California combined waste, nonhazardous industrial waste, and conditionally accepted waste generated at LLNL as well as small amounts from other U.S. Department of Energy (DOE) facilities, as described in the DSA. In addition, several minor treatments (e.g., size reduction and decontamination) are carried out in these facilities. The WASTE STORAGE FACILITIES are located in two portions of the LLNL main site. A625 is located in the southeast quadrant of LLNL. The A625 fenceline is approximately 225 m west of Greenville Road. The DWTF Storage Area, which includes Building 693 (B693), Building 696 Radioactive Waste Storage Area (B696R), and associated yard areas and storage areas within the yard, is located in the northeast quadrant of LLNL in the DWTF complex. The DWTF Storage Area fenceline is approximately 90 m west of Greenville Road. A625 and the DWTF Storage Area are subdivided into various facilities and storage areas

  1. Information management systems for integrating the technical data and regulatory requirements of environmental restoration activities

    International Nuclear Information System (INIS)

    Geffen, C.A.; Garrett, B.A.; Walter, M.B.

    1990-03-01

    Current environmental regulations require that comprehensive planning be conducted before remediating a hazardous waste site to characterize the nature and extent of site contamination, calculate the risk to the public, and assess the effectiveness of various remediation technologies. Remediation of Department of Energy (DOE) sites contaminated with hazardous or mixed wastes will require the effective integration of scientific and engineering data with regulatory and institutional requirements. The information management challenge presented by waste site cleanup activities goes beyond merely dealing with the large quantity of data that will be generated. The information must be stored, managed, and presented in a way that provides some consistency in approach across sites, avoids duplication of effort, and facilitates responses to requests for information from the regulators and the public. This paper provides background information on the regulatory requirements for data gathering and analysis for environmental restoration activities, and outlines the data and information management requirements for completing the pre-remediation phases of an environmental restoration project. Information management systems for integrating the regulatory and institutional requirements of the environmental restoration process with the technical data and analysis requirements are also described. 7 refs

  2. Technical basis for tumbleweed survey requirements and disposal criteria

    International Nuclear Information System (INIS)

    J. D. Arana

    2000-01-01

    This technical basis document describes the technique for surveying potentially contaminated tumbleweeds in areas where the Environmental Restoration Contractor has jurisdiction and the disposal criteria based on these survey results. The report also discusses the statistical basis for surveys and the historical basis for the assumptions that are used to interpret the surveys

  3. Technical Basis for Tumbleweed Survey Requirements and Disposal Criteria

    International Nuclear Information System (INIS)

    Arana, J.D.

    2000-01-01

    This technical basis document describes the technique for surveying potentially contaminated tumbleweeds in areas where the Environmental Restoration Contractor has jurisdiction and the disposal criteria based on these survey results. The report also discusses the statistical basis for surveys and the historical basis for the assumptions that are used to interpret the surveys

  4. Radiation Requirements for Uranium Mining Projects

    International Nuclear Information System (INIS)

    Hondros, Jim

    2014-01-01

    Conclusions: • Radiation impact can be complex and confusing; • Aim to be credible and competent; • Process can be straightforward; – Baseline monitoring; – Project emissions; – Impact of emission; – Management measures. • “Tell the story” (what does it all mean)

  5. Landfill Gas Energy Project Data and Landfill Technical Data

    Science.gov (United States)

    This page provides data from the LMOP Database for U.S. landfills and LFG energy projects in Excel files, a map of project and candidate landfill counts by state, project profiles for a select group of projects, and information about Project Expo sites.

  6. Preliminary waste acceptance requirements - Konrad repository project

    International Nuclear Information System (INIS)

    Brennecke, P.W.; Warnecke, E.H.

    1991-01-01

    In Germany, the planned Konrad repository is proposed for the disposal of all types of radioactive wastes whose thermal influence upon the host rock is negligible. The Bundesamt fuer Strahlenschutz has established Preliminary Waste Acceptance Requirements (as of April 1990) for this facility. The respective requirements were developed on the basis of the results of site-specific safety assessments. They include general requirements on the waste packages to be disposed of as well as more specific requirements on the waste forms, the packaging and the radionuclide inventory per waste package. In addition, the delivery of waste packages was regulated. An outline of the structure and the elements of the Preliminary Waste Acceptance Requirements of April 1990 is given including comments on their legal status. (Author)

  7. Final Technical Report - Modernization of the Boulder Canyon Hydroelectric Project

    Energy Technology Data Exchange (ETDEWEB)

    Taddeucci, Joe [Dept. of Public Works, Boulder, CO (United States). Utilities Division

    2013-03-29

    double nozzle Pelton turbine with a 10-to-1 flow turndown and a maximum turbine/generator efficiency of 88%. This alone represents a 6% increase in overall efficiency. The old turbine operated at low efficiencies due to age and non-optimal sizing of the turbine for the water flow available to the unit. It was shut down whenever water flow dropped to less than 4-5 cfs, and at that flow, efficiency was 55 to 60%. The new turbine will operate in the range of 70 to 88% efficiency through a large portion of the existing flow range and would only have to be shut down at flow rates less than 3.7 cfs. Efficiency is expected to increase by 15-30%, depending on flow. In addition to the installation of new equipment, other goals for the project included: Increasing safety at Boulder Canyon Hydro Increasing protection of the Boulder Creek environment Modernizing and integrating control equipment into Boulder's municipal water supply system, and Preserving significant historical engineering information prior to power plant modernization. From January 1, 2010 through December 31, 2012, combined consultant and contractor personnel hours paid for by both the city and the federal government have totaled approximately 40,000. This equates roughly to seven people working full time on the project from January 2010 through December 2012. This project also involved considerable material expense (steel pipe, a variety of valves, electrical equipment, and the various components of the turbine and generator), which were not accounted for in terms of hours spent on the project. However, the material expense related to this project did help to create or preserve manufacturing/industrial jobs throughout the United States. As required by ARRA, the various components of the hydroelectric project were manufactured or substantially transformed in the U.S. BCH is eligible for nomination to the National Register of Historic Places due in part to its unique engineering features and innovative

  8. Yakima Habitat Improvement Project Master Plan, Technical Report 2003.

    Energy Technology Data Exchange (ETDEWEB)

    Golder Associates, Inc.

    2003-04-22

    result of the planning effort leading to this Master Plan, a Technical Working Group (TWG) was established that represents most, if not all, fish and wildlife agencies/interests in the subbasin. This TWG met regularly throughout the planning process to provide input and review and was instrumental in the development of this plan. Preparation of this plan included the development of a quantitative prioritization process to rank 40,000 parcels within the Urban Growth Area based on the value of fish and wildlife habitat each parcel provided. Biological and physical criteria were developed and applied to all parcels through a GIS-based prioritization model. In the second-phase of the prioritization process, the TWG provided local expert knowledge and review of the properties. In selecting the most critical areas within the Urban Growth Area for protection, this project assessed the value of fish and wildlife habitat on the Yakima River. Well-developed habitat acquisition efforts (e.g., Yakima River Basin Water Enhancement Project by the Bureau of Reclamation and Yakama Nation acquisition projects) are already underway on the Yakima River mainstem. These efforts, however, face several limitations in protection of floodplain function that could be addressed through the support of the Yakima Habitat Improvement Project. This Master Plan integrates tributary habitat acquisition efforts with those ongoing on the Yakima River to best benefit fish and wildlife in the Urban Growth Area. The parcel ranking process identified 25 properties with the highest fish and wildlife value for habitat acquisition in the Yakima Urban Area. These parcels contain important fish and wildlife corridors on Ahtanum and Wide Hollow Creeks and the Naches River. The fifteen highest-ranking parcels of the 25 parcels identified were considered very high priority for protection of fish and wildlife habitat. These 15 parcels were subsequently grouped into four priority acquisition areas. This Master Plan

  9. Requirements: Towards an understanding on why software projects fail

    Science.gov (United States)

    Hussain, Azham; Mkpojiogu, Emmanuel O. C.

    2016-08-01

    Requirement engineering is at the foundation of every successful software project. There are many reasons for software project failures; however, poorly engineered requirements process contributes immensely to the reason why software projects fail. Software project failure is usually costly and risky and could also be life threatening. Projects that undermine requirements engineering suffer or are likely to suffer from failures, challenges and other attending risks. The cost of project failures and overruns when estimated is very huge. Furthermore, software project failures or overruns pose a challenge in today's competitive market environment. It affects the company's image, goodwill, and revenue drive and decreases the perceived satisfaction of customers and clients. In this paper, requirements engineering was discussed. Its role in software projects success was elaborated. The place of software requirements process in relation to software project failure was explored and examined. Also, project success and failure factors were also discussed with emphasis placed on requirements factors as they play a major role in software projects' challenges, successes and failures. The paper relied on secondary data and empirical statistics to explore and examine factors responsible for the successes, challenges and failures of software projects in large, medium and small scaled software companies.

  10. Messiah College Biodiesel Fuel Generation Project Final Technical Report

    Energy Technology Data Exchange (ETDEWEB)

    Zummo, Michael M; Munson, J; Derr, A; Zemple, T; Bray, S; Studer, B; Miller, J; Beckler, J; Hahn, A; Martinez, P; Herndon, B; Lee, T; Newswanger, T; Wassall, M

    2012-03-30

    Many obvious and significant concerns arise when considering the concept of small-scale biodiesel production. Does the fuel produced meet the stringent requirements set by the commercial biodiesel industry? Is the process safe? How are small-scale producers collecting and transporting waste vegetable oil? How is waste from the biodiesel production process handled by small-scale producers? These concerns and many others were the focus of the research preformed in the Messiah College Biodiesel Fuel Generation project over the last three years. This project was a unique research program in which undergraduate engineering students at Messiah College set out to research the feasibility of small-biodiesel production for application on a campus of approximately 3000 students. This Department of Energy (DOE) funded research program developed out of almost a decade of small-scale biodiesel research and development work performed by students at Messiah College. Over the course of the last three years the research team focused on four key areas related to small-scale biodiesel production: Quality Testing and Assurance, Process and Processor Research, Process and Processor Development, and Community Education. The objectives for the Messiah College Biodiesel Fuel Generation Project included the following: 1. Preparing a laboratory facility for the development and optimization of processors and processes, ASTM quality assurance, and performance testing of biodiesel fuels. 2. Developing scalable processor and process designs suitable for ASTM certifiable small-scale biodiesel production, with the goals of cost reduction and increased quality. 3. Conduct research into biodiesel process improvement and cost optimization using various biodiesel feedstocks and production ingredients.

  11. Radiology and the internet, basic principles and technical requirements

    International Nuclear Information System (INIS)

    Boegl, K.

    2000-01-01

    As a new communication media the Internet has revolutionized the global exchange of information which is one of the major sources of progress in medicine. This article reviews the history of the Internet's evolution and describes some fundamental technical concepts. The importance of Internet services for everyday professional work is examined with special consideration of radiology. Special emphasis is laid on the current technical limitations that have delayed a broad practical implementation of tele-medical applications. As a highly innovative medical speciality, radiology has always been at the forefront of research and development in the field of clinical Internet applications. By taking a look at recent innovations, the impact of the Internet on the radiologist's working environment of the future is highlighted. (orig.) [de

  12. Technical safety requirements for the Annular Core Research Reactor Facility (ACRRF)

    International Nuclear Information System (INIS)

    Boldt, K.R.; Morris, F.M.; Talley, D.G.; McCrory, F.M.

    1998-01-01

    The Technical Safety Requirements (TSR) document is prepared and issued in compliance with DOE Order 5480.22, Technical Safety Requirements. The bases for the TSR are established in the ACRRF Safety Analysis Report issued in compliance with DOE Order 5480.23, Nuclear Safety Analysis Reports. The TSR identifies the operational conditions, boundaries, and administrative controls for the safe operation of the facility

  13. 47 CFR 15.513 - Technical requirements for medical imaging systems.

    Science.gov (United States)

    2010-10-01

    ... 47 Telecommunication 1 2010-10-01 2010-10-01 false Technical requirements for medical imaging... DEVICES Ultra-Wideband Operation § 15.513 Technical requirements for medical imaging systems. (a) The UWB... MHz and 10,600 MHz. (b) Operation under the provisions of this section is limited to medical imaging...

  14. 75 FR 18507 - International Cooperation on Harmonisation of Technical Requirements for Registration of...

    Science.gov (United States)

    2010-04-12

    ...] International Cooperation on Harmonisation of Technical Requirements for Registration of Veterinary Medicinal... guidance has been developed for veterinary use by the International Cooperation on Harmonisation of... associations to promote the international harmonization of regulatory requirements. FDA has participated in...

  15. South African CSP projects under the REIPPP programme - Requirements, challenges and opportunities

    Science.gov (United States)

    Relancio, Javier; Cuellar, Alberto; Walker, Gregg; Ettmayr, Chris

    2016-05-01

    Thus far seven Concentrated Solar Power (CSP) projects have been awarded under the Renewable Energy Independent Power Producer Procurement Programme (REIPPPP), totalling 600MW: one project is in operation, four under construction and two on their way to financial close. This provides an excellent opportunity for analysis of key features of the projects that have contributed to or detracted from the programme's success. The paper draws from Mott MacDonald's involvement as Technical Advisor on the seven CSP projects that have been successful under the REIPPPP to date as well as other global CSP developments. It presents how various programme requirements have affected the implementation of projects, such as the technical requirements, time of day tariff structure, economic development requirements and the renewable energy grid code. The increasingly competitive tariffs offered have encouraged developers to investigate efficiency maximising project configurations and cost saving mechanisms, as well as featuring state of the art technology in their proposals. The paper assesses the role of the project participants (developers, lenders and government) with regards to these innovative technologies and solutions. In our paper we discuss the status of projects and the SA market, analysing the main challenges and opportunities that in turn have influenced various aspects such as technology choice, operational regimes and supply chain arrangements.

  16. Making the most of LCA in technical inter-organisational R&D projects

    DEFF Research Database (Denmark)

    Sandin, Gustav; Clancy, Gunilla; Heimersson, Sara

    2014-01-01

    In technical Research and Development (R&D) projects, a Life Cycle Assessment (LCA) of the technology under development is sometimes carried out. Particularly in inter-organisational R&D projects, the roles of LCAs tend to be unclear and arbitrary, and as a consequence, LCA work is not adequately...... designed for the needs of the project. There is a need for research on how to choose an appropriate role for LCA in such projects and how to plan LCA work accordingly. We have identified some possible roles of LCA in inter-organisational R&D projects and used experiences from LCA work in different...... such projects to identify four project characteristics that are decisive for what roles the LCA can have. The project characteristics are: (i) the project's potential influence on environmental impacts, (ii) the degrees of freedom available for the technical direction of the project, (iii) the project...

  17. Projections of energy requirements and their implications

    International Nuclear Information System (INIS)

    Hogroian, P.

    1978-01-01

    The subject is covered in sections, entitled as shown. Numerical data are indicated in parenthesis. The record of nuclear power forecasting (estimates of the growth of world nuclear power, penetration of the electric power market by nuclear power); brief review of energy forecasting techniques and problems; some views of future world energy demand (estimates of world primary energy requirements); possible allocations of energy resources to needs (allocation of resources (oil, oil from tar sands, shale, natural gas, coal, coal to gasification, hydroelectricity, renewable resources, nuclear) to the world's primary energy needs in the year 2000); observations on the adequacy of energy resources; implications for nuclear energy (postulated growth of world nuclear power, annual fuel cycle requirements of the world, annual uranium requirements of the world). (U.K.)

  18. Technical Description Lillgrund Wind Power Plant. Lillgrund Pilot Project

    Energy Technology Data Exchange (ETDEWEB)

    Jeppsson, Joakim; Larsen, Poul Erik; Larsson, Aake [Vattenfall Vindkraft AB, Stockholm (Sweden)

    2008-09-15

    Lillgrund offshore wind power plant comprises 48 wind turbines, each rated at 2.3 MW, bringing the total wind farm capacity to 110 MW. The Lillgrund offshore wind power plant is located in a shallow area of Oeresund, 7 km off the coast of Sweden and 7 km south from the Oeresund Bridge connecting Sweden and Denmark. An average wind speed of around 8,5 m/s at hub height, combined with a relatively low water depth of 4 to 8 meters makes it economically feasible to build here. Vattenfall Vindkraft AB is the owner and operator of Lillgrund offshore wind power plant. Lillgrund is a Swedish pilot project supported by the Swedish Energy Agency. The bidding process was completed during 2005 and the offshore power plant was constructed in the period 2006 to 2007. The wind farm was constructed on time and has now been successfully operational since December 2007. There is, however, always potential for improvement and the aim of this report has been to determine and highlight these areas. It is worth noting out that only the electrical system and the foundations are tailor made at offshore wind power plants. The wind turbines are more or less standard products with none or very limited possibilities for project specific design changes. Geotechnical investigations are expensive and it can be difficult to balance the risks as well as the benefits of this expense in the early phases of a large infrastructure project. As a whole, the geotechnical surveys at Lillgrund proved to be useful. They identified potential issues, such as the fact that extra excavation was required for two of the foundations. It also revealed the location of a small number of boulders that would have to be removed. Vattenfall requested a complete study of the electrical system for Lillgrund to be delivered with the bids. That request was not met. Instead Siemens Wind Power began a complete electrical system study after being awarded the Contract. The electrical system study was completed during the

  19. Requirements Definition for ORNL Trusted Corridors Project

    Energy Technology Data Exchange (ETDEWEB)

    Walker, Randy M [ORNL; Hill, David E [ORNL; Smith, Cyrus M [ORNL; DeNap, Frank A [ORNL; White, James D [ORNL; Gross, Ian G [ORNL; Gorman, Bryan L [ORNL; Hively, Lee M [ORNL; Abercrombie, Robert K [ORNL

    2008-02-01

    The ORNL Trusted Corridors Project has several other names: SensorNet Transportation Pilot; Identification and Monitoring of Radiation (in commerce) Shipments (IMR(ic)S); and Southeastern Transportation Corridor Pilot (SETCP). The project involves acquisition and analysis of transportation data at two mobile and three fixed inspection stations in five states (Kentucky, Mississippi, South Carolina, Tennessee, and Washington DC). Collaborators include the State Police organizations that are responsible for highway safety, law enforcement, and incident response. The three states with fixed weigh-station deployments (KY, SC, TN) are interested in coordination of this effort for highway safety, law enforcement, and sorting/targeting/interdiction of potentially non-compliant vehicles/persons/cargo. The Domestic Nuclear Detection Office (DNDO) in the U.S. Department of Homeland Security (DHS) is interested in these deployments, as a Pilot test (SETCP) to identify Improvised Nuclear Devices (INDs) in highway transport. However, the level of DNDO integration among these state deployments is presently uncertain. Moreover, DHS issues are considered secondary by the states, which perceive this work as an opportunity to leverage these (new) dual-use technologies for state needs. In addition, present experience shows that radiation detectors alone cannot detect DHS-identified IND threats. Continued SETCP success depends on the level of integration of current state/local police operations with the new DHS task of detecting IND threats, in addition to emergency preparedness and homeland security. This document describes the enabling components for continued SETCP development and success, including: sensors and their use at existing deployments (Section 1); personnel training (Section 2); concept of operations (Section 3); knowledge discovery from the copious data (Section 4); smart data collection, integration and database development, advanced algorithms for multiple sensors, and

  20. Requirements Definition for ORNL Trusted Corridors Project

    International Nuclear Information System (INIS)

    Walker, Randy M; Hill, David E; Smith, Cyrus M; DeNap, Frank A; White, James D; Gross, Ian G; Gorman, Bryan L; Hively, Lee M; Abercrombie, Robert K

    2008-01-01

    The ORNL Trusted Corridors Project has several other names: SensorNet Transportation Pilot; Identification and Monitoring of Radiation (in commerce) Shipments (IMR(ic)S); and Southeastern Transportation Corridor Pilot (SETCP). The project involves acquisition and analysis of transportation data at two mobile and three fixed inspection stations in five states (Kentucky, Mississippi, South Carolina, Tennessee, and Washington DC). Collaborators include the State Police organizations that are responsible for highway safety, law enforcement, and incident response. The three states with fixed weigh-station deployments (KY, SC, TN) are interested in coordination of this effort for highway safety, law enforcement, and sorting/targeting/interdiction of potentially non-compliant vehicles/persons/cargo. The Domestic Nuclear Detection Office (DNDO) in the U.S. Department of Homeland Security (DHS) is interested in these deployments, as a Pilot test (SETCP) to identify Improvised Nuclear Devices (INDs) in highway transport. However, the level of DNDO integration among these state deployments is presently uncertain. Moreover, DHS issues are considered secondary by the states, which perceive this work as an opportunity to leverage these (new) dual-use technologies for state needs. In addition, present experience shows that radiation detectors alone cannot detect DHS-identified IND threats. Continued SETCP success depends on the level of integration of current state/local police operations with the new DHS task of detecting IND threats, in addition to emergency preparedness and homeland security. This document describes the enabling components for continued SETCP development and success, including: sensors and their use at existing deployments (Section 1); personnel training (Section 2); concept of operations (Section 3); knowledge discovery from the copious data (Section 4); smart data collection, integration and database development, advanced algorithms for multiple sensors, and

  1. Projecting India's energy requirements for policy formulation

    International Nuclear Information System (INIS)

    Parikh, Kirit S.; Karandikar, Vivek; Rana, Ashish; Dani, Prasanna

    2009-01-01

    Energy policy has to have a long-term perspective. To formulate it one needs to know the contours of energy requirements and options. Different approaches have been followed in literature, each with their own problems. A top down econometric approach provides little guidance on policies, while a bottom up approval requires too much knowledge and too many assumptions. Using top-down econometric approach for aggregate overall benchmarking and a detailed activity analysis model, Integrated Energy System Model, for a few large sectors, provides a unique combination for easing the difficulties of policy formulation. The model is described in this paper. Eleven alternate scenarios are built, designed to map out extreme points of feasible options. Results show that even after employing all domestic energy resource to their full potential, there will be a continued rise of fossil fuel use, continued importance of coal, and continued rise of import dependence. Energy efficiency emerges as a major option with a potential to reduce energy requirement by as much as 17%. Scenario results point towards pushing for development of alternative sources. (author)

  2. Design requirements document for Project W-465, immobilized low-activity waste interim storage

    International Nuclear Information System (INIS)

    Burbank, D.A.

    1998-01-01

    The scope of this Design Requirements Document (DRD) is to identify the functions and associated requirements that must be performed to accept, transport, handle, and store immobilized low-activity waste (ILAW) produced by the privatized Tank Waste Remediation System (TWRS) treatment contractors. The functional and performance requirements in this document provide the basis for the conceptual design of the TWRS ILAW Interim Storage facility project and provides traceability from the program level requirements to the project design activity. Technical and programmatic risk associated with the TWRS planning basis are discussed in the Tank Waste Remediation System Decisions and Risk Assessment (Johnson 1994). The design requirements provided in this document will be augmented by additional detailed design data documented by the project

  3. MORE: Management of Requirements in NPP Modernisation Projects, final report

    International Nuclear Information System (INIS)

    Fredriksen, R.; Katta, V.; Raspotnig, C.; Valkonen, J.

    2008-09-01

    This report documents the work and related activities of the MORE (Management of Requirements in NPP Modernisation Projects) (NKS-R project number NKS-R-2005-47) project. This report also provides a summary of the project activities and deliverables, and discusses possible application areas. The project has aimed at the industrial utilisation of the results from the TACO: (Traceability and Communication of Requirements in Digital I and C Systems Development) (NKS-R project number NKS-R-2002-16, completed June, 2005) project, and practical application of improved approaches and methods for requirements engineering and change management. Finally, the report provides a brief description of the extended industrial network and disseminations of the results in Nordic and NKS related events such as seminars and workshops. (au)

  4. MORE: Management of Requirements in NPP Modernisation Projects, final report

    Energy Technology Data Exchange (ETDEWEB)

    Fredriksen, R.; Katta, V.; Raspotnig, C. (Inst. for energiteknikk (IFE) (Norway)); Valkonen, J. (Technical Research Centre of Finland (VTT) (Finland))

    2008-09-15

    This report documents the work and related activities of the MORE (Management of Requirements in NPP Modernisation Projects) (NKS-R project number NKS-R-2005-47) project. This report also provides a summary of the project activities and deliverables, and discusses possible application areas. The project has aimed at the industrial utilisation of the results from the TACO: (Traceability and Communication of Requirements in Digital I and C Systems Development) (NKS-R project number NKS-R-2002-16, completed June, 2005) project, and practical application of improved approaches and methods for requirements engineering and change management. Finally, the report provides a brief description of the extended industrial network and disseminations of the results in Nordic and NKS related events such as seminars and workshops. (author)

  5. Technical needs and research opportunities provided by projected aeronautical and space systems

    Science.gov (United States)

    Noor, Ahmed K.

    1992-01-01

    The overall goal of the present task is to identify the enabling and supporting technologies for projected aeronautical and space systems. A detailed examination was made of the technical needs in the structures, dynamics and materials areas required for the realization of these systems. Also, the level of integration required with other disciplines was identified. The aeronautical systems considered cover the broad spectrum of rotorcraft; subsonic, supersonic and hypersonic aircraft; extremely high-altitude aircraft; and transatmospheric vehicles. The space systems considered include space transportation systems; spacecrafts for near-earth observation; spacecrafts for planetary and solar exploration; and large space systems. A monograph is being compiled which summarizes the results of this study. The different chapters of the monograph are being written by leading experts from governmental laboratories, industry and universities.

  6. 18 CFR 806.4 - Projects requiring review and approval.

    Science.gov (United States)

    2010-04-01

    ... result of a change of the name, identity, internal corporate structure or place of organization and does... period, and undergoing a change of ownership, unless such project satisfies the requirements of..., and undergoing a change of ownership, unless such project satisfies the requirements of paragraphs (b...

  7. Uganda's National Transmission Backbone Infrastructure Project: Technical Challenges and the Way Forward

    Science.gov (United States)

    Bulega, T.; Kyeyune, A.; Onek, P.; Sseguya, R.; Mbabazi, D.; Katwiremu, E.

    2011-10-01

    Several publications have identified technical challenges facing Uganda's National Transmission Backbone Infrastructure project. This research addresses the technical limitations of the National Transmission Backbone Infrastructure project, evaluates the goals of the project, and compares the results against the technical capability of the backbone. The findings of the study indicate a bandwidth deficit, which will be addressed by using dense wave division multiplexing repeaters, leasing bandwidth from private companies. Microwave links for redundancy, a Network Operation Center for operation and maintenance, and deployment of wireless interoperability for microwave access as a last-mile solution are also suggested.

  8. The database system for the management of technical documentations of PWR fuel design project using CD-ROM

    International Nuclear Information System (INIS)

    Park, Bong Sik; Lee, Won Jae; Ryu, Jae Kwon; Jo, In Hang; Chang, Jong Hwa.

    1996-12-01

    In this report, the database system developed for the management of technical documentation of PWR fuel design project using CD-ROM (compact disk - read only memory) is described. The database system, KIRDOCM (KAERI Initial and Reload Fuel project technical documentation management), is developed and installed on PC using Visual Foxpro 3.0. Descriptions are focused on the user interface of the KIRDOCM. Introduction addresses the background and concept of the development. The main chapter describes the user requirements, the analysis of computing environment, the design of KIRDOCM, the implementation of the KIRDOCM, user's manual of KIRDOCM and the maintenance of the KIRDOCM for future improvement. The implementation of KIRDOCM system provides the efficiency in the management, maintenance and indexing of the technical documents. And, it is expected that KIRDOCM may be a good reference in applying Visual Foxpro for the development of information management system. (author). 2 tabs., 13 figs., 8 refs

  9. Technical Area V (TA-V) transformation project close-out report.

    Energy Technology Data Exchange (ETDEWEB)

    2010-07-01

    Sandia National Laboratories (SNL) Technical Area V (TA-V) has provided unique nuclear experimental environments for decades. The technologies tested in TA-V facilities have furthered the United States Nuclear Weapons program and has contributed to the national energy and homeland security mission. The importance of TA-V working efficiently to produce an attractive and effective platform for experiments should not be underestimated. Throughout its brief history, TA-V has evolved to address multiple and diverse sets of requirements. These requirements evolved over many years; however, the requirements had not been managed nor communicated comprehensively or effectively. A series of programmatic findings over several years of external audits was evidence of this downfall. Today, these same requirements flow down through a new TA-V management system that produces consistently applied and reproducible approaches to work practices. In 2008, the TA-V department managers assessed the state of TA-V services and work activities to understand how to improve customer interfaces, stakeholders perceptions, and workforce efficiencies. The TA-V management team initiated the TA-V Transformation Project after they deemed the pre-June 2008 operational model to be ineffective in managing work and in providing integrated, continuous improvement to TA-V processes. This report summarizes the TA-V Transformation Project goals, activities, and accomplishments.

  10. Selection and approbation of new technical approaches in innovation projects

    International Nuclear Information System (INIS)

    Matvienko, V.A.; Pastushenko, V.N.; Zvorykin, K.O.; Zvorykin, L.O.

    1999-01-01

    Large-scale technical approaches based on the application of new technologies, equipment, tools and other production equipping means (PEM) are to be previously tested by technical and engineering practice and thoroughly approved. These circumstances create objective prerequisites for organization within the infrastructure of the 'OU' of a special sector to solve such a problem. A structure-and-logic model of the infrastructure sector is represented. Principal trends of activities of the proposed new sector of the 'OU' infrastructure may become the following ones: personnel training, skill rising and attestation; adaptation of new samples of universal and auxiliary equipment; new technologies and equipment approbation; approbation of actions in nonstandard situations

  11. Lead Coolant Test Facility Technical and Functional Requirements, Conceptual Design, Cost and Construction Schedule

    International Nuclear Information System (INIS)

    Soli T. Khericha

    2006-01-01

    This report presents preliminary technical and functional requirements (T and FR), thermal hydraulic design and cost estimate for a lead coolant test facility. The purpose of this small scale facility is to simulate lead coolant fast reactor (LFR) coolant flow in an open lattice geometry core using seven electrical rods and liquid lead or lead-bismuth eutectic. Based on review of current world lead or lead-bismuth test facilities and research need listed in the Generation IV Roadmap, five broad areas of requirements of basis are identified: Develop and Demonstrate Prototype Lead/Lead-Bismuth Liquid Metal Flow Loop Develop and Demonstrate Feasibility of Submerged Heat Exchanger Develop and Demonstrate Open-lattice Flow in Electrically Heated Core Develop and Demonstrate Chemistry Control Demonstrate Safe Operation and Provision for Future Testing. These five broad areas are divided into twenty-one (21) specific requirements ranging from coolant temperature to design lifetime. An overview of project engineering requirements, design requirements, QA and environmental requirements are also presented. The purpose of this T and FRs is to focus the lead fast reactor community domestically on the requirements for the next unique state of the art test facility. The facility thermal hydraulic design is based on the maximum simulated core power using seven electrical heater rods of 420 kW; average linear heat generation rate of 300 W/cm. The core inlet temperature for liquid lead or Pb/Bi eutectic is 420 C. The design includes approximately seventy-five data measurements such as pressure, temperature, and flow rates. The preliminary estimated cost of construction of the facility is $3.7M. It is also estimated that the facility will require two years to be constructed and ready for operation

  12. TMI-related requirements for new operating licenses. Technical report

    International Nuclear Information System (INIS)

    1980-06-01

    There are four types of TMI-related requirements and actions approved by the Commission for new operating licenses: (1) those required to be completed by a license applicant prior to receiving a fuel-loading and low-power testing license, (2) those required to be completed by a license applicant prior to receiving a license to operate at appreciable power levels up to full power, (3) those the NRC will take prior to issuing a fuel-loading and low-power testing or a full-power operating license, and (4) those required to be completed by a licensee prior to a specified date. In this report, only those dated requirements that have already been issued are of interest. Other dated requirements are expected to be issued in the future as work progresses in accordance with the TMI Action Plan. This report summarizes the several parts of the list of TMI-related requirements approved by the Commission for new operating licenses

  13. Cluster: Drafting. Course: Basic Technical Drafting. Research Project.

    Science.gov (United States)

    Sanford - Lee County Schools, NC.

    The set of six units is designed for use with an instructor in basic technical drafting and is also keyed to other texts. Each unit contains several task packages specifying prerequisites, rationale for learning, objectives, learning activities to be supervised by the instructor, and learning practice. The units cover: pictorial drawing; screw…

  14. Advising students in technical projects - recognizing problem scenarios

    DEFF Research Database (Denmark)

    Bærentzen, Jacob Andreas; Singh, Karan

    2014-01-01

    In this paper, we consider the advisor’s role during the technical work and the thesis preparation for a student in the final phase of a course of study in an engineering education. We initially claim that there is a marked difference between the learning that takes place in regular course work...

  15. Substantiation of the safety in the technical project of Belene NPP

    International Nuclear Information System (INIS)

    Boyadzhiev, A.

    1990-01-01

    The chapter contains an evaluation of the safety of Belene NPP project, based on an experts study of the corresponding volume of the Technical Project documentation of the main contractor and also on other related documents. The authors state that most of the remarks are constitutive, part of them requiring additional information or research. The general explicit conclusion is that the materials on the safety substantiation provided in the project are insufficient for making final statements on the safety of the NPP and there is a need for a detailed analysis and expertise. There are 12 topical conclusion paragraphs and each of them comprises a number of remarks. Among the remarks there are some related to the reactivity coefficient values in certain modes of operation, the problem of the mechanical safety and control system efficiency, the unacceptable operation at nominal power in case of stringent safety rules enforcement, the insufficiency of the PSA, the automatic control systems and the software codes not standing up to the contemporary requirements. (R.Ts.)

  16. WindFloat Pacific Project, Final Scientific and Technical Report

    Energy Technology Data Exchange (ETDEWEB)

    Banister, Kevin [Principle Power, Inc., Emeryville, CA (United States)

    2017-01-17

    PPI’s WindFloat Pacific project (WFP) was an up to 30 MW floating offshore wind demonstration project proposed off the Coast of Oregon. The project was to be sited approximately 18 miles due west of Coos Bay, in over 1000 ft. of water, and is the first floating offshore wind array proposed in the United States, and the first offshore wind project of any kind proposed off the West Coast. PPI’s WindFloat, a semi-submersible foundation designed for high-capacity (6MW+) offshore wind turbines, is at the heart of the proposed project, and enables access to the world class wind resource at the project site and, equally, to other deep water, high wind resource areas around the country.

  17. 78 FR 12955 - Final Requirements, Definitions, and Selection Criteria-Native American Career and Technical...

    Science.gov (United States)

    2013-02-26

    ... career and technical education programs (20 U.S.C. 2326(e)). This notice does not preclude us from... DEPARTMENT OF EDUCATION 34 CFR Chapter IV [Docket ID ED-2012-OVAE-0053] Final Requirements, Definitions, and Selection Criteria--Native American Career and Technical Education Program (NACTEP) [Catalog...

  18. 76 FR 35103 - Training and Qualification Requirements for Check Airmen and Flight Instructors; Technical Amendment

    Science.gov (United States)

    2011-06-16

    ... which initial and transition flight training must include an in-flight element. Technical Amendment This.... 28471; Amendment Nos. 121-355 and 135-125] RIN 2120-AF08 Training and Qualification Requirements for Check Airmen and Flight Instructors; Technical Amendment AGENCY: Federal Aviation Administration (FAA...

  19. 47 CFR 25.215 - Technical requirements for space stations in the Direct Broadcast Satellite Service.

    Science.gov (United States)

    2010-10-01

    ... 47 Telecommunication 2 2010-10-01 2010-10-01 false Technical requirements for space stations in the Direct Broadcast Satellite Service. 25.215 Section 25.215 Telecommunication FEDERAL COMMUNICATIONS COMMISSION (CONTINUED) COMMON CARRIER SERVICES SATELLITE COMMUNICATIONS Technical Standards § 25.215...

  20. The JET Project Scientific and technical developments 1976

    International Nuclear Information System (INIS)

    1977-01-01

    The JET (Joint European Torus) Project is fully described in EUR 5516e (EUR-JET-R5) 'The JET Project - Design Proposal'. This report describes developments in the project from the stage described in EUR 5516e until late in 1976. An introductory chapter describes the present state of the project and subsequent chapters deal in detail with the following topics: experimental programme aspects; vacuum vessel, pumping system, activation studies; toroidal field coils and mechanical structure; poloidal field system; assembly and maintenance; power supplies; control and data acquisition system; site and buildings

  1. Fabrication of sterile experimental radiopharmaceuticals: technical and regulatory requirements

    International Nuclear Information System (INIS)

    Briand, S.

    2008-03-01

    The radiopharmaceuticals devoted to the biomedical research were the object of the directive 2001/20/C.E. transposition that defined again the conditions of implementation of biomedical research using drugs at human use, whom authorization is delivered by A.f.s.s.a.p.s.. In an other hand the law 2006-686 of the 13. june 2006 ( called law T.S.N.) has modified the regulatory dispositions relative to the radiation protection norms. These new dispositions allow to the health facilities to realize their research projects without difficulties for experimental drugs supply. (N.C.)

  2. 47 CFR 15.319 - General technical requirements.

    Science.gov (United States)

    2010-10-01

    ...-equivalent voltage. The measurement results shall be properly adjusted for any instrument limitations, such... bandwidth, sensitivity, etc., so as to obtain a true peak measurement for the emission in question over the... point. (i) Unlicensed PCS devices are subject to the radiofrequency radiation exposure requirements...

  3. Technical solutions for waste treatment in the Belene project

    International Nuclear Information System (INIS)

    Büttner, K.; Eichhorn, H.

    2011-01-01

    Outline: In June 2010 NUKEM Technologies GmbH was awarded a contract from ATOMSTROYEXPORT JSC to perform the complete work package related to designing and completion of the equipment for treatment of radioactive waste on the turn-key basis for Belene NPP. Technical Solutions: Waste Streams and Technologies at UKC and UKS; Concentration Plant; Thermal Treatment of Resins Sorting Facility; Biological Waste Water Treatment; Conditioning – Cementation • Sorting of Radwaste; Plasma Facility; Grouting; Filter Press; Monitoring and Tracking

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

    International Nuclear Information System (INIS)

    2012-01-01

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

  5. Generation of recycled aggregates and technical requirements for some applications

    OpenAIRE

    MARTÍNEZ LAGE, ISABEL; VÁZQUEZ HERRERO, CRISTINA; GONZÁLEZ FONTEBOA, BELÉN; MARTÍNEZ ABELLA, FERNANDO

    2010-01-01

    In the present framework of sustainable construction, management of construction and demolition (C&D) waste or debris is stressed and its correct implementation requires a previous estimation of the precise quantities and detailed composition of C&D waste.This allows us to make an estimate of the production of recycled aggregate and to analyze the impact of its use in relation to the use of natural aggregate. Research of existing bibliography, the results obtained from both experiment...

  6. Mississippi Ethanol Gasification Project, Final Scientific / Technical Report

    Energy Technology Data Exchange (ETDEWEB)

    Pearson, Larry, E.

    2007-04-30

    The Mississippi Ethanol (ME) Project is a comprehensive effort to develop the conversion of biomass to ethanol utilizing a proprietary gasification reactor technology developed by Mississippi Ethanol, LLC. Tasks were split between operation of a 1/10 scale unit at the Diagnostic Instrumentation and Analysis Laboratory (DIAL) of Mississippi State University (MSU) and the construction, development, and operation of a full scale pilot unit located at the ME facility in Winona, Mississippi. In addition to characterization of the ME reactor gasification system, other areas considered critical to the operational and economic viability of the overall ME concept were evaluated. These areas include syngas cleanup, biological conversion of syngas to alcohol, and effects of gasification scale factors. Characterization of run data from the Pre-Pilot and Pilot Units has allowed development of the factors necessary for scale-up from the small unit to the larger unit. This scale range is approximately a factor of 10. Particulate and tar sampling gave order of magnitude values for preliminary design calculations. In addition, sampling values collected downstream of the ash removal system show significant reductions in observed loadings. These loading values indicate that acceptable particulate and tar loading rates could be attained with standard equipment additions to the existing configurations. Overall operation both the Pre-Pilot and Pilot Units proceeded very well. The Pilot Unit was operated as a system, from wood receiving to gas flaring, several times and these runs were used to address possible production-scale concerns. Among these, a pressure feed system was developed to allow feed of material against gasifier system pressure with little or no purge requirements. Similarly, a water wash system, with continuous ash collection, was developed, installed, and tested. Development of a biological system for alcohol production was conducted at Mississippi State University with

  7. ECOLOGICAL AND TECHNICAL REQUIREMENTS OF RADIOACTIVE WASTE UTILISATION

    Directory of Open Access Journals (Sweden)

    Gabriel Borowski

    2013-01-01

    Full Text Available The paper presents a survey of radioactive waste disposal technologies used worldwide in terms of their influence upon natural environment. Typical sources of radioactive waste from medicine and industry were presented. In addition, various types of radioactive waste, both liquid and solid, were described. Requirements and conditions of the waste’s storage were characterised. Selected liquid and solid waste processing technologies were shown. It was stipulated that contemporary methods of radioactive waste utilisation enable their successful neutralisation. The implementation of these methods ought to be mandated by ecological factors first and only then economical ones.

  8. TEACHING BASIC ELEMENTS IN TECHNICAL DRAWING – ORTHOGONAL PROJECTIONS

    Directory of Open Access Journals (Sweden)

    CLINCIU Ramona

    2017-05-01

    Full Text Available The paper presents applications developed using AutoCAD and 3D Studio MAX programs. These applications are constructed such as to enable, gradually, the development of the spatial abilities of the students and, at the same time, to enable the understanding of the principles for the representation of the orthogonal projections of the parts, as well as for the construction of their axonometric projections.

  9. 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

  10. Technical considerations and policy requirements for plutonium management

    International Nuclear Information System (INIS)

    Christensen, D.C.; Dinehart, S.M.; Yarbro, S.L.

    1995-01-01

    The goals for plutonium management have changed dramatically over the past few years. Today, the challenge is focused on isolating plutonium from the environment and preparing it for permanent disposition. In parallel, the requirements for managing plutonium are rapidly changing. For example, there is a significant increase in public awareness on how facilities operate, increased attention to environmental safety and health (ES and H) concerns, greater interest in minimizing waste, more emphasis on protecting material from theft, providing materials for international inspection, and a resurgence of interest in using plutonium as an energy source. Of highest concern, in the immediate future, is protecting plutonium from theft or diversion, while the national policy on disposition is debated. These expanded requirements are causing a broadening of responsibilities within the Department of Energy (DOE) to include at least seven organizations. An unavoidable consequence is the divergence in approach and short-term goals for managing similar materials within each organization. The technology base does exist, properly, safely, and cost effectively to extract plutonium from excess weapons, residues, waste, and contaminated equipment and facilities, and to properly stabilize it. Extracting the plutonium enables it to be easily inventoried, packaged, and managed to minimize the risk of theft and diversion. Discarding excess plutonium does not sufficiently reduce the risk of diversion, and as a result, long-term containment of plutonium from the environment may not be able to be proven to the satisfaction of the public

  11. Technical considerations and policy requirements for plutonium management

    International Nuclear Information System (INIS)

    Christensen, D.C.; Dinehart, S.M.; Yarbro, S.L.

    1996-01-01

    The goals for plutonium management have changed dramatically over the past few years. Today, the challenge is focused on isolating plutonium from the environment and preparing it for permanent disposition. In parallel, the requirements for managing plutonium are rapidly changing. For example, there is a significant increase in public awareness on how facilities operate, increased attention to environmental safety and health (ES and H) concerns, greater interest in minimizing waste, more emphasis on protecting material from theft, providing materials for international inspection, and a resurgence of interest in using plutonium as an energy source. Of highest concern, in the immediate future, is protecting plutonium from theft or diversion, while the national policy on disposition is debated. These expanded requirements are causing a broadening of responsibilities within the Department of Energy (DOE) to include at least seven organizations. An unavoidable consequence is the divergence in approach and short-term goals for managing similar materials within each organization. The technology base does exist, properly, safely, and cost effectively to extract plutonium from excess weapons, residues, waste, and contaminated equipment and facilities, and to properly stabilize it. Extracting the plutonium enables it to be easily inventoried, packaged, and managed to minimize the risk of theft and diversion. Discarding excess plutonium does not sufficient reduce the risk of diversion, and as a result, long-term containment of plutonium from the environment may not be able to be proven to the satisfaction of the public

  12. 42 CFR 50.208 - Program or project requirements.

    Science.gov (United States)

    2010-10-01

    ... 42 Public Health 1 2010-10-01 2010-10-01 false Program or project requirements. 50.208 Section 50.208 Public Health PUBLIC HEALTH SERVICE, DEPARTMENT OF HEALTH AND HUMAN SERVICES GRANTS POLICIES OF GENERAL APPLICABILITY Sterilization of Persons in Federally Assisted Family Planning Projects § 50.208...

  13. The Basalt Waste Isolation Project technical program evaluation process: A criteria-based method

    International Nuclear Information System (INIS)

    Babad, H.; Evans, C.; Wolfe, B.A.

    1982-01-01

    The need to objectively evaluate the progress being made by the Basalt Waste Isolation Project (BWIP) toward establishing the feasibility of siting a nuclear waste repository in basalt (NWRB) mandates a process for evaluating the technical work of the project. To assist BWIP management in the evaluation process, the Systems Department staff has developed a BWIP Technical Program Evaluation Process (TPEP). The basic process relates progress on project technical work to the BWIP Functional and System Performance Criteria as defined in National Waste Terminal Storage (NWTS) Criteria Documents. The benefits of the TPEP to BWIP and future plans for TPEP are discussed. During fiscal year (FY) 1982, TPEP will be further formalized and further applied to the review of BWIP technical activities

  14. Basalt Waste Isolation Project Technical Program Evaluation Process: a criteria-based method

    International Nuclear Information System (INIS)

    Babad, H.; Evans, G.C.; Wolfe, B.A.

    1982-01-01

    The need to objectively evaluate the progress being made by the Basalt Waste Isolation Project (BWIP) toward establishing the feasibility of siting a nuclear waste repository in basalt (NWRB) mandates a process for evaluating the technical work of the project. To assist BWIP management in the evaluation process, the Systems Department staff has developed a BWIP Technical Program Evaluation Process (TPEP). The basic process relates progress on project technical work to the SWIP Functional and System Performance Criteria as defined in National Waste Terminal Storage (MWTS) Criteria Documents. The benefits of the TPEP to BWIP and future plans for TPEP are discussed. During fiscal year (FY) 1982, TPEP wll be further formalized and further applied to the review of BWIP technical activities

  15. Uranium Mill Tailings Remedial Action Project: technical approach document

    International Nuclear Information System (INIS)

    1986-05-01

    The Uranium Mill Tailings Radiation Control Act of 1978, PL95-604, grants the Secretary of Energy authority and responsibility to perform such actions as are necessary to minimize radiation health hazards and other environmental hazards from inactive uranium mill sites. These cleanup actions are to be performed in compliance with the EPA standards (40 CFR Part 192) which became final on March 7, 1983. This document describes the general technical approaches and design criteria that are adopted by the US Department of Energy (DOE) in order to implement Remedial Action Plans (RAPs) and final designs that comply with EPA standards

  16. Functions and requirements for tank farm restoration and safe operations, Project W-314. Revision 3

    International Nuclear Information System (INIS)

    Garrison, R.C.

    1995-01-01

    This Functions and Requirements document (FRD) establishes the basic performance criteria for Project W-314, in accordance with the guidance outlined in the letter from R.W. Brown, RL, to President, WHC, ''Tank Waste Remediation System (TWRS) Project Documentation Methodology,'' 94-PRJ-018, dated 3/18/94. The FRD replaces the Functional Design Criteria (FDC) as the project technical baseline documentation. Project W-314 will improve the reliability of safety related systems, minimize onsite health and safety hazards, and support waste retrieval and disposal activities by restoring and/or upgrading existing Tank Farm facilities and systems. The scope of Project W-314 encompasses the necessary restoration upgrades of the Tank Farms' instrumentation, ventilation, electrical distribution, and waste transfer systems

  17. Health recommender systems: concepts, requirements, technical basics and challenges.

    Science.gov (United States)

    Wiesner, Martin; Pfeifer, Daniel

    2014-03-03

    During the last decades huge amounts of data have been collected in clinical databases representing patients' health states (e.g., as laboratory results, treatment plans, medical reports). Hence, digital information available for patient-oriented decision making has increased drastically but is often scattered across different sites. As as solution, personal health record systems (PHRS) are meant to centralize an individual's health data and to allow access for the owner as well as for authorized health professionals. Yet, expert-oriented language, complex interrelations of medical facts and information overload in general pose major obstacles for patients to understand their own record and to draw adequate conclusions. In this context, recommender systems may supply patients with additional laymen-friendly information helping to better comprehend their health status as represented by their record. However, such systems must be adapted to cope with the specific requirements in the health domain in order to deliver highly relevant information for patients. They are referred to as health recommender systems (HRS). In this article we give an introduction to health recommender systems and explain why they are a useful enhancement to PHR solutions. Basic concepts and scenarios are discussed and a first implementation is presented. In addition, we outline an evaluation approach for such a system, which is supported by medical experts. The construction of a test collection for case-related recommendations is described. Finally, challenges and open issues are discussed.

  18. Health Recommender Systems: Concepts, Requirements, Technical Basics and Challenges

    Directory of Open Access Journals (Sweden)

    Martin Wiesner

    2014-03-01

    Full Text Available During the last decades huge amounts of data have been collected in clinical databases representing patients’ health states (e.g., as laboratory results, treatment plans, medical reports. Hence, digital information available for patient-oriented decision making has increased drastically but is often scattered across different sites. As as solution, personal health record systems (PHRS are meant to centralize an individual’s health data and to allow access for the owner as well as for authorized health professionals. Yet, expert-oriented language, complex interrelations of medical facts and information overload in general pose major obstacles for patients to understand their own record and to draw adequate conclusions. In this context, recommender systems may supply patients with additional laymen-friendly information helping to better comprehend their health status as represented by their record. However, such systems must be adapted to cope with the specific requirements in the health domain in order to deliver highly relevant information for patients. They are referred to as health recommender systems (HRS. In this article we give an introduction to health recommender systems and explain why they are a useful enhancement to PHR solutions. Basic concepts and scenarios are discussed and a first implementation is presented. In addition, we outline an evaluation approach for such a system, which is supported by medical experts. The construction of a test collection for case-related recommendations is described. Finally, challenges and open issues are discussed.

  19. Summary of the technical guidelines used in the project: The economics of greenhouse gas limitations

    International Nuclear Information System (INIS)

    Halsnaes, Kirsten

    1998-01-01

    This document is a summary version of the technical guidelines for climate change mitigation assessment developed as a part of the Global Environment Facility (GEF) project The Economics of Greenhouse Gas Limitations; Technical guidelines (UNEP 1998). The objectives of this project have been to support the development of a methodology, an implementing framework and a reporting system which countries can use in the construction of national climate change policies and in meeting their future reporting obligations under the FCCC. The methodological framework developed in the guidelines covers key economic concepts, scenario building, modelling tools and common assumptions. It was used by several country studies included in the project. (au)

  20. Final Technical Report for Terabit-scale hybrid networking project.

    Energy Technology Data Exchange (ETDEWEB)

    Veeraraghavan, Malathi [Univ. of Virginia, Charlottesville, VA (United States)

    2015-12-12

    This report describes our accomplishments and activities for the project titled Terabit-Scale Hybrid Networking. The key accomplishment is that we developed, tested and deployed an Alpha Flow Characterization System (AFCS) in ESnet. It is being run in production mode since Sept. 2015. Also, a new QoS class was added to ESnet5 to support alpha flows.

  1. Development of Procedures for Assessing the Impact of Vocational Education Research and Development on Vocational Education (Project IMPACT). Volume 8--A Field Study of Predicting Impact of Research and Development Projects in Vocational and Technical Education.

    Science.gov (United States)

    Malhorta, Man Mohanlal

    As part of Project IMPACT's effort to identify and develop procedures for complying with the impact requirements of Public Law 94-482, a field study was conducted to identify and validate variables and their order of importance in predicting and evaluating impact of research and development (R&D) projects in vocational and technical education.…

  2. The applies specific technical requirements to the services of radiological protection according to the 17025

    Energy Technology Data Exchange (ETDEWEB)

    Marrero Garcia, M.; Fernandez Gomez, I. M.; Prendes Alonso, M.; Molina Perez, D.

    2004-07-01

    The employment in the Center of Radiation Protection and Hygiene (CRPH) of Cuba, of the standard 17025 for the administration of the quality of the calibration laboratories and test that offer services of radiological protection requires of a technical complement to really determine the technical competence. In the standard 17025, the specific requirements, are mentioned in the annex B (with informative character), where it points out that: {sup T}he requirements specified in the standard 17025 are established in general terms and, although they can be applied to all the test laboratories and applications, they could be necessary applications{sup .} In the CRPH these applications are translated in indispensable technical requirements to evaluate the performance of the services of radiological protection that offers, specifically those of personal monitoring, the calibration of instruments and the metrology of radionuclides. Although the standard 17025 is quite rigorous in the evaluation of technical requirements, to have specific materials not serves alone of tool to the laboratories, but also for the body of accreditation . In the CRPH the permanent employment of this tool has not constituted a practice, but had been good before our clients certain nonconformities to evaluate the performance of the laboratory and to achieve the recovery of the trust in its results. With this work we seek to expose some of these experiences. The experiences of the application of some of the technical requirements, in our case, they have been applied to the service of personal monitoring that offers the Laboratory of Personal Dosimetry. This laboratory is accredited by the National Accreditation Board of the Republic of Cuba (NABC) and besides fulfilling that settled down in 17025, the Approaches of Accreditation for test laboratories and calibration and it should also implant that settled down as specific technical requirements for the recognition of technical competence. (Author

  3. PROBLEM-SOLVING METHODS OF PROJECT MANAGEMENT OF TECHNICAL DEVELOPMENT FOR AGRICULTURAL PRODUCERS

    Directory of Open Access Journals (Sweden)

    Александр Васильевич СИДОРЧУК

    2015-05-01

    Full Text Available There have been proposed projects of technical development for agricultural producers. The conclusions about system features research projects that underlie the problem-solving methods of project management, have been made. There have been proved these projects (systems that can be simulated with the help of the research and formalization of many events. These events are components of the seven main factors of the agricultural production. The conclusion about the using the research method of the probabilistic nature events in the field of the crops projects with the help of the statistical and imitational models, have been developed. There have been considered the relation between the forecasting of functional marks of the technological systems and the estimation of their cost. And there have been found the optimum correspondence between parameters of the technical supply and planned features of the crops projects.

  4. Technical Requirements for Fabrication and Installation of Removable Shield for CNRF in HANARO

    Energy Technology Data Exchange (ETDEWEB)

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

    2008-04-15

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

  5. Required doses for projection methods in X-ray diagnosis

    International Nuclear Information System (INIS)

    Hagemann, G.

    1992-01-01

    The ideal dose requirement has been stated by Cohen et al. (1981) by a formula basing on parallel beam, maximum quantum yield and Bucky grid effect depending on the signal to noise ratio and object contrast. This was checked by means of contrast detail diagrams measured at the hole phantom, and was additionally compared with measurement results obtained with acrylic glass phantoms. The optimal dose requirement is obtained by the maximum technically possible approach to the ideal requirement level. Examples are given, besides for x-ray equipment with Gd 2 O 2 S screen film systems for grid screen mammography, and new thoracic examination systems for mass screenings. Finally, a few values concerning the dose requirement or the analogous time required for fluorscent screening in angiography and interventional radiology, are stated, as well as for dentistry and paediatric x-ray diagnostics. (orig./HP) [de

  6. Crystalline Repository Project. Technical progress report, October 1982-March 1983

    International Nuclear Information System (INIS)

    1985-01-01

    This document reports the progress being made periodically on the development of a geologic repository in crystalline rock for the permanent disposal of high-level nuclear waste. The reporting elements are arranged by the work breakdown structure so that related studies are presented together. The studies are reported by the Office of Crystalline Respository Development (OCRD), a prime contractor of the US Department of Energy Repository Project Office. The studies include work by other prime contractors and by subcontractors to OCRD

  7. Technical contribution to the project and operation of pulsed columns

    International Nuclear Information System (INIS)

    Kromek, I.B.; Ikuta, A.

    1976-01-01

    Characteristics and factors that affect the performance of pulse columms used in the purification of metals as thorium, uranium and plutonium are described. The pulse generator and the control instrumentation of these columns are also described. This report is based mainly in the works made by Richardson and Platt and adaptations realized in the project and instalation of the first compound extraction-scrub pulse column in the CEQ/IEA (Sao Paulo, Brazil) [pt

  8. Institutional effectiveness of REDD+ MRV: Countries progress in implementing technical guidelines and good governance requirements

    NARCIS (Netherlands)

    Ochieng, R.M.; Visseren-Hamakers, Ingrid; Arts, B.; Brockhaus, M.; Herold, M.

    2016-01-01

    The UNFCCC requires REDD+ countries wishing to receive results-based payments to measure, report and verify (MRV) REDD+ impacts; and outlines technical guidelines and good governance requirements for MRV. This article examines institutional effectiveness of REDD+ MRV by assessing countries’ progress

  9. Project Based Learning experiences in the space engineering education at Technical University of Madrid

    Science.gov (United States)

    Rodríguez, Jacobo; Laverón-Simavilla, Ana; del Cura, Juan M.; Ezquerro, José M.; Lapuerta, Victoria; Cordero-Gracia, Marta

    2015-10-01

    This work describes the innovation activities performed in the field of space education since the academic year 2009/10 at the Technical University of Madrid (UPM), in collaboration with the Spanish User Support and Operations Center (E-USOC), the center assigned by the European Space Agency (ESA) in Spain to support the operations of scientific experiments on board the International Space Station. These activities have been integrated within the last year of the UPM Aerospace Engineering degree. A laboratory has been created, where students have to validate and integrate the subsystems of a microsatellite using demonstrator satellites. In parallel, the students participate in a Project Based Learning (PBL) training process in which they work in groups to develop the conceptual design of a space mission. One student in each group takes the role of project manager, another one is responsible for the mission design and the rest are each responsible for the design of one of the satellite subsystems. A ground station has also been set up with the help of students developing their final thesis, which will allow future students to perform training sessions and learn how to communicate with satellites, how to receive telemetry and how to process the data. Several surveys have been conducted along two academic years to evaluate the impact of these techniques in engineering learning. The surveys evaluate the acquisition of specific and generic competences, as well as the students' degree of satisfaction with respect to the use of these learning methodologies. The results of the surveys and the perception of the lecturers show that PBL encourages students' motivation and improves their results. They not only acquire better technical training, but also improve their transversal skills. It is also pointed out that this methodology requires more dedication from lecturers than traditional methods.

  10. Preliminary design requirements document (DRD) for Project W-236B, ''Initial Pretreatment Module''

    International Nuclear Information System (INIS)

    Swanson, L.M.

    1995-01-01

    The scope of this Design Requirements Document (DRD) is to identify and define the functions, with associated requirements, which must be performed to separate Hanford Site tank waste supernatants into low-level and high-level fractions. This documents sets forth function requirements, performance requirements, and design constraints necessary to begin conceptual design for the Initial Pretreatment Module (IPM). System and physical interfaces between the IPM project and the Tank Waste Remediation System (TWRS) are identified. The constraints, performance requirements, and transfer of information and data across a technical interface will be documented in an Interface Control Document. Supplemental DRDs will be prepared to provide more detailed requirements specific to systems described in the DRD

  11. Implementation of technical stage of ITER project in Kazakstan

    International Nuclear Information System (INIS)

    Shkol'nik, V.S.; Shemanskij, V.A.; Cherepnin, Yu.S.; Skoz, E.Ya.; Nazarenko, L.I.; Shestakov, V.P.; Tazhibaeva, I.L.

    1996-01-01

    The main executors of ITER project in Kazakstan are: National nuclear Centre; National Joint-stock Co. of the enterprises on atomic engineering and industry (KATEP) and Science and Research Inst. of Experimental and Theoretical Physics of the Kazakh National Univ. Principle directions of Kazakhstan Republic works in 1996/97 under the ITER project is possible to formulate as follows: - irradiation test of materials on the BN-350 reactor; -continuation of in-pile experiments on determination of deuterium interaction parameters with beryllium samples, manufactured by Ulba Metallurgical Plant (KATEP), using Research Water Heterogeneous Reactor; - conducting of in-pile experiments on determination of hydrogen isotope permeation parameters through vanadium alloys using Research Water Heterogeneous Reactor. Conducting of out-pile experiments with beryllium, and vanadium alloys; - investigation of beryllium structure and properties in respect to hydrogen in condition, simulating gas impurities inventory, under thermal and neutron influence; -simulation of plasma disruption on divertor; -simulation of water steam interaction with beryllium; - determination of hydrogen permeation parameters for various materials with 'in situ' surface by electronic spectroscopy; -development of manufacturing technology of beryllium connections with copper alloys

  12. The Hanford Environmental Dose Reconstruction (HEDR) Project: Technical approach

    International Nuclear Information System (INIS)

    Napier, B.A.; Freshley, M.D.; Gilbert, R.O.; Haerer, H.A.; Morgan, L.G.; Rhoads, R.E.; Woodruff, R.K.

    1990-01-01

    Historical measurements and current assessment techniques are being combined to estimate potential radiation doses to people from radioactive releases to the air, the Columbia River, soils, and ground water at the Hanford Site since 1944. Environmental contamination from these releases has been monitored, at varying levels of detail, for 45 yr. Phase I of the Hanford Environmental Reconstruction Project will estimate the magnitude of potential doses, their areal extends, and their associated uncertainties. The Phase I study area comprises 10 counties in eastern Washington and northern Oregon, within a 100-mi radius of the site, including a stretch of the Columbia River that was most significantly affected. These counties contain a range of projected and measured contaminant levels, environmental exposure pathways, and population groups. Phase I dose estimates are being developed for the periods 1944 through 1947 for air pathways and 1964 through 1966 for river pathways. Important radionuclide/pathway combinations include fission products, such as 131 I, in milk for early atmospheric releases and activation products, such as 32 P and 65 Zn, in fish for releases to the river. Potential doses range over several orders of magnitude within the study area. We will expand the time periods and study are in three successive phases, as warranted by results of Phase I

  13. Technical clarity in inter-agency negotiations: Lessons from four hydropower projects

    Science.gov (United States)

    Burkardt, Nina; Lamb, Berton Lee; Taylor, Jonathan G.; Waddle, Terry J.

    1995-01-01

    We investigated the effect of technical clarity on success in multi-party negotiations in the Federal Energy Regulatory Commission (FERC) licensing process. Technical clarity is the shared understanding of dimensions such as the geographic extent of the project, range of flows to be considered, important species and life stages, and variety of water uses considered. The results of four hydropower licensing consultations are reported. Key participants were interviewed to ascertain the level of technical clarity present during the consultations and the degree to which the consultations were successful. Technical clarity appears to be a prerequisite for successful outcomes. Factors that enhance technical clarity include simple project design, new rather than existing projects, precise definition of issues, a sense of urgency to reach agreement, a sense of fairness among participants, and consistency in participation. Negotiators should not neglect the critical pre-negotiation steps of defining technical issues and determining appropriate studies, deciding how to interpret studies, and agreeing on responses to study results.

  14. Technical activities of the Project Surata River for the handling of mercury and cyanide

    International Nuclear Information System (INIS)

    Pinzon, Juan Manuel; Ruiz, Jorge Nelson; Jaimes, Cristian Libardo

    2004-01-01

    The technical works executed by the project have been framed in the philosophy of reducing the contamination for mercury and cyanide in the operations of auriferous benefit, without causing detriment in the economic revenues of the miners, on the contrary, trying to carry out a better use of the auriferous mineral. In this sense, the project has toasted from simple solutions that allow to reduce the use of the pollutants mentioned a little until solutions more complex than they require introduction of gravimetric teams in pro of reducing the quantity of minerals amalgamated y/o cyanidates. This way an action plan was developed that contemplates a diagnosis stage, followed by a stage of executions in which has been worked in the modification of the systems of gravimetric concentration, process of amalgamation and in the cyanidation process. Particular emphasis has noticed to the cyanidation process for percolation, given its importance in the benefit and its degree of environmental affectation. Through a revision of the method used by the miners, it was possible to modify the technique and to reduce in 40% the global consumption of cyanide in the companies of the District Mining Vetas - California. Metallurgic studies in the advised companies allowed to verify that strengthening the gravimetric concentration is possible to gather 80% of the gold (heavy minerals) in 15% of the processed global material. Under these conditions the introduction of the cyanidation is facilitated by agitation, allowing to reduce the contamination for cyanide and to make a bigger use of the auriferous mineral

  15. Technical and scientific report of the Alto project

    CERN Document Server

    Essabaa, S; Grialou, D; Ibrahim, F; Le Scornet, J C

    2002-01-01

    The Alto project means the installation of an electron linear accelerator inside the experimental area of the tandem accelerator of the nuclear physics institute of Orsay (IPNO, France). This linear accelerator comes from CERN where it was operating as a pre-injector for LEP. This equipment will allow IPNO'teams to perform fast kinetics studies in a domain different from that of ELYSE accelerator. The time resolution will not be as high as that of ELYSE (picosecond) but will be sufficient (microsecond) to produce free radicals in aqueous and gaseous media. The main expectations of this installation can be classified according 3 axis: 1) basic research (mainly the study of nuclear matter through photo-fission, 2) research and development of accelerators (by providing a test bench for new high frequency systems and superconducting components), and 3) applied research for industry concerning: biochemistry under irradiation, radiation sensibility, DNA breaking, food and drug sterilization and behaviour of electro...

  16. The ARAMIS project: a concept robot and technical design.

    Science.gov (United States)

    Colizzi, Lucio; Lidonnici, Antonio; Pignolo, Loris

    2009-11-01

    To describe the ARAMIS (Automatic Recovery Arm Motility Integrated System) project, a concept robot applicable in the neuro-rehabilitation of the paretic upper limb after stroke. Methods, results and conclusion: The rationale and engineering of a state-of-the-art, hardware/software integrated robot system, its mechanics, ergonomics, electric/electronics features providing control, safety and suitability of use are described. An ARAMIS prototype has been built and is now available for clinical tests. It allows the therapist to design neuro-rehabilitative (synchronous or asynchronous) training protocols in which sample exercises are generated by a single exoskeleton (operated by the patient's unaffected arm or by the therapist's arm) and mirrored in real-time or offline by the exoskeleton supporting the paretic arm.

  17. International environmental issues and requirements for new power projects

    Energy Technology Data Exchange (ETDEWEB)

    Newman, J.R. [Golder Associates Inc., Gainesville, FL (United States); Maltby, J.H. [Golder Associates Inc., Washington, DC (United States)

    1997-12-31

    The purpose of this presentation was to discuss the emerging role of financial entities in determining environmental requirements for international power projects. The paper outlines the following: emerging conditions; examples of announced privatization energy projects by country; types of government and international financial entity sources; problems for IPPs; similarity and differences between the World Bank and the USEPA; comparison of the international standards and regulations for power plants; recent trends/issues involving international power project approval; and recommendations for understanding/expediting the financial entities` environmental approval process and how to expedite this process.

  18. The impact of technical specification surveillance requirements and allowable outage times on plant availability

    International Nuclear Information System (INIS)

    Webster, S.A.; Finnicum, D.J.

    1985-01-01

    Surveillances required to be conducted by a plant's Technical Specifications have resulted in plant shutdowns and lost availability. This paper looks at shutdowns which have occurred due to required surveillance testing and insufficient repair time allowed by Technical Specifications. A loss of plant availability of almost 3% per plant year was found for U.S. pressurized water reactors during the five year period, 1979 to 1984. This figure excludes major problems which required plant shutdown whether or not mandated by the Technical Specifications. In addition to their affect on availability, such shutdowns can add to the challenges to plant safety systems and can affect plant aging by increasing the thermal cycles on plant components

  19. MORE. Management of Requirements in NPP modernisation projects - Project report 2005

    International Nuclear Information System (INIS)

    Thunem, A.P.J.; Fredriksen, R.; Thunem, H.P.J.; Ventae, O.; Valkonen, J.; Holmberg, J.E.

    2006-04-01

    The overall objective of the project MORE is to improve the means for managing the large amounts of evolving requirements in Nordic NPP modernisation projects. In accordance to this objective, the activity will facilitate the industrial utilisation of the research results from the project TACO. On the basis of experiences in the Nordic countries, the overall aim of the TACO project has been to identify the best practices and most important criteria for ensuring effective communication in relation to requirements elicitation and analysis, understandability of requirements to all parties, and traceability of requirements. The project resulted in the development of a traceability model for handling requirements from their origins and through their final shapes. Particular emphasis for the MORE project in 2005 was put on utilising a prototype of a tool (TRACE) intended to support an adopted approach to dependable requirements engineering, suitable for modelling and handling large amounts of requirements related to all stages of the systems development process and not only those traditionally including requirements at high-level stages. (au)

  20. MORE. Management of Requirements in NPP modernisation projects - Project report 2005

    Energy Technology Data Exchange (ETDEWEB)

    Thunem, A.P.J.; Fredriksen, R.; Thunem, H.P.J. [IFE (Norway); Ventae, O.; Valkonen, J.; Holmberg, J.E. [VTT Technical Research Centre of Finland (Finland)

    2006-04-15

    The overall objective of the project MORE is to improve the means for managing the large amounts of evolving requirements in Nordic NPP modernisation projects. In accordance to this objective, the activity will facilitate the industrial utilisation of the research results from the project TACO. On the basis of experiences in the Nordic countries, the overall aim of the TACO project has been to identify the best practices and most important criteria for ensuring effective communication in relation to requirements elicitation and analysis, understandability of requirements to all parties, and traceability of requirements. The project resulted in the development of a traceability model for handling requirements from their origins and through their final shapes. Particular emphasis for the MORE project in 2005 was put on utilising a prototype of a tool (TRACE) intended to support an adopted approach to dependable requirements engineering, suitable for modelling and handling large amounts of requirements related to all stages of the systems development process and not only those traditionally including requirements at high-level stages. (au)

  1. IFMIF - Layout and arrangement of cells according to requirements of technical logistics, reliability and remote handling

    Energy Technology Data Exchange (ETDEWEB)

    Mittwollen, Martin, E-mail: martin.mittwollen@kit.edu [Karlsruhe Institute of Technology, Institute for Conveying Technology and Logistics, Karlsruhe (Germany); Eilert, Dirk; Kubaschewski, Martin; Madzharov, Vladimir [Karlsruhe Institute of Technology, Institute for Conveying Technology and Logistics, Karlsruhe (Germany); Tian Kuo [Karlsruhe Institute of Technology, Institute for Neutron Physics and Reactor Technology, Karlsruhe (Germany)

    2012-08-15

    Highlights: Black-Right-Pointing-Pointer In a first approach, layout and arrangement of the cells followed a predetermined plant layout. Black-Right-Pointing-Pointer Disadvantages in technical logistics, reliability and remote handling have been detected. Black-Right-Pointing-Pointer Deliberation with project teams opened space for improvements. Black-Right-Pointing-Pointer Layout and arrangement of cells have been improved by simplification of design. Black-Right-Pointing-Pointer Speed and reliability have been increased significantly. - Abstract: The International Fusion Material Irradiation Facility (IFMIF) is designed to study and qualify structural and functional materials which shall be used in future fusion nuclear power plants. During the current engineering validation and engineering design activities (EVEDA) phase the development of e.g. an optimized layout and arrangement of the cells (Access Cell, Test Cell, and Test Module Handling Cells) is of major interest. After defining different functions for the individual cells like e.g. large scale/fine scale disassembling of test modules a first layout has been developed. This design followed requirements like having a minimum of carrier changes to avoid sources of failures. On the other hand it has had to be a compact arrangement of cells due to restrictions from plant layout. A row of changes of transfer direction, and different crane systems were the consequence. Constructive discussion with project team results in the statement, that for reasons of being reliable and fast, layout and arrangement of cells goes first, plant layout then will follow. The chance for big improvements was taken and the result was a simplified design with strong reduced number of functional elements, and increased reliability and speed.

  2. Technical and scientific report of the Alto project

    International Nuclear Information System (INIS)

    Essabaa, S.; Gardes, D.; Grialou, D.; Ibrahim, F.; Le Scornet, J.C.

    2002-01-01

    The Alto project means the installation of an electron linear accelerator inside the experimental area of the tandem accelerator of the nuclear physics institute of Orsay (IPNO, France). This linear accelerator comes from CERN where it was operating as a pre-injector for LEP. This equipment will allow IPNO'teams to perform fast kinetics studies in a domain different from that of ELYSE accelerator. The time resolution will not be as high as that of ELYSE (picosecond) but will be sufficient (microsecond) to produce free radicals in aqueous and gaseous media. The main expectations of this installation can be classified according 3 axis: 1) basic research (mainly the study of nuclear matter through photo-fission, 2) research and development of accelerators (by providing a test bench for new high frequency systems and superconducting components), and 3) applied research for industry concerning: biochemistry under irradiation, radiation sensibility, DNA breaking, food and drug sterilization and behaviour of electronic components under irradiation. This rapport details the research program that could be achieved with this equipment, describes its contributions in terms of economic development, cooperation with industry, student training, and specifies the needed investment and the operating and maintenance costs. (A.C.)

  3. Investigative study on the technical code requirements of natural events hazards for nuclear power plants

    International Nuclear Information System (INIS)

    Ito, Kunio; Aoki, Takayuki

    2012-01-01

    Technical codes and standards on natural phenomena, in particular, earthquake and tsunami for nuclear power plants in the other developed countries including IAEA safety standards were investigated. Then, the results were compared with the corresponding Japanese technical codes and standards. As a results, it was found that: (1) technical codes and standards on natural phenomena, especially those for earthquakes and tsunami/flooding in those foreign countries and their requirements are all included in the Japanese technical codes and standards. (2) Nevertheless, the actual measures against tsunami/flooding in those foreign countries are more advanced than those in Japan which had been taken before Fukushima accident. Therefore, further investigation is needed to clarify the reason why there are such differences by investigating the details of the basic ideas and evaluation methods for the protection of tsunami/flooding. (author)

  4. Guanacaste Geothermal Project. Technical prefeasibility report. Annex E. Geohydrology

    Energy Technology Data Exchange (ETDEWEB)

    1976-12-01

    This report is the fifth of six annexes to the Summary Report on the First Phase of the Guanacaste Geothermal Project. The studies covered an area of 500 km/sup 2/ on the SW flanks of the Rincon de la Vieja and Miravalles volcanoes of the Guanacaste Volcanic Range in NW Costa Rica, and were aimed at locating zones of high geothermal gradient, and reconstruction of the stratigraphic column. An estimate was made of the annual and low-water mark water reserves. Balances were also made for each basin taking into consideration precipitation, evapo-transpiration, and runoff. Determinations were also made of effluent and influent stream, recharge, and deep water circulation zones, and water tables. An underground flow pattern was observed, extending from the volcanic massifs where recharge takes place, to the plains near the Panamerican Highway. Using silica, specific conductivity, and chlorides as natural tracers, it was concluded that the underground and surface drainage patterns generally coincide. In the area around the Miravalles volcano, a zone was found near the township of Guayabal where seepage of deep waters appears to take place, showing high silica and chloride contents (more than 150 and 50 ppM respectively), and high conductivity (more than 500 mhos-cm). Springs with low mineral content, which could be associated with shallow circulation waters, are also present in this zone. This could be indicative of the existence of two horizons, a cold one above and a hot one below, separated by an impermeable layer. Another instance of seepage of deep waters is observed in the zone around the township of Salitral de Bagaces and the Aguas Calientes River. In the northeastern part of the area under study, it was observed that the underground drainage pattern conforms to the surface drainage of the Salitral and Tizate rivers.

  5. Guanacaste Geothermal Project. Technical prefeasibility report. Annex C. Electric resistivity

    Energy Technology Data Exchange (ETDEWEB)

    1976-12-01

    This report is the third of six annexes to the Summary Report on the First Phase of the Guanacaste Geothermal Project. The studies covered an area of 500 km/sup 2/ on the SW flanks of the Rincon de la Vieja and Miravalles volcanoes of the Guanacaste Volcanic Range in NW Costa Rica, and were aimed at locating zones of high geothermal gradient, and reconstruction of the stratigraphic column. The formations in the area under study can be grouped into six resistivity ranges, varying from less than 5 to more than 200 ohm-meters. Values from 200 to as high as 30,000 ohm-meters generally correspond to fractured and porous lavas, their fracturing and porosity, as well as their drainability, increasing with resistivity. The values above 100 ohm-meters were recorded in zones of recent lava flows, in spurs of the volcanoes Rincon de la Vieja and Santa Maria, and in the slopes of the Miravalles volcano, and correspond to shallow formations (maximum depths of 150 meters) which may constitute recharge zones for the underground aquifiers. The values in the 100 to 200 ohm-meter range were generally recorded directly under layers constituted by drained, porous lavas, or under shallow layers where no recent lavas are present. The third group comprises materials with resistivities in the 25 to 100 ohm-meter range, occurring at two different depth levels: a deep one (more than 1000 meters) and a shallow one (less than 400 meters). Resistivities less than 25 ohm-meters were recorded at depths of 250 meters and more, and may correspond to material typical of the Aguacate formation, which probably constitutes the reservoir rock of the geothermal fluids. In order to locate the zones of most geothermal interest, this range was classified into the three remaining of the six groups, viz 10 to 25, 5 to 10, and less than 5 ohm-meters, the last group appearing to be that of greatest geothermal potential.

  6. The decommissioning of WWER type nuclear power plants. Final report on an IAEA regional technical co-operation project

    International Nuclear Information System (INIS)

    2000-01-01

    Numerous WWER-440 nuclear power plants are in operation in central and eastern Europe and a small number have already been shut down. In addition to reactors already shut down, many other reactors will reach the end of their design lifetime in a few years and become candidates for decommissioning. It is unfortunate that little consideration was devoted to decommissioning of WWER-440 reactors at the plant design and construction stage, and little emphasis was placed on planning for decommissioning. It is within this context that the IAEA launched a regional technical co-operation project in 1994 with the aim of providing guidance on planning and management of decommissioning for WWERs. The project, which had a duration of four years (1995-1998), included the organization of workshops and scientific visits to countries having WWERs and other countries where active decommissioning projects were under way. Eventually, participants suggested the consolidation of expert guidance and collective opinions into a TECDOC, which was drafted by both designated participants from project recipient countries and invited experts. The TECDOC has the aim of serving as a stimulus for all concerned parties in central and eastern European countries to initiate concrete decommissioning planning, including assessment of existing and required resources for the eventual implementation of decommissioning plans. In addition, the regional technical co-operation project has managed to bring together in this TECDOC a number of good practices that could be useful in WWER-440 decommissioning

  7. THE SLOAN DIGITAL SKY SURVEY REVERBERATION MAPPING PROJECT: TECHNICAL OVERVIEW

    Energy Technology Data Exchange (ETDEWEB)

    Shen, Yue [Carnegie Observatories, 813 Santa Barbara Street, Pasadena, CA 91101 (United States); Brandt, W. N. [Department of Astronomy and Astrophysics, The Pennsylvania State University, University Park, PA 16802 (United States); Dawson, Kyle S. [Department of Physics and Astronomy, University of Utah, 115 South 1400 East, Salt Lake City, UT 84112 (United States); Hall, Patrick B. [Department of Physics and Astronomy, York University, Toronto, ON M3J 1P3 (Canada); McGreer, Ian D.; Fan, Xiaohui [Steward Observatory, The University of Arizona, 933 North Cherry Avenue, Tucson, AZ 85721-0065 (United States); Anderson, Scott F. [Astronomy Department, University of Washington, Box 351580, Seattle, WA 98195 (United States); Chen, Yuguang [Department of Astronomy, School of Physics, Peking University, Beijing 100871 (China); Denney, Kelly D. [Department of Astronomy, The Ohio State University, 140 West 18th Avenue, Columbus, OH 43210 (United States); Eftekharzadeh, Sarah [Department of Physics and Astronomy, University of Wyoming, 1000 East University Avenue, Laramie, WY 82071 (United States); Gao, Yang [Department of Engineering Physics and Center for Astrophysics, Tsinghua University, Beijing 100084 (China); Green, Paul J. [Harvard-Smithsonian Center for Astrophysics, 60 Garden Street, Cambridge, MA 02138 (United States); Greene, Jenny E. [Department of Astrophysical Sciences, Princeton University, Princeton, NJ 08544 (United States); Ho, Luis C. [Kavli Institute for Astronomy and Astrophysics, Peking University, Beijing 100871 (China); Horne, Keith [SUPA Physics/Astronomy, University of St. Andrews, St. Andrews KY16 9SS (United Kingdom); Jiang, Linhua [School of Earth and Space Exploration, Arizona State University, Tempe, AZ 85287-1504 (United States); Kelly, Brandon C. [Department of Physics, Broida Hall, University of California, Santa Barbara, CA 93107 (United States); and others

    2015-01-01

    The Sloan Digital Sky Survey Reverberation Mapping (SDSS-RM) project is a dedicated multi-object RM experiment that has spectroscopically monitored a sample of 849 broad-line quasars in a single 7 deg{sup 2} field with the SDSS-III Baryon Oscillation Spectroscopic Survey spectrograph. The RM quasar sample is flux-limited to i {sub psf} = 21.7 mag, and covers a redshift range of 0.1 < z < 4.5 without any other cuts on quasar properties. Optical spectroscopy was performed during 2014 January-July dark/gray time, with an average cadence of ∼4 days, totaling more than 30 epochs. Supporting photometric monitoring in the g and i bands was conducted at multiple facilities including the Canada-France-Hawaii Telescope (CFHT) and the Steward Observatory Bok telescope in 2014, with a cadence of ∼2 days and covering all lunar phases. The RM field (R.A., decl. = 14:14:49.00, +53:05:00.0) lies within the CFHT-LS W3 field, and coincides with the Pan-STARRS 1 (PS1) Medium Deep Field MD07, with three prior years of multi-band PS1 light curves. The SDSS-RM six month baseline program aims to detect time lags between the quasar continuum and broad line region (BLR) variability on timescales of up to several months (in the observed frame) for ∼10% of the sample, and to anchor the time baseline for continued monitoring in the future to detect lags on longer timescales and at higher redshift. SDSS-RM is the first major program to systematically explore the potential of RM for broad-line quasars at z > 0.3, and will investigate the prospects of RM with all major broad lines covered in optical spectroscopy. SDSS-RM will provide guidance on future multi-object RM campaigns on larger scales, and is aiming to deliver more than tens of BLR lag detections for a homogeneous sample of quasars. We describe the motivation, design, and implementation of this program, and outline the science impact expected from the resulting data for RM and general quasar science.

  8. THE SLOAN DIGITAL SKY SURVEY REVERBERATION MAPPING PROJECT: TECHNICAL OVERVIEW

    International Nuclear Information System (INIS)

    Shen, Yue; Brandt, W. N.; Dawson, Kyle S.; Hall, Patrick B.; McGreer, Ian D.; Fan, Xiaohui; Anderson, Scott F.; Chen, Yuguang; Denney, Kelly D.; Eftekharzadeh, Sarah; Gao, Yang; Green, Paul J.; Greene, Jenny E.; Ho, Luis C.; Horne, Keith; Jiang, Linhua; Kelly, Brandon C.

    2015-01-01

    The Sloan Digital Sky Survey Reverberation Mapping (SDSS-RM) project is a dedicated multi-object RM experiment that has spectroscopically monitored a sample of 849 broad-line quasars in a single 7 deg 2 field with the SDSS-III Baryon Oscillation Spectroscopic Survey spectrograph. The RM quasar sample is flux-limited to i psf = 21.7 mag, and covers a redshift range of 0.1 < z < 4.5 without any other cuts on quasar properties. Optical spectroscopy was performed during 2014 January-July dark/gray time, with an average cadence of ∼4 days, totaling more than 30 epochs. Supporting photometric monitoring in the g and i bands was conducted at multiple facilities including the Canada-France-Hawaii Telescope (CFHT) and the Steward Observatory Bok telescope in 2014, with a cadence of ∼2 days and covering all lunar phases. The RM field (R.A., decl. = 14:14:49.00, +53:05:00.0) lies within the CFHT-LS W3 field, and coincides with the Pan-STARRS 1 (PS1) Medium Deep Field MD07, with three prior years of multi-band PS1 light curves. The SDSS-RM six month baseline program aims to detect time lags between the quasar continuum and broad line region (BLR) variability on timescales of up to several months (in the observed frame) for ∼10% of the sample, and to anchor the time baseline for continued monitoring in the future to detect lags on longer timescales and at higher redshift. SDSS-RM is the first major program to systematically explore the potential of RM for broad-line quasars at z > 0.3, and will investigate the prospects of RM with all major broad lines covered in optical spectroscopy. SDSS-RM will provide guidance on future multi-object RM campaigns on larger scales, and is aiming to deliver more than tens of BLR lag detections for a homogeneous sample of quasars. We describe the motivation, design, and implementation of this program, and outline the science impact expected from the resulting data for RM and general quasar science

  9. Projection of US LWR spent fuel storage requirements

    International Nuclear Information System (INIS)

    Fletcher, J.F.; Cole, B.M.; Purcell, W.L.; Rau, R.G.

    1982-11-01

    The spent fuel storage requirements projection is based on data supplied for each operating or planned nuclear power power plant by the operting utilities. The data supplied by the utilities encompassed details of plant operating history, past records of fuel discharges, current inventories in reactor spent fuel storage pools, and projections of future discharge patterns. Data on storage capacity of storage pools and on characterization of the discharged fuel are also included. The data supplied by the utilities, plus additional data from other appropriate sources, are maintained on a computerized data base by Pacific Northwest Laboratory. The spent fuel requirements projection was based on utility data updated and verified as of December 31, 1981

  10. 45 CFR 2553.72 - What are project funding requirements?

    Science.gov (United States)

    2010-10-01

    ... local funding sources during the first three years of operations; or (2) An economic downturn, the... sources of local funding support; or (3) The unexpected discontinuation of local support from one or more... 45 Public Welfare 4 2010-10-01 2010-10-01 false What are project funding requirements? 2553.72...

  11. Implementation of quality improvement techniques for management and technical processes in the ACRV project

    Science.gov (United States)

    Raiman, Laura B.

    1992-12-01

    Total Quality Management (TQM) is a cooperative form of doing business that relies on the talents of everyone in an organization to continually improve quality and productivity, using teams and an assortment of statistical and measurement tools. The objective of the activities described in this paper was to implement effective improvement tools and techniques in order to build work processes which support good management and technical decisions and actions which are crucial to the success of the ACRV project. The objectives were met by applications in both the technical and management areas. The management applications involved initiating focused continuous improvement projects with widespread team membership. The technical applications involved applying proven statistical tools and techniques to the technical issues associated with the ACRV Project. Specific activities related to the objective included working with a support contractor team to improve support processes, examining processes involved in international activities, a series of tutorials presented to the New Initiatives Office and support contractors, a briefing to NIO managers, and work with the NIO Q+ Team. On the technical side, work included analyzing data from the large-scale W.A.T.E.R. test, landing mode trade analyses, and targeting probability calculations. The results of these efforts will help to develop a disciplined, ongoing process for producing fundamental decisions and actions that shape and guide the ACRV organization .

  12. Implementation of quality improvement techniques for management and technical processes in the ACRV project

    Science.gov (United States)

    Raiman, Laura B.

    1992-01-01

    Total Quality Management (TQM) is a cooperative form of doing business that relies on the talents of everyone in an organization to continually improve quality and productivity, using teams and an assortment of statistical and measurement tools. The objective of the activities described in this paper was to implement effective improvement tools and techniques in order to build work processes which support good management and technical decisions and actions which are crucial to the success of the ACRV project. The objectives were met by applications in both the technical and management areas. The management applications involved initiating focused continuous improvement projects with widespread team membership. The technical applications involved applying proven statistical tools and techniques to the technical issues associated with the ACRV Project. Specific activities related to the objective included working with a support contractor team to improve support processes, examining processes involved in international activities, a series of tutorials presented to the New Initiatives Office and support contractors, a briefing to NIO managers, and work with the NIO Q+ Team. On the technical side, work included analyzing data from the large-scale W.A.T.E.R. test, landing mode trade analyses, and targeting probability calculations. The results of these efforts will help to develop a disciplined, ongoing process for producing fundamental decisions and actions that shape and guide the ACRV organization .

  13. TANK FARM REMEDIATION TECHNOLOGY DEVELOPMENT PROJECT AN EXERCISE IN TECHNICAL & REGULATORY COLLABORATION

    Energy Technology Data Exchange (ETDEWEB)

    JARAYSI, M.N.

    2007-01-08

    The Tank Farm Remediation Technology Development Project at the Hanford Site focuses on waste storage tanks, pipelines and associated ancillary equipment that are part of the C-200 single-shell tank (SST) farm system located in the C Tank Farm. The purpose of the project is to obtain information on the implementation of a variety of closure activities and to answer questions on technical, operational and regulatory issues associated with closure.

  14. TANK FARM REMEDIATION TECHNOLOGY DEVELOPMENT PROJECT AN EXERCISE IN TECHNICAL and REGULATORY COLLABORATION

    International Nuclear Information System (INIS)

    JARAYSI, M.N.

    2007-01-01

    The Tank Farm Remediation Technology Development Project at the Hanford Site focuses on waste storage tanks, pipelines and associated ancillary equipment that are part of the C-200 single-shell tank (SST) farm system located in the C Tank Farm. The purpose of the project is to obtain information on the implementation of a variety of closure activities and to answer questions on technical, operational and regulatory issues associated with closure

  15. Promoting Gender Parity in Basic Education: Lessons from a Technical Cooperation Project in Yemen

    Science.gov (United States)

    Yuki, Takako; Mizuno, Keiko; Ogawa, Keiichi; Mihoko, Sakai

    2013-01-01

    Many girls are not sent to school in Yemen, despite basic education being free as well as compulsory for all children aged 6-15. Aiming to improve girls' enrollment by increasing parental and community involvement, the Japan International Cooperation Agency (JICA) offered a technical cooperation project in June 2005 called Broadening Regional…

  16. Project T.E.A.M. (Technical Education Advancement Modules). Introduction to Statistical Process Control.

    Science.gov (United States)

    Billings, Paul H.

    This instructional guide, one of a series developed by the Technical Education Advancement Modules (TEAM) project, is a 6-hour introductory module on statistical process control (SPC), designed to develop competencies in the following skill areas: (1) identification of the three classes of SPC use; (2) understanding a process and how it works; (3)…

  17. Project T.E.A.M. (Technical Education Advancement Modules). Advanced Statistical Process Control.

    Science.gov (United States)

    Dunlap, Dale

    This instructional guide, one of a series developed by the Technical Education Advancement Modules (TEAM) project, is a 20-hour advanced statistical process control (SPC) and quality improvement course designed to develop the following competencies: (1) understanding quality systems; (2) knowing the process; (3) solving quality problems; and (4)…

  18. Challenge Study: A Project-Based Learning on a Wireless Communication System at Technical High School

    Science.gov (United States)

    Terasawa, Ikuo

    2016-01-01

    The challenge study is a project based learning curriculum at Technical High School aimed at the construction of a wireless communication system. The first period was engineering issues in the construction of an artificial satellite and the second period was a positional locating system based on the general purpose wire-less device--ZigBee device.…

  19. Technical project of a solar water heating system for Hostal FRATERNIDAD, Santiago de Cuba

    International Nuclear Information System (INIS)

    Arzuaga Machado, Yusnel; Torres Ten, Alonso; Fonseca Fonseca, Susana; Fuetes lombá, Osmanys; Massipe Hernández, J. Raúl; Gonzalez, Wagner Roberto

    2017-01-01

    It is presented the technical project of a solar water heating system for Hostal FRATERNIDAD, Santiago de Cuba, Cuba, 20 Cabannas type tourism and a one of 2 square meter flat solar collector will be used, with a storage tank of 200 liters capacity, that is to say one system per cabin. (author)

  20. 10 CFR 35.647 - Additional technical requirements for mobile remote afterloader units.

    Science.gov (United States)

    2010-01-01

    ... on the remote afterloader unit, on the control console, and in the facility; (3) Viewing and intercom... 10 Energy 1 2010-01-01 2010-01-01 false Additional technical requirements for mobile remote... MATERIAL Photon Emitting Remote Afterloader Units, Teletherapy Units, and Gamma Stereotactic Radiosurgery...

  1. 47 CFR 80.271 - Technical requirements for portable survival craft radiotelephone transceivers.

    Science.gov (United States)

    2010-10-01

    ... craft radiotelephone transceivers. 80.271 Section 80.271 Telecommunication FEDERAL COMMUNICATIONS... Authorization for Compulsory Ships § 80.271 Technical requirements for portable survival craft radiotelephone transceivers. (a) Portable survival craft radiotelephone transceivers must comply with the following: (1) The...

  2. Synergy of Technical Specification, functional specifications and scenarios in requirements specifications

    NARCIS (Netherlands)

    Miedema, J.; van der Voort, Mascha C.; Lutters, Diederick; van Houten, Frederikus J.A.M.; Krause, Frank-Lothar

    2007-01-01

    In the (mechanical) design process, the requirements specification is a formal registration of the conditions that are imposed on a new or altered product design, both preceding as well as during the corresponding product development cycle. For a long time, the use of technical specifications has

  3. Bibliography of technical guidance for the physical protection upgrade rule requirements for fixed sites

    International Nuclear Information System (INIS)

    Evans, L.J. Jr.; Allen, T.

    1980-06-01

    A bibliography of technical references covering physical security systems, components, and procedures was prepared to provide Nuclear Regulatory Commission licensees a listing of available documents that could be used by licensees to select systems, components, and procedures to meet the revised physical protection requirements of 10 CFR Part 73

  4. Needs, requirements and challenges for technical support to nuclear safety authority

    International Nuclear Information System (INIS)

    Madonna, A.; Orsini, G.

    2010-01-01

    To face the very broad range of technical matters on which the regulatory and licensing activity are based, and related research and development activity, the Nuclear Safety Authorities (NSA) may need to rely upon external technical and scientific support. In providing technical support to NSA, the experience shows, from one side, the importance to have technical support organizations (TSO) with recognized competence, independence and appropriate regulatory view, and from the other side, the importance to have within the NSAs well developed management and technical capability to address, coordinate and use the results of the external technical support. Retaining the NSA the full responsibility for the final decision. Under which conditions and modus operandi the external support shall be provided in order to comply with requirements of being independent, competent and timely provided, fulfilling the administrative procedures, is the subject of attention and consideration of TSO function today. The Italian regulatory body is currently going to be institutionally re-established according to new law approved in 2009 /1/ and it needs to be resourced and fully organized with necessary capacities in the nearest future. The perspective of a new nuclear program, recently launched by the government, with significant incoming tasks for regulation and licensing, against the existing limited resources, let foresee a substantial potential need for technical support and advice. ITER-Consult (Ltd), created in 2003 in Italy, has well developed capabilities to provide independent technical evaluation and support to NSAs, to maintain safety culture and updated knowledge, to transfer know how and to establish international cooperation and networking. This mission is guided assuming as values the independence, the professional competence, the transparency, the credibility and the establishment of respectful relationship with the partners. Challenges exist for funding and operational

  5. TA-55 facility control system upgrade project - human-system interface functional requirements

    International Nuclear Information System (INIS)

    Atkins, W.H.; Pope, N.G.; Turner, W.J.; Brown, R.E.

    1995-11-01

    The functional requirements for that part of the Technical Area (TA)-55 Operations Center Upgrade Project that involves the human-system interface (HSI) are described in this document. The upgrade project seeks to replace completely the center's existing computerized data acquisition and display system, which consists of the field multiplexer units, Data General computer systems, and associated peripherals and software. The upgrade project has two parts-the Facility Data Acquisition Interface System (FDAIS) and the HSI. The HSI comprises software and hardware to provide a high-level graphical operator interface to the data acquisition system, as well as data archiving, alarm annunciation, and logging. The new system will be built with modern, commercially available components; it will improve reliability and maintainability, and it can be expanded for future needs

  6. Tolerancing requirements for remote handling at the Hanford vitrification project

    International Nuclear Information System (INIS)

    Keenan, R.M.; Bullis, R.E.; Van Katwijk, C.

    1993-01-01

    The Hanford Waste Vitrification Plant is being designed by Fluor Daniel, Inc. with WasteChem Corporation as Fluor Daniel's major subcontractor specializing in vitrification and remote system technologies. United Engineers and Constructors/Catalytic (UE ampersand C) will construct the plant. Westinghouse Hanford Company (WHC) is the Project Integration manager, manager and as the plant operator provides technical direction to the Architect/Engineer team (A/E) and constructor on behalf of the Department of Energy - Richland Field Office. The A/E has developed, in cooperation with UE ampersand C, WHC and DOE, a new and innovative approach to installations of the many remote nozzles and electrical connectors that must be installed to demanding tolerances. This paper summarizes the key elements of the HWVP approach

  7. Technical evaluation of RETS-required reports for Turkey Point Units No. 3 and 4

    International Nuclear Information System (INIS)

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

    1985-01-01

    A review of the reports required by Federal regulations and the plant specific Radiological Effluent Technical Specifications (RETS) for operations conducted during 1983 was performed. The periodic reports reviewed were the Annual Radiological Environmental Operating Report for 1983 and Semiannual Radioactive Effluent Release Reports for 1983. The principal review guidelines were the plant's specific RETS, NUREG-0133, ''Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants'', and NRC Guidance on the Review of the Process Control Programs. The Licensee's submitted reports were found to be reasonably complete and consistent with the review guidelines

  8. Technical evaluation of RETS-required reports for the La Crosse boiling water reactor

    International Nuclear Information System (INIS)

    Magleby, E.H.; Young, T.E.

    1985-01-01

    A review of the reports required by federal regulations and the plant-specific Radiological Effluent Technical Specifications (RETS) for operations conducted during 1983 was performed. The periodic reports reviewed were the Annual Radiological Environmental Operating Report for 1983 and the Semiannual Radioactive Effluent Release Reports for 1983. The principal review guidelines were the plant-specific RETS, NUREG-0133, ''Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants'', and NRC Guidance on the Review of the Process Control Programs. The Licensee's submitted reports were found to be reasonably complete and consistent with the review guidelines. 5 refs

  9. Technical evaluation of RETS-required reports for Duane Arnold Energy Center Unit No. 1

    International Nuclear Information System (INIS)

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

    1985-01-01

    A review of the reports required by federal regulations and the plant-specific Radiological Effluent Technical Specifications (RETS) for operations conducted during 1983 was performed. The periodic reports reviewed were the Annual Radiological Environmental Operating Report for 1983 and the Semiannual Radioactive Effluent Release Reports for 1983. The principal review guidelines were the plant's specific RETS, NUREG-0133, ''Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants'', and NRC Guidance on the Review of the Process Control Programs. The Licensee's submitted reports were found to be reasonably complete and consistent with the review guidelines. 8 refs

  10. Technical evaluation of RETS-required reports for Kewaunee Nuclear Power Plant for 1983

    International Nuclear Information System (INIS)

    Magleby, E.H.; Young, T.E.

    1985-01-01

    A review of the reports required by Federal regulations and the plant-specific Radiological Effluent Technical Specifications (RETS) for operations conducted at the Kewaunee Nuclear Power Plant during 1983 was performed. The periodic reports reviewed were the two Semiannual Effluent Release Reports for 1983 and the annual Kewaunee Environmental Radioactivity Survey. The principal review guidelines were the plant's specific RETS and NRC guidance given in NUREG-0133, ''Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants.'' The Licensee's submitted reports were found to be reasonably complete and consistent with the review guidelines

  11. Technical requirements on knowledge base and instrumentation system for decision making in plant operation and maintenance

    International Nuclear Information System (INIS)

    Kitamura, Masaharu; Yoshikawa, Shinji; Hasegawa, Makoto

    1998-03-01

    A series of technical surveys and studies are described in this report to examine and identify technical requirements to be posed on knowledge base and instrumentation system as the fundamental in high reliability computational decision making in operation and maintenance of nuclear power plants. Monitoring and diagnosis are focused as the important tasks among the operation/maintenance-related tasks. A concrete monitoring and diagnosis system configuration has been proposed consisting of distributed symptom database and of on-demand measurement subsystem. An prototype of the proposed system configuration has been successfully verified. (author)

  12. Final Technical Report of the project "Controlling Quantum Information by Quantum Correlations"

    Energy Technology Data Exchange (ETDEWEB)

    Girolami, Davide [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2018-01-17

    The report describes hypotheses, aims, methods and results of the project 20170675PRD2, “Controlling Quantum Information by Quantum Correlations”, which has been run from July 31, 2017 to January 7, 2018. The technical work has been performed by Director’s Fellow Davide Girolami of the T-4 Division, Physics of Condensed Matter and Complex Systems, under the supervision of Wojciech Zurek (T-4), Lukasz Cincio (T-4), and Marcus Daniels (CCS-7). The project ended as Davide Girolami has been converted to J. R. Oppenheimer Fellow to work on the project 20180702PRD1, “Optimal Control of Quantum Machines”, started on January 8, 2018.

  13. Comprehensive assessment of the status scientific and technical projects using Technology Project Readiness Level

    Directory of Open Access Journals (Sweden)

    A. N. Petrov

    2016-01-01

    Full Text Available The balanced methodology for assessing the Technology Project Readiness Level for commercialization (TPRL is proposed. TPRL allows to determine the dynamics and balance of development projects that use the standardized approaches used in assessing the readiness of the technology. Validation of the methodology undertaken for the projects of Federal target programs “Research and development on priority directions of development of scientific-technological complex of Russia for 2007–2013” and “Research and development on priority directions of development of scientific-technological complex of Russia for 2014–2020”. The obtained results showed the possibility of application of the methodology for the evaluation of projects, improving efficiency of expert activity in the evaluation of projects, monitoring the status of individual project and group of projects (portfolio. The application of the methodology allowed us to improve the management of individual project and portfolio of projects.Methodology TPRL will allow the implementers, industry partners, investors, and innovative industrial companies to improve the efficiency of its activities.

  14. Projects at the component development and integration facility. Quarterly technical progress report, April 1, 1994--June 30, 1994

    International Nuclear Information System (INIS)

    1994-01-01

    This quarterly technical progress report presents progress on the projects at the Component Development and Integration Facility (CDIF) during the third quarter of FY94. The CDIF is a major Department of Energy test facility in Butte, Montana, operated by MSE, Inc. Projects in progress include: Biomass Remediation Project; Heavy Metal-Contaminated Soil Project; MHD Shutdown; Mine Waste Technology Pilot Program; Plasma Projects; Resource Recovery Project; and Spray Casting Project

  15. Life sciences payloads analyses and technical program planning studies. [project planning of space missions of space shuttles in aerospace medicine and space biology

    Science.gov (United States)

    1976-01-01

    Contractural requirements, project planning, equipment specifications, and technical data for space shuttle biological experiment payloads are presented. Topics discussed are: (1) urine collection and processing on the space shuttle, (2) space processing of biochemical and biomedical materials, (3) mission simulations, and (4) biomedical equipment.

  16. Survey on the Technology Readiness Level of R and D projects for a Technical Risk Management

    International Nuclear Information System (INIS)

    Song, S. J.; Chang, J.; Lee, K. Y.

    2008-01-01

    The purpose of applying the Technology Readiness Level/Design Readiness Level (TRL/DRL) in technical risk management is to make technology assessments, and improve communication among researchers with a consistent, systematic technology readiness Technical risk management for the Nuclear Hydrogen Production project was adopted of experience assessed with Delphi Method from the Next Generation Nuclear Plant(NGNP)of the DOE to improve the poor contactor management of the major projects which experienced cost increases and/or schedule delays in long-term. In the current phase that is doing key technology research and development projects, the technology readiness level was reviewed and applied to the Nuclear Hydrogen Production project to prepare an input for the next design phases. Based on the previous works, pre-conceptional design and key R and D works for the Nuclear Hydrogen Design and Development(NHDD) projects and the results of key research and development projects, the TRL was applied to assess the levels and compared with the advanced design stages of Westinghouse Electric Co. With this process, several issues were identified to apply the design and technology level to the familiar steps of design process and research and development projects. In order to resolve these issues, it is needed to systematically adjust and modify the current process with TRLs

  17. Goals and activities of the JICA technical cooperation project on reduction of seismic risk in Romania

    International Nuclear Information System (INIS)

    Vacareanu, R.; Kato, H.

    2007-01-01

    Japan International Cooperation Agency (JICA) Technical Cooperation Project on Reduction of Seismic Risk for Buildings and Structures started in Romania on October 1, 2002. The aim of the Project is to strengthen the capacity of earthquake disaster related activities in Romania. The Project approval is the result of four years of intensive efforts made by professionals from Technical University of Civil Engineering Bucharest (UTCB), Ministry of Transport, Constructions and Tourism (MTCT), Romania, National Building Research Institute (INCERC) Bucharest, JICA, Building Research Institute (BRI), Tsukuba, and National Institute for Land, Infrastructure and Management (NILIM), Tsukuba, Japan. The duration of the Project is five years. The implementing agency is the National Center for Seismic Risk Reduction (NCSRR) as a public institution of national interest under MTCT. The activities are carried out by NCSRR in partnership with UTCB and INCERC. During the Project period, 29 young Romanian engineers were trained in Japan, 7 Japanese experts and 37 Japanese experts worked for long-term and short-term, respectively in Romania. Equipment for seismic instrumentation, dynamic characterization of soil and structural testing rising up approximately to 260 million yens (i.e. 2.17 million USD) were donated by JICA to Romania, through NCSRR. The total cost of the Project is roughly 7 million USD. The paper describes the main activities and results of the Project until the JICA Final Evaluation Mission (March 2007). (authors)

  18. Database requirements for the Advanced Test Accelerator project

    International Nuclear Information System (INIS)

    Chambers, F.W.

    1984-01-01

    The database requirements for the Advanced Test Accelerator (ATA) project are outlined. ATA is a state-of-the-art electron accelerator capable of producing energetic (50 million electron volt), high current (10,000 ampere), short pulse (70 billionths of a second) beams of electrons for a wide variety of applications. Databasing is required for two applications. First, the description of the configuration of facility itself requires an extended database. Second, experimental data gathered from the facility must be organized and managed to insure its full utilization. The two applications are intimately related since the acquisition and analysis of experimental data requires knowledge of the system configuration. This report reviews the needs of the ATA program and current implementation, intentions, and desires. These database applications have several unique aspects which are of interest and will be highlighted. The features desired in an ultimate database system are outlined. 3 references, 5 figures

  19. Project W-441 cold vacuum drying facility design requirements document

    International Nuclear Information System (INIS)

    O'Neill, C.T.

    1997-01-01

    This document has been prepared and is being released for Project W-441 to record the design basis for the design of the Cold Vacuum Drying Facility. This document sets forth the physical design criteria, Codes and Standards, and functional requirements that were used in the design of the Cold Vacuum Drying Facility. This document contains section 3, 4, 6, and 9 of the Cold Vacuum Drying Facility Design Requirements Document. The remaining sections will be issued at a later date. The purpose of the Facility is to dry, weld, and inspect the Multi-Canister Overpacks before transport to dry storage

  20. National Land Imaging Requirements (NLIR) Pilot Project summary report: summary of moderate resolution imaging user requirements

    Science.gov (United States)

    Vadnais, Carolyn; Stensaas, Gregory

    2014-01-01

    Under the National Land Imaging Requirements (NLIR) Project, the U.S. Geological Survey (USGS) is developing a functional capability to obtain, characterize, manage, maintain and prioritize all Earth observing (EO) land remote sensing user requirements. The goal is a better understanding of community needs that can be supported with land remote sensing resources, and a means to match needs with appropriate solutions in an effective and efficient way. The NLIR Project is composed of two components. The first component is focused on the development of the Earth Observation Requirements Evaluation System (EORES) to capture, store and analyze user requirements, whereas, the second component is the mechanism and processes to elicit and document the user requirements that will populate the EORES. To develop the second component, the requirements elicitation methodology was exercised and refined through a pilot project conducted from June to September 2013. The pilot project focused specifically on applications and user requirements for moderate resolution imagery (5–120 meter resolution) as the test case for requirements development. The purpose of this summary report is to provide a high-level overview of the requirements elicitation process that was exercised through the pilot project and an early analysis of the moderate resolution imaging user requirements acquired to date to support ongoing USGS sustainable land imaging study needs. The pilot project engaged a limited set of Federal Government users from the operational and research communities and therefore the information captured represents only a subset of all land imaging user requirements. However, based on a comparison of results, trends, and analysis, the pilot captured a strong baseline of typical applications areas and user needs for moderate resolution imagery. Because these results are preliminary and represent only a sample of users and application areas, the information from this report should only

  1. An Evaluation of the Science Education Component of the Cross River State Science and Technical Education Project

    Science.gov (United States)

    Ekuri, Emmanuel Etta

    2012-01-01

    The Cross River State Science and Technical Education Project was introduced in 1992 by edict number 9 of 20 December 1991, "Cross River State Science and Technical Education Board Edit, 20 December, 1991", with the aim of improving the quality of science teaching and learning in the state. As the success of the project depends…

  2. Preliminary Design Requirements Document for Project W-314

    Energy Technology Data Exchange (ETDEWEB)

    MCGREW, D.L.

    2000-04-27

    This document sets forth functional requirements, performance requirements, and design constraints for the tank farm systems elements identified in Section 3.1 of this document. These requirements shall be used to develop the Design Requirements Baseline for those system elements. System Overview--The tank farm system at Hanford Site currently consists of 149 single shell tanks and 28 double shell tanks with associated facilities and equipment, located in 18 separate groupings. Each grouping is known as a tank farm. They are located in the areas designated as 200 West and 200 East. Table 1-1 shows the number of tanks in each farm. The farms are connected together through a transfer system consisting of piping, diversion boxes, Double Contained Receiver Tanks (DCRT) and other miscellaneous facilities and elements. The tank farm system also connects to a series of processing plants which generate radioactive and hazardous wastes. The primary functions of the tank farm system are to store, transfer, concentrate, and characterize radioactive and hazardous waste generated at Hanford, until the waste can be safely retrieved, processed and dispositioned. The systems provided by Project W-314 support the store and transfer waste functions. The system elements to be upgraded by Project W-314 are identified in Section 3.1.

  3. Preliminary Design Requirements Document for Project W-314

    International Nuclear Information System (INIS)

    MCGREW, D.L.

    2000-01-01

    This document sets forth functional requirements, performance requirements, and design constraints for the tank farm systems elements identified in Section 3.1 of this document. These requirements shall be used to develop the Design Requirements Baseline for those system elements. System Overview--The tank farm system at Hanford Site currently consists of 149 single shell tanks and 28 double shell tanks with associated facilities and equipment, located in 18 separate groupings. Each grouping is known as a tank farm. They are located in the areas designated as 200 West and 200 East. Table 1-1 shows the number of tanks in each farm. The farms are connected together through a transfer system consisting of piping, diversion boxes, Double Contained Receiver Tanks (DCRT) and other miscellaneous facilities and elements. The tank farm system also connects to a series of processing plants which generate radioactive and hazardous wastes. The primary functions of the tank farm system are to store, transfer, concentrate, and characterize radioactive and hazardous waste generated at Hanford, until the waste can be safely retrieved, processed and dispositioned. The systems provided by Project W-314 support the store and transfer waste functions. The system elements to be upgraded by Project W-314 are identified in Section 3.1

  4. An Approach to Tailoring Major Technical Reviews Based on Project Characteristics and Stakeholder Interests

    Science.gov (United States)

    Richstein, Alan B.; Nolte, Jerome T.; Pfarr, Barbara B.

    2004-01-01

    There are numerous technical reviews that occur throughout the systems engineering process life cycle. Many are well known by project managers and stakeholders such as developers and end users, an example of much is the critical design review (CDR). This major milestone for a large, complex new project may last two or more days, include an extensive agenda of topics, and entail hundreds of hours of developer time to prepare presentation materials and associated documents. Additionally, the weeks of schedule spent on review preparation is at least partly at the expense of other work. This paper suggests an approach for tailoring technical reviews, based on the project characteristics and the project manager s identification of the key stakeholders and understanding of their most important issues and considerations. With this insight the project manager can communicate to, manage expectations oc and establish formal agreement with the stakeholders as to which reviews, and at what depth, are most appropriate to achieve project success. The authors, coming from diverse organizations and backgrounds, have drawn on their personal experiences and summarized the best practices of their own organizations to create a common framework to provide guidance on the adaptation of design reviews to other system engineers.

  5. Development of Regulatory Technical Requirements for the Advanced Integral Type Research Reactor

    International Nuclear Information System (INIS)

    Jo, Jong Chull; Yune, Young Gill; Kim, Woong Sik; Kim, Hho Jung

    2004-01-01

    This paper presents the current status of the study on the development of regulatory technical requirements for the licensing review of an advanced integral type research reactor of which the license application is expected in a few years. According to the Atomic Energy Act of Korea, both research and education reactors are subject to the technical requirements for power reactors in the licensing review. But, some of the requirements may not be applicable or insufficient for the licensing reviews of reactors with unique design features. Thus it is necessary to identify which review topics or areas can not be addressed by the existing requirements and to develop the required ones newly or supplement appropriately. Through the study performed so far, it has been identified that the following requirements need to be developed newly for the licensing review of SMART-P: the use of proven technology, the interfacial facility, the non-safety systems, and the metallic fuels. The approach and basis for the development of each of the requirements are discussed. (authors)

  6. An Engineering Method of Civil Jet Requirements Validation Based on Requirements Project Principle

    Science.gov (United States)

    Wang, Yue; Gao, Dan; Mao, Xuming

    2018-03-01

    A method of requirements validation is developed and defined to meet the needs of civil jet requirements validation in product development. Based on requirements project principle, this method will not affect the conventional design elements, and can effectively connect the requirements with design. It realizes the modern civil jet development concept, which is “requirement is the origin, design is the basis”. So far, the method has been successfully applied in civil jet aircraft development in China. Taking takeoff field length as an example, the validation process and the validation method of the requirements are detailed introduced in the study, with the hope of providing the experiences to other civil jet product design.

  7. A technical basis for meeting waste form stability requirements of 10 CFR 61

    International Nuclear Information System (INIS)

    Chang, W.Y.; Skoski, L.; Eng, R.; Tuite, P.T.

    1988-01-01

    To assure that solidified low level waste forms meet the stability requirements of 10 CFR 61 regulations, the US Nuclear Regulatory Commission (NRC) has published Branch Technical Positions (BTPs) and draft Regulatory Guide on waste form stability. These guidance documents describe the test procedures and acceptance criteria for six stability parameters: leachability, compressive strength, immersion effect, radiation effect, thermal stability and biodegradability. The most recent set of recommended tests and acceptance criteria are presented in the November 1986 Preliminary Draft Regulatory Guide Low Level Waste Form Stability. The objective of this study was to: (1) investigate the regulatory and technical bases for the required stability tests, (2) evaluate the relevance of these tests and acceptance criteria based on actual test results, and (3) recommended alternatives to the testing and acceptance criteria. The latter two objectives are discussed in this paper

  8. Yucca Mountain Project technical status report (TSR), October 1989--March 1990

    International Nuclear Information System (INIS)

    1990-01-01

    This Yucca Mountain Project Technical Status Report (TSR) on site characterization is the second in a series of reports that will be issued at approximately six-month intervals during site characterization. In addition, progress made toward the initiation and conduct of new site characterization activities is included. For this report, information on the technical progress made by Yucca Mountain Project participating organizations has been compiled covering the period from October 1989, through March 31, 1990. The status report consists of three sections: an introductory section; a section on the status of site characterization, which includes preparatory activities, sites programs, repository design, seals system design, waste package design, and performance assessment; and a reference section, which provides a complete listing of all published documents cited in the text. 59 refs

  9. Technical project of complex fast cycle heat treatment of hydrogenous coal preparation

    OpenAIRE

    Moiseev, V. A.; Andrienko, V. G.; Pileckij, V. G.; Urvancev, A. I.; Gvozdyakov, Dmitry Vasilievich; Gubin, Vladimir Evgenievich; Matveev, Aleksandr Sergeevich; Savostiyanova, Ludmila Viktorovna

    2015-01-01

    Problems of heat-treated milled hydrogenous coal preparation site creation in leading fast cycle heat treatment complex were considered. Conditions for effective use of electrostatic methods of heat-treated milled hydrogenous coal preparation were set. Technical project of heat treatment of milled hydrogenous coal preparation site was developed including coupling of working equipment complex on fast heat treatment and experimental samples of equipment being designed for manufacturing. It was ...

  10. Manhattan Project Technical Series The Chemistry of Uranium (I) Chapters 1-10

    International Nuclear Information System (INIS)

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

    1946-01-01

    This constitutes Chapters 1 through 10. inclusive, of The Survey Volume on Uranium Chemistry prepared for the Manhattan Project Technical Series. Chapters are titled: Nuclear Properties of Uranium; Properties of the Uranium Atom; Uranium in Nature; Extraction of Uranium from Ores and Preparation of Uranium Metal; Physical Properties of Uranium Metal; Chemical Properties of Uranium Metal; Intermetallic Compounds and Alloy systems of Uranium; the Uranium-Hydrogen System; Uranium Borides, Carbides, and Silicides; Uranium Nitrides, Phosphides, Arsenides, and Antimonides.

  11. Regional technical cooperation model project, IAEA - RER/2/2004 ''quality control and quality assurance for nuclear analytical techniques'

    International Nuclear Information System (INIS)

    Arikan, P.

    2002-01-01

    An analytical laboratory should produce high quality analytical data through the use of analytical measurements that is accurate, reliable and adequate for the intended purpose. This objective can be accomplished in a cost-effective manner under a planned and documented quality system of activities. It is well-known that serious deficiencies can occur in laboratory operations when insufficient attention is given to the quality of the work. It requires not only a thorough knowledge of the laboratory's purpose and operation, but also the dedication of the management and operating staff to standards of excellence. Laboratories employing nuclear and nuclear-related analytical techniques are sometimes confronted with performance problems which prevent them from becoming accepted and respected by clients, such as industry, government and regulatory bodies, and from being eligible for contracts. The International Standard ISO 17025 has been produced as the result of extensive experience in the implementation of ISO/IEC Guide 25:1990 and EN 45001:1989, which replaces both of them now. It contains all of the requirements that testing and calibration laboratories must meet if they wish to demonstrate that they operate a quality system that is technically competent, and are able to generate technically valid results. The use of ISO 17025 should facilitate cooperation between laboratories and other bodies to assist in the exchange of information and experience, and in the harmonization of standards and procedures. IAEA model project RER/2/004 entitled 'Quality Assurance/Quality Control in Nuclear Analytical Techniques' was initiated in 1999 as a Regional TC project in East European countries to assist Member State laboratories in the region to install a complete quality system according to the ISO/IEC 17025 standard. 12 laboratories from 11 countries plus the Agency's Laboratories in Seibersdorf have been selected as participants to undergo exercises and training with the

  12. Summary report of a technical meeting on covariances of nuclear reaction data: GANDR project

    International Nuclear Information System (INIS)

    Trkov, A.

    2005-04-01

    Highlights of the technical meeting are given with respect to the detailed study of the feasibility of creating a tool for the Global Assessment of Nuclear Data Requirements (GANDR) based on sensitivity and uncertainty analysis. GANDR was concluded to be fully practical on a modern computer of the desktop class. Participants debated their requirements and formulated recommendations and proposals for implementation. Specific tasks were assigned to participants with an estimated time for their execution. (author)

  13. 47 CFR 76.1608 - System technical integration requiring uniform election of must-carry or retransmission consent...

    Science.gov (United States)

    2010-10-01

    ... 47 Telecommunication 4 2010-10-01 2010-10-01 false System technical integration requiring uniform... COMMUNICATIONS COMMISSION (CONTINUED) BROADCAST RADIO SERVICES MULTICHANNEL VIDEO AND CABLE TELEVISION SERVICE Notices § 76.1608 System technical integration requiring uniform election of must-carry or retransmission...

  14. A model technical cooperation project on the marine radioactivity assessment in the Black Sea Region

    International Nuclear Information System (INIS)

    Goektepe, B. G.; Koeksal, G.; Osvath, I.; Koese, A.; Kuecuekcezzar, R.; Varinlioglu, A.; Guengoer, E.

    2002-01-01

    Marine Environmental Assessment of the Black Sea Region is a wide scope Regional Technical Co-operation Project coded as RER/2/003 implemented by the International Atomic Energy Agency (IAEA) in the period 1995-2001.This multidisciplinay project was designed in response to the needs of participating Member States - the six Black Sea coastal countries (Bulgaria, Romania, Ukraine, Russian Federation, Georgia and Turkey)- to establish capabilities for reliably assessing radionuclides in the Black Sea environment and applying tracer techniques to marine pollution studies. The IAEA assisted laboratories in the region by providing expert services, training, equipment and materials (Goektepe et al., 1998; Osvath et al., 1997-2000)

  15. Next Generation Nuclear Plant (NGNP) Prismatic HTGR Conceptual Design Project - Final Technical Report

    Energy Technology Data Exchange (ETDEWEB)

    Saurwein, John

    2011-07-15

    This report is the Final Technical Report for the Next Generation Nuclear Plant (NGNP) Prismatic HTGR Conceptual Design Project conducted by a team led by General Atomics under DOE Award DE-NE0000245. The primary overall objective of the project was to develop and document a conceptual design for the Steam Cycle Modular Helium Reactor (SC-MHR), which is the reactor concept proposed by General Atomics for the NGNP Demonstration Plant. The report summarizes the project activities over the entire funding period, compares the accomplishments with the goals and objectives of the project, and discusses the benefits of the work. The report provides complete listings of the products developed under the award and the key documents delivered to the DOE.

  16. Next Generation Nuclear Plant (NGNP) Prismatic HTGR Conceptual Design Project - Final Technical Report

    International Nuclear Information System (INIS)

    Saurwein, J.

    2011-01-01

    This report is the Final Technical Report for the Next Generation Nuclear Plant (NGNP) Prismatic HTGR Conceptual Design Project conducted by a team led by General Atomics under DOE Award DE-NE0000245. The primary overall objective of the project was to develop and document a conceptual design for the Steam Cycle Modular Helium Reactor (SC-MHR), which is the reactor concept proposed by General Atomics for the NGNP Demonstration Plant. The report summarizes the project activities over the entire funding period, compares the accomplishments with the goals and objectives of the project, and discusses the benefits of the work. The report provides complete listings of the products developed under the award and the key documents delivered to the DOE.

  17. Management and technical requirements for laboratories in charge of water monitoring

    International Nuclear Information System (INIS)

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

    2008-01-01

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

  18. Technical assessment of compliance with workplace air sampling requirements at WRAP

    International Nuclear Information System (INIS)

    HACKWORTH, M.F.

    1999-01-01

    The purpose of this Technical Assessment is to satisfy HSRCM-1, ''Hanford Site Radiological Control Manual'' Article 551.4 for a documented study of facility Workplace Air Monitoring (WAM) programs. HSRCM-1 is the primary guidance for radiological control at Waste Management Federal Services of Hanford, Inc. (WMH). The HSRCM-1 complies with Title 10. Part 835 of the Code of Federal Regulations (10CFR835). This document provides an evaluation of the compliance of the Waste Receiving and Processing facility (WRAP) WAM program to the criteria standards, requirements, and documents compliance with the requirements where appropriate. Where necessary, it also indicates changes needed to bring specific locations into compliance

  19. Framework conditions and requirements to ensure the technical functional safety of reprocessed medical devices.

    Science.gov (United States)

    Kraft, Marc

    2008-09-03

    Testing and restoring technical-functional safety is an essential part of medical device reprocessing. Technical functional tests have to be carried out on the medical device in the course of the validation of reprocessing procedures. These ensure (in addition to the hygiene tests) that the reprocessing procedure is suitable for the medical device. Functional tests are, however, also a part of reprocessing procedures. As a stage in the reprocessing, they ensure for the individual medical device that no damage or other changes limit the performance. When determining which technical-functional tests are to be carried out, the current technological standard has to be taken into account in the form of product-specific and process-oriented norms. Product-specific norms primarily define safety-relevant requirements. The risk management method described in DIN EN ISO 14971 is the basis for recognising hazards; the likelihood of such hazards arising can be minimised through additional technical-functional tests, which may not yet have been standardised. Risk management is part of a quality management system, which must be bindingly certified for manufacturers and processors of critical medical devices with particularly high processing demands by a body accredited by the competent authority.

  20. The research project on technical information basis for aging management in Fukui and Kinki area. Final report

    International Nuclear Information System (INIS)

    Fujimura, Kimiya; Nagayama, Shigeru; Watarumi, Chikae; Toudou, Tsugihiko

    2011-01-01

    The Research Project on Technical Information Basis for Aging Management was initiated in FY2006 by the Nuclear and Industrial Safety Agency (NISA) of the Ministry of Economy, Trade and Industry (METI) as a five-year program effectively, to promote aging management of domestic nuclear power plants. Its main objective was to improve the technical basis on which aging nuclear power plants are regulated. Upon taking part in the technical strategy map for Aging Management and Safe Long Term Operation, the experiences and achievements of the participating organizations were taken into account and the following four topics were chosen. The regional characteristics of the Fukui and Kinki area where 15 nuclear power plants, mainly PWRs, and many nuclear related research institutes and universities are located, were also considered. 1) The improvement of pipe thinning management in nuclear power plants, 2) The development of inspection techniques to monitor the initiation and propagation of defects, 3) The development of a guideline for evaluating weld repair methods, 4) The development of a guideline for evaluating the degradation of main structures. To promote this research project, INSS has established a regional consortium (called the 'Fukui Regional Cluster' in coordination with universities, research institutes, electric utilities and venders in the Fukui and Kinki area. INSS is acting as a coordinator to make contracts, facilitate execution, and compile annual reports. In FY2010, 11 continuing research subjects were proposed for this project and all were accepted. Of these, 5 subjects were related to the first topic (pipe thinning), 4 subjects to the second topic (inspection technique) and 1 subject to each of the other two topics (weld repair and main structures). All the subjects have been completed, fulfilling the requirements and expectations. (author)

  1. Technical approach to finalizing sensible soil cleanup levels at the Fernald Environmental Management Project

    International Nuclear Information System (INIS)

    Carr, D.; Hertel, B.; Jewett, M.; Janke, R.; Conner, B.

    1996-01-01

    The remedial strategy for addressing contaminated environmental media was recently finalized for the US Department of Energy's (DOE) Fernald Environmental Management Project (FEMP) following almost 10 years of detailed technical analysis. The FEMP represents one of the first major nuclear facilities to successfully complete the Remedial Investigation/Feasibility Study (RI/FS) phase of the environmental restoration process. A critical element of this success was the establishment of sensible cleanup levels for contaminated soil and groundwater both on and off the FEMP property. These cleanup levels were derived based upon a strict application of Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) regulations and guidance, coupled with positive input from the regulatory agencies and the local community regarding projected future land uses for the site. The approach for establishing the cleanup levels was based upon a Feasibility Study (FS) strategy that examined a bounding range of viable future land uses for the site. Within each land use, the cost and technical implications of a range of health-protective cleanup levels for the environmental media were analyzed. Technical considerations in driving these cleanup levels included: direct exposure routes to viable human receptors; cross- media impacts to air, surface water, and groundwater; technical practicality of attaining the levels; volume of affected media; impact to sensitive environmental receptors or ecosystems; and cost. This paper will discuss the technical approach used to support the finalization of the cleanup levels for the site. The final cleanup levels provide the last remaining significant piece to the puzzle of establishing a final site-wide remedial strategy for the FEMP, and positions the facility for the expedient completion of site-wide remedial activities

  2. Handbook of methods for risk-based analysis of technical specification requirements

    International Nuclear Information System (INIS)

    Samanta, P.K.; Vesely, W.E.

    1994-01-01

    Technical Specifications (TS) requirements for nuclear power plants define the Limiting Conditions for Operation (LCOs) and Surveillance Requirements (SRs) to assure safety during operation. In general, these requirements were based on deterministic analysis and engineering judgments. Experiences with plant operation indicate that some elements of the requirements are unnecessarily restrictive, while others may not be conducive to safety. Improvements in these requirements are facilitated by the availability of plant specific Probabilistic Safety Assessments (PSAs). The use of risk and reliability-based methods to improve TS requirements has gained wide interest because these methods can: Quantitatively evaluate the risk and justify changes based on objective risk arguments; Provide a defensible basis for these requirements for regulatory applications. The US NRC Office of Research is sponsoring research to develop systematic risk-based methods to improve various aspects of TS requirements. The handbook of methods, which is being prepared, summarizes such risk-based methods. The scope of the handbook includes reliability and risk-based methods for evaluating allowed outage times (AOTs), action statements requiring shutdown where shutdown risk may be substantial, surveillance test intervals (STIs), defenses against common-cause failures, managing plant configurations, and scheduling maintenances. For each topic, the handbook summarizes methods of analysis and data needs, outlines the insights to be gained, lists additional references, and presents examples of evaluations

  3. Handbook of methods for risk-based analysis of Technical Specification requirements

    International Nuclear Information System (INIS)

    Samanta, P.K.; Vesely, W.E.

    1993-01-01

    Technical Specifications (TS) requirements for nuclear power plants define the Limiting Conditions for Operation (LCOs) and Surveillance Requirements (SRs) to assure safety during operation. In general, these requirements were based on deterministic analysis and engineering judgments. Experiences with plant operation indicate that some elements of the requirements are unnecessarily restrictive, while others may not be conducive to safety. Improvements in these requirements are facilitated by the availability of plant specific Probabilistic Safety Assessments (PSAs). The use of risk and reliability-based methods to improve TS requirements has gained wide interest because these methods can: quantitatively evaluate the risk impact and justify changes based on objective risk arguments. Provide a defensible basis for these requirements for regulatory applications. The United States Nuclear Regulatory Commission (USNRC) Office of Research is sponsoring research to develop systematic risk-based methods to improve various aspects of TS requirements. The handbook of methods, which is being prepared, summarizes such risk-based methods. The scope of the handbook includes reliability and risk-based methods for evaluating allowed outage times (AOTs), action statements requiring shutdown where shutdown risk may be substantial, surveillance test intervals (STIs), defenses against common-cause failures, managing plant configurations, and scheduling maintenances. For each topic, the handbook summarizes methods of analysis and data needs, outlines the insights to be gained, lists additional references, and presents examples of evaluations

  4. Technical Analysis of Projects Being Funded by the DOE Hydrogen Program

    Energy Technology Data Exchange (ETDEWEB)

    Edward G. Skolnik

    2006-02-10

    In July 2000, Energetics began a project in which we performed site-visit based technical analyses or evaluations on hydrogen R&D projects for the purpose of providing in-depth information on the status and accomplishments of these projects to the public, and especially to hydrogen stakeholders. Over a three year period, 32 site-visit analyses were performed. In addition two concepts gleaned from the site visits became subjects of in depth techno-economic analyses. Finally, Energetics produced a compilation document that contains each site-visit analysis that we have performed, starting in 1996 on other contracts through the end of Year One of the current project (July 2001). This included 21 projects evaluated on previous contracts, and 10 additional ones from Year One. Reports on projects visited in Years One and Two were included in their respective Annual Reports. The Year Two Report also includes the two In-depth Analyses and the Compilation document. Reports in Year three began an attempt to perform reviews more geared to hydrogen safety. This Final Report contains a summary of the overall project, all of the 32 site-visit analyses and the two In-depth Analyses.

  5. The Environmental Trilogy project: Balancing technical, institutional, and cultural perspectives to environmental management

    International Nuclear Information System (INIS)

    Kurstedt, Pamela S.; Jim, Russell; Wadsworth, Bonnie C.W.; Burke, William H.; Kurstedt, Harold A. Jr.

    1992-01-01

    'The significant problems we face cannot be solved at the same level of thinking we were at when we created them.' Albert Einstein. I've identified an initial set of three perspectives important to building an integrated, comprehensive approach to managing the environment - technical, institutional, and cultural. I've constructed an holistic model (called the Environmental Trilogy) for environmental management, encompassing at least these three perspectives and their interrelationships. In this paper, I outline the model and report the results of a working session facilitated at Virginia Tech in Blacksburg, Virginia, in October 1991, involving three representatives from each of the technical, institutional, and cultural perspectives. The institutional members of this group were people who understand institutional effects, rather than those who represent institutions. The working group discussed and analyzed the technical-institutional, technical-cultural, and institutional-cultural inter- relationships of the environmental trilogy. The goals of the working group were to put structure on the environmental trilogy model, to facilitate the definition of variables, and explore relationships between and among variables. The working group members are to continue studying issues and components, perspectives, connections, and cause-and-effect in the models and report back to interested parties. The outcome is projected to be a more holistic, integrated view of the environment. (author)

  6. Tribal Colleges and Universities/American Indian Research and Education Initiatives Advanced Manufacturing Technical Assistance Project

    Energy Technology Data Exchange (ETDEWEB)

    Atcitty, Stanley [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2017-02-01

    The overall goal of this project is to establish a network of TCUs with essential advanced manufacturing (AM) facilities, associated training and education programs, and private sector and federal agency partnerships to both prepare an American Indian AM workforce and create economic and employment opportunities within Tribal communities through design, manufacturing, and marketing of high quality products. Some examples of high quality products involve next generation grid components such as mechanical energy storage, cabling for distribution of energy, and electrochemical energy storage enclosures. Sandia National Laboratories (Sandia) is tasked to provide technical advising, planning, and academic program development support for the TCU/American Indian Higher Education Consortium (AIHEC) Advanced Manufacturing Project. The TCUs include Bay Mills Community College (BMCC), Cankdeska Cikana Community College (CCCC), Navajo Technical University (NTU), Southwestern Indian Polytechnic Institute (SIPI), and Salish Kooteani College. AIHEC and Sandia, with collaboration from SIPI, will be establishing an 8-week summer institute on the SIPI campus during the summer of 2017. Up to 20 students from TCUs are anticipated to take part in the summer program. The goal of the program is to bring AM science, technology, engineering, and mathematics (STEM) awareness and opportunities for the American Indian students. Prior to the summer institute, Sandia will be providing reviews on curriculum plans at the each of the TCUs to ensure the content is consistent with current AM design and engineering practice. In addition, Sandia will provide technical assistance to each of the TCUs in regards to their current AM activities.

  7. Technology status in support of refined technical baseline for the Spent Nuclear Fuel project. Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    Puigh, R.J.; Toffer, H.; Heard, F.J.; Irvin, J.J.; Cooper, T.D.

    1995-10-20

    The Spent Nuclear Fuel Project (SNFP) has undertaken technology acquisition activities focused on supporting the technical basis for the removal of the N Reactor fuel from the K Basins to an interim storage facility. The purpose of these technology acquisition activities has been to identify technology issues impacting design or safety approval, to establish the strategy for obtaining the necessary information through either existing project activities, or the assignment of new work. A set of specific path options has been identified for each major action proposed for placing the N Reactor fuel into a ``stabilized`` form for interim storage as part of this refined technical basis. This report summarizes the status of technology information acquisition as it relates to key decisions impacting the selection of specific path options. The following specific categories were chosen to characterize and partition the technology information status: hydride issues and ignition, corrosion, hydrogen generation, drying and conditioning, thermal performance, criticality and materials accountability, canister/fuel particulate behavior, and MCO integrity. This report represents a preliminary assessment of the technology information supporting the SNFP. As our understanding of the N Reactor fuel performance develops the technology information supporting the SNFP will be updated and documented in later revisions to this report. Revision 1 represents the incorporation of peer review comments into the original document. The substantive evolution in our understanding of the technical status for the SNFP (except section 3) since July 1995 have not been incorporated into this revision.

  8. Technology status in support of refined technical baseline for the Spent Nuclear Fuel project. Revision 1

    International Nuclear Information System (INIS)

    Puigh, R.J.; Toffer, H.; Heard, F.J.; Irvin, J.J.; Cooper, T.D.

    1995-01-01

    The Spent Nuclear Fuel Project (SNFP) has undertaken technology acquisition activities focused on supporting the technical basis for the removal of the N Reactor fuel from the K Basins to an interim storage facility. The purpose of these technology acquisition activities has been to identify technology issues impacting design or safety approval, to establish the strategy for obtaining the necessary information through either existing project activities, or the assignment of new work. A set of specific path options has been identified for each major action proposed for placing the N Reactor fuel into a ''stabilized'' form for interim storage as part of this refined technical basis. This report summarizes the status of technology information acquisition as it relates to key decisions impacting the selection of specific path options. The following specific categories were chosen to characterize and partition the technology information status: hydride issues and ignition, corrosion, hydrogen generation, drying and conditioning, thermal performance, criticality and materials accountability, canister/fuel particulate behavior, and MCO integrity. This report represents a preliminary assessment of the technology information supporting the SNFP. As our understanding of the N Reactor fuel performance develops the technology information supporting the SNFP will be updated and documented in later revisions to this report. Revision 1 represents the incorporation of peer review comments into the original document. The substantive evolution in our understanding of the technical status for the SNFP (except section 3) since July 1995 have not been incorporated into this revision

  9. Independent technical review of the Sandia National Laboratories Environmental Restoration Project

    International Nuclear Information System (INIS)

    1994-11-01

    An Independent Technical Review was conducted of the Environmental Restoration Project. The objective of the review was recommendations, from a commercial perspective, on a systems level path forward to safe, minimum cost and schedule project completion. The work presented represents the consensus analysis and recommendations of thirteen individuals with varied backgrounds, expertise, and experience. The ITR team recommends that the barriers to the opportunity described in the diagnosis be eliminated using an integrated DOE-Sandia system approach. Piecemeal changes will not result in the desired commercial efficiency. DOE needs to operate as the contracting agency for a Major System Acquisition. If it does not, commercial performance will not be achieved regardless of the contractor. Likewise, Sandia needs to establish and implement the necessary project structure and management systems to operate with commercial contractor like efficiency

  10. Projecting future solid waste management requirements on the Hanford Site

    International Nuclear Information System (INIS)

    Shaver, S.R.; Stiles, D.L.; Holter, G.M.; Anderson, B.C.

    1990-09-01

    The problem of treating and disposing of hazardous transuranic (TRU), low-level radioactive, and mixed waste has become a major concern of the public and the government. At the US Department of Energy's Hanford Site in Washington state, the problem is compounded by the need to characterize, retrieve, and treat the solid waste that was generated and stored for retrieval during the past 20 years. This paper discusses the development and application of a Solid Waste Projection Model that uses forecast volumes and characteristics of existing and future solid waste to address the treatment, storage, and disposal requirements at Hanford. The model uses a data-driven, object-oriented approach to assess the storage and treatment throughout requirements for each operation for each of the distinct waste classes and the accompanying cost of the storage and treatment operations. By defining the elements of each alternative for the total waste management system, the same database can be used for numerous analyses performed at different levels of detail. This approach also helps a variety of users with widely varying information requirements to use the model and helps achieve the high degree of flexibility needed to cope with changing regulations and evolving treatment and disposal technologies. 2 figs

  11. Fiscal Year 2001 Tank Characterization Technical Sampling Basis and Waste Information Requirements Document

    International Nuclear Information System (INIS)

    ADAMS, M.R.

    2000-01-01

    The Fiscal Year 2001 Tank Characterization Technical Sampling Basis and Waste Information Requirements Document (TSB-WIRD) has the following purposes: (1) To identify and integrate sampling and analysis needs for fiscal year (FY) 2001 and beyond. (2) To describe the overall drivers that require characterization information and to document their source. (3) To describe the process for identifying, prioritizing, and weighting issues that require characterization information to resolve. (4) To define the method for determining sampling priorities and to present the sampling priorities on a tank-by-tank basis. (5) To define how the characterization program is going to satisfy the drivers, close issues, and report progress. (6)To describe deliverables and acceptance criteria for characterization deliverables

  12. Technical data for concentrated solar power plants in operation, under construction and in project

    Directory of Open Access Journals (Sweden)

    Ugo Pelay

    2017-08-01

    Full Text Available This article presents technical data for concentrated solar power (CSP plants in operation, under construction and in project all over the world in the form of tables. These tables provide information about plants (e.g., name of the CSP plant, country of construction, owner of the plant, aim of the plant and their technical characteristics (e.g., CSP technology, solar power, area of the plant, presence and type of hybridization system, electricity cost, presence and type of TES, power cycle fluid, heat transfer fluid, operating temperature, operating pressure, type of turbine, type and duration of storage, etc.. Further interpretation of the data and discussions on the current state-of-the-art and future trends of CSP can be found in the associated research article (Pelay et al., 2017 [1].

  13. Technical Support Section Instrument Support Program for nuclear and nonnuclear facilities with safety requirements

    International Nuclear Information System (INIS)

    Adkisson, B.P.; Allison, K.L.

    1995-01-01

    This document describes requirements, procedures, and supervisory responsibilities of the Oak Ridge National Laboratory (ORNL) Instrumentation and Controls (I ampersand C) Division's Technical Support Section (TSS) for instrument surveillance and maintenance in nonreactor nuclear facilities having identified Operational Safety Requirements (OSRs) or Limiting Conditions Document (LCDs). Implementation of requirements comply with the requirements of U.S. Department of Energy (DOE) Orders 5480.5, 5480.22, and 5481.1B; Martin Marietta Energy Systems, Inc. (Energy Systems), Policy Procedure ESS-FS-201; and ORNL SPP X-ESH-15. OSRs and LCDs constitute an agreement or contract between DOE and the facility operating management regarding the safe operation of the facility. One basic difference between OSRs and LCDs is that violation of an OSR is considered a Category II occurrence, whereas violation of an LCD requirement is considered a Category III occurrence (see Energy Systems Standard ESS-OP-301 and ORNL SPP X-GP-13). OSRs are required for high- and moderate-hazard nuclear facilities, whereas the less-rigorous LCDs are required for low-hazard nuclear facilities and selected open-quotes generally acceptedclose quotes operations. Hazard classifications are determined through a hazard screening process, which each division conducts for its facilities

  14. International shock-wave database project : report of the requirements workshop.

    Energy Technology Data Exchange (ETDEWEB)

    Aidun, John Bahram (Institute of Problems of chemical Physics of Russian Academy of Sciences); Lomonosov, Igor V. (Institute of Problems of chemical Physics of Russian Academy of Sciences); Levashov, Pavel R. (Joint Institute for High Temperatures of Russian Academy of Sciences)

    2012-03-01

    We report on the requirements workshop for a new project, the International Shock-Wave database (ISWdb), which was held October 31 - November 2, 2011, at GSI, Darmstadt, Germany. Participants considered the idea of this database, its structure, technical requirements, content, and principles of operation. This report presents the consensus conclusions from the workshop, key discussion points, and the goals and plan for near-term and intermediate-term development of the ISWdb. The main points of consensus from the workshop were: (1) This international database is of interest and of practical use for the shock-wave and high pressure physics communities; (2) Intermediate state information and off-Hugoniot information is important and should be included in ISWdb; (3) Other relevant high pressure and auxiliary data should be included to the database, in the future; (4) Information on the ISWdb needs to be communicated, broadly, to the research community; and (5) Operating structure will consist of an Advisory Board, subject-matter expert Moderators to vet submitted data, and the database Project Team. This brief report is intended to inform the shock-wave research community and interested funding agencies about the project, as its success, ultimately, depends on both of these groups finding sufficient value in the database to use it, contribute to it, and support it.

  15. DECOVALEX II PROJECT. Technical report - Task 1A and 1B

    International Nuclear Information System (INIS)

    Lanru Jing; Stephansson, Ove; Kautsky, F.

    1998-08-01

    DECOVALEX II project started in November 1995 as a continuation of the DECOVALEX I project, which was completed at the end of 1994. The project was initiated by recognizing the fact that a proper evaluation of the current capacities of numerical modelling of the coupled T-H-M processes in fractured media is needed not only for small scale, well controlled laboratory test cases such as those studied in DECOVALEX I, but also for less characterised, more complex and realistic in-situ experiments. This will contribute to validation and confidence building in the current mathematical models, numerical methods and computer codes. Four tasks were defined in the DECOVALEX II project: TASK 1 - numerical study of the RCF3 pumping test and shaft excavation at Sellafield by Nirex, UK; TASK 2 - numerical study of the in-situ T-H-M experiments at Kamaishi Mine by PNC, Japan; TASK 3 - review of current state-of-the-art of rock joint research and TASK 4 - report on the coupled T-H-M issues related to repository design and performance assessment. This report is one of the technical reports of the DECOVALEX II project, describing the work performed for TASK 1A and 1B - the predictions and model calibrations for the RCF 3 pumping test at Sellafield. Presented in this report are the descriptions of the project, tasks, approaches, methods and results of numerical modelling work carried out by the research teams. The report is a summary of the research reports written by the research teams and submitted to the project secretariat, and the discussions held during project workshops and task force group meetings. The opinions and conclusions in this report, however, reflect only ideas of the authors, not necessarily a collective representation of the funding organisations of the project

  16. International scientific consensus on medical plantar pressure measurement devices: technical requirements and performance

    Directory of Open Access Journals (Sweden)

    Claudia Giacomozzi

    2012-01-01

    Full Text Available BACKGROUND: Since 2006, the Italian National Institute of Health (ISS has been conducting independent scientific activities to standardize the technical assessment of plantar pressure measurement devices (PMDs. MATERIAL AND METHODS: On the basis of the ISS results, in 2010 the Pedobarographic Group of the International Foot and Ankle Biomechanics community (i-FAB-PG promoted a consensus activity about the main technical requirements for the appropriate use of PMDs. The activity relied on a moodlebased on-line forum, documents exchange, discussions, reviews, meetings and a final survey. RESULTS: The participation of clinical and technical researchers, users, and manufacturers, contributed to the delivery of the hereby reported recommendations which specifically regard Medical PMDs in the form of platforms. CONCLUSIONS: The i-FAB-PG community reached overall agreement on the recommendations, with a few minor objections which are reported and commented in the document. RELEVANCE: The present document, the highest result achievable within a small scientific community, will hopefully represent the starting point of the wider process of establishing official international guidelines or standards, within scientific communities and standardization organizations.

  17. Fuel cells for transport: can the promise be fulfilled? Technical requirements and demands from customers

    Science.gov (United States)

    Klaiber, Thomas

    The paper discusses the technical requirements and the customer demands for vehicles that have an on-board methanol reformer and fuel cells. The research concentrates on the technical developmental risks which include minimizing volume, reducing weight and, at the same time, improving efficiency and system dynamics. Fuel cell powered vehicles with methanol reformers are not only suitable for a niche market but also these vehicles will compete with conventional vehicles. The greatest hindrance will be the price of the fuel cell. A possible progressive development of the number of fuel cell powered vehicles in conjunction with a reduction in costs will be discussed in the paper. When fuel cell vehicles come to the market it is necessary that an infrastructure for the fuel methanol or hydrogen is installed. Therefore, it will only be possible to introduce fuel cell vehicles into special markets, e.g. California. Such a process will need to be subsidized by additional incentives like tax concessions. Today there are many technical risks and unsolved problems relating to production technologies, infrastructure, and costs. Nevertheless, among the alternative power units, the fuel cell seems to be the only one that might be competitive to the conventional power unit, especially relating to emissions.

  18. Requirements on the provisional safety analyses and technical comparison of safety measures

    International Nuclear Information System (INIS)

    2010-04-01

    decide on the provision of a design license for a repository site for SMA and another one for HAA, or for a common site for both SMA and HAA. The present report concerns the second step and recapitulates the assertions of SGT on the provisional safety analyses and on the safety technical comparison. It establishes the specific requirements of the Swiss Federal Nuclear Safety Inspectorate (ENSI) on provisional safety and the safety technical comparison. Further, it defines the extent and content of the safety technical documentation necessary for step 2

  19. System requirements for the Los Alamos foil-implosion project

    International Nuclear Information System (INIS)

    Brownell, J.; Bowers, R.; Greene, A.; Lindemuth, I.; Nickel, G.; Oliphant, T.; Weiss, D.

    1983-01-01

    The goal of the Los Alamos imploding foil project is the development of an intense source of soft x rays and hot plasma produced from the thermalization of 1 to 10 MJ of plasma kinetic energy. The source will be used for material studies and fusion experiments. Specifically, thin, current-carrying cylindrical metallic plasmas are imploded via their self-magnetic forces. Features of this project are the use of high-explosive-driven flux-compression generators as the prime power source to achieve very high energies and fast opening switches to shorten the electrical pulses. To reach a load kinetic energy of 10 MJ, it is expected that the foil-plasma must carry about 50 MA of current and must implode in less than 1/2 μsec. This imposes the requirements that switch opening times must be less than 1/2 μsec and the transmission line must withstand voltages of about 1 MV. The system being pursued at Los Alamos is described, and model calculations are presented

  20. Republic of the Marshall Islands. Energy Project Development Options and Technical Assessment (2013)

    Energy Technology Data Exchange (ETDEWEB)

    Conrad, Misty Dawn [National Renewable Energy Lab. (NREL), Golden, CO (United States); Olis, Dan [National Renewable Energy Lab. (NREL), Golden, CO (United States); Ness, J. Erik [National Renewable Energy Lab. (NREL), Golden, CO (United States); Esterly, Sean [National Renewable Energy Lab. (NREL), Golden, CO (United States)

    2015-09-01

    The advancement of renewable energy and energy efficient technologies continues to be fluid. There are many technical opportunities and strategies that can be utilized to guide communities to deploy cost-effective commercial alternative energy options; however, to achieve aggressive economic, environmental, and security goals, it requires a comprehensive, integrated approach. This document reports on the initial findings of an energy assessment that was conducted for the Republic of the Marshall Islands.

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

    Science.gov (United States)

    Parrott, Edith L.; Weiland, Karen J.

    2017-01-01

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

  2. Programmatic and technical requirements for the FMDP fresh MOX fuel transport package

    International Nuclear Information System (INIS)

    Ludwig, S.B.; Michelhaugh, R.D.; Pope, R.B.

    1997-12-01

    This document is intended to guide the designers of the package to all pertinent regulatory and other design requirements to help ensure the safe and efficient transport of the weapons-grade (WG) fresh MOX fuel under the Fissile Materials Disposition Program. To accomplish the disposition mission using MOX fuel, the unirradiated MOX fuel must be transported from the MOX fabrication facility to one or more commercial reactors. Because the unirradiated fuel contains large quantities of plutonium and is not sufficient radioactive to create a self-protecting barrier to deter the material from theft, DOE intends to use its fleet of safe secure trailers (SSTs) to provide the necessary safeguards and security for the material in transit. In addition to these requirements, transport of radioactive materials must comply with regulations of the Department of Transportation and the Nuclear Regulatory Commission (NRC). In particular, NRC requires that the packages must meet strict performance requirements. The requirements for shipment of MOX fuel (i.e., radioactive fissile materials) specify that the package design is certified by NRC to ensure the materials contained in the packages are not released and remain subcritical after undergoing a series of hypothetical accident condition tests. Packages that pass these tests are certified by NRC as a Type B fissile (BF) package. This document specifies the programmatic and technical design requirements a package must satisfy to transport the fresh MOX fuel assemblies

  3. Technical Status Report of the Regulatory Assistance Project: October 2001-February 2003

    Energy Technology Data Exchange (ETDEWEB)

    2003-08-01

    This report details the work undertaken from October 2001 to February 2003 by the Regulatory Assistance Project under subcontract to the National Renewable Energy Laboratory. The objectives of this work were to develop regulatory policy options that would reduce the institutional and infrastructure barriers to full-value deployment of distributed power systems. Specific tasks included leading technical workshops on removing or overcoming regulatory barriers to distributed resources for state utility regulators and developing a draft model rule on emission performance standards for distributed generation.

  4. CSCW Challenges in Large-Scale Technical Projects - a case study

    DEFF Research Database (Denmark)

    Grønbæk, Kaj; Kyng, Morten; Mogensen, Preben Holst

    1992-01-01

    This paper investigates CSCW aspects of large-scale technical projects based on a case study of a specific Danish engineering company and uncovers s challenges to CSCW applications in this setting. The company is responsible for management and supervision of one of the worlds largest tunnel....... The initial qualitative analysis identified a number of bottlenecks in daily work, where support for cooperation is needed. Examples of bottlenecks are: sharing materials, issuing tasks, and keeping track of task status. Grounded in the analysis, cooperative design workshops based on scenarios of future work...

  5. Tribal Colleges and Universitie/American Indian Higher Education Consortium Advanced Manufacturing Technical Assistance Project

    Energy Technology Data Exchange (ETDEWEB)

    Atcitty, Stanley [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2017-09-01

    The National Nuclear Security Agency (NNSA) created a Minority Serving Institution Partnership Plan (MSIPP) to 1) align investments in a university capacity and workforce development with the NNSA mission to develop the needed skills and talent for NNSA’s enduring technical workforce at the laboratories and production plants and 2) to enhance research and education at under-represented colleges and universities. Out of this effort, MSIPP launched a new program in early FY17 focused on Tribal Colleges and Universities (TCUs). The following report summarizes the project focus and status update during this reporting period.

  6. Status of Radon Related Activities in Member States Participating in Technical Cooperation Projects in Europe

    International Nuclear Information System (INIS)

    2017-03-01

    This publication summarizes the status of radon programmes at the start of 2014 in the Member States in Europe participating in the IAEA technical cooperation project on establishing enhanced approaches to the control of public exposure to radon. The current status was determined from responses to a questionnaire covering the following elements of a national radon action plan: policies and strategies; radon measurement surveys; establishment of reference levels; managing radon in existing buildings and in future buildings; education and training of professionals; and public awareness initiatives.

  7. Tribal Colleges and Universitie/American Indian Higher Education Consortium Advanced Manufacturing Technical Assistance Project.

    Energy Technology Data Exchange (ETDEWEB)

    Atcitty, Stanley [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2018-02-01

    The National Nuclear Security Agency (NNSA) created a Minority Serving Institution Partnership Plan (MSIPP) to 1) align investments in a university capacity and workforce development with the NNSA mission to develop the needed skills and talent for NNSA’s enduring technical workforce at the laboratories and production plants and 2) to enhance research and education at under-represented colleges and universities. Out of this effort, MSIPP launched a new program in early FY17 focused on Tribal Colleges and Universities (TCUs). The following report summarizes the project focus and status update during this reporting period.

  8. DECOVALEX II PROJECT. Technical report - Task 2A and 2B. (Revised edition)

    International Nuclear Information System (INIS)

    Lanru Jing; Stephansson, Ove

    1998-08-01

    DECOVALEX II project started in November 1995 as a continuation of the DECOVALEX I project, which was completed at the end of 1994. The project was initiated by recognizing the fact that a proper evaluation of the current capacities of numerical modelling of the coupled T-H-M processes in fractured media is needed not only for small scale, well controlled laboratory test cases such as those studied in DECOVALEX 1, but also for less characterised, more complex and realistic in-situ experiments. This will contribute to validation and confidence building in the current mathematical models, numerical methods and computer codes. Four tasks were defined in the DECOVALEX II project: TASK 1 - numerical study of the RCF3 pumping test and shaft excavation at Sellafield by Nirex, UK; TASK 2 - numerical study of the in-situ T-H-M experiments at Kamaishi Mine by PNC, Japan; TASK 3 - review of current state-of-the-art of rock joint research and TASK 4 - report on the coupled T-H-M issues related to repository design and performance assessment. This report is one of the technical reports of the DECOVALEX II project, describing the work performed for TASK 2A and 2B - the predictions and model calibration for the hydro-mechanical effect of the excavation of the test pit for the in-situ T-H-M experiments at Kamaishi Mine by PNC, Japan. Presented in this report are the descriptions of the project, definition of Task 2, and approaches, methods and results of numerical modelling work carried out by the research teams. The report is a summary of the research reports written by the research teams and the discussions held during project workshops and task force group meetings. The opinions and conclusions in this report, however, reflect only ideas of the authors, not necessarily a collective representation of the funding organisations of the project

  9. Wyoming coal-conversion project. Final technical report, November 1980-February 1982. [Proposed WyCoalGas project, Converse County, Wyoming; contains list of appendices with title and identification

    Energy Technology Data Exchange (ETDEWEB)

    None

    1982-01-01

    This final technical report describes what WyCoalGas, Inc. and its subcontractors accomplished in resolving issues related to the resource, technology, economic, environmental, socioeconomic, and governmental requirements affecting a project located near Douglas, Wyoming for producing 150 Billion Btu per day by gasifying sub-bituminous coal. The report summarizes the results of the work on each task and includes the deliverables that WyCoalGas, Inc. and the subcontractors prepared. The co-venturers withdrew from the project for two reasons: federal financial assistance to the project was seen to be highly uncertain; and funds were being expended at an unacceptably high rate.

  10. Linear projection of technical noise for interferometric gravitational-wave detectors

    International Nuclear Information System (INIS)

    Smith, J R; Ajith, P; Grote, H; Hewitson, M; Hild, S; Lueck, H; Strain, K A; Willke, B; Hough, J; Danzmann, K

    2006-01-01

    An international network of interferometric gravitational-wave detectors is now in operation, and has entered a period of intense commissioning focused on bringing the instruments to their theoretical sensitivity limits. To expedite this process, noise analysis techniques have been developed by the groups associated with each instrument. We present methods of noise analysis that were developed and utilized for the commissioning of the GEO 600 detector. The focal point of this paper is a technique called noise projection that is used to determine the levels of contribution of various noise sources to the detector output. Example applications of this method to control loops typical of those employed in an interferometric GW detector are presented. Possible extensions of noise projections, including technical noise subtraction and gravitational-wave vetoes are also discussed

  11. Maintaining project consistency with transportation plans throughout the project life cycle with an emphasis on maintaining air quality conformity: technical report.

    Science.gov (United States)

    2016-07-01

    Federal and state transportation planning statutory and regulatory laws require transportation projects to be : consistent with transportation plans and improvement programs before a federal action can be taken on a : project requiring one. Significa...

  12. Independent technical reviews for groundwater and soil remediation projects at US Department Of Energy sites - 59188

    International Nuclear Information System (INIS)

    Kaback, Dawn S.; Chamberlain, Grover; Morse, John G.; Petersen, Scott W.

    2012-01-01

    The US Department of Energy Office of Environmental Management has supported independent technical reviews of soil and groundwater projects at multiple DOE sites over the last 10 years. These reviews have resulted in significant design improvements to remedial plans that have accelerated cleanup and site closure. Many have also resulted in improved understanding of complex subsurface conditions, promoting better approaches to design and implementation of new technologies. Independent technical reviews add value, because they provide another perspective to problem solving and act as a check for especially challenging problems. By bringing in a team of independent experts with a broad experience base, alternative solutions are recommended for consideration and evaluation. In addition, the independence of the panel is significant, because it is able to address politically sensitive issues. The expert panel members typically bring lessons learned from other sites to help solve the DOE problems. In addition, their recommendations at a particular site can often be applied at other sites, making the review even more valuable. The review process can vary, but some common lessons ensure a successful review: - Use a multi-disciplinary broadly experienced team; - Engage the panel early and throughout the project; - Involve regulators and stakeholders in the workshop, if appropriate. - Provide sufficient background information; - Close the workshop with a debriefing followed by a written report. Many groundwater remediation challenges remain at DOE sites. Independent technical reviews have and will ensure that the best capabilities and experience are applied to reduce risks and uncertainties. Even though the groundwater remediation industry has developed significantly over the last twenty years, advancements are needed to address the complexities of the subsurface at the DOE sites. These advancements have tremendous potential to save millions of dollars and to accelerate the

  13. Promoting gender parity in basic education: Lessons from a technical cooperation project in Yemen

    Science.gov (United States)

    Yuki, Takako; Mizuno, Keiko; Ogawa, Keiichi; Mihoko, Sakai

    2013-06-01

    Many girls are not sent to school in Yemen, despite basic education being free as well as compulsory for all children aged 6-15. Aiming to improve girls' enrolment by increasing parental and community involvement, the Japan International Cooperation Agency (JICA) offered a technical cooperation project in June 2005 called Broadening Regional Initiative for Developing Girls' Education (BRIDGE). Phase 1 of this project ran for three and a half years, piloting a participatory school management model supported by school grants in six districts of the Taiz Governorate in the Southwest of Yemen. To find out how successful this approach has been in a traditional society, the authors of this paper analysed the gender parity index (GPI) of the project's pilot schools. Based on data collected at three points in time (in the initial and final years of the project, and two years after the project's end), their findings suggest that interventions in school management which strongly emphasise girls' education can be effective in improving gender parity rather quickly, regardless of the schools' initial conditions. However, the authors also observe that the pilot schools' post-project performance in terms of gender parity is mixed. While the local government allocated budgets for school grants to all pilot schools even after the project's end, training and monitoring activities were cut back. The authors further observe that the variation in performance appears to be significantly correlated with school leaders' initial perceptions of gender equality and with the number of female teachers employed. These findings point to the importance of providing schools with continuous long-term guidance and of monitoring those which implement school improvement programmes.

  14. The research project on technical information basis for aging management in Fukui and Kinki area (2nd report)

    International Nuclear Information System (INIS)

    Fujimura, Kimiya; Watarumi, Chikae; Toudou, Tsugihiko

    2009-01-01

    The Research Project on Technical Information Basis for Aging Management was initiated in 2006 by the Nuclear and Industrial Safety Agency (NISA) of the Ministry of Economy, Trade and Industry (METI), to promote aging management of domestic nuclear power plants. Its main objective was to improve the technical basis on which aging plants are regulated. Upon taking part in the R and D Roadmaps for Aging Management and Safe Long Term Operation, the experience and results of the participating organizations were considered and the following four topics were extracted. The regional characteristics of the Fukui and Kinki area where 15 nuclear power plants, mainly PWRs, and many nuclear related research institutes and universities are located, were also considered. 1) The improvement of pipe thinning management in nuclear power plants. 2) The development of inspection techniques to monitor the initiation and propagation of defects. 3) The development of a guideline for evaluating weld repair methods. 4) The development of a guideline for evaluating the degradation of main structures. To promote this research project, INSS has established a regional consortium (called the 'Fukui Regional Cluster' in coordination with universities, research institutes, electric utilities and venders in the Fukui and Kinki area. INSS is acting as of coordinator to make a contracts, facilitate execution, and compile annual reports. In FY2008, 11 research subjects were proposed for this project and all were accepted. Of these, 4 subjects were related to the first topic (pipe thinning), 3 subjects were related to the second topic (inspection technique) and I subject was related to each of the other two topics (weld repair and main structures). All the subjects have been completed, fulfilling the requirements and expectations. (author)

  15. The research project on technical information basis for aging management in Fukui and Kinki area. 3rd report

    International Nuclear Information System (INIS)

    Fujimura, Kimiya; Watarumi, Chikae; Toudou, Tsugihiko

    2010-01-01

    The Research Project on Technical Information Basis for Aging Management was initiated in FY2006 by the Nuclear and Industrial Safety Agency (NISA) of the Ministry of Economy, Trade and Industry (METI), to promote aging management of domestic nuclear power plants. Its main objective was to improve the technical basis on which aging nuclear power plants are regulated. Upon taking part in the R and D Roadmaps for Aging Management and Safe Long Term Operation, the experiences and achievements of the participating organizations were taken into account and the following four topics were chosen. The regional characteristics of the Fukui and Kinki area where 15 nuclear power plants, mainly PWRs, and many nuclear related research institutes and universities are located, were also considered. (1) The improvement of pipe thinning management in nuclear power plants, (2) The development of inspection techniques to monitor the initiation and propagation of defects, (3) The development of a guideline for evaluating weld repair methods, (4) The development of a guideline for evaluating the degradation of main structures. To promote this research project, INSS has established a regional consortium (called the 'Fukui Regional Cluster' in coordination with universities, research institutes, electric utilities and venders in the Fukui and Kinki area. INSS is acting as a coordinator to make contracts, facilitate execution, and compile annual reports. In FY2009, 11 research subjects were proposed for this project and all were accepted. Of these, 4 subjects were related to the first topic (pipe thinning), 3 subjects to the second topic (inspection technique) and 1 subject to each of the other two topics (weld repair and main structures). All the subjects have been completed, fulfilling the requirements and expectations. (author)

  16. MORE - Management of requirements in NPP modernisation projects. Project report 2006

    Energy Technology Data Exchange (ETDEWEB)

    Thunem, A.P.J.; Thunem, H.P.J. [IFE (Norway); Valkonen, J. [VTT (Finland)

    2007-02-15

    The purpose of the report is to document the work and related activities in the period January 1 December 31 in 2006, including dissemination activities. The work in this period has been concentrated on further research for adopting an approach for dependable requirements engineering and its supporting tool. The majority of the efforts in 2006, however, was spent on making the researchers, developers, utilities and licensees more aware of the importance of the area of requirements engineering, and in that respect organising an international seminar on dependable requirements engineering. This seminar was defined as a deliverable in the Activity Plan for 2006 and became also the most important deliverable for 2006. Therefore, this report naturally features a detailed summary of the seminar, which proved to be a true success and at the same time a door opener for more initiatives within the topic, proposed by several participants. More efforts within dissemination of the background and objectives of the project MORE within the nuclear community and towards NPPs that do carry out modernisation projects continued to be one important focus. (au)

  17. MORE - Management of requirements in NPP modernisation projects. Project report 2006

    International Nuclear Information System (INIS)

    Thunem, A.P.J.; Thunem, H.P.J.; Valkonen, J.

    2007-02-01

    The purpose of the report is to document the work and related activities in the period January 1 December 31 in 2006, including dissemination activities. The work in this period has been concentrated on further research for adopting an approach for dependable requirements engineering and its supporting tool. The majority of the efforts in 2006, however, was spent on making the researchers, developers, utilities and licensees more aware of the importance of the area of requirements engineering, and in that respect organising an international seminar on dependable requirements engineering. This seminar was defined as a deliverable in the Activity Plan for 2006 and became also the most important deliverable for 2006. Therefore, this report naturally features a detailed summary of the seminar, which proved to be a true success and at the same time a door opener for more initiatives within the topic, proposed by several participants. More efforts within dissemination of the background and objectives of the project MORE within the nuclear community and towards NPPs that do carry out modernisation projects continued to be one important focus. (au)

  18. The technical and economical optimization of the French geological repository project - 59275

    International Nuclear Information System (INIS)

    Raffard, Rodolphe; Labalette, Thibaud

    2012-01-01

    Document available in abstract form only. Full text of publication follows: The French Act of 28 June 2006 made the choice of reversible geological repository for long term management of high level and long-lived intermediate level waste. Andra is in charge of designing, building and operating the future industrial repository Cigeo. Current major issues consist in preparing the application to be examined in 2015, planning the construction so that operation would start in 2025 and optimizing the design on both technical and economical points of view. The Dossier 2005 -provided by Andra prior to the 2006 Act- established the feasibility of the project, especially towards compliance with safety and reversibility. Design options were presented at that time with the objective of demonstrating feasibility without ruling out possibilities of further optimization. Along with the scientific and technical review of Dossier 2005, a number of design optimization topics were identified in 2006. Working groups involved Andra's specialists as well as external experts. A particular attention was given to (i) the industrial experience of waste producers and (ii) the characteristics of the clay layer investigated in the Meuse/Haute-Marne Underground Research Laboratory. The 2006 optimization topics were prioritized taking into account their economical impact and the development plan of the project

  19. American Recovery and Reinvestment Act (ARRA) FEMP Technical Assistance for Geothermal Resource Evaluation Projects

    Energy Technology Data Exchange (ETDEWEB)

    Robert P. Breckenridge; Thomas R. Wood; Joel Renner

    2010-09-01

    The purpose of this document is to report on the evaluation of geothermal resource potential on and around three different United States (U. S.) Air Force Bases (AFBs): Nellis AFB and Air Force Range (AFR) in the State of Nevada (see maps 1 and 5), Holloman AFB in the State of New Mexico (see map 2), and Mountain Home AFB in the State of Idaho (see map 3). All three sites are located in semi-arid parts of the western U. S. The U. S. Air Force, through its Air Combat Command (ACC) located at Langley AFB in the State of Virginia, asked the Federal Energy Management Program (FEMP) for technical assistance to conduct technical and feasibility evaluations for the potential to identify viable geothermal resources on or around three different AFBs. Idaho National Laboratory (INL) is supporting FEMP in providing technical assistance to a number of different Federal Agencies. For this report, the three different AFBs are considered one project because they all deal with potential geothermal resource evaluations. The three AFBs will be evaluated primarily for their opportunity to develop a geothermal resource of high enough quality grade (i.e., temperature, productivity, depth, etc.) to consider the possibility for generation of electricity through a power plant. Secondarily, if the resource for the three AFBs is found to be not sufficient enough for electricity generation, then they will be described in enough detail to allow the base energy managers to evaluate if the resource is suitable for direct heating or cooling. Site visits and meetings by INL personnel with the staff at each AFB were held in late FY-2009 and FY-2010. This report provides a technical evaluation of the opportunities and challenges for developing geothermal resources on and around the AFBs. An extensive amount of literature and geographic information was evaluated as a part of this assessment. Resource potential maps were developed for each of the AFBs.

  20. The Role of Requirements in the Success or Failure of Software Projects

    OpenAIRE

    Hussain, Azham; Mkpojiogu, Emmanuel O.C.; Kamal, Fazillah Mohmad

    2016-01-01

    Requirements engineering is pivotal and central to every successful software development project. There are several reasons why software projects fail; however, poorly elicited, documented, validated and managed requirements contribute grossly to software projects failure. Software project failures are normally very costly and risky and these could even a times be life threatening also. Projects that overlook requirements engineering processes often suffer or are most likely to suffer from fa...

  1. Technical Requirements For Reactors To Be Deployed Internationally For the Global Nuclear Energy Partnership

    International Nuclear Information System (INIS)

    Ingersoll, Daniel T.

    2007-01-01

    The Global Nuclear Energy Partnership (GNEP) seeks to create an international regime to support large-scale growth in the worldwide use of nuclear energy. Fully meeting the GNEP vision may require the deployment of thousands of reactors in scores of countries, many of which do not use nuclear energy currently. Some of these needs will be met by large-scale Generation III and III+ reactors (>1000 MWe) and Generation IV reactors when they are available. However, because many developing countries have small and immature electricity grids, the currently available Generation III(+) reactors may be unsuitable since they are too large, too expensive, and too complex. Therefore, GNEP envisions new types of reactors that must be developed for international deployment that are 'right sized' for the developing countries and that are based on technologies, designs, and policies focused on reducing proliferation risk. The first step in developing such systems is the generation of technical requirements that will ensure that the systems meet both the GNEP policy goals and the power needs of the recipient countries. Reactor systems deployed internationally within the GNEP context must meet a number of requirements similar to the safety, reliability, economics, and proliferation goals established for the DOE Generation IV program. Because of the emphasis on deployment to nonnuclear developing countries, the requirements will be weighted differently than with Generation IV, especially regarding safety and non-proliferation goals. Also, the reactors should be sized for market conditions in developing countries where energy demand per capita, institutional maturity and industrial infrastructure vary considerably, and must utilize fuel that is compatible with the fuel recycle technologies being developed by GNEP. Arrangements are already underway to establish Working Groups jointly with Japan and Russia to develop requirements for reactor systems. Additional bilateral and multilateral

  2. Technical assessment of compliance with workplace air sampling requirements in the 300 Area

    International Nuclear Information System (INIS)

    Olsen, P.A.

    1995-01-01

    The purpose of this Technical Work Document is to satisfy HSRCM-1, the ''Hanford Site Radiological Control Manual.'' Article 551.4 of that manual states a requirement for a documented study of facility workplace air sampling programs (WPAS). This first revision of the original Supporting Document covers the period from January 1, 1995 to December 31, 1995. HSRCM-1 is the primary guidance for radiological control at Westinghouse Hanford Company (WHC). It was written to implement DOE/EH-0256T ''US Department of Energy Radiological Control Manual'' as it applies to programs at Hanford. As such, it complies with Title 10, Part 835 of the Code of Federal Regulations. There are also several Department of Energy (DOE) Orders, national consensus standards, and reports that provide criteria, standards, and requirements for workplace air sampling programs. This document provides a summary of these, as they apply to WHC facility workplace air sampling programs. This document also provides an evaluation of the compliance of 300 Areas' workplace air sampling program to the criteria, standards, and requirements and documents compliance with the requirements where appropriate. Where necessary, it also indicates changes needed to bring specific locations into compliance. The areas evaluated were the 340 Facility, the Advanced Reactor Operations Division Facilities, the N Reactor Fuels Supply Facility, and The Geotechnical Engineering Laboratory

  3. Defining user requirements for tele-nuclear medicine applications: from technical feasibility to clinical results

    International Nuclear Information System (INIS)

    Todd-Pokropek, A.; Chanachai, R.

    2002-01-01

    Purpose: Defining the user requirements for tele-nuclear medicine systems, in particular in developing countries, is an important prerequisite to establishing a service. However, the availability of low cost PC based servers and, now, access to local ISPs, has made the technical provision of such networks relatively simple and low cost, although transfer of data to and form legacy systems still present many difficulties. Method and Materials: The key driving force in developing countries is the imbalance between skills in the relatively few centres of excellence and the increasing number of installations overall. Requirements include both very rapid remote reporting and/or overnight tele-consultation. Original raw NM data must be available not just 'images'. Using current network standards (VPN) data transfer rate requirements are low. Provision of image fusion between NM, CT and MRI is also highly desirable. Results: Experience has been obtained e.g. in Thailand and Morocco, where a network of servers and remote users, with cardiac application of particular importance, has demonstrated benefit, and increasing volumes of usage. Conclusions: However, the requirements need to be clearly defined, and a staff training program is essential, as is a full evaluation. The transfer of skills is important in raising the overall quality of health care

  4. Teaching Power Electronics with a Design-Oriented, Project-Based Learning Method at the Technical University of Denmark

    Science.gov (United States)

    Zhang, Zhe; Hansen, Claus Thorp; Andersen, Michael A. E.

    2016-01-01

    Power electronics is a fast-developing technology within the electrical engineering field. This paper presents the results and experiences gained from applying design-oriented project-based learning to switch-mode power supply design in a power electronics course at the Technical University of Denmark (DTU). Project-based learning (PBL) is known…

  5. A research review on clinical needs, technical requirements, and normativity in the design of surgical robots.

    Science.gov (United States)

    Díaz, Carlos Eduardo; Fernández, Roemi; Armada, Manuel; García, Felipe

    2017-12-01

    Nowadays robots play an important role in society, mainly due to the significant benefits they provide when utilized for assisting human beings in the execution of dangerous or repetitive tasks. Medicine is one of the fields in which robots are gaining greater use and development, especially those employed in minimally invasive surgery (MIS). However, due to the particular conditions of the human body where robots have to act, the design of these systems is complex, not only from a technical point of view, but also because the clinical needs and the normativity aspects are important considerations that have to be taken into account in order to achieve better performances and more secure systems for patients and surgeons. Thus, this paper explores the clinical needs and the technical requirements that will trace the roadmap for the next scientific and technological advances in the field of robotic surgery, the metrics that should be defined for safe technology development and the standards that are being elaborated for boosting the industry and facilitating systems integration. Copyright © 2017 John Wiley & Sons, Ltd.

  6. General technical requirements (GTR) for inventory monitoring systems (IMS) for the trilateral initiative

    International Nuclear Information System (INIS)

    Pshakin, Gennady M.; Kuleshov, I.; Shea, T.; Puckett, J.M.; Zhukov, I.; Mangan, Dennis L.; Matter, John C.; Waddoups, I.; Smathers, D.; Abhold, M.E.; Hsue, S.-T.; Chiaro, P.

    2002-01-01

    Pursuant to the Trilateral Initiative, the three parties (The Russian Federation, the United States, and the International Atomic Energy Agency) have been engaged in discussions concerning the structure of reliable monitoring systems for storage facilities having large inventories. The intent of these monitoring systems is to provide the capability for the IAEA to maintain continuity of knowledge in a sufficiently reliable manner that should there be equipment failure, loss of continuity of knowledge would be restricted to a small population of the inventory, and thus reinventory of the stored items would be minimized These facility-specific monitoring systems, referred to as Inventory Monitoring Systems (IMS) are to provide the principal means for the M A to assure that the containers of fissile material remain accounted under the Verification Agreements which are to be concluded between the IAEA and the Russian Federation and the lAEA and the United States for the verification of weapon-origin and other fissile material specified by each State as released from its defense programs. A technical experts working group for inventory monitoring systems has been meeting since Feb- of 2000 to formulate General Technical Requirements (GTR) for Inventory Monitoring Systems for the Trilateral Initiative. Although provisional agreement has been reached by the three parties concerning the GTR, it is considered a living document that can be updated as warranted by the three parties. This paper provides a summary of the GTR as it currently exists.

  7. 42 CFR 59.5 - What requirements must be met by a family planning project?

    Science.gov (United States)

    2010-10-01

    ... requirements must be met by a family planning project? (a) Each project supported under this part must: (1... (iii) Promote continued participation in the project by persons to whom family planning services may be... services purchased for project participants will be authorized by the project director or his designee on...

  8. Approaches to Formation of Technical Reserves of Insurance Organizations: Domestic Realities and International Requirements

    Directory of Open Access Journals (Sweden)

    Prykaziuk Natalia V.

    2017-03-01

    Full Text Available he aim of the article is to study approaches to formation of insurance reserves by insurance companies in Ukraine and the world. The essence and peculiarities of the formation of reserves by insurance organizations in Ukraine are investigated. The provisions of the Solvency II Directive in terms of formation of reserves and financial stability in insurance organizations are considered. A comparative characteristic of the requirements for the solvency of insurers in accordance with the legislation of Ukraine and the requirements of Solvency II is presented. Differences in methods of formation of technical reserves by insurance organizations in Ukraine and the world are determined, factors affecting it are indicated. Methods of formation of insurance reserves in the countries of the European Union are considered. The directions of improving the process of formation of insurance reserves of the insurer are justified. The problems of introducing the experience of foreign countries and Solvency II requirements are analyzed taking into account the realities of the domestic insurance market. The strengths and weaknesses of the introduction of Solvency II in the Ukrainian insurance market are explored.

  9. Consensus statement for use and technical requirements of thyroid ultrasound in endocrinology units.

    Science.gov (United States)

    Martín-Hernández, Tomás; Díez Gómez, Juan José; Díaz-Soto, Gonzalo; Torres Cuadro, Alberto; Navarro González, Elena; Oleaga Alday, Amelia; Sambo Salas, Marcel; Reverter Calatayud, Jordi L; Argüelles Jiménez, Iñaki; Mancha Doblas, Isabel; Fernández García, Diego; Galofré, Juan Carlos

    2017-03-01

    Thyroid nodule detection has increased with widespread use of ultrasound, which is currently the main tool for detection, monitoring, diagnosis and, in some instances, treatment of thyroid nodules. Knowledge of ultrasound and adequate instruction on its use require a position statement by the scientific societies concerned. The working groups on thyroid cancer and ultrasound techniques of the Spanish Society of Endocrinology and Nutrition have promoted this document, based on a thorough analysis of the current literature, the results of multicenter studies and expert consensus, in order to set the requirements for the best use of ultrasound in clinical practice. The objectives include the adequate framework for use of thyroid ultrasound, the technical and legal requirements, the clinical situations in which it is recommended, the levels of knowledge and learning processes, the associated responsibility, and the establishment of a standardized reporting of results and integration into hospital information systems and endocrinology units. Copyright © 2017 SEEN. Publicado por Elsevier España, S.L.U. All rights reserved.

  10. 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

  11. REQUIREMENT VERIFICATION AND SYSTEMS ENGINEERING TECHNICAL REVIEW (SETR) ON A COMMERCIAL DERIVATIVE AIRCRAFT (CDA) PROGRAM

    Science.gov (United States)

    2017-09-01

    VERIFICATION AND SYSTEMS ENGINEERING TECHNICAL REVIEW (SETR) ON A COMMERCIAL DERIVATIVE AIRCRAFT (CDA) PROGRAM by Theresa L. Thomas September... ENGINEERING TECHNICAL REVIEW (SETR) ON A COMMERCIAL DERIVATIVE AIRCRAFT (CDA) PROGRAM 5. FUNDING NUMBERS 6. AUTHOR(S) Theresa L. Thomas 7...CODE 13. ABSTRACT (maximum 200 words) The Naval Air Systems Command (NAVAIR) systems engineering technical review (SETR) process does not

  12. Aviation Trends Related to Atmospheric Environment Safety Technologies Project Technical Challenges

    Science.gov (United States)

    Reveley, Mary S.; Withrow, Colleen A.; Barr, Lawrence C.; Evans, Joni K.; Leone, Karen M.; Jones, Sharon M.

    2014-01-01

    Current and future aviation safety trends related to the National Aeronautics and Space Administration's Atmospheric Environment Safety Technologies Project's three technical challenges (engine icing characterization and simulation capability; airframe icing simulation and engineering tool capability; and atmospheric hazard sensing and mitigation technology capability) were assessed by examining the National Transportation Safety Board (NTSB) accident database (1989 to 2008), incidents from the Federal Aviation Administration (FAA) accident/incident database (1989 to 2006), and literature from various industry and government sources. The accident and incident data were examined for events involving fixed-wing airplanes operating under Federal Aviation Regulation (FAR) Parts 121, 135, and 91 for atmospheric conditions related to airframe icing, ice-crystal engine icing, turbulence, clear air turbulence, wake vortex, lightning, and low visibility (fog, low ceiling, clouds, precipitation, and low lighting). Five future aviation safety risk areas associated with the three AEST technical challenges were identified after an exhaustive survey of a variety of sources and include: approach and landing accident reduction, icing/ice detection, loss of control in flight, super density operations, and runway safety.

  13. Advanced Mixed Waste Treatment Project melter system preliminary design technical review meeting

    International Nuclear Information System (INIS)

    Eddy, T.L.; Raivo, B.D.; Soelberg, N.R.; Wiersholm, O.

    1995-02-01

    The Idaho National Engineering Laboratory Advanced Mixed Waste Treatment Project sponsored a plasma are melter technical design review meeting to evaluate high-temperature melter system configurations for processing heterogeneous alpha-contaminated low-level radioactive waste (ALLW). Thermal processing experts representing Department of Energy contractors, the Environmental Protection Agency, and private sector companies participated in the review. The participants discussed issues and evaluated alternative configurations for three areas of the melter system design: plasma torch melters and graphite arc melters, offgas treatment options, and overall system configuration considerations. The Technical Advisory Committee for the review concluded that graphite arc melters are preferred over plasma torch melters for processing ALLW. Initiating involvement of stakeholders was considered essential at this stage of the design. For the offgas treatment system, the advisory committee raised the question whether to a use wet-dry or a dry-wet system. The committee recommended that the waste stream characterization, feed preparation, and the control system are essential design tasks for the high-temperature melter treatment system. The participants strongly recommended that a complete melter treatment system be assembled to conduct tests with nonradioactive surrogate waste material. A nonradioactive test bed would allow for inexpensive design and operational changes prior to assembling a system for radioactive waste treatment operations

  14. Advanced Mixed Waste Treatment Project melter system preliminary design technical review meeting

    Energy Technology Data Exchange (ETDEWEB)

    Eddy, T.L.; Raivo, B.D.; Soelberg, N.R.; Wiersholm, O.

    1995-02-01

    The Idaho National Engineering Laboratory Advanced Mixed Waste Treatment Project sponsored a plasma are melter technical design review meeting to evaluate high-temperature melter system configurations for processing heterogeneous alpha-contaminated low-level radioactive waste (ALLW). Thermal processing experts representing Department of Energy contractors, the Environmental Protection Agency, and private sector companies participated in the review. The participants discussed issues and evaluated alternative configurations for three areas of the melter system design: plasma torch melters and graphite arc melters, offgas treatment options, and overall system configuration considerations. The Technical Advisory Committee for the review concluded that graphite arc melters are preferred over plasma torch melters for processing ALLW. Initiating involvement of stakeholders was considered essential at this stage of the design. For the offgas treatment system, the advisory committee raised the question whether to a use wet-dry or a dry-wet system. The committee recommended that the waste stream characterization, feed preparation, and the control system are essential design tasks for the high-temperature melter treatment system. The participants strongly recommended that a complete melter treatment system be assembled to conduct tests with nonradioactive surrogate waste material. A nonradioactive test bed would allow for inexpensive design and operational changes prior to assembling a system for radioactive waste treatment operations.

  15. LLNL/YMP Waste Container Fabrication and Closure Project; GFY technical activity summary

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1990-10-01

    The Department of Energy`s Office of Civilian Radioactive Waste Management (OCRWM) Program is studying Yucca Mountain, Nevada as a suitable site for the first US high-level nuclear waste repository. Lawrence Livermore National Laboratory (LLNL) has the responsibility for designing and developing the waste package for the permanent storage of high-level nuclear waste. This report is a summary of the technical activities for the LLNL/YMP Nuclear Waste Disposal Container Fabrication and Closure Development Project. Candidate welding closure processes were identified in the Phase 1 report. This report discusses Phase 2. Phase 2 of this effort involved laboratory studies to determine the optimum fabrication and closure processes. Because of budget limitations, LLNL narrowed the materials for evaluation in Phase 2 from the original six to four: Alloy 825, CDA 715, CDA 102 (or CDA 122) and CDA 952. Phase 2 studies focused on evaluation of candidate material in conjunction with fabrication and closure processes.

  16. Trace of the 'Fugen' project. Its technical development results to be succeeded

    International Nuclear Information System (INIS)

    Ishikure, Kenkichi; Kikuchi, Saburo; Kobayashi, Hiromasa; Hino, Minoru

    2003-01-01

    A prototype reactor of the advanced thermal reactor (ATR), 'Fugen' will be finished its operation on March, 2003. And, the 'Fugen' project advanced by self technology development has largely contributed to nuclear energy development in Japan at various fields. Nuclear energy is now laid at change of its environment without previous experiences, such as relaxation of regulation, liberalization of electric powers, cost down, and so on. A history on challenge of self technology development must be valuable experiences essential for present and future nuclear energy. To succeed results with and without shapes obtained by the 'Fugen', to generation sharing coming future, here were investigated verifications on its technical results and self technology development results and how their results are activated to future. (G.K.)

  17. TECHNICAL BASIS FOR VENTILATION REQUIREMENTS IN TANK FARMS OPERATING SPECIFICATIONS DOCUMENTS

    Energy Technology Data Exchange (ETDEWEB)

    BERGLIN, E J

    2003-06-23

    This report provides the technical basis for high efficiency particulate air filter (HEPA) for Hanford tank farm ventilation systems (sometimes known as heating, ventilation and air conditioning [HVAC]) to support limits defined in Process Engineering Operating Specification Documents (OSDs). This technical basis included a review of older technical basis and provides clarifications, as necessary, to technical basis limit revisions or justification. This document provides an updated technical basis for tank farm ventilation systems related to Operation Specification Documents (OSDs) for double-shell tanks (DSTs), single-shell tanks (SSTs), double-contained receiver tanks (DCRTs), catch tanks, and various other miscellaneous facilities.

  18. The Test Blanket Modules project in Europe: From the strategy to the technical plan over next ten years

    International Nuclear Information System (INIS)

    Poitevin, Y.; Zmitko, M.; Orco, G. dell; Laesser, R.; Diegele, E.; Sundstroem, J.; Boccaccini, L.; Salavy, J.-F.

    2006-01-01

    The testing of Breeding Blanket concepts in ITER is recognized as an essential milestone in the development of a future reactor ensuring tritium self-sufficiency, extraction of high grade heat and electricity production. Europe is currently developing two reference breeding blankets for DEMO reactor specifications that will be tested in ITER: the Helium-Cooled Lithium-Lead (HCLL) blanket which uses the eutectic Pb-15. 7 Li as both breeder and neutron multiplier, and the Helium-Cooled Pebble-Bed (HCPB) blanket which features lithiated ceramic pebbles (Li 4 SiO 4 or Li 2 TiO 3 ) as breeder and beryllium pebbles as neutron multiplier. Both blankets are using the pressurized He technology for heat extraction (8 MPa, inlet/outlet temperature 300/500 o C) and a 9% CrWVTa Reduced Activation Ferritic Martensitic (RAFM) steel as structural material, the EUROFER. Referring to the so called '' fast-track '' EU scenario, those concepts are intended to be tested in ITER, getting the maximum of information required for launching the DEMO blanket design and construction after the first 10 years of ITER operation. For that, the EU has adopted a blanket testing strategy based on the development of Test Blanket Modules (TBMs) that are expected to use DEMO relevant technologies and are designed for each ITER plasma phase to optimize the feedback and to avoid any impact on ITER availability. Following the decision on ITER construction, the EU has reviewed and detailed the fundamental elements for an implementation of the future EU TBMs Project aimed at delivering TBMs Systems to ITER under suitable schedule and acceptance standards. For that the following items have been analyzed in detail and are reported in the present paper: · Impact of the ITER environment (design, standards, schedule, operational scheme) on the TBM systems design and development plan · Project technical plan with focus on the next ten years up to the installation of the first TBMs in ITER · Project risk

  19. Technical requirements for the ASME PRA standard for nuclear power plant applications

    International Nuclear Information System (INIS)

    Fleming, Karl N.; Bernsen, Sidney A.; Simard, Ronald L.

    2000-01-01

    In 1998 the American Society of Mechanical Engineers (ASME) formed the Committee on Nuclear Risk Management (CNRM) and a Project Team to develop a standard on PRAs for use in risk informed applications. This ASME standard is being developed to help provide an adequate level of quality in PRAs that are being used to support ASME initiatives to risk informed in-service inspection (ISI) and in-service testing (IST) of nuclear power plant components. A related need supported by the industry and the U.S. Nuclear Regulatory Commission is to reduce the level of effort that is being expended in pilot applications of risk informed initiatives to address questions about the sufficiency of quality in the supporting PRA models. The purpose of this paper is to discuss the authors' views on some of the technical issues that were encountered in the effort to develop the ASME PRA standard. Draft 12 of this standard has been issued for comment, and is currently being finalized with the aim of releasing the standard in early 2001. (author)

  20. Technical requirements for the actinide source-term waste test program

    Energy Technology Data Exchange (ETDEWEB)

    Phillips, M.L.F.; Molecke, M.A.

    1993-10-01

    This document defines the technical requirements for a test program designed to measure time-dependent concentrations of actinide elements from contact-handled transuranic (CH TRU) waste immersed in brines similar to those found in the underground workings of the Waste Isolation Pilot Plant (WIPP). This test program wig determine the influences of TRU waste constituents on the concentrations of dissolved and suspended actinides relevant to the performance of the WIPP. These influences (which include pH, Eh, complexing agents, sorbent phases, and colloidal particles) can affect solubilities and colloidal mobilization of actinides. The test concept involves fully inundating several TRU waste types with simulated WIPP brines in sealed containers and monitoring the concentrations of actinide species in the leachate as a function of time. The results from this program will be used to test numeric models of actinide concentrations derived from laboratory studies. The model is required for WIPP performance assessment with respect to the Environmental Protection Agency`s 40 CFR Part 191B.

  1. Westinghouse Hanford Company safety analysis reports and technical safety requirements upgrade program

    International Nuclear Information System (INIS)

    Busche, D.M.

    1995-09-01

    During Fiscal Year 1992, the US Department of Energy, Richland Operations Office (RL) separately transmitted the following US Department of Energy (DOE) Orders to Westinghouse Hanford Company (WHC) for compliance: DOE 5480.21, ''Unreviewed Safety Questions,'' DOE 5480.22, ''Technical Safety Requirements,'' and DOE 5480.23, ''Nuclear Safety Analysis Reports.'' WHC has proceeded with its impact assessment and implementation process for the Orders. The Orders are closely-related and contain some requirements that are either identical, similar, or logically-related. Consequently, WHC has developed a strategy calling for an integrated implementation of the three Orders. The strategy is comprised of three primary objectives, namely: Obtain DOE approval of a single list of DOE-owned and WHC-managed Nuclear Facilities, Establish and/or upgrade the ''Safety Basis'' for each Nuclear Facility, and Establish a functional Unreviewed Safety Question (USQ) process to govern the management and preservation of the Safety Basis for each Nuclear Facility. WHC has developed policy-revision and facility-specific implementation plans to accomplish near-term tasks associated with the above strategic objectives. This plan, which as originally submitted in August 1993 and approved, provided an interpretation of the new DOE Nuclear Facility definition and an initial list of WHC-managed Nuclear Facilities. For each current existing Nuclear Facility, existing Safety Basis documents are identified and the plan/status is provided for the ISB. Plans for upgrading SARs and developing TSRs will be provided after issuance of the corresponding Rules

  2. Technical requirements for the actinide source-term waste test program

    International Nuclear Information System (INIS)

    Phillips, M.L.F.; Molecke, M.A.

    1993-10-01

    This document defines the technical requirements for a test program designed to measure time-dependent concentrations of actinide elements from contact-handled transuranic (CH TRU) waste immersed in brines similar to those found in the underground workings of the Waste Isolation Pilot Plant (WIPP). This test program wig determine the influences of TRU waste constituents on the concentrations of dissolved and suspended actinides relevant to the performance of the WIPP. These influences (which include pH, Eh, complexing agents, sorbent phases, and colloidal particles) can affect solubilities and colloidal mobilization of actinides. The test concept involves fully inundating several TRU waste types with simulated WIPP brines in sealed containers and monitoring the concentrations of actinide species in the leachate as a function of time. The results from this program will be used to test numeric models of actinide concentrations derived from laboratory studies. The model is required for WIPP performance assessment with respect to the Environmental Protection Agency's 40 CFR Part 191B

  3. Reflecting socio-technical combinations in radioactive waste management. Results from the InSOTEC European research project

    International Nuclear Information System (INIS)

    Kallenbach-Herbert, Beate; Bergmans, Anne; Martell, Meritxell; Schroeder, Jantine

    2015-01-01

    InSOTEC is a three-year collaborative social sciences research project funded under the European Atomic Energy Community's 7th Framework Programme FP7. The project aims to generate a better understanding of the complex interplay between the technical and the social in the context of geological disposal of radioactive waste. In doing so, InSOTEC has moved beyond the social and technical division that is frequently being found in this context by - investigating the consideration of social sciences and the recognition of socio-technical combinations in research programs on geological disposal, - analyzing the socio-technical entanglement in selected contexts like siting, reversibility and retrievability, demonstrating safety and technology transfer on the basis of case studies, and - exploring the integration of diverse stakeholders in technology oriented networks. The analyses reveal that activities in the context of geological disposal, whether related to research, planning, siting etc., rather support the divide of social and technical aspects than fostering the consideration of their entanglement. Reasons identified for this are manifold. The wish to reduce complexity by focusing stakeholder involvement on social questions and fixing the technical part ''when acceptance is reached'' is only one of them. However, the analyses also show that over the long timescales of repository planning and implementation, robust management strategies must provide the flexibility to adapt to both technical and social developments and demands. Understanding the socio-technical interplay and creating structures for its consideration provides the basis for dealing with this challenge. This presentation will focus on the main findings of the InSOTEC project with regard to the consideration of socio-technical combinations in practice. These insights are currently under development and will be finalized at the end of the project in June 2014. We will reflect on

  4. Reflecting socio-technical combinations in radioactive waste management. Results from the InSOTEC European research project

    Energy Technology Data Exchange (ETDEWEB)

    Kallenbach-Herbert, Beate [Oeko-Institut e.V., Darmstadt (Germany); Bergmans, Anne [Antwerp Univ. (Belgium); Martell, Meritxell [Merience Strategic Thinking, Olerdola (Spain); Schroeder, Jantine [Antwerp Univ. (Belgium); SCK - CEN, Mol (Belgium)

    2015-07-01

    InSOTEC is a three-year collaborative social sciences research project funded under the European Atomic Energy Community's 7th Framework Programme FP7. The project aims to generate a better understanding of the complex interplay between the technical and the social in the context of geological disposal of radioactive waste. In doing so, InSOTEC has moved beyond the social and technical division that is frequently being found in this context by - investigating the consideration of social sciences and the recognition of socio-technical combinations in research programs on geological disposal, - analyzing the socio-technical entanglement in selected contexts like siting, reversibility and retrievability, demonstrating safety and technology transfer on the basis of case studies, and - exploring the integration of diverse stakeholders in technology oriented networks. The analyses reveal that activities in the context of geological disposal, whether related to research, planning, siting etc., rather support the divide of social and technical aspects than fostering the consideration of their entanglement. Reasons identified for this are manifold. The wish to reduce complexity by focusing stakeholder involvement on social questions and fixing the technical part ''when acceptance is reached'' is only one of them. However, the analyses also show that over the long timescales of repository planning and implementation, robust management strategies must provide the flexibility to adapt to both technical and social developments and demands. Understanding the socio-technical interplay and creating structures for its consideration provides the basis for dealing with this challenge. This presentation will focus on the main findings of the InSOTEC project with regard to the consideration of socio-technical combinations in practice. These insights are currently under development and will be finalized at the end of the project in June 2014. We will reflect on

  5. Puget Sound Tidal Energy In-Water Testing and Development Project Final Technical Report

    Energy Technology Data Exchange (ETDEWEB)

    Collar, Craig W

    2012-11-16

    others. All required permit and license applications were completed and submitted under this award, including a Final License Application for a pilot hydrokinetic license from the Federal Energy Regulatory Commission. The tasks described above have brought the project through all necessary requirements to construct a tidal pilot project in Admiralty Inlet with the exception of final permit and license approvals, and the selection of a general contractor to perform project construction.

  6. Projects at the Western Environmental Technology Office. Quarterly technical progress report, July 1, 1995--September 30, 1995

    International Nuclear Information System (INIS)

    1996-01-01

    The goal of this project is to demonstrate the technical and economic feasibility of commercializing a biotechnology that uses plants to remediate soils, sediments, surface waters, and groundwaters contaminated by heavy metals and radionuclides. This technology, known as phytoremediation, is particularly suited to remediation of soils or water where low levels of contaminants are widespread. Project objectives are to provide an accurate estimate of the capability and rate of phytoremediation for removal of contaminants of concern from soils and groundwaters at Department of Energy (DOE) sites and to develop data suitable for engineering design and economic feasibility evaluations, including methods for destruction or final disposition of plants containing contaminants of concern. The bioremediation systems being evaluated could be less expensive than soil removal and treatment systems, given the areal extent and topography of sites under consideration and the investment of energy and money in soil-moving and -treating processes. In situ technology may receive regulatory acceptance more easily than ex situ treatments requiring excavation, processing, and replacement of surface soils. In addition, phytoremediation may be viable for cleanup of contaminated waters, either as the primary treatment or the final polishing stage, depending on the contaminant concentrations and process economics considerations

  7. Projects at the Western Environmental Technology Office. Quarterly technical progress report, July 1, 1995--September 30, 1995

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-01-01

    The goal of this project is to demonstrate the technical and economic feasibility of commercializing a biotechnology that uses plants to remediate soils, sediments, surface waters, and groundwaters contaminated by heavy metals and radionuclides. This technology, known as phytoremediation, is particularly suited to remediation of soils or water where low levels of contaminants are widespread. Project objectives are to provide an accurate estimate of the capability and rate of phytoremediation for removal of contaminants of concern from soils and groundwaters at Department of Energy (DOE) sites and to develop data suitable for engineering design and economic feasibility evaluations, including methods for destruction or final disposition of plants containing contaminants of concern. The bioremediation systems being evaluated could be less expensive than soil removal and treatment systems, given the areal extent and topography of sites under consideration and the investment of energy and money in soil-moving and -treating processes. In situ technology may receive regulatory acceptance more easily than ex situ treatments requiring excavation, processing, and replacement of surface soils. In addition, phytoremediation may be viable for cleanup of contaminated waters, either as the primary treatment or the final polishing stage, depending on the contaminant concentrations and process economics considerations.

  8. Water balance and fertigation for crop improvement in West Asia. Results of a technical co-operation project

    International Nuclear Information System (INIS)

    2002-01-01

    Mediterranean countries have a severe shortage of water resources for agricultural, municipal and industrial purposes. This situation is aggravated daily due to the rapidly increasing population in the area. Agriculture is the biggest consumer of water with about 80% of the renewable resource used for irrigation. Traditional irrigation methods are highly inefficient: only about one-third of the applied water is actually transpired by the crops. Clearly, there is great scope for improved irrigation management. Intensification of agricultural production to meet growing market demand requires the simultaneous application of irrigation water and fertilizers. Application of fertilizer in drip irrigation (fertigation) is an effective way to promote efficient use of these scarce and expensive resources. There is widespread interest in Mediterranean countries in fertigation. Nevertheless, information on the form and concentration of the nutrients required for different crops is presently inadequate. Moreover, the low fertilizer recoveries due to extensive fertilization practiced during the last few decades have created serious agricultural and environmental problems. High nitrate concentrations in groundwater and deterioration of some important quality parameters of agricultural products are the main concerns. Recognizing the potential role of nuclear techniques in identifying improved water and fertilizer management practices, the IAEA implemented two regional technical co-operation projects during the period 1995-2000 with eight participating countries from the West Asia region: The Islamic Republic of Iran, Jordan, Lebanon, Saudi Arabia, the Syria Arab Republic, Turkey, United Arab Emirates and Yemen. The main objective was to establish water balance and fertigation practices using nuclear techniques, with a view to improving crop production in arid and semi-arid zones. The projects aimed to compare the following parameters under conventional fertilizer and water

  9. Project Manager’s Guide to the Scientific and Technical Information (STINFO) Program and Technical Publications Process

    Science.gov (United States)

    1993-12-01

    Iaporta .. y be definitive for the tubjoct proaentod, exploratory in natura, or an evaluation of critical Aubayato• or of technical problema , 4...International Security 9 Social and Natural Science Studies Field 41 Edit: (Type 3) -Entry of an invalid code when Performance Type is "C" or "M" will...analysis SF Foreign area social science research SP Foreign area policy planAing research BF Identifies databases with data on foreign forces or

  10. Improvement of technical measures to detect and respond to illicit trafficking of nuclear and radioactive materials [Results of a coordinated research project 2003-2006

    International Nuclear Information System (INIS)

    2008-07-01

    This publication summarizes the research conducted during an IAEA Coordinated Research Project (CRP) undertaken to address technical and operational difficulties in the detection of and response to illicit trafficking of nuclear material. Equipment to detect illicit trafficking of nuclear and radioactive materials at borders has specific technical and operational requirements that are very different from equipment used in other radiation monitoring cases. Automated and manual measurements need to be done in the field, often outdoors, at land or sea borders, crossing points or airports. The free flow of goods and passengers must not be impacted, thus requiring that the measurement time be short. The design needs to take into account that the users of the equipment are not experts in radiation detection; thus the results of the measurements should be easy to understand

  11. Accelerator technical design report for high-intensity proton accelerator facility project, J-PARC

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2003-03-01

    This report presents the detail of the technical design of the accelerators for the High-Intensity Proton Accelerator Facility Project, J-PARC. The accelerator complex comprises a 400-MeV room-temperature linac (600-MeV superconducting linac), 3-GeV rapid-cycling synchrotron (RCS), and a 50-GeV synchrotron (MR). The 400-MeV beam is injected to the RCS, being accelerated to 3 GEV. The 1-MW beam thus produced is guided to the Materials Life Science Experimental Facility, with both the pulsed spallation neutron source and muon source. A part of the beam is transported to the MR, which provides the 0.75-MW beam to either the Nuclear and Fundamental Particle Experimental Facility or the Neutrino Production Target. On the other hand, the beam accelerated to 600 MeV by the superconducting linac is used for the Nuclear Waster Transmutation Experiment. In this way, this facility is unique, being multipurpose one, including many new inventions and Research and Development Results. This report is based upon the accomplishments made by the Accelerator Group and others of the Project Team, which is organized on the basis of the Agreement between JAERI and KEK on the Construction and Research and Development of the High-Intensity Proton Accelerator Facility. (author)

  12. TECHNICAL AND ECONOMIC SUBSTANTIATION OF PROJECTS OF THE AFFORDABLE HOUSING CONSTRUCTION

    Directory of Open Access Journals (Sweden)

    KRAVCHUNOVSKA T. S.

    2015-12-01

    Full Text Available Summary. Problem statement. The development of inhabitant locality of Ukraine is characterized by significant differences in levels of socio and economic development. An excessive concentration of population and industry in large cities, inefficient, slow development of most medium and small cities, towns and villages, considerable territorial disproportions of economic development of the country, considerable shortcomings in the territorial organization of society are observed. At the same time the tendency of the total area of increasing of inhabitant locality. The lands are used inefficiently. Among the most common problems of inhabitant locality is the housing problem. When making a decision on the design of affordable housing construction is one of the most important stages in the development of the technique and economic substantiation of the project is determination of the advisability and effectiveness of construction. The substantiation of advisability and effectiveness of affordable housing based on the definition of technical and economic indicators of projects, one of the most important among them is the cost, in its calculation is necessary to take into account the influence of organizational and technological factors, reflecting the features of construction in condition of compacted construction. Purpose. Development of methodical recommendations on substantiation of cost construction of affordable housing in the conditions of compacted construction. Conclusion. To provide a processing and the analysis of data is necessary development of the applied software on the basis of the developed block scheme of justification of cost construction of affordable housing.

  13. Supervision and technical coordination of the German activities in the 2D/3D-project

    International Nuclear Information System (INIS)

    Mayinger, F.

    1988-01-01

    The German Federal Minister for Research and Technology, the Japanese Atomic Energy Bureau, represented by the Japan Atomic Energy Research Institute (JAERI) and the United States Nuclear Regulatory Commission (USNRC) made a contract to cooperate in the field of nuclear safety research with the aim to improve and to guarantee the safety of water-cooled nuclear reactors on an international basis by joint research activities in the 2D/3D-project. The necessity for these research activities results from gaps in the status of knowledge for a best-estimate analysis in emergency core cooling, from the legally established duty to minimize the radioactive emission to the environment as consequence of an incident, and from the effort to optimize the safeguard systems of nuclear reactors continuously and steadily. The activities which were performed in the frame of this project concentrated on the coordination of the experimental and theoretical work, as well as on the technical supervision with respect to an efficient attainment of the internationally aspired research aim and to an optimal adjustment with respect to the emergency core cooling problems of pressurized water reactors. (orig.) [de

  14. Technical basis and programmatic requirements for large block testing of coupled thermal-mechanical-hydrological-chemical processes

    International Nuclear Information System (INIS)

    Lin, Wunan.

    1993-09-01

    This document contains the technical basis and programmatic requirements for a scientific investigation plan that governs tests on a large block of tuff for understanding the coupled thermal- mechanical-hydrological-chemical processes. This study is part of the field testing described in Section 8.3.4.2.4.4.1 of the Site Characterization Plan (SCP) for the Yucca Mountain Project. The first, and most important objective is to understand the coupled TMHC processes in order to develop models that will predict the performance of a nuclear waste repository. The block and fracture properties (including hydrology and geochemistry) can be well characterized from at least five exposed surfaces, and the block can be dismantled for post-test examinations. The second objective is to provide preliminary data for development of models that will predict the quality and quantity of water in the near-field environment of a repository over the current 10,000 year regulatory period of radioactive decay. The third objective is to develop and evaluate the various measurement systems and techniques that will later be employed in the Engineered Barrier System Field Tests (EBSFT)

  15. An analysis of Technical Security Control Requirements For Digital I and C Systems in Nuclear Power Plants

    International Nuclear Information System (INIS)

    Song, Jaegu; Lee, Jungwoon; Park, Geeyong; Kwon, Keechoon; Lee, Dongyoung; Lee, Cheolkwon

    2013-01-01

    Instrumentation and control systems in nuclear power plants have been digitalized for the purpose of maintenance and precise operation. This digitalization, however, brings out issues related to cyber security. In the most recent past, international standard organizations, regulatory institutes, and research institutes have performed a number of studies addressing these systems cyber security. In order to provide information helpful to the system designers in their application of cyber security for the systems, this paper presents methods and considerations to define attack vectors in a target system, to review and select the requirements in the Regulatory Guide 5.71, and to integrate the results to identify applicable technical security control requirements. In this study, attack vectors are analyzed through the vulnerability analyses and penetration tests with a simplified safety system, and the elements of critical digital assets acting as attack vectors are identified. Among the security control requirements listed in Appendices B and C to Regulatory Guide 5.71, those that should be implemented into the systems are selected and classified in groups of technical security control requirements using the results of the attack vector analysis. For the attack vector elements of critical digital assets, all the technical security control requirements are evaluated to determine whether they are applicable and effective, and considerations in this evaluation are also discussed. The technical security control requirements in three important categories of access control, monitoring and logging, and encryption are derived and grouped according to the elements of attack vectors as results for the sample safety system

  16. An analysis of Technical Security Control Requirements For Digital I and C Systems in Nuclear Power Plants

    Energy Technology Data Exchange (ETDEWEB)

    Song, Jaegu; Lee, Jungwoon; Park, Geeyong; Kwon, Keechoon; Lee, Dongyoung; Lee, Cheolkwon [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2013-10-15

    Instrumentation and control systems in nuclear power plants have been digitalized for the purpose of maintenance and precise operation. This digitalization, however, brings out issues related to cyber security. In the most recent past, international standard organizations, regulatory institutes, and research institutes have performed a number of studies addressing these systems cyber security. In order to provide information helpful to the system designers in their application of cyber security for the systems, this paper presents methods and considerations to define attack vectors in a target system, to review and select the requirements in the Regulatory Guide 5.71, and to integrate the results to identify applicable technical security control requirements. In this study, attack vectors are analyzed through the vulnerability analyses and penetration tests with a simplified safety system, and the elements of critical digital assets acting as attack vectors are identified. Among the security control requirements listed in Appendices B and C to Regulatory Guide 5.71, those that should be implemented into the systems are selected and classified in groups of technical security control requirements using the results of the attack vector analysis. For the attack vector elements of critical digital assets, all the technical security control requirements are evaluated to determine whether they are applicable and effective, and considerations in this evaluation are also discussed. The technical security control requirements in three important categories of access control, monitoring and logging, and encryption are derived and grouped according to the elements of attack vectors as results for the sample safety system.

  17. Analysis of technical-economic requirements for the construction of a solar power plant on the roof of the business building of the Electrical Engineering Institute 'Nikola Tesla'

    Directory of Open Access Journals (Sweden)

    Grbić Maja

    2014-01-01

    Full Text Available This paper presents an analysis of the technical-economic requirements for the construction of a solar power plant on the roof of the business building of the Electrical Engineering Institute 'Nikola Tesla' in Belgrade. Calculation of solar irradiation is performed and the conceptual design of the disposition of solar panels on the roof of the building is shown as well as their connections to the inverters. Conditions for connecting the plant to the distribution network are checked and an economic analysis of the project is performed.

  18. IFMIF – Layout and arrangement of cells according to requirements of technical logistics, reliability and remote handling

    International Nuclear Information System (INIS)

    Mittwollen, Martin; Eilert, Dirk; Kubaschewski, Martin; Madzharov, Vladimir; Tian Kuo

    2012-01-01

    Highlights: ► In a first approach, layout and arrangement of the cells followed a predetermined plant layout. ► Disadvantages in technical logistics, reliability and remote handling have been detected. ► Deliberation with project teams opened space for improvements. ► Layout and arrangement of cells have been improved by simplification of design. ► Speed and reliability have been increased significantly. - Abstract: The International Fusion Material Irradiation Facility (IFMIF) is designed to study and qualify structural and functional materials which shall be used in future fusion nuclear power plants. During the current engineering validation and engineering design activities (EVEDA) phase the development of e.g. an optimized layout and arrangement of the cells (Access Cell, Test Cell, and Test Module Handling Cells) is of major interest. After defining different functions for the individual cells like e.g. large scale/fine scale disassembling of test modules a first layout has been developed. This design followed requirements like having a minimum of carrier changes to avoid sources of failures. On the other hand it has had to be a compact arrangement of cells due to restrictions from plant layout. A row of changes of transfer direction, and different crane systems were the consequence. Constructive discussion with project team results in the statement, that for reasons of being reliable and fast, layout and arrangement of cells goes first, plant layout then will follow. The chance for big improvements was taken and the result was a simplified design with strong reduced number of functional elements, and increased reliability and speed.

  19. Assessment of technical risks and R and D requirements for a magnetic confinement fusion fuel system. Final report

    International Nuclear Information System (INIS)

    DeFreece, D.A.

    1983-11-01

    This report documents a specific use and results of a novel technique for assessing the technical risks associated with the hardware development of a possible future commercial fusion power plant fuel system. Technical risk is defined as the risk that a particular technology or component which is currently under development will not achieve a set of required technical specifications. A technical risk assessment is the quantification of this risk. This Technical Risk Assessment (TRA) methodology was applied to a deuterium-tritium fuel system for a magnetic-confinement fusion power plant. The fuel system is defined to support a generic commercial reactor with at least two viable options for each critical subsystem. Each subsystem option is defined in detail including nominal performance requirements and subsystem interfaces. Subsystem experts were canvassed to obtain values for past, present and future technical performance parameters for each of the subsystem options. These forecasts are presented as probabilities of achieving given levels of performance in specific time periods for assumed funding scenarios. Several funding scenarios were examined to discern whether performance limitations are caused by funding or technology. A computerized Fuel System simulation is described which uses these subsystem performance parameter forecasts as inputs

  20. Technical requirements for implementation of an individual monitoring service for evaluation of operational quantity HP(10) using thermoluminescent dosimetry

    International Nuclear Information System (INIS)

    Francisco, Adelaide Benedita Armando

    2016-01-01

    This work aims to establish technical requirements for the development of a TLDs system for the assessment of operational quantity H P (10), in order to implement an external individual monitoring service in countries who do not have. This allows a better understanding of the technic and the thermoluminescent dosimetry system, thus contributing to identify the technical criteria to be followed by a dosimetry laboratory and evaluation of the dosimetric system performance. For this, the review of the specific literature of the dosimetry field was conducted and later the type and performance tests that must be followed by a dosimetric system were reproduced in practice. In additional was made a analysis of internationals standards norms and the technical regulation used in Brazil, to define the essentials type testes to a dosimetric system. To check the performance of a dosimetry system, a performance analysis of the Brazilian TLDs system was carried out over the past 6 years using the trumpet curve, where it was observed that most of TLDs system, in this review period, were approved and have excellent performance. The technical requirements for the development of a thermoluminescent dosimetry system ensure that the system provides technically reliable results and allow demonstration of compliance with the standard criteria established by national and international standards, and the implementation of the dosimetry system, is verified the compliance of the annual doses limits set for occupationally exposed. (author)

  1. Requirements for the project management in the client / engineering contractor relationship

    International Nuclear Information System (INIS)

    Hack, W.L.

    1995-01-01

    Investment projects impose a multitude of requirements upon clients and engineering contractors to cope with the management of project inherent conflicts. The paper reviews certain aspects on why such conflicts develop, and how they may be resolved. (orig.)

  2. 78 FR 53712 - Surface Transportation Project Delivery Program Application Requirements

    Science.gov (United States)

    2013-08-30

    ... application, and discussion of classes of multimodal projects that may be best handled on a case-by-case basis... submissions; a paragraph discussing the joint application process; and a paragraph authorizing the Agencies to... early enough to allow for a joint application of the Secretary's responsibilities before the...

  3. Which non-technical skills do junior doctors require to prescribe safely? A systematic review.

    Science.gov (United States)

    Dearden, Effie; Mellanby, Edward; Cameron, Helen; Harden, Jeni

    2015-12-01

    Prescribing errors are a major source of avoidable morbidity and mortality. Junior doctors write most in-hospital prescriptions and are the least experienced members of the healthcare team. This puts them at high risk of error and makes them attractive targets for interventions to improve prescription safety. Error analysis has shown a background of complex environments with multiple contributory conditions. Similar conditions in other high risk industries, such as aviation, have led to an increased understanding of so-called human factors and the use of non-technical skills (NTS) training to try to reduce error. To date no research has examined the NTS required for safe prescribing. The aim of this review was to develop a prototype NTS taxonomy for safe prescribing, by junior doctors, in hospital settings. A systematic search identified 14 studies analyzing prescribing behaviours and errors by junior doctors. Framework analysis was used to extract data from the studies and identify behaviours related to categories of NTS that might be relevant to safe and effective prescribing performance by junior doctors. Categories were derived from existing literature and inductively from the data. A prototype taxonomy of relevant categories (situational awareness, decision making, communication and team working, and task management) and elements was constructed. This prototype will form the basis of future work to create a tool that can be used for training and assessment of medical students and junior doctors to reduce prescribing error in the future. © 2015 The British Pharmacological Society.

  4. Technical meeting of project counterparts on 'Cyclotron production of Iodine-123'. Report

    International Nuclear Information System (INIS)

    2002-01-01

    Several cyclotron laboratory facilities are very much interested in the production of Iodine-123 for medical applications in view of its optimal physical and chemical properties. Some of these countries have in the past used the solid target technology based on utilization of enriched Tellurium targets and are currently involved in the development of enriched Xenon-124 gas targets to improved radionuclidic purity as required by the needs of modern nuclear medicine. With the purpose of discussing the advances in the later route of production and to foster mutual co-operation among the developing countries interested in this technology, a meeting was convened with the participation of scientists from Argentina, Brazil, Iran, Korea and Syria. A scientist from the United States was also invited as an expert to provide advise on particular aspects of the technology. This publication contains as an annex technical reports from the participating institutions. All of these reports have been separately indexed and provided with abstracts

  5. Fear extinction requires infralimbic cortex projections to the basolateral amygdala.

    Science.gov (United States)

    Bloodgood, Daniel W; Sugam, Jonathan A; Holmes, Andrew; Kash, Thomas L

    2018-03-06

    Fear extinction involves the formation of a new memory trace that attenuates fear responses to a conditioned aversive memory, and extinction impairments are implicated in trauma- and stress-related disorders. Previous studies in rodents have found that the infralimbic prefrontal cortex (IL) and its glutamatergic projections to the basolateral amygdala (BLA) and basomedial amygdala (BMA) instruct the formation of fear extinction memories. However, it is unclear whether these pathways are exclusively involved in extinction, or whether other major targets of the IL, such as the nucleus accumbens (NAc) also play a role. To address this outstanding issue, the current study employed a combination of electrophysiological and chemogenetic approaches in mice to interrogate the role of IL-BLA and IL-NAc pathways in extinction. Specifically, we used patch-clamp electrophysiology coupled with retrograde tracing to examine changes in neuronal activity of the IL and prelimbic cortex (PL) projections to both the BLA and NAc following fear extinction. We found that extinction produced a significant increase in the intrinsic excitability of IL-BLA projection neurons, while extinction appeared to reverse fear-induced changes in IL-NAc projection neurons. To establish a causal counterpart to these observations, we then used a pathway-specific Designer Receptors Exclusively Activated by Designer Drugs (DREADD) strategy to selectively inhibit PFC-BLA projection neurons during extinction acquisition. Using this approach, we found that DREADD-mediated inhibition of PFC-BLA neurons during extinction acquisition impaired subsequent extinction retrieval. Taken together, our findings provide further evidence for a critical contribution of the IL-BLA neural circuit to fear extinction.

  6. Experimentation on accuracy of non functional requirement prioritization approaches for different complexity projects

    OpenAIRE

    Raj Kumar Chopra; Varun Gupta; Durg Singh Chauhan

    2016-01-01

    Non functional requirements must be selected for implementation together with functional requirements to enhance the success of software projects. Three approaches exist for performing the prioritization of non functional requirements using the suitable prioritization technique. This paper performs experimentation on three different complexity versions of the industrial software project using cost-value prioritization technique employing three approaches. Experimentation is conducted to analy...

  7. Technical and administrative approach for the West Valley Demonstration Project Safety Program

    International Nuclear Information System (INIS)

    Newsom, P.C.; Roberts, C.J.; Yuchien Yuan; Marchetti, S.

    1987-06-01

    The principal objective of the West Valley Demonstration Project (WVDP) is to vitrify the 2.2 million liters of high-level radioactive waste (HLW) stored at the Western New York Nuclear Service Center (WNYNSC). This simple statement of purpose, however, does not convey a sense of the complexity of the undertaking. The vitrification task is not only complex in and of itself, but requires a myriad of other activities to be accomplished on an intricate and fast paced schedule in order to support it. The West Valley Demonstration Project Act (P.L 96-368), U.S. Department of Energy Order DOE-5481.1A, Idaho Operations Office Order ID-5481.1 and standard nuclear industry practice all require that proposed systems and operations involving hazards not routinely encountered by the general public be analyzed to identify potential hazards and consequences, and to assure that reasonable measures are taken to eliminate, control, or mitigate these potential consequences. Virtually every substantive aspect of the WVDP involves hazards beyond those routinely encountered and accepted by the general public. In order to assure the safety of the public and the workers at the WVDP, a system of hazard identification, categorization, analysis and review has been established. In parallel with this system, a procedure for developing the minimum design specifications and quality assurance requirements has been developed for Project systems, components, and structures which play a role in the safety of a specific major facility or the overall Project. 29 refs., 3 figs., 6 tabs

  8. Defining project scenarios for the agile requirements engineering product-line development questionnaire

    OpenAIRE

    Feng, Kunwu; Lempert, Meli; Tang, Yan; Tian, Kun; Cooper, Kendra M.L.; Franch Gutiérrez, Javier

    2007-01-01

    Current agile methods are focused on practices of small, rapid developing and iteration, more people oriented, less documentation projects, and the use of the methods in large, product line projects are somehow difficult. UTD and GESSI have started a project to develop an expert system that can assist a requirements enginer in selecting a requirements engineering process that is well suited for their project, in particular with respect to the use of agile and product line engineering methods....

  9. Modelling and Reasoning about Security Requirements in Socio-Technical Systems

    NARCIS (Netherlands)

    Paja, Elda; Dalpiaz, Fabiano; Giorgini, Paolo

    2015-01-01

    Modern software systems operate within the context of larger socio-technical systems, wherein they interact—by exchanging data and outsourcing tasks—with other technical components, humans, and organisations. When interacting, these components (actors) operate autonomously; as such, they may

  10. Aspects of the role of scientific-technical expert knowledge in administrative court procedures on licensing of large technical projects

    International Nuclear Information System (INIS)

    Wagner, H.

    1983-01-01

    On the basis of atomic energy law, the author explains some specific problems associated with the respective roles of experts (or expert bodies) and courts of law. In legal theory, it is comparatively easy to draw the line between the two functions, but in practice this delimination meets with difficulties. Finally, the author proposes to improve the definitions of the respective functions of experts (expert bodies) and courts of law in procedures dealing with permits of large technical facilities as follows: A highly qualified, independent body of experts in a technically representative composition lays down, in a binding way, the main elements of the safety standard of a specific plant or type of plant. The responsible administrative authority, after having examined all other legal conditions, grants the permit for that plant. There are no objections to such a model in the light either of aspects of constitutional law or of legal policy or constitutional policy, not are there any practical reasons against this approach. The only doubtful aspect is the present political feasibility. (orig.) [de

  11. Impact of Requirements Elicitation Processes on Success of Information System Development Projects

    Directory of Open Access Journals (Sweden)

    Bormane Līga

    2016-12-01

    Full Text Available Requirements articulating user needs and corresponding to enterprise business processes are a key to successful implementation of information system development projects. However, the parties involved in projects frequently are not able to agree on a common development vision and have difficulties expressing their needs. Several industry experts have acknowledged that requirements elicitation is one of the most difficult tasks in development projects. This study investigates the impact of requirements elicitation processes on project outcomes depending on the applied project development methodology.

  12. 77 FR 30512 - Native American Career and Technical Education Program; Final Waivers and Extension of Project...

    Science.gov (United States)

    2012-05-23

    ... DEPARTMENT OF EDUCATION Native American Career and Technical Education Program; Final Waivers and... American Career and Technical Education Program Catalog of Federal Domestic Assistance (CFDA) Number: 84... and Technical Education Program (NACTEP), the Secretary waives 34 CFR 75.250 and 75.261(c)(2) in order...

  13. Evaluation model of commercial geological exploration and mining development project and analysis of some technical problems in commercial negotiation

    International Nuclear Information System (INIS)

    Yao Zhenkai

    2012-01-01

    A composite evaluation model of commercial geological exploration and mining development project was discussed, this new model consists of polity-economy-technique (PET) synthetic evaluation sub-model and geology-mining-metallurgy (GMM) technique evaluation sub-model. Besides, some key technical problems in commercial negotiation, such as information screening, quoted price and analysis of deadline, were briefly analyzed. (author)

  14. Laboratory and project based learning in the compulsory course Biological Chemistry enhancing collaboration and technical communication between groups

    DEFF Research Database (Denmark)

    Agersø, Yvonne; Bysted, Anette; Jensen, Lars Bogø

    2011-01-01

    The aim of this paper was to describe how changes of laboratory training and project based learning were implemented in order to train the students in making a study design, basic laboratory skills, handling of data, technical communication, collaboration and presentation....

  15. Procedural Influence on Internal and External Assessment Scores of Undergraduate Vocational and Technical Education Research Projects in Nigerian Universities

    Science.gov (United States)

    A. C., John; Manabete, S. S.

    2015-01-01

    This study sought to determine the procedural influence on internal and external assessment scores of undergraduate research projects in vocational and technical education programmes in the university under study. A survey research design was used for the conduct of this study. The population consisted of 130 lecturers and 1,847 students in the…

  16. Technical database and management system (DBMS) for the UMTRA project processing sites

    International Nuclear Information System (INIS)

    Hillman, R.L.; Mohr, D.E.

    1985-01-01

    The technical DBMS is a structured and organized method for collecting, storing, retrieving, and analyzing technical data based upon standard operating procedures and quality control measures. The automated environment created by this design exists both as a repository for processing site technical data and the analysis techniques used against this data for site characterization, evaluation, and design. The system is composed of diverse technical subjects that are collectively used to address remedial action problems associated with mill tailings disposal. These technical subjects include hydrology, geology, geochemistry, radiology, and engineering

  17. Telemetry system for monitoring the ECG for patients with high cardiovascular risk. Main design requirements and technical solutions

    International Nuclear Information System (INIS)

    Rodriguez, J; Meissimilly, G; Berovides, JD

    2005-01-01

    In this paper the main design requirements concerning the setting up of a telemetry ECG monitoring system are presented. The design's most important technical solutions as well as some details are also discussed. This system is intended to provide skilled medical assistance during the cardiac rehabilitation of both asymptomatic and high risk coronary patients

  18. 47 CFR 25.214 - Technical requirements for space stations in the satellite digital audio radio service and...

    Science.gov (United States)

    2010-10-01

    ... 47 Telecommunication 2 2010-10-01 2010-10-01 false Technical requirements for space stations in the satellite digital audio radio service and associated terrestrial repeaters. 25.214 Section 25.214 Telecommunication FEDERAL COMMUNICATIONS COMMISSION (CONTINUED) COMMON CARRIER SERVICES SATELLITE COMMUNICATIONS...

  19. C2 Link Security for UAS: Technical Literature Study and Preliminary Functional Requirements. Version 0.9 (Working Draft)

    Science.gov (United States)

    2005-01-01

    This document provides a study of the technical literature related to Command and Control (C2) link security for Unmanned Aircraft Systems (UAS) for operation in the National Airspace System (NAS). Included is a preliminary set of functional requirements for C2 link security.

  20. STTR Phase 1 Final Technical Report for Project Entitled "Developing a Mobile Torrefaction Machine"

    Energy Technology Data Exchange (ETDEWEB)

    James, Joseph J. [President, ATP

    2014-03-11

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

  1. Alcan Kitimat smelter modernization project remedial action scheme functional requirements

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2008-09-09

    This paper identified remedial actions for reducing islanding and voltage collapse at the Alcan Kitimat smelter modernization project. The study was conducted after an earlier study indicated that the proposed project significantly increased electricity loads and stresses on Alcan's power system. Remedial actions included shedding the appropriate number of Kemano (KMO) generators; reducing Kitimat potline loads by de-saturating saturable reactors and lowering tap changers; and shedding potlines to preserve the Kitimat auxiliary load and facilitate power restoration. Power flow and transient stability studies were conducted to evaluate the impact of the remedial actions on the KMO generators and the transmission system. Results showed that fast load reduction improved power system response. Load reduction by changing the converter transformer tap reduced significant amounts of loads, but was too slow to be effective during fast voltage collapse. The study showed that although the remedial action scheme (RAS) reduced the impact of various contingencies on the Alcan system, performance was degraded due to the significant load increase. Fast load shedding capability was also reduced. It was concluded that further research is needed to develop and implement the RAS. 3 tabs., 7 figs.

  2. Projected transuranic waste loads requiring treatment, storage, and disposal

    International Nuclear Information System (INIS)

    Hong, K.; Kotek, T.

    1996-01-01

    This paper provides information on the volume of TRU waste loads requiring treatment, storage, and disposal at DOE facilities for three siting configurations. Input consisted of updated inventory and generation data from. Waste Isolation Pilot plant Transuranic Waste Baseline Inventory report. Results indicate that WIPP's design capacity is sufficient for the CH TRU waste found throughout the DOE Complex

  3. IT Requirements Integration in High-Rise Construction Design Projects

    Science.gov (United States)

    Levina, Anastasia; Ilin, Igor; Esedulaev, Rustam

    2018-03-01

    The paper discusses the growing role of IT support for the operation of modern high-rise buildings, due to the complexity of managing engineering systems of buildings and the requirements of consumers for the IT infrastructure. The existing regulatory framework for the development of design documentation for construction, including high-rise buildings, is analyzed, and the lack of coherence in the development of this documentation with the requirements for the creation of an automated management system and the corresponding IT infrastructure is stated. The lack of integration between these areas is the cause of delays and inefficiencies both at the design stage and at the stage of putting the building into operation. The paper proposes an approach to coordinate the requirements of the IT infrastructure of high-rise buildings and design documentation for construction. The solution to this problem is possible within the framework of the enterprise architecture concept by coordinating the requirements of the IT and technological layers at the design stage of the construction.

  4. Presentation note of the order project related to the general technical regulation applicable to INBs

    International Nuclear Information System (INIS)

    2010-01-01

    This document presents the scope of the order project which defines the main requirements applicable to INBs (base nuclear installations) in terms of protection of people and of the environment in front of risks of accident, of pollutions and other nuisances. More precisely, the document explains the scope of the several specific aspects addressed by this order: safety policy and management, accident risk management, management of nuisance and of the installation impact on population and on the environment, management and elimination of wastes and fuels spent by a base nuclear installation, management of emergency situations, population information, authorization request procedures, and other provisions

  5. Data description and quality assessment of ionospheric electron density profiles for ARPA modeling project. Technical report

    International Nuclear Information System (INIS)

    Conkright, R.O.

    1977-03-01

    This report presents a description of the automated method used to produce electron density (N(h)) profiles from ionograms recorded on 35mm film and an assessment of the resulting data base. A large data base of about 30,000 profiles was required for an ionospheric modeling project. This motivated a search for an automated method of producing profiles. The automated method used is fully described, the resulting data are given a quality grade, and the noon and midnight profiles are presented. Selected portions of this data base are compared with profiles produced by the standard profiling method in use by the Environmental Data Service at Boulder, Colorado

  6. Technical Safety Requirements for the B695 Segment of the Decontamination and Waste Treatment Facility

    International Nuclear Information System (INIS)

    Larson, H L

    2007-01-01

    This document contains Technical Safety Requirements (TSRs) for the Radioactive and Hazardous Waste Management (RHWM) Division's B695 Segment of the Decontamination and Waste Treatment Facility (DWTF) at Lawrence Livermore National Laboratory (LLNL). The TSRs constitute requirements regarding the safe operation of the B695 Segment of the DWTF. The TSRs are derived from the Documented Safety Analysis (DSA) for the B695 Segment of the DWTF (LLNL 2004). The analysis presented there determined that the B695 Segment of the DWTF is a low-chemical hazard, Hazard Category 3, nonreactor nuclear facility. The TSRs consist primarily of inventory limits as well as controls to preserve the underlying assumptions in the hazard analyses. Furthermore, appropriate commitments to safety programs are presented in the administrative controls section of the TSRs. The B695 Segment of the DWTF (B695 and the west portion of B696) is a waste treatment and storage facility located in the northeast quadrant of the LLNL main site. The approximate area and boundary of the B695 Segment of the DWTF are shown in the B695 Segment of the DWTF DSA. Activities typically conducted in the B695 Segment of the DWTF include container storage, lab-packing, repacking, overpacking, bulking, sampling, waste transfer, and waste treatment. B695 is used to store and treat radioactive, mixed, and hazardous waste, and it also contains equipment used in conjunction with waste processing operations to treat various liquid and solid wastes. The portion of the building called Building 696 Solid Waste Processing Area (SWPA), also referred to as B696S in this report, is used primarily to manage solid radioactive waste. Operations specific to the SWPA include sorting and segregating low-level waste (LLW) and transuranic (TRU) waste, lab-packing, sampling, and crushing empty drums that previously contained LLW. A permit modification for B696S was submitted to DTSC in January 2004 to store and treat hazardous and mixed

  7. Technical Safety Requirements for the B695 Segment of the Decontamination and Waste Treatment Facility

    Energy Technology Data Exchange (ETDEWEB)

    Larson, H L

    2007-09-07

    This document contains Technical Safety Requirements (TSRs) for the Radioactive and Hazardous Waste Management (RHWM) Division's B695 Segment of the Decontamination and Waste Treatment Facility (DWTF) at Lawrence Livermore National Laboratory (LLNL). The TSRs constitute requirements regarding the safe operation of the B695 Segment of the DWTF. The TSRs are derived from the Documented Safety Analysis (DSA) for the B695 Segment of the DWTF (LLNL 2004). The analysis presented there determined that the B695 Segment of the DWTF is a low-chemical hazard, Hazard Category 3, nonreactor nuclear facility. The TSRs consist primarily of inventory limits as well as controls to preserve the underlying assumptions in the hazard analyses. Furthermore, appropriate commitments to safety programs are presented in the administrative controls section of the TSRs. The B695 Segment of the DWTF (B695 and the west portion of B696) is a waste treatment and storage facility located in the northeast quadrant of the LLNL main site. The approximate area and boundary of the B695 Segment of the DWTF are shown in the B695 Segment of the DWTF DSA. Activities typically conducted in the B695 Segment of the DWTF include container storage, lab-packing, repacking, overpacking, bulking, sampling, waste transfer, and waste treatment. B695 is used to store and treat radioactive, mixed, and hazardous waste, and it also contains equipment used in conjunction with waste processing operations to treat various liquid and solid wastes. The portion of the building called Building 696 Solid Waste Processing Area (SWPA), also referred to as B696S in this report, is used primarily to manage solid radioactive waste. Operations specific to the SWPA include sorting and segregating low-level waste (LLW) and transuranic (TRU) waste, lab-packing, sampling, and crushing empty drums that previously contained LLW. A permit modification for B696S was submitted to DTSC in January 2004 to store and treat hazardous and

  8. Using Project Complexity Determinations to Establish Required Levels of Project Rigor

    Energy Technology Data Exchange (ETDEWEB)

    Andrews, Thomas D.

    2015-10-01

    This presentation discusses the project complexity determination process that was developed by National Security Technologies, LLC, for the U.S. Department of Energy, National Nuclear Security Administration Nevada Field Office for implementation at the Nevada National Security Site (NNSS). The complexity determination process was developed to address the diversity of NNSS project types, size, and complexity; to fill the need for one procedure but with provision for tailoring the level of rigor to the project type, size, and complexity; and to provide consistent, repeatable, effective application of project management processes across the enterprise; and to achieve higher levels of efficiency in project delivery. These needs are illustrated by the wide diversity of NNSS projects: Defense Experimentation, Global Security, weapons tests, military training areas, sensor development and testing, training in realistic environments, intelligence community support, sensor development, environmental restoration/waste management, and disposal of radioactive waste, among others.

  9. Requirements Analysis Study for Master Pump Shutdown System Project Development Specification [SEC 1 and 2

    International Nuclear Information System (INIS)

    BEVINS, R.R.

    2000-01-01

    This document has been updated during the definitive design portion of the first phase of the W-314 Project to capture additional software requirements and is planned to be updated during the second phase of the W-314 Project to cover the second phase of the Project's scope. The objective is to provide requirement traceability by recording the analysis/basis for the functional descriptions of the master pump shutdown system. This document identifies the sources of the requirements and/or how these were derived. Each requirement is validated either by quoting the source or an analysis process involving the required functionality, performance characteristics, operations input or engineering judgment

  10. The Interactive Electronic Technical Manual: Requirements, Current Status, and Implementation. Strategy Considerations.

    Science.gov (United States)

    1991-07-01

    authoring systems. Concurrently, great strides in computer-aided design and computer-aided maintenance have contributed to this capability. 12 Junod ...J.; William A. Nugent; and L. John Junod . Plan for the Navy/Air Force Test of the Interactive Electronic Technical Manual (IETM) at Cecil Field...AFHRL Logistics and Human Factors Division, WPAFB. Aug 1990. 12. Junod , John L. PY90 Interactive Electronic Technical Manual (IETM) Portable Delivery

  11. MORE: Management of requirements in NPP modernisation projects. Project report 2007

    International Nuclear Information System (INIS)

    Fredriksen, R.; Katta, V.; Raspotnig, C.; Valkonen, J.

    2008-03-01

    This report documents the work and related activities of the MORE project in the period January 1 - December 31 in 2007. The focus of this report is on improvements of the former project results, to identify and apply a couple of case studies from NPP projects, and activities in order to initiate and implement the industrial take-up and utilisation of the research results in real modernisation projects. The report also provides a brief description of the extended industrial network and disseminations of the results in Nordic and NKS related events such as seminars and workshops. (au)

  12. MORE: Management of requirements in NPP modernisation projects. Project report 2007

    Energy Technology Data Exchange (ETDEWEB)

    Fredriksen, R.; Katta, V.; Raspotnig, C. [Institutt for energiteknikk (IFE) (Norway); Valkonen, J. [Technical Research Centre of Finland (VTT) (Finland)

    2008-03-15

    This report documents the work and related activities of the MORE project in the period January 1 - December 31 in 2007. The focus of this report is on improvements of the former project results, to identify and apply a couple of case studies from NPP projects, and activities in order to initiate and implement the industrial take-up and utilisation of the research results in real modernisation projects. The report also provides a brief description of the extended industrial network and disseminations of the results in Nordic and NKS related events such as seminars and workshops. (au)

  13. 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

  14. 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.

  15. Detroit Works Long-Term Planning Project: Engagement Strategies for Blending Community and Technical Expertise

    Directory of Open Access Journals (Sweden)

    Toni L. Griffin

    2014-10-01

    Full Text Available In January 2013, civic leaders, community stakeholders, and residents came together to release Detroit Future City: 2012 Detroit Strategic Framework Plan, a guiding blueprint for transforming Detroit from its current state of population loss and excessive vacancy into a model for the reinvention of post-industrial American cities. Three years prior, the U.S. Census had reported that the city had lost 24% of its population over the last decade and had experienced a 20% increase in vacant and abandoned property, bringing total vacancy to roughly the size of Manhattan. In addition to physical and economic challenges, Detroiters had also acknowledged significant barriers to effective civic engagement. Foremost among these barriers were a profound sense of immobilization, planning fatigue, and a general perception of cynicism about planning and engagement efforts. These challenges were compounded by historic racial dynamics and tension. This case study elaborates on the comprehensive and innovative civic engagement executed in a citywide planning process called the Detroit Works Project, which took place from late 2010 through late 2012. For the citywide planning process to be successful and sustainable, civic leaders and project funders committed to a planning initiative that would be different from previous efforts, in large part because the “owners” of the process would be diverse and inclusive across all community sectors. The case study, written by three of the key consultants from the project, describes four key civic engagement strategies deployed in the creation of the strategic framework: (1 addressing profound challenges of culture, race, and politics by deliberately building trust; (2 elevating community expertise by fostering a sense of ownership of the process; (3 blending technical and community expertise; and (4 viewing civic engagement as an ongoing two-way conversation rather than a series of large-scale episodic events. This

  16. Optimal Locations for Siting Wind Energy Projects: Technical Challenges, Economics, and Public Preferences

    Science.gov (United States)

    Lamy, Julian V.

    project - both to their community through increased tax revenue, and to individuals through reduced monthly energy bills. Further, participants in both samples preferred onshore to offshore projects, but that preference was much stronger in the coastal community. I also find that participants from the coastal community preferred expanding an existing wind projects rather than building an entirely new one, whereas those in the U.S.-wide sample were indifferent, and equally supportive of the two options. These differences are likely driven by the prior positive experience the coastal community has had with an existing onshore wind project as well as their strong cultural identity that favors ocean views. I conclude that preference for increased distance from a wind project (NIMBY) is likely small or non-existent and that offshore wind projects within 5 miles from shore could cause large welfare losses to coastal communities. Finally, in Chapter 6, I provide a discussion and policy recommendations from my work. Importantly, I recommend that future research should combine the various topics throughout my chapters (i.e., transmission requirements, hourly power production, variability impacts to the grid, and public preferences) into a comprehensive model that identifies optimal locations for wind projects across the United States.

  17. 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

  18. 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

  19. Environmental management requirements/defensible costs project. Final report

    International Nuclear Information System (INIS)

    1996-02-01

    Lockheed Idaho Technologies Company (LITCO) used a systems engineering approach to develop the first formal requirements baseline for Idaho National Engineering Laboratory (INEL) Environmental Management (EM) Programs. The recently signed Settlement Agreement with the State of Idaho (Batt Agreement), along with dramatically reduced EM funding targets from Department of Energy (DOE) headquarters, drove the immediacy of this effort. Programs have linked top-level requirements to work scope to cost estimates. All EM work, grouped by decision units, was scrubbed by INEL EM programs and by an independent open-quotes Murder Board.close quotes Direct participation of upper level management from LITCO and the DOE-Idaho Operations Office ensured best information and decisions. The result is a scrubbed down, defensible budget tied to top-level requirements for use in the upcoming DOE-Headquarters' budget workout, the Internal Review Board, the FY98 Activity Data Sheets submittal, and preparation of the FY97 control accounts and out-year plans. In addition to the remarkable accomplishments during the past eight weeks, major issues were identified and documented and follow-on tasks are underway which will lead to further improvements in INEL EM program management

  20. Environmental management requirements/defensible costs project. Final report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-02-01

    Lockheed Idaho Technologies Company (LITCO) used a systems engineering approach to develop the first formal requirements baseline for Idaho National Engineering Laboratory (INEL) Environmental Management (EM) Programs. The recently signed Settlement Agreement with the State of Idaho (Batt Agreement), along with dramatically reduced EM funding targets from Department of Energy (DOE) headquarters, drove the immediacy of this effort. Programs have linked top-level requirements to work scope to cost estimates. All EM work, grouped by decision units, was scrubbed by INEL EM programs and by an independent {open_quotes}Murder Board.{close_quotes} Direct participation of upper level management from LITCO and the DOE-Idaho Operations Office ensured best information and decisions. The result is a scrubbed down, defensible budget tied to top-level requirements for use in the upcoming DOE-Headquarters` budget workout, the Internal Review Board, the FY98 Activity Data Sheets submittal, and preparation of the FY97 control accounts and out-year plans. In addition to the remarkable accomplishments during the past eight weeks, major issues were identified and documented and follow-on tasks are underway which will lead to further improvements in INEL EM program management.

  1. Technical evaluation of RETS-required reports for Browns Ferry Nuclear Power Station, Units 1, 2, and 3, for 1983

    International Nuclear Information System (INIS)

    Young, T.E.; Magleby, E.H.

    1985-01-01

    A review was performed of reports required by federal regulations and the plant-specific radiological effluent technical specifications (RETS) for operations conducted at Tennessee Valley Authority's Browns Ferry Nuclear Station, Units 1, 2, and 3, during 1983. The two periodic reports reviewed were (a) the Effluents and Waste Disposal Semiannual Report, First Half 1983 and (b) the Effluents and Waste Disposal Semiannual Report, Second Half 1983. The principal review guidelines were the plant's specific RETs and NRC guidance given in NUREG-0133, ''Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants.'' The Licensee's submitted reports were found to be reasonably complete and consistent with the review guidelines

  2. Technical evaluation of RETS-required reports for Zion Nuclear Power Station, Units 1 and 2 for 1983

    International Nuclear Information System (INIS)

    Young, T.E.; Magleby, E.H.

    1985-01-01

    A review was performed on the reports required by Federal regulations and the plant-specific Radiological Effluent Technical Specifications (RETS) for operations conducted at Commonwealth Edison's Zion Nuclear Power Station during 1983. The two periodic reports reviewed: (1) were the Effluent and Waste Disposal Semiannual Report, July-December 1983, and (2) the Radioactive Waste and Environmental Monitoring Annual Report - 1983. The principal review guidelines were the plant's specific RETS and NRC guidance given in NUREG-0133, ''Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants.'' The Licensee's submitted reports were found to be reasonably complete and consistent with the review guidelines

  3. Technical evaluation of RETS-required reports for the Edwin I. Hatch Nuclear Plant, Units 1 and 2

    International Nuclear Information System (INIS)

    Young, T.E.; Magleby, E.H.

    1985-01-01

    A review of the reports required by federal regulations and the plant-specific Radiological Effluent Technical Specifications (RETS) for operations conducted during 1983 was performed. The periodic reports reviewed for the Edwin I. Hatch Nuclear Plant were the Annual Radiological Environmental Operating Report for 1983 and the Semiannual Radioactive Effluent Release Reports for 1983. The principal review guidelines were the plant's specific RETS, NUREG-0133, ''Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants'', and NRC Guidance on the Review of the Process Control Programs. The Licensee's submitted reports were found to be reasonably complete and consistent with the review guidelines. 7 refs

  4. Technical evaluation of RETS-required reports for Rancho Seco Nuclear Generating Station, Unit 1 for 1983

    International Nuclear Information System (INIS)

    Magleby, E.H.; Young, T.E.

    1985-01-01

    A review of the reports required by Federal regulations and the plant-specific Radiological Effluent Technical Specifications (RETS) for operations conducted during 1983 was performed. The periodic reports reviewed for the Rancho Seco Nuclear Generating Station, Unit 1 were the Semiannual Effluent Release Report, January 1, 1983 to June 30, 1983 and the Radiation Exposure, Environmental Protection, Effluent and Waste Disposal Report. The principal review guidelines were the plant's specific RETS which were based on NRC guidance given in NUREG-0133, ''Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants.'' The Licensee's submitted reports were found to be reasonably complete and consistent with the review guidelines

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

    Energy Technology Data Exchange (ETDEWEB)

    Karpeta, B; Kolar, J

    1979-01-01

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

  6. AN ANALYSIS OF TECHNICAL SECURITY CONTROL REQUIREMENTS FOR DIGITAL I&C SYSTEMS IN NUCLEAR POWER PLANTS

    Directory of Open Access Journals (Sweden)

    JAE-GU SONG

    2013-10-01

    Full Text Available Instrumentation and control systems in nuclear power plants have been digitalized for the purpose of maintenance and precise operation. This digitalization, however, brings out issues related to cyber security. In the most recent past, international standard organizations, regulatory institutes, and research institutes have performed a number of studies addressing these systems cyber security. In order to provide information helpful to the system designers in their application of cyber security for the systems, this paper presents methods and considerations to define attack vectors in a target system, to review and select the requirements in the Regulatory Guide 5.71, and to integrate the results to identify applicable technical security control requirements. In this study, attack vectors are analyzed through the vulnerability analyses and penetration tests with a simplified safety system, and the elements of critical digital assets acting as attack vectors are identified. Among the security control requirements listed in Appendices B and C to Regulatory Guide 5.71, those that should be implemented into the systems are selected and classified in groups of technical security control requirements using the results of the attack vector analysis. For the attack vector elements of critical digital assets, all the technical security control requirements are evaluated to determine whether they are applicable and effective, and considerations in this evaluation are also discussed. The technical security control requirements in three important categories of access control, monitoring and logging, and encryption are derived and grouped according to the elements of attack vectors as results for the sample safety system.

  7. International Socio-Technical Challenges for Geological Disposal (InSOTEC): Project Aims and Preliminary Results - 12236

    Energy Technology Data Exchange (ETDEWEB)

    Bergmans, Anne; Schroeder, Jantine [University of Antwerp, Faculty of Political and Social Sciences, 2000 Antwerp (Belgium); Simmons, Peter [University of East Anglia, School of Environmental Sciences, NR4 7TJ Norwich (United Kingdom); Barthe, Yannick; Meyer, Morgan [CNRS, Ecole des Mines, 75272 Paris (France); Sundqvist, Goeran [Universitetet i Oslo, Centre for Studies of Technology, Innovation and Culture, 0851 Oslo (Norway); Martell, Merixell [MERIENCE Strategic Thinking, 08734 Olerdola (Spain); Kallenbach-Herbert, Beate [Oeko Institut, 64295 Darmstadt (Germany)

    2012-07-01

    InSOTEC is a social sciences research project which aims to generate a better understanding of the complex interplay between the technical and the social in radioactive waste management and, in particular, in the design and implementation of geological disposal. It currently investigates and analyses the most striking socio-technical challenges to implementing geological disposal of radioactive waste in 14 national programs. A focus is put on situations and issues where the relationship between the technical and social components is still unstable, ambiguous and controversial, and where negotiations are taking place in terms of problem definitions and preferred solutions. Such negotiations can vary from relatively minor contestation, over mild commotion, to strong and open conflicts. Concrete examples of socio-technical challenges are: the question of siting, introducing the notion of reversibility / retrievability into the concept of geological disposal, or monitoring for confidence building. In a second stage the InSOTEC partners aim to develop a fine-grained understanding of how the technical and the social influence, shape, build upon each other in the case of radioactive waste management and the design and implementation of geological disposal. How are socio-technical combinations in this field translated and materialized into the solutions finally adopted? With what kinds of tools and instruments are they being integrated? Complementary to providing better theoretical insight into these socio-technical challenges/combinations, InSOTEC aims to provide concrete suggestions on how to address these within national and international contexts. To this end, InSOTEC will deliver insights into how mechanisms for interaction between the technical community and a broad range of socio-political actors could be developed. (authors)

  8. Preliminary draft industrial siting administration permit application: Socioeconomic factors technical report. Final technical report, November 1980-May 1982. [Proposed WyCoalGas project in Converse County, Wyoming

    Energy Technology Data Exchange (ETDEWEB)

    1982-01-01

    Under the with-project scenario, WyCoalGas is projected to make a difference in the long-range future of Converse County. Because of the size of the proposed construction and operations work forces, the projected changes in employment, income, labor force, and population will alter Converse County's economic role in the region. Specifically, as growth occurs, Converse County will begin to satisfy a larger portion of its own higher-ordered demands, those that are currently being satisfied by the economy of Casper. Business-serving and household-serving activities, currently absent, will find the larger income and population base forecast to occur with the WyCoalGas project desirable. Converse County's economy will begin to mature, moving away from strict dependence on extractive industries to a more sophisticated structure that could eventually appeal to national, and certainly, regional markets. The technical demand of the WyCoalGas plant will mean a significant influx of varying occupations and skills. The creation of basic manufacturing, advanced trade and service sectors, and concomitant finance and transportation firms will make Converse County more economically autonomous. The county will also begin to serve market center functions for the smaller counties of eastern Wyoming that currently rely on Casper, Cheyenne or other distant market centers. The projected conditions expected to exist in the absence of the WyCoalGas project, the socioeconomic conditions that would accompany the project, and the differences between the two scenarios are considered. The analysis is keyed to the linkages between Converse County and Natrona County.

  9. Metrology for hydrogen energy applications: a project to address normative requirements

    Science.gov (United States)

    Haloua, Frédérique; Bacquart, Thomas; Arrhenius, Karine; Delobelle, Benoît; Ent, Hugo

    2018-03-01

    Hydrogen represents a clean and storable energy solution that could meet worldwide energy demands and reduce greenhouse gases emission. The joint research project (JRP) ‘Metrology for sustainable hydrogen energy applications’ addresses standardisation needs through pre- and co-normative metrology research in the fast emerging sector of hydrogen fuel that meet the requirements of the European Directive 2014/94/EU by supplementing the revision of two ISO standards that are currently too generic to enable a sustainable implementation of hydrogen. The hydrogen purity dispensed at refueling points should comply with the technical specifications of ISO 14687-2 for fuel cell electric vehicles. The rapid progress of fuel cell technology now requires revising this standard towards less constraining limits for the 13 gaseous impurities. In parallel, optimized validated analytical methods are proposed to reduce the number of analyses. The study aims also at developing and validating traceable methods to assess accurately the hydrogen mass absorbed and stored in metal hydride tanks; this is a research axis for the revision of the ISO 16111 standard to develop this safe storage technique for hydrogen. The probability of hydrogen impurity presence affecting fuel cells and analytical techniques for traceable measurements of hydrogen impurities will be assessed and new data of maximum concentrations of impurities based on degradation studies will be proposed. Novel validated methods for measuring the hydrogen mass absorbed in hydrides tanks AB, AB2 and AB5 types referenced to ISO 16111 will be determined, as the methods currently available do not provide accurate results. The outputs here will have a direct impact on the standardisation works for ISO 16111 and ISO 14687-2 revisions in the relevant working groups of ISO/TC 197 ‘Hydrogen technologies’.

  10. Requirements Analysis Study for Master Pump Shutdown System Project Development Specification

    International Nuclear Information System (INIS)

    BEVINS, R.R.

    2000-01-01

    This study is a requirements document that presents analysis for the functional description for the master pump shutdown system. This document identifies the sources of the requirements and/or how these were derived. Each requirement is validated either by quoting the source or an analysis process involving the required functionality, performance characteristics, operations input or engineering judgment. The requirements in this study apply to the first phase of the W314 Project. This document has been updated during the definitive design portion of the first phase of the W314 Project to capture additional software requirements and is planned to be updated during the second phase of the W314 Project to cover the second phase of the project's scope

  11. Project consistency with transportation plans and air quality conformity workshops : technical report.

    Science.gov (United States)

    2015-04-01

    This implementation project supports streamlined project delivery, one of the goals outlined by the Texas : Department of Transportation (TxDOT) leadership to achieve an efficient and effective transportation system : in Texas. The project benefits T...

  12. Private capital requirements for international biomass energy projects

    Energy Technology Data Exchange (ETDEWEB)

    Goldemberg, J [University of Sao Paulo, Sao Paulo (Brazil)

    1995-12-01

    In developing countries, the use of biomass for energy production faces two contradictory pressures. On the one hand, biomass costs very little and it is used inefficiently for fuel or charcoal production, leading to widespread destruction of forested areas and environmental degradation; this problem is being attenuated by the promotion, through aid programmes, of more efficient cook stoves for poor people. On the other hand, the conversion of biomass into high-grade fuel such as ethanol from sugar cane or burning urban refuse or gasifying it to produce electricity is not economically competitive at this time and requires subsidies of approximately 30% to make it as attractive as conventional fuels. Only electricity production using residues from sawmills, crops and other biomass by-products is competitive, and a number of plants are in operation in some countries, particularly the United States. For such plants, the usual rates of return and long-term contract purchases that characterize investments of this kind are applied. Although technologies are available for the widespread efficient use of biomass, the financial hurdle of high initial costs has impeded their market penetration, which in turn precludes any decline in costs that might otherwise have come from production increases. Intervention by governments or by GEF, justified on grounds of environmental protection, is needed to accelerate the introduction of the new technologies. The only private flows that are taking place at the moment are those from enlightened investors wishing to guarantee themselves a strong position in the area for the future or to preempt command and control regulations, such as carbon taxes, imposed by governments. The joint implementation of biomass technologies between industrialized and developing countries might be one method of accelerating this flow. (author) 9 refs, 4 figs, 3 tabs

  13. Private capital requirements for international biomass energy projects

    International Nuclear Information System (INIS)

    Goldemberg, J.

    1995-01-01

    In developing countries, the use of biomass for energy production faces two contradictory pressures. On the one hand, biomass costs very little and it is used inefficiently for fuel or charcoal production, leading to widespread destruction of forested areas and environmental degradation; this problem is being attenuated by the promotion, through aid programmes, of more efficient cook stoves for poor people. On the other hand, the conversion of biomass into high-grade fuel such as ethanol from sugar cane or burning urban refuse or gasifying it to produce electricity is not economically competitive at this time and requires subsidies of approximately 30% to make it as attractive as conventional fuels. Only electricity production using residues from sawmills, crops and other biomass by-products is competitive, and a number of plants are in operation in some countries, particularly the United States. For such plants, the usual rates of return and long-term contract purchases that characterize investments of this kind are applied. Although technologies are available for the widespread efficient use of biomass, the financial hurdle of high initial costs has impeded their market penetration, which in turn precludes any decline in costs that might otherwise have come from production increases. Intervention by governments or by GEF, justified on grounds of environmental protection, is needed to accelerate the introduction of the new technologies. The only private flows that are taking place at the moment are those from enlightened investors wishing to guarantee themselves a strong position in the area for the future or to preempt command and control regulations, such as carbon taxes, imposed by governments. The joint implementation of biomass technologies between industrialized and developing countries might be one method of accelerating this flow. (author)

  14. Addressing the technical capacity constraints on community-based labour intensive road projects - a case study of the Amadiba road project

    CSIR Research Space (South Africa)

    Lachman, A

    2006-09-01

    Full Text Available effect. 3. AIMS AND OBJECTIVE OF THE PAPER The main aim of this paper is to discuss the technical capacity constraints experienced on the Amadiba Road Project and to outline the measures taken to address them. Some of the objectives of this paper... are to: � Highlight the socioeconomic status of the community � Highlight the capacity needed on the project � Discuss some of the capacity building issues � Highlight the current state of the community 4. SOCIOECONOMIC STATUS OF THE AMADIBA...

  15. Employability and Technical Skill Required to Establish a Small Scale Automobile Workshop

    Science.gov (United States)

    Olaitan, Olawale O.; Ikeh, Joshua O.

    2015-01-01

    The study focused on identifying the employability and technical skills needed to establish small-scale automobile workshop in Nsukka Urban of Enugu State. Five purposes of the study were stated to guide the study. Five research questions were stated and answered in line with the purpose of the study. The population for the study is 1,500…

  16. Technical report on the project for improving the JAEA's enterprise resource planning system

    International Nuclear Information System (INIS)

    Kimura, Hideo; Aoyagi, Tetsuo; Sato, Taiichi; Sakai, Manabu; Suzuki, Hitoshi; Tsuji, Minoru; Hikasa, Naoki

    2011-09-01

    The financial accounting and contract management system of JAEA, built on a commercial ERP package, had suffered from serious problems of high lifecycle cost, poor response, and lack of extensibility, due to the too much customization to the ERP package, and disorganized software structure. To solve those problems, three approaches were applied; 1) conducting thorough analysis of business flow and fit/gap under the cooperation of users and system engineers, which enabled removing all customization brought to the ERP package; 2) dividing the system into subsystems each of which corresponds to a business unit, and clearly defining interfaces between the subsystems with international standards, which increases the transparency, extensibility and performance of the system; 3) outsourcing the development of the subsystems to multiple venders to reduce the development cost and controlling the risk of multiple outsourcing with a project management method used successfully in the very large R and D project in JAEA for developing JT60, a fusion plasma research facility. Those approaches can be useful for developing business information systems using commercial software to save time and cost, while meeting the unique requirements of an organization. (author)

  17. Virginia Offshore Wind Technology Advancement Project (VOWTAP) DOE EE0005985 Final Technical Report Rev 1a

    Energy Technology Data Exchange (ETDEWEB)

    Pietryk, Steven [Dominion, Richmond, VA (United States)

    2017-01-31

    The primary purpose of the VOWTAP was to advance the offshore wind industry in the United States (U.S.) by demonstrating innovative technologies and process solutions that would establish offshore wind as a cost-effective renewable energy resource. The VOWTAP Team proposed to design, construct, and operate a 12 megawatt (MW) offshore wind facility located approximately 27 statute miles (mi) (24 nautical miles [nm], 43 kilometers [km]) off the coast of Virginia. The proposed Project would consist of two Alstom Haliade™ 150-6 MW turbines mounted on inward battered guide structures (IBGS), a 34.5-kilovolt (kV) alternating current (AC) submarine cable interconnecting the WTGs (inter-array cable), a 34.5-kV AC submarine transmission cable (export cable), and a 34.5 kV underground cable (onshore interconnection cable) that would connect the Project with existing Dominion infrastructure located in Virginia Beach, Virginia (Figure 1). Interconnection with the existing Dominion infrastructure would also require an onshore switch cabinet, a fiber optic cable, and new interconnection station to be located entirely within the boundaries of the Camp Pendleton State Military Reservation (Camp Pendleton). The VOWTAP balanced technology innovation with commercial readiness such that turbine operations were anticipated to commence by 2018. Dominion, as the leaseholder of the Virginia Wind Energy Area (WEA), anticipated leveraging lessons learned through the VOWTAP, and applying them to future commercial-scale offshore wind development.

  18. Traceability and communication of requirements in digital and I and C systems development - Project report 2003

    International Nuclear Information System (INIS)

    Sivertsen, T.; Frederiksen, R.; Thunem, A.P.J.; Holmberg, J.E.; Valkonen, J.; Ventae, O.

    2004-03-01

    The overall objective of the TACO project is to improve the knowledge on principles and best practices related to the issues concretised in the preproject. On basis of experiences in the Nordic countries, the project aims at identifying the best practices and most important criteria for ensuring effective communication in relation to requirements elicitation and analysis, understandability of requirements to all parties, and traceability of requirements through the different design phases. It is expected that the project will provide important input to the development of guidelines and establishment of recommended practices related to these activities. In the year 2003, the TACO-project concentrated on four central issues: 1) Representation of requirements origins. 2) Traceability techniques. 3) Configuration management and the traceability of requirements. 4) Identification and categorisation of system aspects and their models The work was presented at the first TACO Industrial Seminar, which took place in Stockholm on the 12th of December 2003. The seminar was hosted by SKI. (au)

  19. Report of the first meeting of the Project Advisory Committee (Technical) 21-24 March 1983, at NEMROCK, Cairo

    International Nuclear Information System (INIS)

    Taylor, C.B.G.

    1983-05-01

    The Project Advisory Committee (Technical) (PACT) met on 21-24 March 1983, at NEMROCK, Cairo, Egypt, to discuss the joint IAEA/WHO project on Intracavitary Radiation Therapy for Cancer of the Uterus (Egypt/6/004). At this four day meeting the committee (1) identified a well-defined administrative framework in which earlier diagnosis of uterine cancer may be organized, on a limited but firm basis. (2) Agreed on the clinical and dosimetric principles to be followed in implementing the project. (3) Decided on the types and quantities of equipment which it will need in its first two years. (4) Developed the outline of the syllabus for the first training course, and fixed its date (three weeks from 83-10-29). (5) Reviewed the costs which will be incurred in carrying through the project and found them to be consistent with the funds available

  20. Technical basis for high-level waste repository land control requirements for Palo Duro Basin, Paradox Basin, and Richton Dome

    International Nuclear Information System (INIS)

    Chen, C.P.; Raines, G.E.

    1987-02-01

    Three sites, the Palo Duro Basin in Texas, the Paradox Basin in Utah, and the Richton Dome in Mississippi, are being investigated by the US Department of Energy for high-level radioactive-waste disposal in mined, deep geologic repositories in salt. This report delineates the use of regulatory, engineering, and performance assessment information to establish the technical basis for controlled area requirements. Based on the size of the controlled area determined, plus that of the geologic repository operations area, recommendations of possible land control or ownership area requirements for each locale are provided. On a technical basis, the following minimum land control or ownership requirements are recommended, assuming repository operations area of 2240 ac (907 ha), or 3.5 mi 2 (9.1 km 2 ): Palo Duro Basin - 4060 ac (1643 ha), or 6.3 mi 2 (16.4 km 2 ); Paradox Basin - 4060 ac (1643 ha), or 6.3 mi 2 (16.4 km 2 ); and Richton Dome - 5000 ac (2024 ha), or 7.8 mi 2 (20.2 km 2 ). Of the factors used to determine the technically based recommendations, one was found to dominate each locale. For the Palo Duro and Paradox Basins, the dominant factor was the need to limit potential radionuclide release by ground-water flow to the accessible environment. For the Richton Dome, the dominant factor was the need to limit the potential effects of solution mining on dome and repository integrity

  1. Management of technical documents: a projection at the University of Zulia

    Directory of Open Access Journals (Sweden)

    Ana Judith Paredes Chacin

    2015-11-01

    Full Text Available Objective. This paper analyze comprehensively and systematically the principles of organization and technical procedure, which support document management based on the use of information technologies. Method. We developed a study based on the documentary descriptive method in the context of the Dirección de Infraestructura (Dinfra from the Universidad del Zulia. Results. We find evidence of efficiency in the processes that support the management of technical documents: Plans, metrics and memories generated by the Dinfra. Conclusion. The conceptual basis of organizational and technical archives contribute to the systematization, shelter save and documental preservation, and ensure the timely retrieval of technical information for the management of the University of Zulia.

  2. Next Generation Nuclear Plant Project Technology Development Roadmaps: The Technical Path Forward

    Energy Technology Data Exchange (ETDEWEB)

    John Collins

    2009-01-01

    This document presents the Next Generation Nuclear Plant (NGNP) Systems, Subsystems, and Components, establishes a baseline for the current technology readiness status, and provides a path forward to achieve increasing levels of technical maturity.

  3. 76 FR 35864 - Proposed Priority; Special Demonstration Programs-National Technical Assistance Projects To...

    Science.gov (United States)

    2011-06-20

    ... have national significance and improve the performance of State vocational rehabilitation (VR) agencies... Centers, the American Indian Vocational Rehabilitation Technical Assistance Center, and the Independent... of each priority as absolute, competitive preference, or invitational through a notice in the Federal...

  4. The Importance of Detail and Organization of Technical Drawings for the Project Management

    Directory of Open Access Journals (Sweden)

    Diego de Avila

    2015-11-01

    Full Text Available This research takes into account the process of technical improvement through the development and interpretation of technical drawing with the appropriate software. However, it’s known that the technical design, no longer being new in business, tends to effect the production process in a clear and objective way, but there is a concern for the training and use of this standardized form tool. This article presents a case study detailing the use of standardized technical drawing by CAD system and continuously. Seeking to meet the improvement of quality control, production flexibility, reduced costs, documentation and even security, in a company in the northern region of the State of Rio Grande do Sul.

  5. An impact evaluation of the safe motherhood promotion project in Bangladesh: evidence from Japanese aid-funded technical cooperation.

    Science.gov (United States)

    Kamiya, Yusuke; Yoshimura, Yukie; Islam, Mohammad Tajul

    2013-04-01

    This paper reports the findings from a quasi-experimental impact evaluation of the Safe Motherhood Promotion Project (SMPP) conducted in the Narsingdi district of Bangladesh. SMPP is a Japanese aid-funded technical cooperation project aimed at developing local capacities to tackle maternal and newborn health problems in rural areas. We assessed whether the project interventions, in particular, community-based activities under the Model Union approach, had a favorable impact on women's access to and knowledge of maternal health care during pregnancy and childbirth. The project comprises a package of interlinked interventions to facilitate safe motherhood practices at primary and secondary care levels. The primary-level activities focused on community mobilization through participatory approaches. The secondary-level activities aimed at strengthening organizational and personnel capacities for delivering emergency obstetric care (EmOC) at district and sub-district level hospitals. The project impact was estimated by difference-in-differences logistic regressions using two rounds of cross-sectional household survey data. The results showed that the project successfully increased the utilization of antenatal visits and postpartum EmOC services and also enhanced women's knowledge of danger signs during pregnancy and delivery. The project also reduced income inequalities in access to antenatal care. In contrast, we found no significant increase in the use of skilled birth attendants (SBA) in the project site. Nonetheless, community mobilization activities and the government's voucher scheme played a complementary role in promoting the use of SBA. Copyright © 2013 Elsevier Ltd. All rights reserved.

  6. Structuring Requirements in a Multi-Project Environment in the Construction Industry

    DEFF Research Database (Denmark)

    Wörösch, Michael

    2012-01-01

    Being in control of requirements in building projects is vital, since it helps securing the often small profit margins and the reputation of the responsible company. Hence this research aims to introduce requirements management to the construction industry. By means of case study and action...... in this industry, yet, success is here defined as an accomplished and accepted implementation of requirements management processes that are used by the relevant project members in their daily work and where the benefits of implementing requirements management outweighs the cost of invested resources. Furthermore...... it is argued that when running technology development, product development, product platform development, and a portfolio of building projects at the same time the use of requirements management is advantageous and an intelligent way of structuring requirements is needed. This article also demonstrates...

  7. Habitat Evaluation Procedures (HEP) Report; Iskuulpa Wildlife Mitigation and Watershed Project, Technical Report 1998-2003.

    Energy Technology Data Exchange (ETDEWEB)

    Quaempts, Eric

    2003-01-01

    U.S. Fish and Wildlife Service (USFWS) Habitat Evaluation Procedures (HEP) were used to determine the number of habitat units credited to evaluate lands acquired and leased in Eskuulpa Watershed, a Confederated Tribes of the Umatilla Indian Reservation watershed and wildlife mitigation project. The project is designed to partially credit habitat losses incurred by BPA for the construction of the John Day and McNary hydroelectric facilities on the Columbia River. Upland and riparian forest, upland and riparian shrub, and grasslands cover types were included in the evaluation. Indicator species included downy woodpecker (Picuides puhescens), black-capped chickadee (Pams atricopillus), blue grouse (Beadragapus obscurus), great blue heron (Ardea herodias), yellow warbler (Dendroica petschia), mink (Mustela vison), and Western meadowlark (Sturnello neglects). Habitat surveys were conducted in 1998 and 1999 in accordance with published HEP protocols and included 55,500 feet of transects, 678 m2 plots, and 243 one-tenth-acre plots. Between 123.9 and f 0,794.4 acres were evaluated for each indicator species. Derived habitat suitability indices were multiplied by corresponding cover-type acreages to determine the number of habitat units for each species. The total habitat units credited to BPA for the Iskuulpa Watershed Project and its seven indicator species is 4,567.8 habitat units. Factors limiting habitat suitability are related to the direct, indirect, and cumulative effects of past livestock grazing, road construction, and timber harvest, which have simplified the structure, composition, and diversity of native plant communities. Alternatives for protecting and improving habitat suitability include exclusion of livestock grazing or implementation of restoration grazing schemes, road de-commissioning, reforestation, large woody debris additions to floodplains, control of competing and unwanted vegetation, reestablishing displaced or reduced native vegetation species

  8. Evaluation of data requirements for computerized constructability analysis of pavement rehabilitation projects.

    Science.gov (United States)

    2013-08-01

    This research aimed to evaluate the data requirements for computer assisted construction planning : and staging methods that can be implemented in pavement rehabilitation projects in the state of : Georgia. Results showed that two main issues for the...

  9. Technical specifications, South Texas Project, Unit No. 1 (Docket No. 50-498): Appendix ''A'' to License No. NPF-71

    International Nuclear Information System (INIS)

    1987-08-01

    This report presents specifications for the South Texas Project, Unit No. 1 concerning: safety limits, and limiting safety system settings; limiting conditions for operation and surveillance requirements; design features; and administrative controls

  10. Technical assessment of compliance with work place air sampling requirements at T Plant. Revision No. 1

    International Nuclear Information System (INIS)

    Hackworth, M.F.

    1995-01-01

    The US DOE requires its contractors to conduct air sampling to detect and evaluate airborne radioactive material in the workplace. Hanford Reservation T Plant compliance with workplace air sampling requirements has been assessed. Requirements, basis for determining compliance and recommendations are included

  11. Design requirements document for project W-520, immobilized low-activity waste disposal

    International Nuclear Information System (INIS)

    Ashworth, S.C.

    1998-01-01

    This design requirements document (DRD) identifies the functions that must be performed to accept, handle, and dispose of the immobilized low-activity waste (ILAW) produced by the Tank Waste Remediation System (TWRS) private treatment contractors and close the facility. It identifies the requirements that are associated with those functions and that must be met. The functional and performance requirements in this document provide the basis for the conceptual design of the Tank Waste Remediation System Immobilized Low-Activity Waste disposal facility project (W-520) and provides traceability from the program-level requirements to the project design activity

  12. Design requirements document for project W-520, immobilized low-activity waste disposal

    Energy Technology Data Exchange (ETDEWEB)

    Ashworth, S.C.

    1998-08-06

    This design requirements document (DRD) identifies the functions that must be performed to accept, handle, and dispose of the immobilized low-activity waste (ILAW) produced by the Tank Waste Remediation System (TWRS) private treatment contractors and close the facility. It identifies the requirements that are associated with those functions and that must be met. The functional and performance requirements in this document provide the basis for the conceptual design of the Tank Waste Remediation System Immobilized Low-Activity Waste disposal facility project (W-520) and provides traceability from the program-level requirements to the project design activity.

  13. Projects at the Western Environmental Technology Office. Quarterly technical progress report, April 1--June 30, 1995

    International Nuclear Information System (INIS)

    1995-01-01

    This report contains brief outlines of the multiple projects under the responsibility of the Western Environmental Technology Office in Butte Montana. These projects include biomass remediation, remediation of contaminated soils, mine waste technology, and several other types of remediation

  14. Using Model-Based Systems Engineering To Provide Artifacts for NASA Project Life-Cycle and Technical Reviews

    Science.gov (United States)

    Parrott, Edith L.; Weiland, Karen J.

    2017-01-01

    The ability of systems engineers to use model-based systems engineering (MBSE) to generate self-consistent, up-to-date systems engineering products for project life-cycle and technical reviews is an important aspect for the continued and accelerated acceptance of MBSE. Currently, many review products are generated using labor-intensive, error-prone approaches based on documents, spreadsheets, and chart sets; a promised benefit of MBSE is that users will experience reductions in inconsistencies and errors. This work examines features of SysML that can be used to generate systems engineering products. Model elements, relationships, tables, and diagrams are identified for a large number of the typical systems engineering artifacts. A SysML system model can contain and generate most systems engineering products to a significant extent and this paper provides a guide on how to use MBSE to generate products for project life-cycle and technical reviews. The use of MBSE can reduce the schedule impact usually experienced for review preparation, as in many cases the review products can be auto-generated directly from the system model. These approaches are useful to systems engineers, project managers, review board members, and other key project stakeholders.

  15. A review of the information required by technical justifications and its availability

    International Nuclear Information System (INIS)

    Worrall, G.M.; Conroy, P.J.; Whittle, M.J.; Roscoe, P.

    1997-03-01

    A central feature of the European approach to Inspection Qualification (IQ) is the use of Technical Justifications (TJ). This arises from the recognition that practical trials of an inspection can never, by themselves, generate sufficient information to provide confidence in an inspection. The central role of TJ has raised concerns that information which is vital to their production may currently not be available. The range of roles that TJ can play in IQ is described in this report, their typical structure, the key input information, and the essential variables defined. The extent to which this information currently is available is then discussed. Information needs are defined. 10 refs

  16. Traceability and communication of requirements in digital I and C systems development - the TACO project

    International Nuclear Information System (INIS)

    Sivertsen, Terje; Fredriksen, Rune; Thunem, Atoosa P-J.

    2004-01-01

    This paper summarizes some of the issues studied in the TACO project, a current activity partially funded by Nordic nuclear safety research through the NKS-R programme (NKS-R project number NKS R2 002 1 6). For more details, the reader is referred to the two project reports already delivered by the project (see section 9). On basis of experiences in the Nordic countries, the TACO project aims at identifying the best practices and most important criteria for ensuring effective communication in relation to requirements elicitation and analysis, understandability of requirements to all parties, and traceability of requirements through the different design phases. It is expected that the project will provide important input to the development of guidelines and establishment of recommended practices related to these activities. The overall aim of the preproject, which was carried out in the second half of 2002, was to identify the main issues related to traceability and communication of requirements in digital I and C systems development. By focusing on the identification of main issues, the preproject provided a basis for prioritising further work, while at the same time providing some initial recommendations related to these issues. The establishment of a Nordic expert network within the subject was another important result of the preproject. Further work has concentrated on four central and related issues, viz.; Representation of requirements origins; Traceability techniques; Configuration management and the traceability of requirements; Identification and categorisation of system aspects and their models. (Author)

  17. Analysis of compatibility of current Czech initial documentation in the area of technical assurance of nuclear safety with the requirements of the EUR document

    International Nuclear Information System (INIS)

    Zdebor, J.; Zdebor, R.; Kratochvil, L.

    2001-11-01

    The publication is structured as follows: Description of existing documentation. General requirements, goals, principles and design principles: Documents being compared; Method of comparison; Results and partial evaluation of comparison of requirements between EUR and Czech regulations (basic goals and safety philosophy; quantitative safety objectives; basic design requirements; extended design requirements; external and internal threats; technical requirements; site conditions); Summary of the comparison of safety requirements. Comparison of requirements for the systems: Requirements for the nuclear reactor unit systems; Barrier systems (fuel system; reactor cooling system; containment system); Remaining systems (control systems; protection systems; coolant makeup and purification system; residual heat removal system; emergency cooling system; power systems); Common technical requirements for systems (technical requirements for systems; internal and external events). (P.A.)

  18. Technical evaluation of RETS-required reports for Crystal River Nuclear Generating Plant, Unit 3, for 1983

    International Nuclear Information System (INIS)

    Magleby, E.H.; Young, T.E.

    1985-01-01

    A review was performed on the reports required by Federal regulations and the plant-specific Radiological Effluent Technical Specifications (RETS) for operations conducted at Florida Power Corporation's Crystal River Nuclear Plant, Unit 3, during 1983. The three periodic reports reviewed were (1) the Effluent and Waste Disposal Semiannual Report, January 1-June 30, 1983, (2) the Effluent and Waste Disposal Semiannual Report, July 1-December 31, 1983, and (3) the Annual Environmental Operating Report, Radiological, 1983. The principal review guidelines were the plant's specific RETS and NRC guidance given in NUREG-0133, ''Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants.'' The Licensee's submitted reports were found to be reasonably complete and consistent with the review guidelines

  19. Fuel Cell-Powered Lift Truck Fleet Deployment Projects Final Technical Report May 2014

    Energy Technology Data Exchange (ETDEWEB)

    Klingler, James J [GENCO Infrastructure Solutions, Inc.

    2014-05-06

    The overall objectives of this project were to evaluate the performance, operability and safety of fork lift trucks powered by fuel cells in large distribution centers. This was accomplished by replacing the batteries in over 350 lift trucks with fuel cells at five distribution centers operated by GENCO. The annual cost savings of lift trucks powered by fuel cell power units was between $2,400 and $5,300 per truck compared to battery powered lift trucks, excluding DOE contributions. The greatest savings were in fueling labor costs where a fuel cell powered lift truck could be fueled in a few minutes per day compared to over an hour for battery powered lift trucks which required removal and replacement of batteries. Lift truck operators where generally very satisfied with the performance of the fuel cell power units, primarily because there was no reduction in power over the duration of a shift as experienced with battery powered lift trucks. The operators also appreciated the fast and easy fueling compared to the effort and potential risk of injury associated with switching heavy batteries in and out of lift trucks. There were no safety issues with the fueling or operation of the fuel cells. Although maintenance costs for the fuel cells were higher than for batteries, these costs are expected to decrease significantly in the next generation of fuel cells, making them even more cost effective.

  20. Salt Repository Project transportation system interface requirements: Transportation system/repository receiving facility interface requirements

    International Nuclear Information System (INIS)

    Smith, L.A.; Insalaco, J.W.; Trainer, T.A.

    1988-01-01

    This report is a preliminary review of the interface between the transportation system and the repository receiving facility for a nuclear waste mined geologic disposal system in salt. Criteria for generic cask and facility designs are developed. These criteria are derived by examining the interfaces that occur as a result of the operations needed to receive nuclear waste at a repository. These criteria provide the basis for design of a safe, operable, practical nuclear waste receiving facility. The processing functions required to move the shipping unit from the gate into the unloading area and back to the gate for dispatch are described. Criteria for a generic receiving facility are discussed but no specific facility design is presented or evaluated. The criteria are stated in general terms to allow application to a wide variety of cask and facility designs. 9 refs., 6 figs., 4 tabs

  1. INDEPENDENT TECHNICAL ASSESSMENT OF MANAGEMENT OF STORMWATER AND WASTEWATER AT THE SEPARATIONS PROCESS RESEARCH UNIT (SPRU) DISPOSITION PROJECT, NEW YORK

    Energy Technology Data Exchange (ETDEWEB)

    Abitz, R.; Jackson, D.; Eddy-Dilek, C.

    2011-06-27

    The U.S. Department of Energy (DOE) is currently evaluating the water management procedures at the Separations Process Research Unit (SPRU). The facility has three issues related to water management that require technical assistance: (1) due to a excessive rainfall event in October, 2010, contaminated water collected in basements of G2 and H2 buildings. As a result of this event, the contractor has had to collect and dispose of water offsite; (2) The failure of a sump pump at a KAPL outfall resulted in a Notice of Violation issued by the New York State Department of Environment and Conservation (NYSDEC) and subsequent Consent Order. On-site water now requires treatment and off-site disposition; and (3) stormwater infiltration has resulted in Strontium-90 levels discharged to the storm drains that exceed NR standards. The contractor has indicated that water management at SPRU requires major staff resources (at least 50 persons). The purpose of this review is to determine if the contractor's technical approach warrants the large number of staff resources and to ensure that the technical approach is compliant and in accordance with federal, state and NR requirements.

  2. 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.

  3. 7 CFR Appendix B to Part 4280 - Technical Reports for Projects With Total Eligible Project Costs Greater Than $200,000

    Science.gov (United States)

    2010-01-01

    ... Agency's satisfaction before the application will be approved. The applicant must submit the original... to bioenergy projects, which are, as defined in § 4280.103, renewable energy systems that produce... requirements and obtaining those agreements. This is required even if the system is installed on the customer...

  4. Yucca Mountain Project: A summary of technical support activities, January 1987--June 1988

    International Nuclear Information System (INIS)

    1989-05-01

    This report is a summary of the technical support activities of Mifflin ampersand Associates, Inc., during the 18-month period beginning 01 January 1987 and ending on 30 June 1988. It covers the following topics: Vadose zone drilling site selection, permits and quality assurance (QA) procedures; climate change; geochemistry, mineralogy; disturbed zone; hydrogeology; and review of technical documents. The report is organized by generally discussing each topic from the following perspectives: issue(s), objective(s) of activity, finding(s), interpretation of finding(s), additional work needed, recommended program, and existing program

  5. Project W-236A, work plan for preparation of a design requirements document

    International Nuclear Information System (INIS)

    Groth, B.D.

    1995-01-01

    This work plan outlines the tasks necessary, and defines the organizational responsibilities for preparing a Design Requirements Document (DRD) for project W-236A, Multi-Function Waste Tank Facility (MWTF). A DRD is a Systems Engineering document which bounds, at a high level, the requirements of a discrete system element of the Tank Waste Remediation System (TWRS) Program. This system element is usually assigned to a specific project, in this case the MWTF. The DRD is the document that connects the TWRS program requirements with the highest level projects requirements and provides the project's link to the overall TWRS mission. The MWTF DRD effort is somewhat unique in that the project is already in detailed design, whereas a DRO is normally prepared prior to preliminary design. The MWTF design effort was initiated with a Functional Design Criteria (FDC) and a Supplemental Design Requirements Document (SDRD) bounding the high level requirements. Another unique aspect of this effort is that some of the TWRS program requirements are still in development. Because of these unique aspects of the MWTF DRD development, the MWTF will be developed from existing TWRS Program requirements and project specific requirements contained in the FDC and SDRD. The following list describes the objectives of the MWTF DRD: determine the primary functions of the tanks through a functional decomposition of the TWRS Program high level functions; allocate the primary functions to a sub-system architecture for the tanks; define the fundamental design features in terms of performance requirements for the system and subsystems; identify system interfaces and design constraints; and document the results in a DRD

  6. Optimizing experimental parameters for the projection requirement in HAADF-STEM tomography

    Energy Technology Data Exchange (ETDEWEB)

    Aveyard, R., E-mail: r.a.aveyard@tudelft.nl [Department of Imaging Physics, Delft University of Technology, 2628CJ Delft (Netherlands); Zhong, Z.; Batenburg, K.J. [Centrum Wiskunde and Informatica, Science Park 123, NL-1098 XG Amsterdam (Netherlands); Rieger, B., E-mail: b.rieger@tudelft.nl [Department of Imaging Physics, Delft University of Technology, 2628CJ Delft (Netherlands)

    2017-06-15

    Highlights: • The extent to which HAADF-STEM meets the projection requirement has been studied. • Multislice simulations used to model beam propagation and study signal linearity. • Propagation in crystalline and amorphous materials considered. • Optimal experimental set-up for the projection requirement is discussed. - Abstract: Tomographic reconstruction algorithms offer a means by which a tilt-series of transmission images can be combined to yield a three dimensional model of the specimen. Conventional reconstruction algorithms assume that the measured signal is a linear projection of some property, typically the density, of the material. Here we report the use of multislice simulations to investigate the extent to which this assumption is met in HAADF-STEM imaging. The use of simulations allows for a systematic survey of a range of materials and microscope parameters to inform optimal experimental design. Using this approach it is demonstrated that the imaging of amorphous materials is in good agreement with the projection assumption in most cases. Images of crystalline specimens taken along zone-axes are found to be poorly suited for conventional linear reconstruction algorithms due to channelling effects which produce enhanced intensities compared with off-axis images, and poor compliance with the projection requirement. Off-axis images are found to be suitable for reconstruction, though they do not strictly meet the linearity requirement in most cases. It is demonstrated that microscope parameters can be selected to yield improved compliance with the projection requirement.

  7. Optimizing experimental parameters for the projection requirement in HAADF-STEM tomography

    International Nuclear Information System (INIS)

    Aveyard, R.; Zhong, Z.; Batenburg, K.J.; Rieger, B.

    2017-01-01

    Highlights: • The extent to which HAADF-STEM meets the projection requirement has been studied. • Multislice simulations used to model beam propagation and study signal linearity. • Propagation in crystalline and amorphous materials considered. • Optimal experimental set-up for the projection requirement is discussed. - Abstract: Tomographic reconstruction algorithms offer a means by which a tilt-series of transmission images can be combined to yield a three dimensional model of the specimen. Conventional reconstruction algorithms assume that the measured signal is a linear projection of some property, typically the density, of the material. Here we report the use of multislice simulations to investigate the extent to which this assumption is met in HAADF-STEM imaging. The use of simulations allows for a systematic survey of a range of materials and microscope parameters to inform optimal experimental design. Using this approach it is demonstrated that the imaging of amorphous materials is in good agreement with the projection assumption in most cases. Images of crystalline specimens taken along zone-axes are found to be poorly suited for conventional linear reconstruction algorithms due to channelling effects which produce enhanced intensities compared with off-axis images, and poor compliance with the projection requirement. Off-axis images are found to be suitable for reconstruction, though they do not strictly meet the linearity requirement in most cases. It is demonstrated that microscope parameters can be selected to yield improved compliance with the projection requirement.

  8. 75 FR 18504 - International Cooperation on Harmonisation of Technical Requirements for Registration of...

    Science.gov (United States)

    2010-04-12

    ... which will facilitate the universal acceptance of the generated residue depletion data to fulfill this... design recommendations which will facilitate the universal acceptance of the generated residue depletion... ``requirement,'' unless FDA is using these words to describe a statutory or regulatory requirement. The draft...

  9. Spacelab user implementation assessment study. (Software requirements analysis). Volume 2: Technical report

    Science.gov (United States)

    1976-01-01

    The engineering analyses and evaluation studies conducted for the Software Requirements Analysis are discussed. Included are the development of the study data base, synthesis of implementation approaches for software required by both mandatory onboard computer services and command/control functions, and identification and implementation of software for ground processing activities.

  10. INFLUENCE OF ORGANIZATIONAL AND TECHNOLOGICAL SOLUTIONS TO TECHNICAL AND ECONOMICAL INDICATORS IN PROJECT OF HEAT INSULATION FACADES

    Directory of Open Access Journals (Sweden)

    BABIJ I. N. Cand. Sc. (Tech., Associate Professor,

    2016-09-01

    Full Text Available Summary. Raising of problem. The article dedicated to the solution important problems of choosing rational technical and economic indicators of the duration and cost the process heat insulation facades of buildings by means of experimental and statistical modeling organizational and technological solutions. For this we used the results of numerical experiment, theory a shorthand experiment planning and contemporary computer programs. Purpose. We used experimentally-statistical modeling to establish the impact of organizational and technological solutions for heat insulation of facades by hinged ventilated systems on technical and economic parameters of the project, such as duration and cost. Conclusion. We investigated depending duration assembly jobs and manufacturing cost on the value and combination of variable factors experimental and statistical modeling of construction processes and results patterns of change in studied parameters.

  11. MDRC's Career and Technical Education Projects. Issue Focus

    Science.gov (United States)

    MDRC, 2017

    2017-01-01

    The past decade has seen a resurgence of interest in career and technical education (CTE) as a way to engage students, help people build the skills necessary to succeed in a technologically advanced economy, and meet employer demand for workers. MDRC--which has a two-decade history of developing and evaluating CTE programs, including their…

  12. Diversifying Assessment through Multimedia Creation in a Non-Technical Module: Reflections on the MAIK Project

    Science.gov (United States)

    Cox, Andrew M.; Vasconcelos, Ana Cristina; Holdridge, Peter

    2010-01-01

    Creation of multimedia (MM) could be a valuable diversification of assessment methods within non-technical modules. The apparent popularity of sites based on user-generated video content such as YouTube and also of podcasting suggests that relevant skills and interest are becoming more mainstream. Translating book learned knowledge into visual…

  13. Scientific and Technical Serials Holdings Optimization in an Inefficient Market: A LSU Serials Redesign Project Exercise.

    Science.gov (United States)

    Bensman, Stephen J.; Wilder, Stanley J.

    1998-01-01

    Analyzes the structure of the library market for scientific and technical (ST) serials. Describes an exercise aimed at a theoretical reconstruction of the ST-serials holdings of Louisiana State University (LSU) Libraries. Discusses the set definitions, measures, and algorithms necessary in the design of a computer program to appraise ST serials.…

  14. PROJECT EVALUATION OF TECHNICAL CONDITION OF SHIP STRUCTURES WITH USE OF INFORMATION RETRIEVAL SYSTEMS

    Directory of Open Access Journals (Sweden)

    Юлия Алексеевна КАЗИМИРЕНКО

    2015-06-01

    Full Text Available The mechanisms for evaluation of technical conditions of ship constructions were investigated and was developed a new specialized informational and search system for the collection, analysis and processing the defects of new materials during the designing, construction, operation of ships and floating structures for transportation of goods 1, 4, 6-8 classes of danger.

  15. 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;…

  16. 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…

  17. 18 CFR 401.36 - Water supply projects-Conservation requirements.

    Science.gov (United States)

    2010-04-01

    ... 18 Conservation of Power and Water Resources 2 2010-04-01 2010-04-01 false Water supply projects-Conservation requirements. 401.36 Section 401.36 Conservation of Power and Water Resources DELAWARE RIVER BASIN... Compact § 401.36 Water supply projects—Conservation requirements. Maximum feasible efficiency in the use...

  18. Development of U.S. Government General Technical Requirements for UAS Flight Safety Systems Utilizing the Iridium Satellite Constellation

    Science.gov (United States)

    Murray, Jennifer; Birr, Richard

    2010-01-01

    This slide presentation reviews the development of technical requirements for Unmanned Aircraft Systems (UAS) utilization of the Iridium Satellite Constellation to provide flight safety. The Federal Aviation Authority (FAA) required an over-the-horizon communication standard to guarantee flight safety before permitting widespread UAS flights in the National Air Space (NAS). This is important to ensure reliable control of UASs during loss-link and over-the-horizon scenarios. The core requirement was to utilize a satellite system to send GPS tracking data and other telemetry from a flight vehicle down to the ground. Iridium was chosen as the system because it is one of the only true satellite systems that has world wide coverage, and the service has a highly reliable link margin. The Iridium system, the flight modems, and the test flight are described.

  19. The Development of a Project-Based Collaborative Technical Writing Model Founded on Learner Feedback in a Tertiary Aeronautical Engineering Program

    Science.gov (United States)

    Tatzl, Dietmar; Hassler, Wolfgang; Messnarz, Bernd; Fluhr, Holger

    2012-01-01

    The present article describes and evaluates collaborative interdisciplinary group projects initiated by content lecturers and an English-as-a-Foreign-Language (EFL) instructor for the purpose of teaching technical writing skills in an aeronautical engineering degree program. The proposed technical writing model is assessed against the results of a…

  20. Standardizing instream flow requirements at hydropower projects in the Cascade Mountains, Washington

    Energy Technology Data Exchange (ETDEWEB)

    Smith, I.M.; Sale, M.J.

    1993-06-01

    Instream flow requirements are common mitigation measures instituted in the bypassed reaches of hydroelectric diversion projects. Currently, there are two extremes among the ways to determine instream flow requirements: generic standard-setting methods and detailed, habitat-based, impact assessment methods such as the Instream Flow Incremental Methodology (IFIM). Data from streams in Washington state show a consistent pattern in the instream flow requirements resulting from the IFIM. This pattern can be used to refine the simpler standard-setting approaches and thereby provide better estimates of flow needs during early stages of project design.

  1. 76 FR 2683 - Notice of a Project Waiver of Section 1605: (Buy American Requirement) of the American Recovery...

    Science.gov (United States)

    2011-01-14

    ... to delay shovel ready projects by requiring entities, like the IEUA, to revise their design and... the ``shovel ready'' status for this project. Further delay of this project would contravene the most...

  2. 76 FR 18218 - Notice of a Project Waiver of Section 1605 (Buy American Requirement) of the American Recovery...

    Science.gov (United States)

    2011-04-01

    ... delay projects that are ``shovel ready'' by requiring cities such as Salt Lake City to revise their... unreasonable delay and thus displace the ``shovel ready'' status for this project. To further delay project...

  3. 76 FR 2684 - Notice of a Project Waiver of Section 1605 (Buy American Requirement) of the American Recovery...

    Science.gov (United States)

    2011-01-14

    ... construction, not to delay shovel ready projects by requiring entities, like Lake County, to revise their... thus displace the ``shovel ready'' status for this project. Further delay of this project would...

  4. MDEP VICWG-02 Technical Report - Survey on quality assurance program requirements

    International Nuclear Information System (INIS)

    2011-01-01

    The survey was prepared using the requirements of Appendix B to 10 CFR Part 50, 'Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants'. These requirements form the basis upon which the U.S. NRC oversees the activities of vendors providing parts and services to the commercial U.S. nuclear power industry. As discussed and agreed to at the October 2008 Vendor Inspection Cooperation Working Group meeting in Dijon, France, the survey that follows was developed using these requirements. The survey is divided into the 18 basic criteria of Appendix B to 10 CFR Part 50. Within each criteria there are individual requirements that have been identified as separate and distinct elements that are covered during the inspection of vendor activities. In addition to the requirements of Appendix B to 10 CFR Part 50, the requirements of 10 CFR Part 21, 'Reporting of Defects and Non-compliance', have been listed at the end of the survey as an example of 'Other Requirements Related To Vendor Inspections', for the NRC. (authors)

  5. Spring Chinook Supplementation Monitoring; Yakima Fisheries Project Management Plan, 1996 Technical Report.

    Energy Technology Data Exchange (ETDEWEB)

    Busack, Craig A. (Washington Department of Fish and Wildlife, Olympia, WA); Watson, Bruce; Johnston, Mark (Confederated Tribes and Bands of the Yakama Nation, Fisheries Resource Management, Toppenish, WA)

    1997-08-01

    The Yakima Fisheries Project (YFP), a key element in the Northwest Power Planning Council's Fish and Wildlife Program, has been in planning for more than ten years. It was initially conceived as, and is still intended to be, a multipurpose project. Besides increasing fish production in the Yakima basin, it is also intended to yield information about supplementation that will be of value to the entire Columbia basin, and hopefully the entire region. Because of this expectation of increased knowledge resulting from the project, a large and comprehensive monitoring program has always been seen as an integral part of the project. Despite the importance of monitoring to the project, monitoring planning has been slow to develop. The only general written statement of monitoring planning for the project is Chapter 9 of the current Project Status Report (PSR), written in 1993. That document is a reasonably good overview, and presents some important basic principles of monitoring, but is decidedly lacking in specifics. Throughout 1996 the Monitoring Implementation and Planning Team (MIPT), an interdisciplinary group of biologists who have worked on the project for several years, worked to develop a comprehensive spring chinook monitoring plan for the project. The result is the present document.

  6. [Implementation of the technical requirements of the UNE-EN-ISO 15189 quality standard in a mycobacterial laboratory].

    Science.gov (United States)

    Guna Serrano, M del Remedio; Ocete Mochón, M Dolores; Lahiguera, M José; Bresó, M Carmen; Gimeno Cardona, Concepción

    2013-02-01

    The UNE-EN-ISO 15189:2007 standard defines the requirements for quality and competence that must be met by medical laboratories. These laboratories should use this international standard to develop their own quality management systems and to evaluate their own competencies; in turn, this standard will be used by accreditation bodies to confirm or recognize the laboratories' competence. In clinical microbiology laboratories, application of the standard implies the implementation of the technical and specific management requirements that must be met to achieve optimal quality when carrying out microbiological tests. In Spain, accreditation is granted by the Spanish Accreditation Body (Entidad Nacional de Acreditación). This review aims to discuss the practical application of the standard's technical requirements in mycobacterial laboratory. Firstly, we define the scope of accreditation. Secondly, we specify how the items of the standard on personnel management, control of equipment, environmental facilities, method validation, internal controls and customer satisfaction surveys were developed and implemented in our laboratory. Copyright © 2013 Elsevier España, S.L. All rights reserved.

  7. Experimentation on accuracy of non functional requirement prioritization approaches for different complexity projects

    Directory of Open Access Journals (Sweden)

    Raj Kumar Chopra

    2016-09-01

    Full Text Available Non functional requirements must be selected for implementation together with functional requirements to enhance the success of software projects. Three approaches exist for performing the prioritization of non functional requirements using the suitable prioritization technique. This paper performs experimentation on three different complexity versions of the industrial software project using cost-value prioritization technique employing three approaches. Experimentation is conducted to analyze the accuracy of individual approaches and the variation of accuracy with the complexity of the software project. The results indicate that selecting non functional requirements separately, but in accordance with functionality has higher accuracy amongst the other two approaches. Further, likewise other approaches, it witnesses the decrease in accuracy with increase in software complexity but the decrease is minimal.

  8. 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…

  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. Final Technical Report: The Water-to-Wire (W2W) Project

    Energy Technology Data Exchange (ETDEWEB)

    Lissner, Daniel N. [Free Flow Power Corporation, Boston, MA (United States); Edward, Lovelace C. [Free Flow Power Corporation, Boston, MA (United States)

    2013-12-24

    The purpose of the Free Flow Power (FFP) Water-to-Wire Project (Project) was to evaluate and optimize the performance, environmental compatibility, and cost factors of FFP hydrokinetic turbines through design analyses and deployments in test flumes and riverine locations.

  11. Analysis of Aviation Safety Reporting System Incident Data Associated With the Technical Challenges of the Vehicle Systems Safety Technology Project

    Science.gov (United States)

    Withrow, Colleen A.; Reveley, Mary S.

    2014-01-01

    This analysis was conducted to support the Vehicle Systems Safety Technology (VSST) Project of the Aviation Safety Program (AVsP) milestone VSST4.2.1.01, "Identification of VSST-Related Trends." In particular, this is a review of incident data from the NASA Aviation Safety Reporting System (ASRS). The following three VSST-related technical challenges (TCs) were the focus of the incidents searched in the ASRS database: (1) Vechicle health assurance, (2) Effective crew-system interactions and decisions in all conditions; and (3) Aircraft loss of control prevention, mitigation, and recovery.

  12. OPTIMIZATION OF TIMES AND COSTS OF PROJECT OF HORIZONTAL LAMINATOR PRODUCTION USING PERT/CPM TECHNICAL

    Directory of Open Access Journals (Sweden)

    Fernando Henrique Lermen

    2016-09-01

    Full Text Available The PERT/CPM is a technique widely used in both the scheduling and in the project feasibility in terms of cost control and time.  In order to optimize time and costs involved in production, the work presented here aims to apply the PERT/CPM technique in the production project of the Horizontal Laminator, a machine used to cut polyurethane foam blocks in the mattresses industries. For the application of PERT/CPM technique in the project of Horizontal Laminator production were identified the activities that compose the project, the dependence between them, the normal and accelerated durations and the normal and accelerated costs. In this study, deterministic estimates for the duration of the activities were considered. The results show that the project can be completed in 520 hours at a total cost of R$7,042.50, when all activities are performed in their normal durations.  When all the activities that compose the critical path are accelerated, the project can be completed in 333.3 hours at a total cost of R$9,263.01. If the activities slacks have been exploited, it can obtain a final total cost of R$6,157.8, without changing the new duration of the project. It is noteworthy that the final total cost of the project if the slacks are used, will be lower than the initial cost. Regarding the initial cost of the project, after the application of the PERT/CPM technique, it presents a decrease of 12.56% of the total project cost.

  13. General laws of competition duel and universal requirements to technical-tactic fitness of elite wrestlers

    Directory of Open Access Journals (Sweden)

    G.V. Korobeynikov

    2016-02-01

    Full Text Available Purpose: to determine and formulate general technical-tactic laws (rules of competition duel in modern free style wrestling. Material: competition functioning of free style wrestlers at Olympic Games has been analyzed. Results of authors’ own pedagogic observations and advanced experience of free style wrestling specialists have been generalized. Results: it was found that victory in duel can be resulted only from attacking tactic of duel. It was determined that wrestlers’ activity (quantity of actual attacks in unit of time varies from 1 to 2.2 attacks per minute. Reliability of attack (ratio of quantity of assessed attacks to quantity of actually fulfilled attacks is within 0.33-0.63. Reliability of defense (ratio of quantity of successfully repelled opponent’s attacks to general quantity of his actual attacks is from 0.55-0.78. Efficiency of fighting in stance is within 0.6-1.3 points per minute. Efficiency of ground fighting is 1.3-2.3 points per minute. Conclusions: coach shall bring the formulated laws in compliance with specificity of his functioning and consider them, when planning training process of junior wrestlers.

  14. Probabilistic safety analysis of DC power supply requirements for nuclear power plants. Technical report

    International Nuclear Information System (INIS)

    Baranowsky, P.W.; Kolaczkowski, A.M.; Fedele, M.A.

    1981-04-01

    A probabilistic safety assessment was performed as part of the Nuclear Regulatory Commission generic safety task A-30, Adequacy of Safety Related DC Power Supplies. Event and fault tree analysis techniques were used to determine the relative contribution of DC power related accident sequences to the total core damage probability due to shutdown cooling failures. It was found that a potentially large DC power contribution could be substantially reduced by augmenting the minimum design and operational requirements. Recommendations included (1) requiring DC power divisional independence, (2) improved test, maintenance, and surveillance, and (3) requiring core cooling capability be maintained following the loss of one DC power bus and a single failure in another system

  15. Advanced Public Transportation Systems. Technical Assistance Brief 2

    Science.gov (United States)

    1993-01-01

    The Advanced Public Transportation Systems (APTS) Program requires evaluation : of pilot projects. This technical assistance brief discusses the guidelines set : for developing evaluation framework and methodology for local projects. 4p.

  16. Functions and requirements for Project W-236B, Initial Pretreatment Module: Revision 1

    International Nuclear Information System (INIS)

    Swanson, L.M.

    1994-01-01

    Hanford Site tank waste supernatants will be pretreated to separate the low-level and high-level fractions. The low-level waste fraction, containing the bulk of the chemical constituents, must be processed into a vitrified waste product which will be disposed of onsite, in a safe, environmentally sound, and cost effective manner. The high-level waste fraction separated during supernatant pretreatment (primarily cesium) will be recombined with an additional high-level waste fraction generated from pretreatment of the tank waste sludges and solids. This combined high-level waste fraction will be immobilized as glass and disposed in a geological repository. The purpose of this document is to establish the functional requirements baseline for Project W-236B, Initial Pretreatment Module, by defining the level 5 and 6 functions and requirements for the project. A functional analysis approach has been used to break down the program functions and associated physical requirements that each function must meet. As the systems engineering process evolves, the design requirements document will replace this preliminary functions and requirements document. The design requirements document (DRD) will identify key decisions and associated uncertainties that impact the project. A revision of this document to a DRD is not expected to change the performance requirements or open issues. However, additional requirements and issues may be identified

  17. 76 FR 57056 - International Cooperation on Harmonisation of Technical Requirements for Registration of...

    Science.gov (United States)

    2011-09-15

    ... guidance document is intended to provide study design recommendations that will facilitate the universal... objective of this guidance is to provide study design recommendations that will facilitate the universal... using these words to describe a statutory or regulatory requirement. This guidance represents the Agency...

  18. Technical insight on the requirements for CO2-saturated growth of microalgae in photobioreactors.

    Science.gov (United States)

    Yuvraj; Padmanabhan, Padmini

    2017-06-01

    Microalgal cultures are usually sparged with CO 2 -enriched air to preclude CO 2 limitation during photoautotrophic growth. However, the CO 2 vol% specifically required at operating conditions to meet the carbon requirement of algal cells in photobioreactor is never determined and 1-10% v/v CO 2 -enriched air is arbitrarily used. A scheme is proposed and experimentally validated for Chlorella vulgaris that allows computing CO 2 -saturated growth feasible at given CO 2 vol% and volumetric O 2 mass-transfer coefficient (k L a) O . CO 2 sufficiency in an experiment can be theoretically established to adjust conditions for CO 2 -saturated growth. The methodology completely eliminates the requirement of CO 2 electrode for online estimation of dissolved CO 2 to determine critical CO 2 concentration (C crit ), specific CO 2 uptake rate (SCUR), and volumetric CO 2 mass-transfer coefficient (k L a) C required for the governing CO 2 mass-transfer equation. C crit was estimated from specific O 2 production rate (SOPR) measurements at different dissolved CO 2 concentrations. SCUR was calculated from SOPR and photosynthetic quotient (PQ) determined from the balanced stoichiometric equation of growth. Effect of light attenuation and nutrient depletion on biomass estimate is also discussed. Furthermore, a simple design of photosynthetic activity measurement system was used, which minimizes light attenuation by hanging a low depth (ca. 10 mm) culture over the light source.

  19. Overview on seismic evaluation and retrofitting within JICA Technical Cooperation Project on reduction of seismic risk in Romania

    International Nuclear Information System (INIS)

    Seki, M.; Vacareanu, R.; Pavel, M.; Lozinca, E.; Cotofana, D.; Chesca, B.; Georgescu, B.; Kaminosono, T.

    2007-01-01

    The objective of this paper is to give an overview on the seismic evaluation and retrofitting procedures of reinforced concrete buildings within JICA technical cooperation project in Romania. The content of the paper covers a) an outline of the seismic evaluation; history and comparison of Romanian seismic design codes with the Japanese seismic evaluation guidelines, b) an outline of the retrofitting techniques which were transferred from Japan to Romania and structural tests for retrofitting techniques employed in Romania and c) retrofitting details that were used by JICA/NCSRR in the retrofitting design of two vulnerable buildings in Bucharest. The above-mentioned retrofitting projects are now under development of detailed design and therefore, in the near future, refining and improvement of solutions will be performed. (authors)

  20. Teaching Power Electronics with a Design-Oriented and Project-Based Learning Method at the Technical University of Denmark

    DEFF Research Database (Denmark)

    Zhang, Zhe; Hansen, Claus Thorp; Andersen, Michael A. E.

    2016-01-01

    Power electronics is a fast developing technology within the electrical engineering field. This paper presents the results and experiences gained from DesignOriented Project Based Learning of switch-mode power supply design within a power electronics course at the Technical University of Denmark...... (DTU). Project-based learning (PBL) is known to be a motivating and problem-centered teaching method that not only places students at the core of the teaching and learning activities but also gives students the ability to transfer their acquired scientific knowledge into industrial practices. Students...... are asked to choose a specification from different power converter applications such as a fuel cell power conditioning converter, a light-emitting diode (LED) driver or a battery charger. Based upon their choice, the students select topology, design magnetic components, calculate input/output filters...