WorldWideScience

Sample records for site development design

  1. Site development

    International Nuclear Information System (INIS)

    Gaynor, R.K.

    1989-01-01

    Development of a low-level radioactive waste land disposal facility is little different than any industrial development of similar scope. Consideration must be made for normal business and operations management, security, facility maintenance, traffic control and necessary amenities for personnel. The item specific to the low-level waste site is the handling of radioactive waste materials and the regulatory and environmental protection procedures that must be planned for and accomodated in the site design and development. Each of these elements and the facility as a whole must be designed to be compatible with local land use plans, available transportation and support services, and the social and economic goals of the local community. Plans should also be made for quality control and orderly construction. This chapter deals with those aspects of the facility, its design and construction which are integral parts to the overall performance of the site

  2. Designing a responsive web site

    OpenAIRE

    Fejzić , Diana

    2016-01-01

    Due to the increasing prevalence of smartphones and tablet computers design became a crucial part of web design. For a user, responsive web design enables the best user experience, regardless of whether a user is visiting the site via a mobile phone, a tablet or a computer. This thesis covers the process of planning, designing and responsive web site development, for a fictitious company named “Creative Design d.o.o.”, with the help of web technologies. In the initial part of the thesis, w...

  3. Development of a design basis tornado and structural design criteria for the Nevada Test Site, Nevada. Final report

    International Nuclear Information System (INIS)

    McDonald, J.R.; Minor, J.E.; Mehta, K.C.

    1975-06-01

    In order to evaluate the ability of critical facilities at the Nevada Test Site to withstand the possible damaging effects of extreme winds and tornadoes, parameters for the effects of tornadoes and extreme winds and structural design criteria for the design and evaluation of structures were developed. The meteorological investigations conducted are summarized, and techniques used for developing the combined tornado and extreme wind risk model are discussed. The guidelines for structural design include methods for calculating pressure distributions on walls and roofs of structures and methods for accommodating impact loads from wind-driven missiles. Calculations for determining the design loads for an example structure are included

  4. Development of a design basis tornado and structural design criteria for Lawrence Livermore Laboratory's Site 300

    International Nuclear Information System (INIS)

    McDonald, J.R.; Minor, J.E.; Mehta, K.C.

    1975-11-01

    Criteria are prescribed and guidance is provided for professional personnel who are involved with the evaluation of existing buildings and facilities at Site 300 near Livermore, California to resist the possible effects of extreme winds and tornadoes. The development of parameters for the effects of tornadoes and extreme winds and guidelines for evaluation and design of structures are presented. The investigations conducted are summarized and the techniques used for arriving at the combined tornado and extreme wind risk model are discussed. The guidelines for structural design methods for calculating pressure distributions on walls and roofs of structures and methods for accommodating impact loads from missiles are also presented

  5. The development of quality management techniques in civil engineering design and site supervision

    International Nuclear Information System (INIS)

    Cowan, A.J.

    1991-01-01

    Quality assurance techniques have developed considerably over the past few years, and in particular the application of Quality Management within a service industry such as civil engineering has evolved into a well developed management control system. James Williamson and Partners were the first members of the Association of Consulting Engineers successfully to achieve third party accreditation with BSI for civil and structural design. The initial system was generated for work on Torness Power Station in the early 1980s, and the firm has, in the last ten years, developed a flexible quality system to effectively control and co-ordinate complex projects. This paper discusses the use of quality assurance (QA) techniques in a civil engineering design office, looking at a few areas where the requirements of BS 5750 and BS 5882 are difficult to interpret. Some observations are also made on the adoption of QA for site supervision. (author)

  6. Conceptual design report, TWRS Privatization Phase I, site development and roads, subproject W-505

    International Nuclear Information System (INIS)

    Singh, G.

    1997-01-01

    This document includes Conceptual Design Report (CDR) for the site development, construction of new roads and improvements at existing road intersections, habitat mitigation, roadway lighting, and construction power needed for the construction of two Private Contractor (PC) Facilities. Approximately 50 hectare (124 acres) land parcel, east of the Grout Facility, is planned for the PC facilities

  7. Development of a Online Nuclear Emergency Response System (ONERS) for Kalpakkam site - the design aspects

    Energy Technology Data Exchange (ETDEWEB)

    Raja Shekhar, S. S.; Bhatawadekar, Shantanu; Krishna Murthy, Y. V.N., [Regional Remote Sensing Service Centre, Department of Space, Nagpur (India); Srinivas, C. V.; Venkatesan, [Radiological Safety Division, Radiological Safety and Environmental Group, Indira Gandhi Centre for Atomic Research, Kalapakkam (India)

    2012-07-01

    An Online Nuclear Emergency Response System (ONERS) is developed for the nuclear power plant site at Kalpakkam as part of the Department of Atomic Energy (DAE) initiative. ONERS is a GIS based spatial analysis system designed indigenously to provide decision support in the event of a radioactive leak or accident from any of the nuclear facilities by assessing the dispersion and deposition patterns of the atmospheric releases, integrate with spatial geographical database for impact assessment and guidance for mitigation. The system is designed with open software tools (UMN Map server, MYSQL, PHP, Java scripts) and its main features include assessment of dose, short and long term forecast, counter measure support, impact assessment to minimize potential threat to man and environment during radiological emergencies. The system is implemented in live mode with integration of numerical models and spatial data base for the site region and is presently operational for the Kalpakkam site. (author)

  8. Development of a Online Nuclear Emergency Response System (ONERS) for Kalpakkam site - the design aspects

    International Nuclear Information System (INIS)

    Raja Shekhar, S.S.; Bhatawadekar, Shantanu; Krishna Murthy, Y.V.N.; Srinivas, C.V.; Venkatesan

    2012-01-01

    An Online Nuclear Emergency Response System (ONERS) is developed for the nuclear power plant site at Kalpakkam as part of the Department of Atomic Energy (DAE) initiative. ONERS is a GIS based spatial analysis system designed indigenously to provide decision support in the event of a radioactive leak or accident from any of the nuclear facilities by assessing the dispersion and deposition patterns of the atmospheric releases, integrate with spatial geographical database for impact assessment and guidance for mitigation. The system is designed with open software tools (UMN Map server, MYSQL, PHP, Java scripts) and its main features include assessment of dose, short and long term forecast, counter measure support, impact assessment to minimize potential threat to man and environment during radiological emergencies. The system is implemented in live mode with integration of numerical models and spatial data base for the site region and is presently operational for the Kalpakkam site. (author)

  9. Design characteristics of EU-APR1400 on-site power system

    International Nuclear Information System (INIS)

    Kim, D.H.; Kim, Y.S.; Kim, Y.S.

    2014-01-01

    In the global nuclear market, US and European design requirements have been largely used to develop the design of nuclear power plants(NPPs). The APR1400 design was developed on the basis of US regulatory guide and EPRI utility requirements document(URD). In order to enlarge the export market of APR1400, KHNP (Korea Hydro & Nuclear Power Co., Ltd) has developed the EU-APR1400 design which complies with the European nuclear design requirements. In this paper, the design characteristics of EU-APR1400 on-site power system developed according to the European design requirements of electrical power system are described. The European main design requirements of electrical power system involve 50 Hz rated frequency, 400/110 kV grid voltage, the application of the diversity and the redundancy, and so on. The EU-APR1400 on-site power system has been developed on the basis of these requirements. The representative designs include the redundancy, diversity, independence design, the emergency power supply design, the design for providing electrical power to the dedicated severe accident systems, and the design for European grid requirements. (author)

  10. 41 CFR 102-76.55 - What sustainable development principles must Federal agencies apply to the siting, design, and...

    Science.gov (United States)

    2010-07-01

    ... and Construction Sustainable Development § 102-76.55 What sustainable development principles must... Acquisition,” Federal agencies must apply sustainable development principles to the siting, design, and... 41 Public Contracts and Property Management 3 2010-07-01 2010-07-01 false What sustainable...

  11. Technology development for the design of shallow land burial facilities at arid sites

    International Nuclear Information System (INIS)

    Nyhan, J.W.; Abeele, W.V.; Cokal, E.J.; Perkins, B.A.; Lane, L.J.

    1984-01-01

    The field research program involving technology development for arid shallow land burial (SLB) sites is described. Field tests of biointrusion barriers at waste disposal sites and in experimental plots at Los Alamos are reported. Results of completed and on-going experiments with migration barriers for water and contaminant movement are presented. An envelope wick experiment for subsurface water management is described, and preliminary field data are reported. An integrated field experiment was designed to test individual SLB component tests related to erosion control, biobarriers, and subsurface capillary and migration barriers, and the progress made in emplacing the experiment is presented. Efforts to utilize the field data collected to validate hydrologic models (TRACR3D) important to waste management strategies are also presented. 11 references, 14 figures, 1 table

  12. Status of small reactor designs without on-site refuelling

    International Nuclear Information System (INIS)

    2007-01-01

    There is an ongoing interest in member states in the development and application of small and medium sized reactors (SMRs). In the near term, most new NPPs are likely to be evolutionary designs building on proven systems while incorporating technological advances and often the economics of scale, resulting from the reactor outputs of up to 1600 MW(e). For the longer term, the focus is on innovative designs aiming to provide increased benefits in the areas of safety and security, non-proliferation, waste management, resource utilization and economy, as well as to offer a variety of energy products and flexibility in design, siting and fuel cycle options. Many innovative designs are reactors within the small-to-medium size range, having an equivalent electric power less than 700 MW(e) or even less than 300 MW(e). A distinct trend in design and technology development, accounting for about half of the SMR concepts developed worldwide, is represented by small reactors without on-site refuelling. Such reactors, also known as battery-type reactors, could operate without reloading and shuffling of fuel in the core over long periods, from 5 to 25 years and beyond. Upon the advice and with the support of IAEA member states, within its Programme 1 'Nuclear Power, Fuel Cycle, and Nuclear Science', the IAEA provides a forum for the exchange of information by experts and policy makers from industrialized and developing countries on the technical, economic, environmental, and social aspects of SMRs development and implementation in the 21st century, and makes this information available to all interested Member States by producing status reports and other publications dedicated to advances in SMR technology. The objective of this report is to provide Member States, including those just considering the initiation of nuclear power programmes and those already having practical experience in nuclear power, with a balanced and objective information on important development trends and

  13. A design method for an intuitive web site

    Energy Technology Data Exchange (ETDEWEB)

    Quinniey, M.L.; Diegert, K.V.; Baca, B.G.; Forsythe, J.C.; Grose, E.

    1999-11-03

    The paper describes a methodology for designing a web site for human factor engineers that is applicable for designing a web site for a group of people. Many web pages on the World Wide Web are not organized in a format that allows a user to efficiently find information. Often the information and hypertext links on web pages are not organized into intuitive groups. Intuition implies that a person is able to use their knowledge of a paradigm to solve a problem. Intuitive groups are categories that allow web page users to find information by using their intuition or mental models of categories. In order to improve the human factors engineers efficiency for finding information on the World Wide Web, research was performed to develop a web site that serves as a tool for finding information effectively. The paper describes a methodology for designing a web site for a group of people who perform similar task in an organization.

  14. Development of technology for the design of shallow land burial facilities at arid sites

    International Nuclear Information System (INIS)

    Nyhan, J.W.; Abeele, W.V.; Drennon, B.J.; Herrera, W.J.; Lopez, E.A.; Langhorst, G.J.; Stallings, E.A.; Walker, R.D.; Martinez, J.L.

    1985-01-01

    The Los Alamos field research program involving technology development for arid shallow land burial (SLB) sites is described. Field data are presented for an integrated field experiment, which was designed to test individual SLB component experiments related to erosion control, biobarriers, and subsurface capillary and migration barriers. Field tests of biointrusion barriers at waste disposal sites and in experimental plots are reported. The results of a joint DOE/NRC experiment to evaluate leaching and transport of sorbing (Cs, Sr, Li) and nonsorbing (I, Br) solutes in sandy silt backfill are presented for steady-state and unsteady-state flow conditions. A capillary barrier experiment performed in a large caisson (3-m diameter, 6.1 m deep) is described and a year's worth of field data is presented

  15. Site-specific design optimization of wind turbines

    DEFF Research Database (Denmark)

    Fuglsang, P.; Bak, C.; Schepers, J.G.

    2002-01-01

    This article reports results from a European project, where site characteristics were incorporated into the design process of wind turbines, to enable site-specific design. Two wind turbines of different concept were investigated at six different sites comprising normal flat terrain, offshore...... and complex terrain wind farms. Design tools based on numerical optimization and aeroelastic calculations were combined with a cost model to allow optimization for minimum cost of energy. Different scenarios were optimized ranging from modifications of selected individual components to the complete design...... of a new wind turbine. Both annual energy yield and design-determining loads depended on site characteristics, and this represented a potential for site-specific design. The maximum variation in annual energy yield was 37% and the maximum variation in blade root fatigue loads was 62%. Optimized site...

  16. Repository surface design site layout analysis

    International Nuclear Information System (INIS)

    Montalvo, H.R.

    1998-01-01

    The purpose of this analysis is to establish the arrangement of the Yucca Mountain Repository surface facilities and features near the North Portal. The analysis updates and expands the North Portal area site layout concept presented in the ACD, including changes to reflect the resizing of the Waste Handling Building (WHB), Waste Treatment Building (WTB), Carrier Preparation Building (CPB), and site parking areas; the addition of the Carrier Washdown Buildings (CWBs); the elimination of the Cask Maintenance Facility (CMF); and the development of a concept for site grading and flood control. The analysis also establishes the layout of the surface features (e.g., roads and utilities) that connect all the repository surface areas (North Portal Operations Area, South Portal Development Operations Area, Emplacement Shaft Surface Operations Area, and Development Shaft Surface Operations Area) and locates an area for a potential lag storage facility. Details of South Portal and shaft layouts will be covered in separate design analyses. The objective of this analysis is to provide a suitable level of design for the Viability Assessment (VA). The analysis was revised to incorporate additional material developed since the issuance of Revision 01. This material includes safeguards and security input, utility system input (size and location of fire water tanks and pump houses, potable water and sanitary sewage rates, size of wastewater evaporation pond, size and location of the utility building, size of the bulk fuel storage tank, and size and location of other exterior process equipment), main electrical substation information, redundancy of water supply and storage for the fire support system, and additional information on the storm water retention pond

  17. Preliminary site design for the SP-100 ground engineering test

    International Nuclear Information System (INIS)

    Cox, C.M.; Miller, W.C.; Mahaffey, M.K.

    1986-04-01

    In November, 1985, Hanford was selected by the Department of Energy (DOE) as the preferred site for a full-scale test of the integrated nuclear subsystem for SP-100. The Hanford Engineering Development Laboratory, operated by Westinghouse Hanford Company, was assigned as the lead contractor for the Test Site. The nuclear subsystem, which includes the reactor and its primary heat transport system, will be provided by the System Developer, another contractor to be selected by DOE in late FY-1986. In addition to reactor operations, test site responsibilities include preparation of the facility plus design, procurement and installation of a vacuum chamber to house the reactor, a secondary heat transport system to dispose of the reactor heat, a facility control system, and postirradiation examination. At the conclusion of the test program, waste disposal and facility decommissioning are required. The test site must also prepare appropriate environmental and safety evaluations. This paper summarizes the preliminary design requirements, the status of design, and plans to achieve full power operation of the test reactor in September, 1990

  18. Part 2: Conserving and Planting Trees at Development Sites

    Science.gov (United States)

    Karen Cappiella; Tom Schueler; Tiffany Wright

    2006-01-01

    This manual presents specific ways to enable developers, engineers or landscape architects to incorporate more trees into a development site. The proposed approach focuses on protecting existing trees, planting trees in storm water treatment practices, and planting trees in other open spaces at the development site. This manual introduces conceptual designs for storm...

  19. The content and design of Web sites : an empirical study

    NARCIS (Netherlands)

    Huizingh, EKRE

    2000-01-01

    To support the emergence of a solid knowledge base for analyzing Web activity, we have developed a framework to analyze and categorize the capabilities of Web sites. This distinguishes content from design. Content refers to the information, features, or services that are offered in the Web site,

  20. Development of in-structure design spectra for dome mounted equipment on underground waste storage tanks at the Hanford Site

    International Nuclear Information System (INIS)

    Julyk, L.J.

    1995-09-01

    In-structure response spectra for dome mounted equipment on underground waste storage tanks at the Hanford Site are developed on the basis of recent soil-structure-interaction analyses. Recommended design spectra are provided for various locations on the tank dome

  1. OSU TOMF Program Site Selection and Preliminary Concept Design Report

    Energy Technology Data Exchange (ETDEWEB)

    Spadling, Steve [Oklahoma State Univ., Stillwater, OK (United States)

    2012-05-10

    The purpose of this report is to confirm the programmatic requirements for the new facilities, identify the most appropriate project site, and develop preliminary site and building concepts that successfully address the overall project goals and site issues. These new facilities will be designed to accommodate the staff, drivers and maintenance requirements for the future mixed fleet of passenger vehicles, Transit Style Buses and School Buses.

  2. Hanford Site Development Plan

    International Nuclear Information System (INIS)

    Rinne, C.A.; Curry, R.H.; Hagan, J.W.; Seiler, S.W.; Sommer, D.J.; Yancey, E.F.

    1990-01-01

    The Hanford Site Development Plan (Site Development Plan) is intended to guide the short- and long-range development and use of the Hanford Site. All acquisition, development, and permanent facility use at the Hanford Site will conform to the approved plan. The Site Development Plan also serves as the base document for all subsequent studies that involve use of facilities at the Site. This revision is an update of a previous plan. The executive summary presents the highlights of the five major topics covered in the Site Development Plan: general site information, existing conditions, planning analysis, Master Plan, and Five-Year Plan. 56 refs., 67 figs., 31 tabs

  3. Hanford Site Development Plan

    Energy Technology Data Exchange (ETDEWEB)

    Rinne, C.A.; Curry, R.H.; Hagan, J.W.; Seiler, S.W.; Sommer, D.J. (Westinghouse Hanford Co., Richland, WA (USA)); Yancey, E.F. (Pacific Northwest Lab., Richland, WA (USA))

    1990-01-01

    The Hanford Site Development Plan (Site Development Plan) is intended to guide the short- and long-range development and use of the Hanford Site. All acquisition, development, and permanent facility use at the Hanford Site will conform to the approved plan. The Site Development Plan also serves as the base document for all subsequent studies that involve use of facilities at the Site. This revision is an update of a previous plan. The executive summary presents the highlights of the five major topics covered in the Site Development Plan: general site information, existing conditions, planning analysis, Master Plan, and Five-Year Plan. 56 refs., 67 figs., 31 tabs.

  4. Design Status and Applications of Small reactors without On-site Refuelling

    International Nuclear Information System (INIS)

    Kuznetsov, V.

    2006-01-01

    Small reactors without on-site refuelling are the reactors that can operate without reloading and shuffling of fuel for a reasonably long period, consistent with plant economy and considerations of energy security, with no fresh or spent fuel being stored at a site during reactor operation. Such reactors could simplify the implementation of safeguards and provide certain guarantees of sovereignty to those countries that would prefer to lease fuel from a foreign vendor or, perhaps, an international fuel cycle centre. About 30 concepts of such reactors are being analyzed or developed in 6 IAEA Member States. They cover all principle reactor lines: water cooled, fast gas cooled, sodium cooled, lead or lead bismuth cooled and molten salt cooled reactors. An increased refuelling interval could be achieved with reduced core power density, burnable absorbers, or high conversion ratio. The design goals for small reactors without on-site refuelling, inter alia, include: difficult unauthorized access to fuel; design provisions to facilitate the implementation of safeguards; capability to survive all postulated accident scenarios without requiring emergency response in the public domain; economic competitiveness for anticipated market conditions and applications; the capability to achieve higher manufacturing quality through factory mass production, design standardization and common basis for design certification; and a flexibility in siting and applications. Such reactors are often considered in conjunction with fuel or NPP leasing Small reactors without on-site refuelling have many common technology development issues related to the provision of lifetime core operation, economic competitiveness, high level of safety and proliferation resistance. Reestablishment of a practice of licensing by test and establishment of legal provisions and the insurance scheme for a transit of fuel loads or factory fabricated reactors through the territory of a third country are mentioned as

  5. Development and Application of SITES

    International Nuclear Information System (INIS)

    Park, Jo Wan; Yoon; Yoon, Jeong Hyoun; Kim, Chank Lak; Cho, Sung IL

    2008-01-01

    SITES (Site Information and Total Environmental Data Management System) has been developed for the purpose of systematically managing site characteristics and environmental data produced during the pre-operational, operational, and post-closure phases of a radioactive waste disposal facility. SITES is an integration system, which consists of 4 modules, to be available for maintenance of site characteristics data, for safety assessment, and for site/environment monitoring; site environmental data management module (SECURE), integrated safety assessment module (SAINT), site/environment monitoring module (SUDAL) and geological information module for geological data management (SITES-GIS). Each module has its database with the functions of browsing, storing, and reporting data and information. Data from SECURE and SUDAL are interconnected to be utilized as inputs to SAINT. SAINT has the functions that multi-user can access simultaneously via client-server system, and the safety assessment results can be managed with its embedded Quality Assurance feature. Comparison between assessment results and environmental monitoring data can be made and visualized in SUDAL and SITES-GIS. Also, SUDAL is designed that the periodic monitoring data and information could be opened to the public via internet homepage. SITES has applied to the Wolsong low- and intermediate-level radioactive waste disposal center in Korea, and is expected to enhance the function of site/environment monitoring in other nuclear-related facilities and also in industrial facilities handling hazardous materials.

  6. Quantum mechanical design of enzyme active sites.

    Science.gov (United States)

    Zhang, Xiyun; DeChancie, Jason; Gunaydin, Hakan; Chowdry, Arnab B; Clemente, Fernando R; Smith, Adam J T; Handel, T M; Houk, K N

    2008-02-01

    The design of active sites has been carried out using quantum mechanical calculations to predict the rate-determining transition state of a desired reaction in presence of the optimal arrangement of catalytic functional groups (theozyme). Eleven versatile reaction targets were chosen, including hydrolysis, dehydration, isomerization, aldol, and Diels-Alder reactions. For each of the targets, the predicted mechanism and the rate-determining transition state (TS) of the uncatalyzed reaction in water is presented. For the rate-determining TS, a catalytic site was designed using naturalistic catalytic units followed by an estimation of the rate acceleration provided by a reoptimization of the catalytic site. Finally, the geometries of the sites were compared to the X-ray structures of related natural enzymes. Recent advances in computational algorithms and power, coupled with successes in computational protein design, have provided a powerful context for undertaking such an endeavor. We propose that theozymes are excellent candidates to serve as the active site models for design processes.

  7. Hanford Site Development Plan

    International Nuclear Information System (INIS)

    Hathaway, H.B.; Daly, K.S.; Rinne, C.A.; Seiler, S.W.

    1993-05-01

    The Hanford Site Development Plan (HSDP) provides an overview of land use, infrastructure, and facility requirements to support US Department of Energy (DOE) programs at the Hanford Site. The HSDP's primary purpose is to inform senior managers and interested parties of development activities and issues that require a commitment of resources to support the Hanford Site. The HSDP provides an existing and future land use plan for the Hanford Site. The HSDP is updated annually in accordance with DOE Order 4320.1B, Site Development Planning, to reflect the mission and overall site development process. Further details about Hanford Site development are defined in individual area development plans

  8. PHWR safety: design, siting and construction

    International Nuclear Information System (INIS)

    Sharma, V.K.

    2002-01-01

    In all activities associated with NPPs viz. siting, design, construction, commissioning and operation, safety is given overriding importance. The safety design principles of PHWRs are based on defence-in-depth approach, physical and functional separation between process and safety systems and also among various safety systems, redundancy to meet single failure criteria and postulation of a number of design basis events for which the plant must be designed. Apart from engineered safety systems, PHWRs have inherent characteristics which contribute to safety. In siting of a NPP, it is required to ensure that the given site does not pose undue radiological hazard to public and the environment both during normal operation as well as during and following an accident condition. For this purpose, all site related external events, both natural and man induced, are assessed for their effect on the plant and are considered as part of the design basis. Possible radiological impact of the NPP on environment and surrounding population is assessed and ensured to be within acceptable limits. During construction phase, it is essential that the NPP be built in accordance with design intent and with required quality of workmanship to ensure that the NPP will remain safe during all states of operation. This is achieved through careful execution and QA activities encompassing all aspects of component fabrication at manufacturer works, civil construction, site erection, assembly, and commissioning. Future trends in nuclear safety will continue to be based on existing principles which have proved to be sound. These will be further strengthened by features such as increasing use of passive means of performing safety functions and a more explicit treatment of severe accidents. (author)

  9. Development of on-site spent fuel transfer system designs

    International Nuclear Information System (INIS)

    Lambert, R.W.; Pennington, C.W.; Guerra, G.V.

    1993-01-01

    The Electric Power Research Institute (EPRI) of the United States has sponsored development of conceptual designs for accomplishing spent fuel transfer from spent fuel pools to casks and from one cask to another. Under an EPRI research contract, transnuclear has developed several concepts for spent fuel transfer systems. (J.P.N.)

  10. Beyond Information Architecture: A Systems Integration Approach to Web-site Design

    Directory of Open Access Journals (Sweden)

    Krisellen Maloney

    2017-09-01

    Full Text Available Users' needs and expectations regarding access to information have fundamentally changed, creating a disconnect between how users expect to use a library Web site and how the site was designed. At the same time, library technical infrastructures include legacy systems that were not designedf or the Web environment. The authors propose a framework that combines elements of information architecture with approaches to incremental system design and implementation. The framework allows for the development of a Web site that is responsive to changing user needs, while recognizing the need for libraries to adopt a cost-effective approach to implementation and maintenance.

  11. Hanford Site Development Plan

    International Nuclear Information System (INIS)

    Hathaway, H.B.; Daly, K.S.; Rinne, C.A.; Seiler, S.W.

    1992-05-01

    The Hanford Site Development Plan (HSDP) provides an overview of land use, infrastructure, and facility requirements to support US Department of Energy (DOE) programs at the Hanford Site. The HSDP's primary purpose is to inform senior managers and interested parties of development activities and issues that require a commitment of resources to support the Hanford Site. The HSDP provides a land use plan for the Hanford Site and presents a picture of what is currently known and anticipated in accordance with DOE Order 4320.1B. Site Development Planning. The HSDP wig be updated annually as future decisions further shape the mission and overall site development process. Further details about Hanford Site development are defined in individual area development plans

  12. Direct-to-consumer advertising via the Internet: the role of Web site design.

    Science.gov (United States)

    Sewak, Saurabh S; Wilkin, Noel E; Bentley, John P; Smith, Mickey C

    2005-06-01

    Recent attempts to propose criteria for judging the quality of pharmaceutical and healthcare Web sites do not distinguish between attributes of Web site design related to content and other attributes not related to the content. The Elaboration Likelihood Model from persuasion literature is used as a framework for investigating the effects of Web site design on consequents like attitude and knowledge acquisition. A between-subjects, 2 (high or low involvement)x2 (Web site designed with high or low aspects of visual appeal) factorial design was used in this research. College students were randomly assigned to these treatment groups yielding a balanced design with 29 observations per treatment cell. Analysis of variance results for the effects of involvement and Web site design on attitude and knowledge indicated that the interaction between the independent variables was not significant in both analyses. Examination of main effects revealed that participants who viewed the Web site with higher visual appeal actually had slightly lower knowledge scores (6.32) than those who viewed the Web site with lower visual appeal (7.03, F(1,112)=3.827, P=.053). Results of this research seem to indicate that aspects of Web site design (namely aspects of visual appeal and quality) may not play a role in attaining desired promotional objectives, which can include development of favorable attitudes toward the product and facilitating knowledge acquisition.

  13. A User-centered Model for Web Site Design

    Science.gov (United States)

    Kinzie, Mable B.; Cohn, Wendy F.; Julian, Marti F.; Knaus, William A.

    2002-01-01

    As the Internet continues to grow as a delivery medium for health information, the design of effective Web sites becomes increasingly important. In this paper, the authors provide an overview of one effective model for Web site design, a user-centered process that includes techniques for needs assessment, goal/task analysis, user interface design, and rapid prototyping. They detail how this approach was employed to design a family health history Web site, Health Heritage . This Web site helps patients record and maintain their family health histories in a secure, confidential manner. It also supports primary care physicians through analysis of health histories, identification of potential risks, and provision of health care recommendations. Visual examples of the design process are provided to show how the use of this model resulted in an easy-to-use Web site that is likely to meet user needs. The model is effective across diverse content arenas and is appropriate for applications in varied media. PMID:12087113

  14. Development of a design package for a viscous barrier at the Savannah River Site

    International Nuclear Information System (INIS)

    Moridis, G.J.; James, A.; Oldenburg, C.

    1996-10-01

    This paper describes elements of a design for a pilot-scale field demonstration of a new subsurface containment technology for waste isolation developed at the Lawrence Berkeley National Laboratory (LBNL), which uses a new generation of barrier liquids for permeation grouting. The demonstration site was Retention Basin 281-3H, a shallow catchment basin at the Savannah River Site (SRS), originally built to control contaminated runoff for the H Reactor, and which has been contaminated mainly by radionuclides. The LBNL viscous barrier technology employs barrier liquids which, when injected into the subsurface, produce chemically benign nearly impermeable barriers through a very large increase in viscosity. The initially low-viscosity liquids are emplaced through multiple injection points in the subsurface and the intersecting plumes merge and completely surround the contaminant source and/or plume. Once in place, they gel or cure to form a nearly impermeable barrier. The barrier liquid to be used in this application is Colloidal Silica (CS), an aqueous suspension of silica microspheres in a stabilizing electrolyte. It has excellent durability characteristics, poses no health hazard, is practically unaffected by filtration, and is chemically and biologically benign

  15. SLAC site design aesthetics

    International Nuclear Information System (INIS)

    Hall, F.F.

    1985-10-01

    Stanford Linear Accelerator Center (SLAC) is a single mission laboratory dedicated to basic research in high energy particle physics. SLAC site also houses Stanford Synchrotron Radiation Laboratory (SSRL) which is a multi-mission laboratory for research using beams of ultraviolet light and low energy photons as emitted tangentially from SLAC colliding beam facilities. This paper discusses various aspects of SLAC site design aesthetics under the following headings: (1) imposed footprint of SLAC, (2) description of selected site, (3) use of earth cover for radiation and sight screens, (4) use of landscaping for cosmetic purposes, (5) use of exterior paint colors to soften SLAC impact on neighbors, (6) relocation of SLAC main entrance, (7) relocation of SLAC collider arcs and experimental hall, (8) parking lots and storage yards, and (9) land use zoning at SLAC

  16. WSDM : A user-centred design method for web sites

    NARCIS (Netherlands)

    de Troyer, O.M.F.; Leune, C.J.

    1998-01-01

    WSDM is a user-centered method for the design of kiosk Web Sites. By explicitly starting from the requirements of the users or visitors, WSDM solves Web site problems that are primarily caused by that fact that a site has no underlying design at all, or that the design is mostly data-driven.

  17. Design/licensing of on-site package for core component

    International Nuclear Information System (INIS)

    Ogasawara, K.; Chohzuka, T.; Shimura, T.; Kikuchi, T.; Fujiwara, R.; Karigome, S.; Takani, M.

    1993-01-01

    For storage of used core components which are produced from reactors, Tohoku EPCO decided to construct a site bunker at Onagawa site. It was also decided to develop and fabricate one packaging to transport core components from the reactor buildings to the site bunker. The packaging will be used within the power station; therefore, it shall comply with 'The Law for the Business of Electric Power' and relevant Notification. The main requirements of the packaging are as follows: 1) The number of contents, such as channel boxes and control rods, shall be as large as possible. 2) The weight and the outer dimensions of the packaging shall be within the limitation of the reactor building and the site bunker. 3) Materials shall be selected from those which have been already applied for existing packagings and utilized without any problems. 4) It shall be considered during design of trunnions that handling equipment, such as lifting beam, can be used for not only this packaging but also for existing spent fuel packagings. The design of the packaging is completed and has been licensed. The packaging is scheduled to be utilized from November, 1993. (J.P.N.)

  18. Beyond Trust: Web Site Design Preferences Across Cultures

    OpenAIRE

    Dianne Cyr; Carole Bonanni; John Bowes; Joe Ilsever

    2005-01-01

    The growth of Internet shopping motivates a better understanding of how e-loyalty is built online between businesses and consumers. In this study, Web site design and culture are advanced as important to Web site trust, Web site satisfaction, and e-loyalty in online business relationships. Based on data collected in Canada, the U.S., Germany, and Japan, the research considers (1) examining within culture preferences for design elements of a local vs. a foreign Web site and subsequent particip...

  19. 75 FR 54497 - Ocean Dumping; Guam Ocean Dredged Material Disposal Site Designation

    Science.gov (United States)

    2010-09-08

    .... SUMMARY: The EPA is designating the Guam Deep Ocean Disposal Site (G- DODS) as a permanent ocean dredged... administration of ocean disposal permits; (2) development and maintenance of a site monitoring program; (3... include: (1) Regulating quantities and types of material to be disposed, including the time, rates, and...

  20. Designation of facility usage categories for Hanford Site facilities

    International Nuclear Information System (INIS)

    Wodrich, D.; Ellingson, D.; Scott, M.; Schade, A.

    1991-01-01

    This report summarizes the Hanford Site methodology used to ensure facility compliance with the natural phenomena design criteria set forth in the US Department of Energy orders and guidance. In particular, the Hanford Site approach to designating a suitable facility open-quotes Usage Category,close quotes is presented. The current Hanford Site methodology for Usage Category designation is based on an engineered feature's safety function and on the feature's assigned Safety Class. At the Hanford Site, Safety Class assignments are deterministic in nature and are based on the consequences of failure, without regard to the likelihood of occurrence. The report also proposes a risk-based approach to Usage Category designation, which is being considered for future application at the Hanford Site. To establish a proper Usage Category designation, the safety analysis and engineering design processes must be coupled. This union produces a common understanding of the safety function(s) to be accomplished by the design feature(s) and a sound basis for the assignment of Usage Categories to the appropriate systems, structures, and components

  1. Site characterization plan: Yucca Mountain Site, Nevada Research and Development Area, Nevada: Volume 9, Index

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1988-12-01

    This site characterization plan (SCP) has been developed for the candidate repository site at Yucca Mountain in the State of Nevada. The SCP includes a description of the Yucca Mountain site (Chapters 1-5), a conceptual design for the repository (Chapter 6), a description of the packaging to be used for the waste to be emplaced in the repository (Chapter 7), and a description of the planned site characterization activities (Chapter 8). The schedules and milestones presented in Sections 8.3 and 8.5 of the SCP were developed to be consistent with the June 1988 draft Amendment to the DOE`s Mission Plan for the Civilian Radioactive Waste Management Program. The five month delay in the scheduled start of exploratory shaft construction that was announced recently is not reflected in these schedules.

  2. A GIS connection between brownfield sites, transportation and economic development.

    Science.gov (United States)

    2011-08-01

    "This report outlines the design and development of a web-based data distribution system for brownfield site redevelopment in Toledo-Lucas County, Ohio. The system is designed to advance smart growth initiatives by creating the link between transport...

  3. The development of an on-site container

    International Nuclear Information System (INIS)

    Glass, R.E.; McAllaster, M.E.; Jones, P.L.; McKinney, A.L.

    1993-01-01

    This paper describes the results of the development of a packaging designed for on-site transportation of chemical munitions. The criteria for the package were patterned after the requirements for Type B packagings, but were modified to take credit for the operational controls that could be applied on-site. The design phase has been completed and a contract has been placed for fabrication of 165 units. In addition to the tests completed during the design phase, a complete sequence of verification tests will be performed on the first fleet unit. This sequence will consist of: (1) a 22,700-kg load placed on the packaging for 24 hours, (2) the flat side free drop, (3) the center-of-gravity over closure joint puncture test, and (4) a 15-min all-engulfing JP-4 pool-fire test. At the completion of the test sequence, the package will be required to meet the less than 1 x 10 -1 std cc/s leak test. (J.P.N.)

  4. Development of the on-site power supply in German nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    Simon, M. [Gesellschaft fuer Reaktorsicherheit - GRS mbH, Schwertnergasse 1, D-5000 Koeln 1, Cologne (Germany)

    1986-02-15

    The design of the on-site power supply is different in German Nuclear Power Plants, depending on age and size of the plant. The cause for this is the evolution of the safety requirements. The general development of the design of safety Systems, which resulted in a strict separation of redundant trains is also reflected in the design of the emergency power system and even the complete on-site power supply System. This will be demonstrated by different examples. The advantages of this design with respect to the availability of on-site power will be explained and verified by means of operating experience. (author)

  5. California LLW disposal site development update: Ahead of milestone schedule

    International Nuclear Information System (INIS)

    Romano, S.A.; Gaynor, R.K.

    1987-01-01

    US Ecology has been designated by the State of California to locate, develop and operate a low-level radioactive waste disposal facility. In early 1986, the firm identified eighteen desert basins in southeastern California for siting consideration. Three candidate sites were selected for detailed field characterization work in February, 1987. A preferred site for licensing purposes will be identified in early 1988. California is currently ahead of the siting milestone schedule mandated by the Low-Level Radioactive Waste Policy Amendments Act. It is likely that a license application will be filed before the 1990 milestone date. This paper describes the process undertaken by US Ecology to identify three candidates sites for characterization, and the public involvement program supporting this decision. Future activities leading to final site development are also described

  6. Development of a laboratory niche Web site.

    Science.gov (United States)

    Dimenstein, Izak B; Dimenstein, Simon I

    2013-10-01

    This technical note presents the development of a methodological laboratory niche Web site. The "Grossing Technology in Surgical Pathology" (www.grossing-technology.com) Web site is used as an example. Although common steps in creation of most Web sites are followed, there are particular requirements for structuring the template's menu on methodological laboratory Web sites. The "nested doll principle," in which one object is placed inside another, most adequately describes the methodological approach to laboratory Web site design. Fragmentation in presenting the Web site's material highlights the discrete parts of the laboratory procedure. An optimally minimal triad of components can be recommended for the creation of a laboratory niche Web site: a main set of media, a blog, and an ancillary component (host, contact, and links). The inclusion of a blog makes the Web site a dynamic forum for professional communication. By forming links and portals, cloud computing opens opportunities for connecting a niche Web site with other Web sites and professional organizations. As an additional source of information exchange, methodological laboratory niche Web sites are destined to parallel both traditional and new forms, such as books, journals, seminars, webinars, and internal educational materials. Copyright © 2013 Elsevier Inc. All rights reserved.

  7. SiteGuide: An example-based approach to web site development assistance

    NARCIS (Netherlands)

    Hollink, V.; de Boer, V.; van Someren, M.; Filipe, J.; Cordeiro, J.

    2009-01-01

    We present ‘SiteGuide’, a tool that helps web designers to decide which information will be included in a new web site and how the information will be organized. SiteGuide takes as input URLs of web sites from the same domain as the site the user wants to create. It automatically searches the pages

  8. Designation of facility usage categories for Hanford Site facilities

    International Nuclear Information System (INIS)

    Woodrich, D.D.; Ellingson, D.R.; Scott, M.A.; Schade, A.R.

    1991-10-01

    This report summarizes the Hanford Site methodology used to ensure facility compliance with the natural phenomena design criteria set forth in the US Department of Energy Orders and guidance. The current Hanford Site methodology for Usage Category designation is based on an engineered feature's safety function and on the feature's assigned Safety Class. At the Hanford Site, Safety Class assignments are deterministic in nature and are based on teh consequences of failure, without regard to the likelihood of occurrence. The report also proposes a risk-based approach to Usage Category designation, which is being considered for future application at the Hanford Site. To establish a proper Usage Category designation, the safety analysis and engineering design processes must be coupled. This union produces a common understanding of the safety function(s) to be accomplished by the design feature(s) and a sound basis for the assignment of Usage Categories to the appropriate systems, structures, and components. 4 refs., 9 figs., 1 tab

  9. Technology development for the design of waste repositories at arid sites: field studies of biointrusion and capillary barriers

    International Nuclear Information System (INIS)

    Nyhan, J.W.; Abeele, W.; Hakonson, T.; Lopez, E.A.

    1986-03-01

    The field research program involving the development of technology for arid shallow land burial (SLB) sites is described. Results of field testing of biointrusion barriers installed at an active low-level radioactive waste disposal site (Area G) at Los Alamos are presented. A second experiment was designed to test the ability of a capillary barrier to effectively convey water infiltrating a SLB trench around and away from underlying buried wastes. The performance of the capillary barrier was tested in the field for a barrier of known thickness (2 m), slope (10%), and slope length (2 m), and for one combination of porous materials [a crushed tuff-clay (2% w/w) mixture overlying Ottawa sand] subjected to a known water addition rate. The waste management implications of both studies are also discussed

  10. Experimental site and design

    Energy Technology Data Exchange (ETDEWEB)

    Guenette, C. C. [SINTEF Applied Cemistry, Trondheim (Norway)

    1999-08-01

    Design and site selection criteria for the Svalbard oil spill experiments are described. All three experimental sites have coarse and mixed sediment beaches of sand and pebble; within each site wave exposure is very similar; along-shore and across-shore sediment characteristics are also relatively homogeneous. Tidal range is in the order of 0.6 m at neaps, and 1.8 m at springs. All three sites are open to wave action and are ice-free during the experimental period of mid-July to mid-October. Study plots at each site were selected for different treatments from within the continuous stretch of oiled shoreline, with oiled buffer zones between plots and at either end of the oiled zone. Treatments included mixing (tilling), sediment relocation (surf washing) and bioremediation (nutrient enrichment). Measurements and observations were carried out during the summers of 1997 and 1998. The characteristics measured were: wave and wind conditions; beach topography and elevation; sediment grain size distribution; mineral fines size distribution and mineral composition; background hydrocarbons; concentration of oil within experimental plots and the rate of oil loss over time; depth of oil penetration and thickness of the oiled sediment layer; oil concentration and toxicity of near-shore benthic sediments; mineral composition of suspended particulate material captured in sub-tidal sediment traps; and oil-fines interaction in near-shore water samples. 1 fig.

  11. Experimental site and design

    Energy Technology Data Exchange (ETDEWEB)

    Guenette, C. C. [SINTEF Applied Cemistry, Trondheim (Norway)

    1999-07-01

    Design and site selection criteria for the Svalbard oil spill experiments are described. All three experimental sites have coarse and mixed sediment beaches of sand and pebble; within each site waveexposure is very similar; along-shore and across-shore sediment characteristics are also relatively homogeneous. Tidal range is in the order of 0.6 m at neaps, and 1.8 m at springs. All three sites are open to wave action and are ice-free during the experimental period of mid-July to mid-October. Study plots at each site were selected for different treatments from within the continuous stretch of oiled shoreline, with oiled buffer zones between plots and at either end of the oiled zone. Treatments included mixing (tilling), sediment relocation (surf washing) and bioremediation (nutrient enrichment). Measurements and observations were carried out during the summers of 1997 and 1998. The characteristics measured were: wave and wind conditions; beach topography and elevation; sediment grain size distribution; mineral fines size distribution and mineral composition; background hydrocarbons; concentration of oil within experimental plots and the rate of oil loss over time; depth of oil penetration and thickness of the oiled sediment layer; oil concentration and toxicity of near-shore benthic sediments; mineral composition of suspended particulate material captured in sub-tidal sediment traps; and oil-fines interaction in near-shore water samples. 1 fig.

  12. Progress on building design and site layout, and preparation for procurement

    International Nuclear Information System (INIS)

    Haange, R.

    2004-01-01

    The ITER site layout and buildings retain many of the major features worked out for the original 1998 design of ITER. By mid-2001, the design had been adjusted to take account of the reductions in size of the tokamak and in the performance and capability of its supporting plant systems, with a view to providing a building construction cost reduction near the target of 50%. The present status of the site layout and buildings is that, with the exception of the hot cell building, designs are available for the ITER buildings and site layout, in different degrees of detail, ready for final review as soon as the drawings and 3D models have been updated. The ITER site layout is determined by the functions of the various plant systems provided in support of the ITER tokamak. These systems are located in different buildings on the ITER site. Changes in the plant layout inside buildings can, therefore, have an important impact on the overall site layout. The general layout of the site assumes electrical power comes in from the west, heat rejection is on the east, access into the main building for assembly is from the south, and removal of waste is from the north. These orientations are purely notional, determining only the relative positions. Both the European and Japanese potential ITER sites will most likely use seismic isolation of the main tokamak complex. As a result, the detailed design of these buildings and in particular the piping connections to them developed for the 'generic' ITER site will require redesign. Also, the footprint of the main tokamak complex will increase, and hence the layout of the utility tunnel network will have to be updated. A draft Site Facilities Procurement Specification has been written by the International Team. This will require considerable specific input when the site has been selected. Furthermore, the present site layout will have to be reviewed in detail. The generic site has been kept compact. Once a site is available, it may be

  13. Design considerations for on-site spent-fuel transfer systems

    International Nuclear Information System (INIS)

    Jones, R.H.; Jones, C.R.

    1989-06-01

    Studies on spent fuel shipping logistics and operation make it clear that the use of large casks, i.e., 100--125 tons, is superior to smaller casks of similar construction. This superiority manifests itself in both transportation and/or shipping economics and safety as well as reduced personnel exposure in the processing of the casks. An on-site system for the transfer of spent fuel from the storage pool to a large shipping or storage cask, as well as the transfer of spent fuel directly from a storage cask to a shipping cask, could bring the large cask benefits to those restricted reactors. Sensing the need to look more closely at this opportunity, EPRI contracted with S. Levy, Incorporated of Campbell, CA to develop a set of design considerations for such transfer systems. Rather then embark on another design study, EPRI decided to first identify the system considerations that must be factored into any design. The format for this effort presents both the Consideration and the Rationale for the consideration. The resulting work identified thirty-six General Considerations and two Special Considerations. The Considerations are in the form of mandatory requirements and desirable but nonmandatory requirements. Additionally, a brief economic study was performed to get a feel for the cost considerations of on-site transfers. The study results suggest a relatively narrow set of scenarios where on-site transfers are economically superior to alternatives. These scenarios generally involve the use of concrete casks as on-site storage devices

  14. Development of variable LRFD \\0x03C6 factors for deep foundation design due to site variability.

    Science.gov (United States)

    2012-04-01

    The current design guidelines of Load and Resistance Factor Design (LRFD) specifies constant values : for deep foundation design, based on analytical method selected and degree of redundancy of the pier. : However, investigation of multiple sites in ...

  15. Site characterization plan: Yucca Mountain site, Nevada research and development area, Nevada: Consultation draft, Nuclear Waste Policy Act

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1988-01-01

    Chapter six describes the basis for facility design, the completed facility conceptual design, the completed analytical work relating to the resolution of design issues, and future design-related work. The basis for design and the conceptual design information presented in this chapter meet the requirements of the Nuclear Waste Policy Act of 1982, for a conceptual repository design that takes into account site-specific requirements. This information is presented to permit a critical evaluation of planned site characterization activities. Chapter seven describes waste package components, emplacement environment, design, and status of research and development that support the Nevada Nuclear Waste Storage Investigation (NNWSI) Project. The site characterization plan (SCP) discussion of waste package components is contained entirely within this chapter. The discussion of emplacement environment in this chapter is limited to considerations of the environment that influence, or which may influence, if perturbed, the waste packages and their performance (particularly hydrogeology, geochemistry, and borehole stability). The basis for conceptual waste package design as well as a description of the design is included in this chapter. The complete design will be reported in the advanced conceptual design (ACD) report and is not duplicated in the SCP. 367 refs., 173 figs., 68 tabs.

  16. Site characterization plan: Yucca Mountain site, Nevada research and development area, Nevada: Consultation draft, Nuclear Waste Policy Act

    International Nuclear Information System (INIS)

    1988-01-01

    Chapter six describes the basis for facility design, the completed facility conceptual design, the completed analytical work relating to the resolution of design issues, and future design-related work. The basis for design and the conceptual design information presented in this chapter meet the requiremenrs of the Nuclear Waste Policy Act of 1982, for a conceptual repository design that takes into account site-specific requirements. This information is presented to permit a critical evaluation of planned site characterization activities. Chapter seven describes waste package components, emplacement environment, design, and status of research and development that support the Nevada Nuclear Waste Storage Investigation (NNWSI) Project. The site characterization plan (SCP) discussion of waste package components is contained entirely within this chapter. The discussion of emplacement environment in this chapter is limited to considerations of the environment that influence, or which may influence, if perturbed, the waste packages and their performance (particularly hydrogeology, geochemistry, and borehole stability). The basis for conceptual waste package design as well as a description of the design is included in this chapter. The complete design will be reported in the advanced conceptual design (ACD) report and is not duplicated in the SCP. 367 refs., 173 figs., 68 tabs

  17. Conceptual design report for regional low-level waste interim storage site

    International Nuclear Information System (INIS)

    Bird, M.V.; Thompson, J.D.

    1981-08-01

    An interim storage site design concept was developed for receiving 100,000 ft 3 low-level waste per year, in the form of solidified wastes in 55-gallon drums with a dose rate of < 200 mrem per hour at contact

  18. Development of cloud-operating platform for detention facility design

    Science.gov (United States)

    Tun Lee, Kwan; Hung, Meng-Chiu; Tseng, Wei-Fan; Chan, Yi-Ping

    2017-04-01

    In the past 20 years, the population of Taiwan has accumulated in urban areas. The land development has changed the hydrological environment and resulted in the increase of surface runoff and shortened the time to peak discharge. The change of runoff characteristics increases the flood risk and reduces resilient ability of the city during flood. Considering that engineering measures may not be easy to implement in populated cities, detention facilities set on building basements have been proposed to compromise the increase of surface runoff resulting from development activities. In this study, a web-based operational platform has been developed to integrate the GIS technologies, hydrological analyses, as well as relevant regulations for the design of detention facilities. The design procedure embedded in the system includes a prior selection of type and size of the detention facility, integrated hydrological analysis for the developing site, and inspection of relevant regulations. After login the platform, designers can access the system database to retrieve road maps, land use coverages, and storm sewer information. Once the type, size, inlet, and outlet of the detention facility are assigned, the system can acquire the rainfall intensity-duration-frequency information from adjacent rain gauges to perform hydrological analyses for the developing site. The increase of the runoff volume due to the development and the reduction of the outflow peak through the construction of the detention facility can be estimated. The outflow peak at the target site is then checked with relevant regulations to confirm the suitability of the detention facility design. The proposed web-based platform can provide a concise layout of the detention facility and the drainageway of the developing site on a graphical interface. The design information can also be delivered directly through a web link to authorities for inspecting to simplify the complex administrative procedures.

  19. Adaptation of the ITER facility design to a Canadian site

    International Nuclear Information System (INIS)

    Smith, S.

    2001-01-01

    This paper presents the status of Canadian efforts to adapt the newly revised ITER facility design to suit the specific characteristics of the proposed Canadian site located in Clarington, west of Toronto, Ontario. ITER Canada formed a site-specific design team in 1999, comprising participants from three Canadian consulting companies to undertake this work. The technical aspects of this design activity includes: construction planning, geotechnical investigations, plant layout, heat sink design, electrical system interface, site-specific modifications and tie-ins, seismic design, and radwaste management. These areas are each addressed in this paper. (author)

  20. Remedial design services for Montclair/West Orange and Glen Ridge Superfund sites

    International Nuclear Information System (INIS)

    Urbaniak, T.F.; Tomiczek, P.W. Jr.

    1994-01-01

    The Montclair/West Orange and Glen Ridge Superfund Sites are located 12 miles west of New York City in Essex County, New Jersey. The sites are contaminated with waste materials from radium-processing facilities which operated in the area during the early 1900's. The waste materials, containing radium and other radioactive isotopes were placed in three separate landfill sites. Major public health risks are indoor radon gas build-up and indoor/ outdoor gamma radiation. In 1989, the EPA issued a Record of Decision (ROD) which chose excavation and off-site disposal of material as the preferred alternative. The purpose of this presentation is to highlight key elements of the design process for the remedial action at Montclair. Those key elements are as follows: meeting community relations challenges; measuring radioactive contamination; developing plans and specifications; packaging of remedial action contacts; and continually improving both the process and the designs

  1. THE IMPORTANCE OF WEB DESIGN: VISUAL DESIGN EVALUATION OF DESTINATION WEB SITES

    OpenAIRE

    Fırlar, Belma; Okat Özdem, Özen

    2013-01-01

    As in the literature, the researchs about web site efficiency are mostly about site context. The analysis about function are mostly superficial. Whereas, controlling every little part of a web site respective is a necessity to show its efficiency. Here in this context in the study of perception and response event web sites that play an important role in visual design criteria are below the lens as featured and the web sites evaulated by heuristic evaluation method.The research focus of this s...

  2. Constructing sites at a large scale - towards new design (education) methods

    DEFF Research Database (Denmark)

    Braae, Ellen Marie; Tietjen, Anne

    2010-01-01

    of the design disciplines within the development of our urban landscapes. At the same time, urban and landscape designers are confronted with new methodological problems. Within a strategic transformation perspective the formulation of the design problem or brief becomes an integrated part of the design process......Since the 1990s the regional scale has regained importance in urban and landscape design. In parallel, the focus in design tasks has shifted from master plans for urban extension to strategic urban transformation projects. The current paradigm of planning by projects reinforces the role....... This paper discusses new design (education) methods based on a relational concept of urban sites and design processes using the actor-network-theory as theoretical frame....

  3. Linkage between site characterization program and performance and design data needs

    International Nuclear Information System (INIS)

    Blanchard, M.B.; Dobson, D.C.; Younker, J.L.; Voegele, M.D.

    1990-01-01

    The basis for identifying site-specific data needs for the Yucca Mountain site was a thorough review and evaluation of the regulatory requirements for a geologic repository. The US Nuclear Regulatory Commission's (NRC) regulation governing disposal of high-level waste in a geologic repository utilizes a multiple barrier approach that includes reliance on both engineered and natural elements. Given an understanding of the regulatory requirements, the next step was to identify the natural features of the site and the components of the engineered barriers considered most likely to make significant contributions to isolation of waste at Yucca Mountain. The intent was to develop a site testing program that focused on understanding those natural site characteristics and processes most likely to contribute to waste isolation; and providing site data necessary to design and assess the performance of engineered barriers. 3 refs., 3 figs

  4. Remedial Action Plan and site design for stabilization of the inactive uranium mill tailings site at Durango, Colorado: Attachment 2, Geology report

    International Nuclear Information System (INIS)

    1991-12-01

    Detailed investigations of geologic, geomorphic, and seismic conditions at the Bodo Canyon disposal site were conducted. The purpose of these investigations was basic site characterization and identification of potential geologic hazards that could affect long-term site stability. Subsequent engineering studies, such as analyses of hydrologic and liquefaction hazards, used the data developed in these studies. The geomorphic analysis was employed in the design of effective erosion protection. Studies of the regional and local seismotectonic setting, which included a detailed search for possible capable faults within a 65 kilometer radius of the site, provided the basis for seismic design parameters. The scope of work performed included the following: Compilation and analysis of previous published and unpublished geologic literature and maps; Review of historical and instrumental earthquake data; Review of site-specific subsurface geologic data, including lithologic and geophysical logs of exploratory boreholes advanced in the site area; Photogeologic interpretations of existing conventional aerial photographs; and, Ground reconnaissance and mapping of the site region

  5. Impact of Site Elevation on Mg Smelter Design

    Science.gov (United States)

    Baker, Phillip W.

    Site elevation has many surprising and significant impacts on the engineering design of metallurgical plant of all types. Electrolytic magnesium smelters maybe built at high elevation for a variety of reasons including availability of raw material, energy or electric power. Because of the unit processes they typically involve, Mg smelters can be extensively impacted by site elevation. In this paper, generic examples of the design changes required to adapt a smelter originally designed for sea level to operate at 2700 m are presented. While the examples are drawn from a magnesium plant design case, these changes are generically applicable to all industrial plants utilizing similar unit processes irrespective of product.

  6. Potentials for site-specific design of MW sized wind turbines

    DEFF Research Database (Denmark)

    Thomsen, K.; Fuglsang, P.; Schepers, G.

    2001-01-01

    The potential for site specific design of MW sized wind turbines is quantified by comparing design loads for wind turbines installed at a range of different sites. The sites comprise on-shore normal flat terrain stand-alone conditions and wind farm conditions together with offshore and mountainous...

  7. Development of Mitigation Strategy for Beyond Design Basis External Events for NRC Design Certification

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Dong Hak; Lee, Jae Jong; Kim, Myung Ki [KHNP Central Research Institute, Daejeon (Korea, Republic of)

    2013-10-15

    In this study, how to develop FLEX strategy for beyond-design-basis external events for U. S. NRC design certification is examined. The development method of FLEX strategy for U. S. NRC design certification is examined. The applicants should make unit-specific FLEX strategy and establish the minimum coping capabilities consistent with unit-specific evaluation of the potential impacts and responses to BDBEEs. NEI 12-06 outlines the process to define and deploy the diverse and flexible mitigation strategies(FLEX strategy) that will increase defense-in-depth for beyond-design-basis scenarios to address the extended loss of alternating current (ac) power (ELAP) and loss of normal access to the ultimate heat sink (LUHS) occurring simultaneously at all units on a site. The order (EA-12-049) is issued to all reactor licensees, including holders of active, Construction Permit (CP) holders, and Combined License (COL) holders. Applicants for the new reactor design certification should prepare and submit FLEX strategy for NRC staff's review. Site-specific data related with the new reactor can't be determined during the new reactor design certification applications so that the unit-specific FLEX strategy should be developed.

  8. Development of Mitigation Strategy for Beyond Design Basis External Events for NRC Design Certification

    International Nuclear Information System (INIS)

    Kim, Dong Hak; Lee, Jae Jong; Kim, Myung Ki

    2013-01-01

    In this study, how to develop FLEX strategy for beyond-design-basis external events for U. S. NRC design certification is examined. The development method of FLEX strategy for U. S. NRC design certification is examined. The applicants should make unit-specific FLEX strategy and establish the minimum coping capabilities consistent with unit-specific evaluation of the potential impacts and responses to BDBEEs. NEI 12-06 outlines the process to define and deploy the diverse and flexible mitigation strategies(FLEX strategy) that will increase defense-in-depth for beyond-design-basis scenarios to address the extended loss of alternating current (ac) power (ELAP) and loss of normal access to the ultimate heat sink (LUHS) occurring simultaneously at all units on a site. The order (EA-12-049) is issued to all reactor licensees, including holders of active, Construction Permit (CP) holders, and Combined License (COL) holders. Applicants for the new reactor design certification should prepare and submit FLEX strategy for NRC staff's review. Site-specific data related with the new reactor can't be determined during the new reactor design certification applications so that the unit-specific FLEX strategy should be developed

  9. THE DESIGN AND IMPLEMETATION OF THE RESEARCH CENTER FOR AERONAUTICS AND SPACE WEB SITE

    Directory of Open Access Journals (Sweden)

    LEHADUS Daniel

    2010-11-01

    Full Text Available This paper presents some elements and principles commonly used in web design. It’s addressed to anyone with an interest in developing their skills as a visual communicator, anyone who wants to learn the basics of graphical design, so they can develop their artistic skills and make more powerful and effective web sites.

  10. Site characterization design and techniques used at the Southern Shipbuilding Corporation site

    International Nuclear Information System (INIS)

    Mueller, J.P.; Geraghty, C.A.; Moore, G.W.; Mullins, J.R.

    1995-01-01

    The Southern Shipbuilding Corporation (SSC) site is an inactive barge/ship manufacturing and repair facility situated on approximately 54 acres in Slidell, St. Tammany Parish, Louisiana. Two unlined surface impoundments (North and South impoundments) are situated on the northwest portion of the site and are surrounded on three sides by Bayou Bonfouca. These impoundments are the sources of carcinogenic polynuclear aromatic hydrocarbon (CPAH) contamination at the site. Inadequate containment has resulted in the release of impoundment wastes into the bayou. To evaluate potential response alternatives for the site, an Engineering Evaluation/Cost Analysis (EE/CA) field investigation was conducted from July through October 1994. A two phase sampling approach was used in combination with innovative and traditional sampling techniques, field screening technologies, and exploitation of the visual characteristics of the waste to determine the extent of waste migration with limited off-site laboratory confirmation. A skid-mounted mobile drilling unit, secured to a specialized sampling platform designed for multiple applications, was used for collection of sediment cores from the bayou as well as tarry sludge cores from the impoundments. Field screening of core samples was accomplished on site using an organic vapor analyzer and a total petroleum hydrocarbon (TPH) field analyzer. Pollutants of concern include metals, cyanide, dioxin, and organic compounds. This paper presents details on the sampling design and characterization techniques used to accomplish the EE/CA field investigation

  11. Radiotracers for per studies of neurotransmitter binding sites: Design considerations

    International Nuclear Information System (INIS)

    Kilbourn, M.R.

    1991-01-01

    Neurotransmitter binding sites, such as receptors, neuronal uptake systems, and vesicular uptake systems, are important targets for new radiopharmaceutical design. Selection of potential radioligands can be guided by in vitro laboratory data including such characteristics as selectivity and affinity for specific binding sites. However, development of PET radiotracers for use in vivo must include considerations of in vivo pharmacokinetics and metabolism. Introduction of potential radioligands is further narrowed by the demands of the radiochemical synthesis, which must produce radioligands of high chemical and radiochemical purity and of high specific activity. This paper will review examples of previous and current attempts by radiopharmaceutical chemists to meet these demands for new positron emitter-labeled radioligands for PET studies of a wide array of neurotransmitter binding sites

  12. Site development

    International Nuclear Information System (INIS)

    Noack, J.

    1975-01-01

    The subject of this paper is a general view over all necessary considerations to develop the site after it has been chosen and before starting with the construction of a nuclear power plant. (orig./RW) [de

  13. Urban Environment Development based on Universal Design Principles

    Science.gov (United States)

    Harsritanto, Bangun Ir

    2018-02-01

    Universal Design is a design which facilitated full range of human diversity. By applying Universal design principles, urban environment can be more functional and more user-friendly for everyone. This study examined five urban streets of South Korea as a country experienced on developing various urban street designs based on universal design. This study aimed to examine and compare the South Korea cases using seven principles of universal design. The research methods of this study are literature study, case study, and site observation. The results of this study are: South Korea cases are good practices, urgency of implementing the direction into local regulations; and change of urban development paradigm.

  14. Hanford Site Permanent Isolation Surface Barrier Development Program: Fiscal year 1992 and 1993 highlights

    International Nuclear Information System (INIS)

    Cadwell, L.L.; Link, S.O.; Gee, G.W.

    1993-09-01

    The Hanford Site Permanent Isolation Surface Barrier Development Program was jointly developed by the Pacific Northwest Laboratory and Westinghouse Hanford Company to design and test an earthen cover system that can be used to inhibit water infiltration; plant, animal, and human intrusion; and wind and water erosion. Kaiser Engineers Hanford Company provided engineering design support for the program. Work on barrier design has been under way at Hanford for nearly 10 years. The comprehensive development of a long-term barrier, formerly the Hanford Site Protective Barrier Development Program, was initiated in FY 1986, and a general field-tested design is expected to be completed by FY 1998. Highlights of efforts in FY 1992 and FY 1993 included the resumption of field testing, the completion of the prototype barrier design, and the convening of an external peer review panel, which met twice with the barrier development team. The review panel provided helpful guidance on current and future barrier development activities, while commending the program for its significant technical contributions to innovative barrier technology development

  15. Site characterization plan: Yucca Mountain site, Nevada research and development area, Nevada: Consultation draft, Nuclear Waste Policy Act: Volume 2

    International Nuclear Information System (INIS)

    1988-01-01

    The Yucca Mountain site in Nevada is one of three candidate sites for the first geologic repository for radioactive waste. On May 28, 1986, it was recommended for detailed study in a program of site characterization. This site characterization plan (SCP) has been prepared in accordance with the requirements of the Nuclear Waste Policy Act to summarize the information collected to date about the geologic conditions at the site; to describe the conceptual designs for the repository and the waste package and to present the plans for obtaining the geologic information necessary to demonstrate the suitability of the site for a repository, to design the repository and the waste package, to prepare an environmental impact statement, and to obtain from the US Nuclear Regulatory Commission (NRC) an authorization to construct the repository. Chapter 3 summarizes present knowledge of the regional and site hydrologic systems. The purpose of the information presented is to (1) describe the hydrology based on available literature and preliminary site-exploration activities that have been or are being performed and (2) provide information to be used to develop the hydrologic aspects of the planned site characterization program. Chapter 4 contains geochemical information about the Yucca Mountain site. The chapter references plan for continued collection of geochemical data as a part of the site characterization program. Chapter 4 describes and evaluates data on the existing climate and site meterology, and outlines the suggested procedures to be used in developing and validating methods to predict future climatic variation. 534 refs., 100 figs., 72 tabs

  16. Site characterization plan: Yucca Mountain site, Nevada research and development area, Nevada: Consultation draft, Nuclear Waste Policy Act: Volume 2

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1988-01-01

    The Yucca Mountain site in Nevada is one of three candidate sites for the first geologic repository for radioactive waste. On May 28, 1986, it was recommended for detailed study in a program of site characterization. This site characterization plan (SCP) has been prepared in accordance with the requirements of the Nuclear Waste Policy Act to summarize the information collected to date about the geologic conditions at the site; to describe the conceptual designs for the repository and the waste package and to present the plans for obtaining the geologic information necessary to demonstrate the suitability of the site for a repository, to design the repository and the waste package, to prepare an environmental impact statement, and to obtain from the US Nuclear Regulatory Commission (NRC) an authorization to construct the repository. Chapter 3 summarizes present knowledge of the regional and site hydrologic systems. The purpose of the information presented is to (1) describe the hydrology based on available literature and preliminary site-exploration activities that have been or are being performed and (2) provide information to be used to develop the hydrologic aspects of the planned site characterization program. Chapter 4 contains geochemical information about the Yucca Mountain site. The chapter references plan for continued collection of geochemical data as a part of the site characterization program. Chapter 4 describes and evaluates data on the existing climate and site meterology, and outlines the suggested procedures to be used in developing and validating methods to predict future climatic variation. 534 refs., 100 figs., 72 tabs.

  17. Site study plan for EDBH [Engineering Design Boreholes] seismic surveys, Deaf Smith County site, Texas: Revision 1

    International Nuclear Information System (INIS)

    Hume, H.

    1987-12-01

    This site study plan describes seismic reflection surveys to run north-south and east-west across the Deaf Smith County site, and intersecting near the Engineering Design Boreholes (EDBH). Both conventional and shallow high-resolution surveys will be run. The field program has been designed to acquire subsurface geologic and stratigraphic data to address information/data needs resulting from Federal and State regulations and Repository program requirements. The data acquired by the conventional surveys will be common-depth- point, seismic reflection data optimized for reflection events that indicate geologic structure near the repository horizon. The data will also resolve the basement structure and shallow reflection events up to about the top of the evaporite sequence. Field acquisition includes a testing phase to check/select parameters and a production phase. The field data will be subjected immediately to conventional data processing and interpretation to determine if there are any anamolous structural for stratigraphic conditions that could affect the choice of the EDBH sites. After the EDBH's have been drilled and logged, including vertical seismic profiling, the data will be reprocessed and reinterpreted for detailed structural and stratigraphic information to guide shaft development. The shallow high-resulition seismic reflection lines will be run along the same alignments, but the lines will be shorter and limited to immediate vicinity of the EDBH sites. These lines are planned to detect faults or thick channel sands that may be present at the EDBH sites. 23 refs. , 7 figs., 5 tabs

  18. Site characterization plan: Yucca Mountain site, Nevada research and development area, Nevada: Consultation draft, Nuclear Waste Policy Act

    International Nuclear Information System (INIS)

    1988-01-01

    The Yucca Mountain site in Nevada is one of three candidate sites for the first geologic repository for radioactive waste. On May 28, 1986, it was recommended by the Secretary of Energy and approved by the President for detailed study in a program of site characterization. This site characterization plan (SCP) has been prepared by the US Department of Energy (DOE) in accordance with the requirements of the Nulcear Waste Policy Act to summarize the information collected to date about the geologic conditions at the site;to describe the conceptual designs for the repository and the waste package;and to present the plans for obtaining the geologic information necessary to demonstrate the suitability of the site for a repository, to design the repository and the waste package, to prepare an environmental impact statement, and to obtain from the US Nuclear Regulatory Commission (NRC) an authorization to construct the repository. This introduction begins with a brief section on the process for siting and developing a repository, followed by a discussion of the pertinent legislation and regulations. A description of site characterization is presented next;it describes the facilities to be constructed for the site characterization program and explains the principal activities to be conducted during the program. Finally, the purpose, content, organizing principles, and organization of the site characterization plan are oulined, and compliance with applicable regulations is discussed

  19. Site characterization plan: Yucca Mountain site, Nevada research and development area, Nevada: Consultation draft, Nuclear Waste Policy Act

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1988-01-01

    The Yucca Mountain site in Nevada is one of three candidate sites for the first geologic repository for radioactive waste. On May 28, 1986, it was recommended by the Secretary of Energy and approved by the President for detailed study in a program of site characterization. This site characterization plan (SCP) has been prepared by the US Department of Energy (DOE) in accordance with the requirements of the Nulcear Waste Policy Act to summarize the information collected to date about the geologic conditions at the site;to describe the conceptual designs for the repository and the waste package;and to present the plans for obtaining the geologic information necessary to demonstrate the suitability of the site for a repository, to design the repository and the waste package, to prepare an environmental impact statement, and to obtain from the US Nuclear Regulatory Commission (NRC) an authorization to construct the repository. This introduction begins with a brief section on the process for siting and developing a repository, followed by a discussion of the pertinent legislation and regulations. A description of site characterization is presented next;it describes the facilities to be constructed for the site characterization program and explains the principal activities to be conducted during the program. Finally, the purpose, content, organizing principles, and organization of the site characterization plan are oulined, and compliance with applicable regulations is discussed.

  20. Definitive design status of the SP-100 Ground Engineering System Test Site

    International Nuclear Information System (INIS)

    Renkey, E.J. Jr.; Bazinet, G.D.; Bitten, E.J.; Brackenbury, P.J.; Carlson, W.F.; Irwin, J.J.; Edwards, P.A.; Shen, E.J.; Titzler, P.A.

    1989-05-01

    The SP-100 reactor will be ground tested at the SP-100 Ground Engineering System (GES) Test Site on the US Department of Energy (DOE) Hanford Site near Richland, Washington. Project direction and the flight system design evolution have resulted in a smaller reactor size and the consequential revision to Test Site features to accommodate the design changes and reduce Test Site costs. The significant design events since the completion of the Conceptual Design are discussed in this paper

  1. Definitive design status of the SP-100 Ground Engineering System Test Site

    Energy Technology Data Exchange (ETDEWEB)

    Renkey, E.J. Jr.; Bazinet, G.D.; Bitten, E.J.; Brackenbury, P.J.; Carlson, W.F.; Irwin, J.J.; Edwards, P.A.; Shen, E.J.; Titzler, P.A.

    1989-05-01

    The SP-100 reactor will be ground tested at the SP-100 Ground Engineering System (GES) Test Site on the US Department of Energy (DOE) Hanford Site near Richland, Washington. Project direction and the flight system design evolution have resulted in a smaller reactor size and the consequential revision to Test Site features to accommodate the design changes and reduce Test Site costs. The significant design events since the completion of the Conceptual Design are discussed in this paper.

  2. Early Site Permit Demonstration Program: Guidelines for determining design basis ground motions

    International Nuclear Information System (INIS)

    1993-01-01

    This report develops and applies a methodology for estimating strong earthquake ground motion. The motivation was to develop a much needed tool for use in developing the seismic requirements for structural designs. An earthquake's ground motion is a function of the earthquake's magnitude, and the physical properties of the earth through which the seismic waves travel from the earthquake fault to the site of interest. The emphasis of this study is on ground motion estimation in Eastern North America (east of the Rocky Mountains), with particular emphasis on the Eastern United States and southeastern Canada. Eastern North America is a stable continental region, having sparse earthquake activity with rare occurrences of large earthquakes. While large earthquakes are of interest for assessing seismic hazard, little data exists from the region to empirically quantify their effects. The focus of the report is on the attributes of ground motion in Eastern North America that are of interest for the design of facilities such as nuclear power plants. This document, Volume II, contains Appendices 2, 3, 5, 6, and 7 covering the following topics: Eastern North American Empirical Ground Motion Data; Examination of Variance of Seismographic Network Data; Soil Amplification and Vertical-to-Horizontal Ratios from Analysis of Strong Motion Data From Active Tectonic Regions; Revision and Calibration of Ou and Herrmann Method; Generalized Ray Procedure for Modeling Ground Motion Attenuation; Crustal Models for Velocity Regionalization; Depth Distribution Models; Development of Generic Site Effects Model; Validation and Comparison of One-Dimensional Site Response Methodologies; Plots of Amplification Factors; Assessment of Coupling Between Vertical ampersand Horizontal Motions in Nonlinear Site Response Analysis; and Modeling of Dynamic Soil Properties

  3. Development of new low level radioactive waste disposal sites: A progress report

    International Nuclear Information System (INIS)

    Anderson, Robert T.; Antonucci, George J.; Ryan, Michael T.

    1992-01-01

    The status of the development of three new low level radioactive waste disposal facilities for the Central Midwest (Illinois), Southeastern (North Carolina) and Appalachian (Pennsylvania) compacts is presented. These three sites will dispose of about 50-65 percent of the commercial low-level waste (LLW) generated in the U.S. annually. Chem-Nuclear, as developer and proposed operator of all three sites has used a common approach to site development. This approach has been based on their twenty-plus years of operating experience and a standard technical approach. The technology employed is an above-grade, multiple engineered barrier design. The paper also contrasts actual progress at each site with a generalized project schedule. Areas of schedule delays are noted along with the steps being taken to accelerate schedule. Finally, we note that continued progress and timely start-up of operations of these new sites is critical on a national basis. This is due to the possibility of near-term closure of the existing LLW disposal sites. (author)

  4. The development of an on-site container

    International Nuclear Information System (INIS)

    Glass, R.E.; McAllaster, M.E.; Jones, P.L.; McKinney, A.L.

    1992-01-01

    Sandia National Laboratories (SNL) has developed a package for the on-site transport of chemical munitions for the US Army. This package was designed to prevent the release of lethal quantities of chemical agents during transportation of munitions to the demilitarization facilities on-site. The packaging prevents auto-ignition of the munitions by limiting the thermal and structural assault on the munitions during an accident. This package, with some modifications to account for contents, may be suitable for the on-site transport of mixed wastes at United States Department of Energy facilities. This paper discusses the design and verification testing of the package. The safety criteria for the package were modeled after the International Atomic Energy Agency (IAEA) hypothetical accident sequence and modified to take credit for operational controls. The modified accident sequence consisted of drop, puncture, and thermal events. The post-accident leak rate was established to prevent harm to an exposed worker. The packaging has a mass of 8600 kg and can accommodate up to 3600 kg of contents. The interior of the package is 188 cm in diameter and 232 cm long. Two sample ports can be used to sample the interior of the package prior to opening the closure and an o-ring test port can be used to determine the leak rates prior to and after transport

  5. Configuration system development of site and environmental information for radwaste disposal facility

    International Nuclear Information System (INIS)

    Park, Se-Moon; Yoon, Bong-Yo; Kim, Chang-Lak

    2005-01-01

    License for the nuclear facilities such as radioactive waste repository demands documents of site characterization, environmental assessment and safety assessment. This performance will produce bulk of the relevant data. For the safe management of radioactive waste repository, data of the site and environment have to be collected and managed systematically. Particularly for the radwaste repository, which has to be institutionally controlled for a long period after closure, the data will be collected and maintained through the monitoring programme. To meet this requirement, a new programme called 'Site Information and Total Environmental data management System (SITES)' has been developed. The scope and function of the SITES is issued in data DB, safety assessment and monitoring system. In this respect, SITES is designed with two modules of the SITES Database Module (SDM) and the Monitoring and Assesment (M and A). The SDM module is composed of three sub-modules. One is the Site Information Management System (SIMS), which manages data of site characterization such as topography, geology, hydrogeology, engineering geology, etc. The other is the ENVironmental Information management System (ENVIS) and Radioactive ENVironmental Information management System (RENVIS), which manage environmental data required for environmental assessment performance. ENVIS and RENVIS covered almost whole items of environmental assessment report required by Korean government. The SDM was constructed based on Entity Relationship Diagram produced from each item. Also using ArcGIS with the spatial characteristics of the data, it enables groundwater and water property monitoring networks, etc. To be analyzed in respect of every theme. The sub-modules of M and A called the Site and Environment Monitoring System (SEMS) and the Safety Assessment System (SAS) were developed. SEMS was designed to manage the inspection records of the individual measuring instruments and facilities, and the on

  6. Procurement Specifications Templates for On-Site Solar Photovoltaic: For Use in Developing Federal Solicitations

    Energy Technology Data Exchange (ETDEWEB)

    Robinson, G. [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States)

    2017-01-16

    With the increasing adaption of on-site renewable energy systems designed to feed site loads, there is a critical need to develop tools that allow the federal sector to become a mature and sophisticated consumer. This document is intended to reduce project development and operational risks while increasing the speed at which projects are completed; two necessary components to reach the scale required to meet mandates and achieve cost savings for taxpayers. This guide is intended to act as a living document where lessons learned from the increasing number of projects can be incorporated and provide guidance for efforts. While additional guides will be developed to cover other renewable technologies, this guide covers on-site solar photovoltaic systems with an emphasis on third-party designed, financed, owned, and operated systems.

  7. Design surface covers: an approach to long-term waste site stabilization

    International Nuclear Information System (INIS)

    Beedlow, P.A.; Cadwell, L.L.; McShane, M.C.

    1983-02-01

    The wide range of existing environmental conditions, potential contaminants and available cover materials at waste disposal sites necessitates site-specific designing of surface covers for effective long-term erosion resistance. This paper presents a systematic approach to designing surface covers for hazardous waste repositories that can be tailored to conditions at any site. The approach consists of three phases: (1) an assessment, during which the degree of required surface protection (erosion potential) is determined; (2) a preliminary design that integrates surface cover design with the need to minimize transport of contaminants; and (3) a final design, where the cost and effectiveness of the surface cover are determined. 1 figure

  8. Remedial action plan and site design for stabilization of the inactive uranium mill tailings sites at Rifle, Colorado

    Energy Technology Data Exchange (ETDEWEB)

    1992-02-01

    This appendix assesses the present conditions and data gathered about the two inactive uranium mill tailings sites near Rifle, Colorado, and the designated disposal site six miles north of Rifle in the area of Estes Gulch. It consolidates available engineering, radiological, geotechnical, hydrological, meteorological, and other information pertinent to the design of the Remedial Action Plan (RAP). The data characterize conditions at the mill, tailings, and disposal site so that the Remedial Action Contractor (RAC) may complete final designs for the remedial actions.

  9. INTEGRATED REMOTE SENSING AND GIS FOR MODELING ECONOMIC REHABILITATION DEVELOPMENT OF EX-MINE SITES

    Directory of Open Access Journals (Sweden)

    Junaidi Junaidi

    2017-11-01

    Full Text Available The potential environmental impacts of mining, increasing environmental legislation and public awareness have received increased attention world-wide in the last two decades. The focus of concern by the industry, environmental regulatory agencies and members of the public is the systematic rehabilitation of ex-mine sites to improve the quality at site for potential future commercial land use. The minerals extracted from these mine/quarry sites are essential in the construction, semiconductor, high-technology, ceramic and other manufacturing sectors for further industrial development. However, efficient engineering design and systematic economic evaluation of mine sites for site rehabilitation are required in maintaining the expected standards of environmental compliance.  With escalating production costs and the keen competitiveness of the mining industry world-wide, the necessity to increase the efficiency in site rehabilitation is getting more prominence.  A coordinated environmental protection and rehabilitation programme is essential if the environmental awareness of the community and the demands of the respective planning authorities are to be accommodated. There is thus a need to increase the base of knowledge for efficient planning in the systematic and progressive rehabilitation of current and future ex-mine sites. An efficient modeling tool is required for the systematic planning and design of potential economic land development of ex-mine sites. The applicability of Remote Sensing and Geographic Information System (GIS technology is a useful tool to acquire spatial information for the systematic design and planning of potential development of ex-mine sites. This research was conducted to detect the trends in the suitability of land cover changes via land cover change detection of ex-mine sites and validated with reality. The findings are useful to assist in the development of a tool for efficient modeling and design of potential

  10. L.V. switchgear - design and development

    International Nuclear Information System (INIS)

    Armes, D.S.; Brown, R.D.

    1992-01-01

    This work describes the methods employed in the design and development of L.V. switchgear to meet the prospective conditions and operational requirements imposed on equipment at sites of PWR power stations. The work concentrates on the aspects of design, manufacture, qualification work and quality assurance particular to the range of L.V. switchgear distribution boards manufactured by Laurence, Scott and Electromotors Ltd. for Sizewell B Power Station and contrasts this equipment with other equipment for conventional (i.e. non-nuclear) power station purposes. (Author)

  11. Site characterization plan: Yucca Mountain site, Nevada research and development area, Nevada: Consultation draft, Nuclear Waste Policy Act: Volume 6

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1988-01-01

    The Yucca Mountain site in Nevada is one of three candidate sites for the first geologic repository for radioactive waste. On May 28, 1986, it was recommended for detailed study in a program of site characterization. This site characterization plan (SCP) has been prepared in accordance with the requirements of the Nuclear Waste Policy Act to summarize the information collected to date about the geologic conditions at the site;to describe the conceptual designs for the repository and the waste package;and to present the plans for obtaining the geologic information necessary to demonstrate the suitability of the site for repository, to design the repository and the waste package, to prepare an environmental impact statement, and to obtain from the US Nuclear Regulatory Commission (NRC) an authorization to construct the repository. This introduction begins with a brief section on the process for siting and developing a repository, followed by a discussion of the pertinent legislation and regulations. A description of site characterization is presented next;it describes the facilities to be constructed for the site characterization program and explains the principal activities to be conducted during the program. Finally, the purpose, content, organizing principles, and organization of this site characterization plan are outlined, and compliance with applicable regulations is discussed.

  12. Site characterization plan: Yucca Mountain site, Nevada research and development area, Nevada: Consultation draft, Nuclear Waste Policy Act: Volume 7

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1988-01-01

    The Yucca Mountain site in Neavada is one of three candidate sites for the first geologic repository for radioactive waste. On May 28, 1986, it was recommended and approved for detailed study in a program of site characterization. This site characterization plan (SCP) has been prepared in accordance with the requirements of the Nuclear Waste Policy Act to summarize the information collected to date about the geologic conditions at the site;to describe the conceptual designs for the repository and the waste package;and to present the plans for obtaining hte geologic information necessary to demonstrate the suitability of the site for a repository, to design the repository and the waste package, to prepare and environmental impact statement, and to obtain from the US Nuclear Regulatory Commission (NRC) an authorization to construct the repository. This introduction begins with a brief section on the process for siting and developing a repository, followed by a discussion of the pertinent legislation and regulations. A description of site characterization is presented next;it describes the facilities to be constructed for the site characterization program and explains the principal activities to be conducted during the program. Finally, the purpose, content, organizing principles, and organization of this site characterization plan are outlined, and compliance with applicable regulations is discussed.

  13. Site characterization plan: Yucca Mountain site, Nevada research and development area, Nevada: Consultation draft, Nuclear Waste Policy Act: Volume 7

    International Nuclear Information System (INIS)

    1988-01-01

    The Yucca Mountain site in Neavada is one of three candidate sites for the first geologic repository for radioactive waste. On May 28, 1986, it was recommended and approved for detailed study in a program of site characterization. This site characterization plan (SCP) has been prepared in accordance with the requirements of the Nuclear Waste Policy Act to summarize the information collected to date about the geologic conditions at the site;to describe the conceptual designs for the repository and the waste package;and to present the plans for obtaining hte geologic information necessary to demonstrate the suitability of the site for a repository, to design the repository and the waste package, to prepare and environmental impact statement, and to obtain from the US Nuclear Regulatory Commission (NRC) an authorization to construct the repository. This introduction begins with a brief section on the process for siting and developing a repository, followed by a discussion of the pertinent legislation and regulations. A description of site characterization is presented next;it describes the facilities to be constructed for the site characterization program and explains the principal activities to be conducted during the program. Finally, the purpose, content, organizing principles, and organization of this site characterization plan are outlined, and compliance with applicable regulations is discussed

  14. Remedial Action Plan and site design for stabilization of the inactive uranium mill tailings site at Durango, Colorado: Attachment 2, Geology report. Revised final report

    Energy Technology Data Exchange (ETDEWEB)

    1991-12-01

    Detailed investigations of geologic, geomorphic, and seismic conditions at the Bodo Canyon disposal site were conducted. The purpose of these investigations was basic site characterization and identification of potential geologic hazards that could affect long-term site stability. Subsequent engineering studies, such as analyses of hydrologic and liquefaction hazards, used the data developed in these studies. The geomorphic analysis was employed in the design of effective erosion protection. Studies of the regional and local seismotectonic setting, which included a detailed search for possible capable faults within a 65 kilometer radius of the site, provided the basis for seismic design parameters. The scope of work performed included the following: Compilation and analysis of previous published and unpublished geologic literature and maps; Review of historical and instrumental earthquake data; Review of site-specific subsurface geologic data, including lithologic and geophysical logs of exploratory boreholes advanced in the site area; Photogeologic interpretations of existing conventional aerial photographs; and, Ground reconnaissance and mapping of the site region.

  15. EBS modelling for the development of repository concepts tailored to siting environments

    International Nuclear Information System (INIS)

    Ishiguro, K.; Ueda, H.; Wakasugi, K.; Sakabe, Y.; Kitayama, K.; Umeki, H.; Takase, H.

    2007-01-01

    The Japanese siting approach for a HLW repository calls for volunteer host municipalities and thereby places particular emphasis on design flexibility. In particular, the repository concept needs to be tailored to the specific site characteristics. Starting from the H12 repository concept, NUMO has been examining a range of possible repository design options, including the EBS. In this paper. the requirements and strategy for the development of models for performance assessment and process understanding are discussed, taking into account the step-wise, iterative process of developing repository concepts. The areas requiring further development of models and databases in the long-term R and D programme have been identified as a 'wish list' that relates to the evaluation of a range of potential repository concepts, focusing on the near-field for the early stages of the development process. Among the issues on the list, NUMO has started the development of a flexible computer code for modelling three-dimensional mass transport to evaluate the impacts of various design options and components of the EBS. This tool has been applied to the analysis of the barrier effects of the tunnel plugs located in fractured rock. (authors)

  16. Web Site Development Support

    Science.gov (United States)

    Abdul, Hameed

    2016-01-01

    This summer I assisted the RPT Program Office in developing a design plan to update their existing website to current NASA web standards. The finished website is intended for the general public, specifically potential customers interested in learning about NASA's chemical rocket test facility capabilities and test assignment process. The goal of the website is to give the public insight about the purpose and function of the RPT Program. Working on this project gave me the opportunity to learn skills necessary for effective project management. The RPT Program Office manages numerous facilities so they are required to travel often to other sites for meetings throughout the year. Maneuvering around the travel schedule of the office and the workload priority of the IT Department proved to be quite the challenge. I overcame the travel schedule of the office by frequently communicating and checking in with my mentor via email and telephone.

  17. Design of an environmental site assessment template for open radioactive site contamination : a radioecological risk approach and case study

    International Nuclear Information System (INIS)

    Nguyen, T.

    2004-01-01

    To reduce redundancy, cost, and time, while at the same time ultimately increasing the effectiveness of the radioactive risk management process, a logical framework incorporating risk assessments (human cancer and environmental risks) into the environmental site assessment process was designed for radioactive open site contamination. Risk-based corrective action is becoming an increasingly more acceptable approach for the remediation of contaminated sites. In the past, cleanup goals were usually established without any regard to the risk involved, by mandating remediation goals based solely on maximum contamination levels. Now, a multi-stage environmental site assessment template has been developed on a radioecological approach. The template gives a framework for making environmentally sound decisions based on relevant regulations and guidelines. The first stage involves the comparison of the background screening activity level to the regulated activity level, the second stage involves the use of site-specific information to determine the risk involved with the contamination, and the third stage provides a remediation decision matrix based on results from the first two stages. This environmental site assessment template is unique because it incorporates the modified Canadian National Classification System for radioactive contaminated sites and two different types of risk assessments (human cancer risks and the newly designed ecological risk) into the decision making process. The template was used to assess a radiologically contaminated site at the Canadian Forces Base at Suffield (Alberta) as a case study, and it reaffirms the Department of National Defence's action as appropriate. This particular site is a Class 3, has an overall insignificant human cancer risk ( -6 ) and a low environmental risk, and conforms to all regulated guidelines. Currently, it is restricted and should be left as is, provided that the subsurface is not disturbed. (author)

  18. Mobile Design and Development Practical concepts and techniques for creating mobile sites and web apps

    CERN Document Server

    Fling, Brian

    2009-01-01

    Mobile devices outnumber desktop and laptop computers three to one worldwide, yet little information is available for designing and developing mobile applications. Mobile Design and Development fills that void with practical guidelines, standards, techniques, and best practices for building mobile products from start to finish. With this book, you'll learn basic design and development principles for all mobile devices and platforms. You'll also explore the more advanced capabilities of the mobile web, including markup, advanced styling techniques, and mobile Ajax. If you're a web designer,

  19. Identification of sites for the low-level waste disposal development and demonstration program

    International Nuclear Information System (INIS)

    Ketelle, R.H.; Lee, D.W.

    1988-04-01

    This report presents the results of site selection studies for potential low-level radioactive waste disposal sites on the Oak Ridge Reservation (ORR). Summaries of the site selection procedures used and results of previous site selection studies on the ORR are included. This report includes recommendations of sites for demonstration of shallow land burial using engineered trench designs and demonstration of above-grade disposal using design concepts similar to those used in tumulus disposal. The site selection study, like its predecessor (ORNL/TM-9717, Use of DOE Site Selection Criteria for Screening Low-Level Waste Disposal Sites on the Oak Ridge Reservation), involved application of exclusionary site screening criteria to the region of interest to eliminate unacceptable areas from consideration. Also like the previous study, the region of interest for this study was limited to the Oak Ridge Department of Energy Reservation. Reconnaissance-level environmental data were used in the study, and field inspections of candidate sites were made to verify the available reconnaissance data. Five candidate sites, all underlain by Knox dolomite residuum and bedrock, were identified for possible development of shallow land burial facilities. Of the five candidate sites, the West Chestnut site was judged to be best suited for deployment of the shallow land burial technology. Three candidate sites, all underlain by the Conasauga Group in Bear Creek Valley, were identified for possible development of above-grade disposal technologies. Of the three sites identified, the Central Bear Creek Valley site lying between State Route 95 and Gum Hollow Road was ranked most favorable for deployment of the above-grade disposal technology

  20. Development of a site-wide accident management center for the Savannah River Site

    International Nuclear Information System (INIS)

    Heal, D.W.; Britt, T.E.

    1992-01-01

    In 1990, the Safety Analysis Group at the Savannah River Site (SRS) began development of an Accident Management program. The program was designed to provide a total system which would meet the Department of Energy (DOE) Safety Performance Criteria, in regard to severe accident management, in the most effective manner. This paper will present two significant changes in the current SRS Accident Management program which will be used to meet these expanded needs. The first and most significant change will be to expand the diversity of the groups involved in the Accident Management process. In the future, organizations such as Environmental Safety, Health ampersand Quality Assurance, Emergency Planning, Site Management, Human Factors, Risk Assessment, and many others will work as an integrated team to solve facility problems. Organizations such as Materials Technology, Equipment Engineering and many of the laboratories on site will be utilized as support groups to increase the technical capability for specific accident analyses. This phase of the program is currently being structured, and should be operational by January of 1993

  1. 1000kW on-site PAFC power plant development and demonstration

    Energy Technology Data Exchange (ETDEWEB)

    Satomi, Tomohide; Koike, Shunichi [Phosphoric Acid Fuel Cell Technology Research Association (PAFC-TRA), Osaka (Japan); Ishikawa, Ryou [New Energy and Industrial Technology Development Organization (NEDO), Tokyo (Japan)

    1996-12-31

    Phosphoric Acid Fuel Cell Technology Research Association (PAFC-TRA) and New Energy and Industrial Technology Development Organization (NEDO) have been conducting a joint project on development of a 5000kW urban energy center type PAFC power plant (pressurized) and a 1000kW on-site PAFC power plant (non-pressurized). The objective of the technical development of 1000kW on-site PAFC power plant is to realize a medium size power plant with an overall efficiency of over 70% and an electrical efficiency of over 36%, that could be installed in a large building as a cogeneration system. The components and system integration development work and the plant design were performed in 1991 and 1992. Manufacturing of the plant and installation at the test site were completed in 1994. PAC test was carried out in 1994, and generation test was started in January 1995. Demonstration test is scheduled for 1995 and 1996.

  2. A study on development of monitoring and assessment module for sites

    International Nuclear Information System (INIS)

    Park, Se Moon; Yoon, Bong Yo; Kim, Dae Jung; Park, Joo Wan; Kim, Chang Lak

    2006-01-01

    As the development of total management systems for sites along with site environmental information is becoming standard, the system known as the Site Information and Total Environmental database management System (SITES) has been developed over the last two years. The first result was a database management system for storing data obtained from facilities, and a site characterization in addition to an environmental assessment of a site. The SITES database is designed to be effective and practical for use with facility management and safety assessment in relation to Geographic Information Systems. SITES is a total management program, which includes its database, its data analysis system required for site characterization, a safety assessment modeling system and an environment monitoring system. I can contribute to the institutional management of the facility and to its safety reassessment. SITES is composed of two main modules: the SITES Database Module (SDM) and the Monitoring and Assessment (M and A) module. The M and A module is subdivided into two sub-modules: the Safety Assessment System (SAS) and the Site Environmental Monitoring System (SEMS). SAS controls the data (input and output) from the SITES DB for the site safety assessment, whereas SEMS controls the data obtained from the records of the measuring sensors and facilities. The on-line site and environmental monitoring data is managed in SEMS. The present paper introduces the procedure and function of the M and A modules

  3. Peer Influence on Ethnic-Racial Identity Development: A Multi-Site Investigation.

    Science.gov (United States)

    Santos, Carlos E; Kornienko, Olga; Rivas-Drake, Deborah

    2017-05-01

    The peer context features prominently in theory, and increasingly in empirical research, about ethnic-racial identity (ERI) development, but no studies have assessed peer influence on ERI using methods designed to properly assess peer influence. We examined peer influence on ERI centrality, private, and public regard using longitudinal social network analysis. Data were drawn from two sites: a predominantly Latina/o Southwestern (SW) school (N = 1034; Mage = 12.10) and a diverse Midwestern (MW) school (N = 513; Mage = 11.99). Findings showed that peers influenced each other's public regard over time at both sites. However, peer influence on centrality was evident in the SW site, whereas peer influence on private regard was evident in the MW site. Importantly, peer influence was evident after controlling for selection effects. Our integration of developmental, contextual, and social network perspectives offers a fruitful approach to explicate how ERI content may shift in early adolescence as a function of peer influence. © 2017 The Authors. Child Development © 2017 Society for Research in Child Development, Inc.

  4. Site Characterization Plan: Yucca Mountain Site, Nevada Research and Development Area, Nevada: Volume 3, Part A: Chapters 6 and 7

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1988-12-01

    This site characterization plan (SCP) has been developed for the candidate repository site at Yucca Mountain in the State of Nevada. The SCP includes a description of the Yucca Mountain site (Chapters 1-5), a conceptual design for the repository (Chapter 6), a description of the packaging to be used for the waste to be emplaced in the repository (Chapter 7), and a description of the planned site characterization activities (Chapter 8). The schedules and milestones presented in Sections 8.3 and 8.5 of the SCP were developed to be consistent with the June 1988 draft Amendment to the DOE`s Mission Plan for the Civilian Radioactive Waste Management Program. The five month delay in the scheduled start of exploratory shaft construction that was announced recently is not reflected in these schedules. 218 figs., 50 tabs.

  5. Site characterization plan: Yucca Mountain Site, Nevada Research and Development Area, Nevada: Volume 3, Part A: Chapters 6 and 7

    International Nuclear Information System (INIS)

    1988-12-01

    This site characterization plan (SCP) has been developed for the candidate repository site at Yucca Mountain in the State of Nevada. The SCP includes a description of the Yucca Mountain site (Chapters 1-5), a conceptual design for the repository (Chapter 6), a description of the packaging to be used for the waste to be emplaced in the repository (Chapter 7), and a description of the planned site characterization activities (Chapter 8). The schedules and milestones presented in Sections 8.3 and 8.5 of the SCP were developed to be consistent with the June 1988 draft Amendment to the DOE's Mission Plan for the Civilian Radioactive Waste Management Program. The five month delay in the scheduled start of exploratory shaft construction that was announced recently is not reflected in these schedules. 218 figs., 50 tabs

  6. Site characterization plan: Yucca Mountain Site, Nevada Research and Development Area, Nevada: Volume 1, Part A: Chapters 1 and 2

    International Nuclear Information System (INIS)

    1988-12-01

    This site characterization plan (SCP) has been developed for the candidate repository site at Yucca Mountain in the State of Nevada. The SCP includes a description of the Yucca Mountain site (Chapters 1-5), a conceptual design for the repository (Chapter 6), a description of the packaging to be used for the waste to be emplaced in the repository (Chapter 7), and a description of the planned site characterization activities (Chapter 8). The schedules and milestones presented in Sections 8.3 and 8.5 of the SCP were developed to be consistent with the June 1988 draft Amendment to the DOE's Mission Plan for the Civilian Radioactive Waste Management Program. The five month delay in the scheduled start of exploratory shaft construction that was announced recently is not reflected in these schedules. 750 refs., 123 figs., 42 tabs

  7. Site characterization plan: Yucca Mountain Site, Nevada Research and Development Area, Nevada: Volume 1, Part A: Chapters 1 and 2

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1988-12-01

    This site characterization plan (SCP) has been developed for the candidate repository site at Yucca Mountain in the State of Nevada. The SCP includes a description of the Yucca Mountain site (Chapters 1-5), a conceptual design for the repository (Chapter 6), a description of the packaging to be used for the waste to be emplaced in the repository (Chapter 7), and a description of the planned site characterization activities (Chapter 8). The schedules and milestones presented in Sections 8.3 and 8.5 of the SCP were developed to be consistent with the June 1988 draft Amendment to the DOE`s Mission Plan for the Civilian Radioactive Waste Management Program. The five month delay in the scheduled start of exploratory shaft construction that was announced recently is not reflected in these schedules. 750 refs., 123 figs., 42 tabs.

  8. Design criteria for a worldwide directory of radioactively contaminated sites (DRCS)

    International Nuclear Information System (INIS)

    2001-11-01

    The publication attempts to fulfil two main objectives: (a) to describe the activities and underlying considerations and concepts for the development by the IAEA of a worldwide Directory of Radioactively Contaminated Sites; (b) to give some recommendations for the development of such directories at the Member States level. In addition to a discussion of the conceptual considerations on the design of an IAEA-level directory, the results of previous efforts on data collation are presented. The DRCS also intends to collate technical information on remedial actions taken or proposed, thus giving examples for consultation in similar cases. Hence, the information available in such a Directory is intended to provide decision makers with a useful reference frame for their own actions. In this the IAEA attempts to assume the role of a clearing-house of information pertinent to characterization of radioactively contaminated sites and their remediation and restoration

  9. Design criteria for a worldwide directory of radioactively contaminated sites (DRCS)

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-11-01

    The publication attempts to fulfil two main objectives: (a) to describe the activities and underlying considerations and concepts for the development by the IAEA of a worldwide Directory of Radioactively Contaminated Sites; (b) to give some recommendations for the development of such directories at the Member States level. In addition to a discussion of the conceptual considerations on the design of an IAEA-level directory, the results of previous efforts on data collation are presented. The DRCS also intends to collate technical information on remedial actions taken or proposed, thus giving examples for consultation in similar cases. Hence, the information available in such a Directory is intended to provide decision makers with a useful reference frame for their own actions. In this the IAEA attempts to assume the role of a clearing-house of information pertinent to characterization of radioactively contaminated sites and their remediation and restoration.

  10. Review and comment on the US Department of Energy Site Characterization Plan Conceptual Design report

    International Nuclear Information System (INIS)

    1988-10-01

    The ''Site Characterization Plan Conceptual Design Report,'' as prepared by the United States Department of Energy and its contractors, depicts the conceptual designs being proposed for the Yucca Mountain, Nevada High-Level Waste Repository. Much of the report is comprised of designs based on large assumptions that lead to inconclusiveness in terms of technical integrity and reasonableness. As a result, the likely success of the designs proposed within the report is highly questionable from a technical and even constructibility standpoint. Grave deficiencies have been found throughout the report ranging from the over-simplification of the geologic and geohydrologic setting to the incorrect determination of the repository horizon's host rock strength. All of these deficiencies found within the report relate directly to the probable outcome of the site characterization of Yucca Mountain and the possible design and construction of a high-level waste repository at the site. It does not appear that a concerted effort has been put forth to develop many of the concepts within the report to a reasonable level of engineering and scientific integrity that would be suitable to meet the needs of and provide the results to the Nation's High-Level Waste Program

  11. Brownfields Recommendations for Sustainable Site Design — Green Landscape Plan

    Science.gov (United States)

    The assessment of conditions contained in this report focuses on site-specific environmental and soil conditions that might affect recommendations related to sustainable landscaping and site design, stormwater management, and stormwater reuse.

  12. Building arrangement and site layout design guides for on site low level radioactive waste storage facilities

    International Nuclear Information System (INIS)

    McMullen, J.W.; Feehan, M.J.

    1986-01-01

    Many papers have been written by AE's and utilities describing their onsite storage facilities, why they are needed, NRC regulations, and disposal site requirements. This paper discusses a typical storage facility and address the design considerations and operational aspects that are generally overlooked when designing and siting a low level radioactive waste storage facility. Some topics to be addressed are: 1. Container flexibility; 2. Modular expansion capabilities; 3. DOT regulations; 4. Meterological requirements; 5. OSHA; 6. Fire protection; 7. Floods; 8. ALARA

  13. Design and implementation of an identification system in construction site safety for proactive accident prevention.

    Science.gov (United States)

    Yang, Huanjia; Chew, David A S; Wu, Weiwei; Zhou, Zhipeng; Li, Qiming

    2012-09-01

    Identifying accident precursors using real-time identity information has great potential to improve safety performance in construction industry, which is still suffering from day to day records of accident fatality and injury. Based on the requirements analysis for identifying precursor and the discussion of enabling technology solutions for acquiring and sharing real-time automatic identification information on construction site, this paper proposes an identification system design for proactive accident prevention to improve construction site safety. Firstly, a case study is conducted to analyze the automatic identification requirements for identifying accident precursors in construction site. Results show that it mainly consists of three aspects, namely access control, training and inspection information and operation authority. The system is then designed to fulfill these requirements based on ZigBee enabled wireless sensor network (WSN), radio frequency identification (RFID) technology and an integrated ZigBee RFID sensor network structure. At the same time, an information database is also designed and implemented, which includes 15 tables, 54 queries and several reports and forms. In the end, a demonstration system based on the proposed system design is developed as a proof of concept prototype. The contributions of this study include the requirement analysis and technical design of a real-time identity information tracking solution for proactive accident prevention on construction sites. The technical solution proposed in this paper has a significant importance in improving safety performance on construction sites. Moreover, this study can serve as a reference design for future system integrations where more functions, such as environment monitoring and location tracking, can be added. Copyright © 2011 Elsevier Ltd. All rights reserved.

  14. Site characterization plan: Conceptual design report, Volume 2: Chapters 4-9: Nevada Nuclear Waste Storage Investigations Project

    International Nuclear Information System (INIS)

    MacDougall, H.R.; Scully, L.W.; Tillerson, J.R.

    1987-09-01

    This document presents a description of a prospective geologic repository for high-level radioactive waste to support the development of the Site Characterization Plan for the Yucca Mountain site. The target horizon for waste emplacement is a sloping bed of densely welded tuff more than 650 ft below the surface and typically more than 600 ft above the water table. The conceptual design described in this report is unique among repository designs in that it uses ramps in addition to shafts to gain access to the underground facility, the emplacement horizon is located above the water table, and it is possible that 300- to 400-ft-long horizontal waste emplacement boreholes will be used. This report summarizes the design bases (site and properties of the waste package), design and performance criteria, and the design analyses performed. The current status of meeting the preclosure performance objectives for licensing and of resolving the repository design and preclosure issues is presented. The repository design presented in this report will be expanded and refined during the advanced conceptual design, the license application design, and the final procurement and construction design phases. 147 refs., 145 figs., 83 tabs

  15. Long-term climate change assessment study plan for the Hanford Site Permanent Isolation Barrier Development Program

    International Nuclear Information System (INIS)

    Petersen, K.L.; Chatters, J.C.; Waugh, W.J.

    1993-05-01

    The Hanford Site Permanent Isolation Barrier Development Program (Barrier Development Program) was organized to develop the technology needed to provide an in-place disposal capability for low-level nuclear waste for the US Department of Energy at the Hanford Site in south-central Washington. The goal of the Barrier Development Program is to provide defensible evidence that final barrier design(s) will adequately control water infiltration, plant and animal intrusion, and wind and water erosion for a minimum of 1,000 yr; to isolate wastes from the accessible environment; and to use markers to warn inadvertent human intruders. Evidence for barrier performance will be obtained by conducting laboratory experiments, field tests, computer modeling, and other studies that establish confidence in the barrier's ability to meet its 1,000-yr design life

  16. Computational design of trimeric influenza-neutralizing proteins targeting the hemagglutinin receptor binding site

    Energy Technology Data Exchange (ETDEWEB)

    Strauch, Eva-Maria; Bernard, Steffen M.; La, David; Bohn, Alan J.; Lee, Peter S.; Anderson, Caitlin E.; Nieusma, Travis; Holstein, Carly A.; Garcia, Natalie K.; Hooper, Kathryn A.; Ravichandran, Rashmi; Nelson, Jorgen W.; Sheffler, William; Bloom, Jesse D.; Lee, Kelly K.; Ward, Andrew B.; Yager, Paul; Fuller, Deborah H.; Wilson, Ian A.; Baker , David (UWASH); (Scripps); (FHCRC)

    2017-06-12

    Many viral surface glycoproteins and cell surface receptors are homo-oligomers1, 2, 3, 4, and thus can potentially be targeted by geometrically matched homo-oligomers that engage all subunits simultaneously to attain high avidity and/or lock subunits together. The adaptive immune system cannot generally employ this strategy since the individual antibody binding sites are not arranged with appropriate geometry to simultaneously engage multiple sites in a single target homo-oligomer. We describe a general strategy for the computational design of homo-oligomeric protein assemblies with binding functionality precisely matched to homo-oligomeric target sites5, 6, 7, 8. In the first step, a small protein is designed that binds a single site on the target. In the second step, the designed protein is assembled into a homo-oligomer such that the designed binding sites are aligned with the target sites. We use this approach to design high-avidity trimeric proteins that bind influenza A hemagglutinin (HA) at its conserved receptor binding site. The designed trimers can both capture and detect HA in a paper-based diagnostic format, neutralizes influenza in cell culture, and completely protects mice when given as a single dose 24 h before or after challenge with influenza.

  17. Intranet Development and Design that Works

    International Nuclear Information System (INIS)

    BACA, BOBBY G.; CASSIDY, ANDREA L.

    1999-01-01

    Making information available and easy to find is the objective of designing a good web site. A company's Intranet typically provides a great deal of information to its employees in an effort to help them better perform their jobs. If the information is available but is difficult to locate, the usefulness of this information is diminished. Sandia National Laboratories performed a redesign of its home page and has obtained a successful design which enables its employees to locate information quickly and efficiently. Three phases of usability testing were conducted to develop and optimize the home page. This paper will discuss the redesign of the Intranet home page and describe how usability studies were used to help ensure a usable design

  18. Recent Developments in the Definition of Design Earthquake ...

    African Journals Online (AJOL)

    Recent developments in the definition of design ground motions for seismic analysis of structures are presented. A summary of results of empirical and analytical site-effect studies are provided and recent findings from empirical studies on instrumental records are compared against similar results from earlier studies.

  19. Kinetic energy recovery turbine technology: resource assessment and site development strategy

    Energy Technology Data Exchange (ETDEWEB)

    Briand, Marie-Helene; Ng, Karen

    2010-09-15

    New technologies to extract readily available energy from waves, tides and river flow are being developed and are promising but are still at the demonstration stage. Harnessing kinetic energy from currents (hydrokinetic power) is considered an attractive and cost-effective renewable energy solution to replace thermal generation without requiring construction of a dam or large civil works. The nature of this innovative hydrokinetic technology requires an adaptation of conventional approach to project engineering and environmental impact studies. This paper presents the approach developed by RSW to design a hydrokinetic site in the riverine environment, from resource assessment to detailed engineering design.

  20. Early Site Permit Demonstration Program: Station design alternatives report

    International Nuclear Information System (INIS)

    1993-03-01

    This report provides the results of investigating the basis for including Station Design Alternatives (SDAs) in the regulatory guidance given for nuclear plant environmental reports (ERs), explains approaches or processes for evaluating SDAs at the early site permit (ESP) stage, and applies one of the processes to each of the ten systems or subsystems considered as SDAS. The key objective o this report s to demonstrate an adequate examination of alternatives can be performed without the extensive development f design data. The report discusses the Composite Suitability Approach and the Established Cutoff Approach in evaluating station design alternatives and selects one of these approaches to evaluate alternatives for each of the plant or station that were considered. Four types of ALWRs have been considered due to the availability of extensive plant data: System 80+, AP600, Advanced Boiling Reactor (ABWR), and Simplified Boiling Water Reactor (SBWR). This report demonstrates the feasibility of evaluating station design alternatives when reactor design detail has not been determined, quantitatively compares the potential ental impacts of alternatives, and focuses the ultimate selection of a alternative on cost and applicant-specific factors. The range of alternatives system is deliberately limited to a reasonable number to demonstrate the or to the three most commonly used at operating plants

  1. Site characterization plan: Yucca Mountain Site, Nevada Research and Development Area, Nevada: Volume 2, Part A: Chapters 3, 4, and 5

    International Nuclear Information System (INIS)

    1988-12-01

    This site characterization plan (SCP) has been developed for the candidate repository site at Yucca Mountain in the State of Nevada. The SCP includes a description of the Yucca Mountain site (Chapters 1--5), a conceptual design for the repository (Chapter 6), a description of the packaging to be used for the waste to be emplaced in the repository (Chapter 7), and a description of the planned site characterization activities (Chapter 8). The schedules and milestones presented in Sections 8.3 and 8.5 of the SCP were developed to be consistent with the June 1988 draft Amendment to the DOE's Mission Plan for the Civilian Radioactive Waste Management Program. The five month delay in the scheduled start of exploratory shaft construction that was announced recently is not reflected in these schedules. 575 refs., 84 figs., 68 tabs

  2. Site characterization plan: Yucca Mountain Site, Nevada Research and Development Area, Nevada: Volume 2, Part A: Chapters 3, 4, and 5

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1988-12-01

    This site characterization plan (SCP) has been developed for the candidate repository site at Yucca Mountain in the State of Nevada. The SCP includes a description of the Yucca Mountain site (Chapters 1--5), a conceptual design for the repository (Chapter 6), a description of the packaging to be used for the waste to be emplaced in the repository (Chapter 7), and a description of the planned site characterization activities (Chapter 8). The schedules and milestones presented in Sections 8.3 and 8.5 of the SCP were developed to be consistent with the June 1988 draft Amendment to the DOE`s Mission Plan for the Civilian Radioactive Waste Management Program. The five month delay in the scheduled start of exploratory shaft construction that was announced recently is not reflected in these schedules. 575 refs., 84 figs., 68 tabs.

  3. Hanford Site Protective Barrier Development Program: Fiscal year 1990 highlights

    International Nuclear Information System (INIS)

    Cadwell, L.L.

    1991-09-01

    The Hanford Site Protective Barrier Development Program was jointly developed by Pacific Northwest Laboratory (PNL) and Westinghouse Hanford Company (WHC) to design and test an earthen cover system(s) that can be used to inhibit water infiltration; plant, animal, and human intrusion; and wind and water erosion. The joint PNL/WHC program was initiated in FY 1986. To date, research findings support the initial concepts of barrier designs for the Hanford Site. A fine-soil surface is planned to partition surface water into runoff and temporary storage. Transpiration by vegetation that grows in the fine-soil layer will return stored water to the atmosphere as will surface evaporation. A capillary break created by the interface of the fine-soil layer and coarser textured materials below will further limit the downward migration of surface water, making it available over a longer period of time for cycling to the atmosphere. Should water pass the interface, it will drain laterally through a coarse textured sand/gravel layer. Tested barrier designs appear to work adequately to prevent drainage under current and postulated wetter-climate (added precipitation) conditions. Wind and water erosion tasks are developing data to predict the extent of erosion on barrier surfaces. Data collected during the last year confirm the effectiveness of small burrowing animals in removing surface water. Water infiltrating through burrows of larger mammals was subsequently lost by natural processes. Natural analog and climate change studies are under way to provide credibility for modeling the performance of barrier designs over a long period of time and under shifts in climate. 10 refs., 30 figs

  4. Hanford Site Protective Barrier Development Program: Fiscal year 1990 highlights

    Energy Technology Data Exchange (ETDEWEB)

    Cadwell, L.L. (ed.)

    1991-09-01

    The Hanford Site Protective Barrier Development Program was jointly developed by Pacific Northwest Laboratory (PNL) and Westinghouse Hanford Company (WHC) to design and test an earthen cover system(s) that can be used to inhibit water infiltration; plant, animal, and human intrusion; and wind and water erosion. The joint PNL/WHC program was initiated in FY 1986. To date, research findings support the initial concepts of barrier designs for the Hanford Site. A fine-soil surface is planned to partition surface water into runoff and temporary storage. Transpiration by vegetation that grows in the fine-soil layer will return stored water to the atmosphere as will surface evaporation. A capillary break created by the interface of the fine-soil layer and coarser textured materials below will further limit the downward migration of surface water, making it available over a longer period of time for cycling to the atmosphere. Should water pass the interface, it will drain laterally through a coarse textured sand/gravel layer. Tested barrier designs appear to work adequately to prevent drainage under current and postulated wetter-climate (added precipitation) conditions. Wind and water erosion tasks are developing data to predict the extent of erosion on barrier surfaces. Data collected during the last year confirm the effectiveness of small burrowing animals in removing surface water. Water infiltrating through burrows of larger mammals was subsequently lost by natural processes. Natural analog and climate change studies are under way to provide credibility for modeling the performance of barrier designs over a long period of time and under shifts in climate. 10 refs., 30 figs.

  5. Estimating open population site occupancy from presence-absence data lacking the robust design.

    Science.gov (United States)

    Dail, D; Madsen, L

    2013-03-01

    Many animal monitoring studies seek to estimate the proportion of a study area occupied by a target population. The study area is divided into spatially distinct sites where the detected presence or absence of the population is recorded, and this is repeated in time for multiple seasons. However, when occupied sites are detected with probability p Ecology 84, 2200-2207) developed a multiseason model for estimating seasonal site occupancy (ψt ) while accounting for unknown p. Their model performs well when observations are collected according to the robust design, where multiple sampling occasions occur during each season; the repeated sampling aids in the estimation p. However, their model does not perform as well when the robust design is lacking. In this paper, we propose an alternative likelihood model that yields improved seasonal estimates of p and Ψt in the absence of the robust design. We construct the marginal likelihood of the observed data by conditioning on, and summing out, the latent number of occupied sites during each season. A simulation study shows that in cases without the robust design, the proposed model estimates p with less bias than the MacKenzie et al. model and hence improves the estimates of Ψt . We apply both models to a data set consisting of repeated presence-absence observations of American robins (Turdus migratorius) with yearly survey periods. The two models are compared to a third estimator available when the repeated counts (from the same study) are considered, with the proposed model yielding estimates of Ψt closest to estimates from the point count model. Copyright © 2013, The International Biometric Society.

  6. On site PWR fuel inspection measurements for operational and design verification

    International Nuclear Information System (INIS)

    1996-01-01

    The on-site inspection of irradiated Pressurized Water Reactor (PWR) fuel and Non-Fuel Bearing Components (NFBC) is typically limited to visual inspections during refuelings using underwater TV cameras and is intended primarily to confirm whether the components will continue in operation. These inspections do not normally provide data for design verification nor information to benefit future fuel designs. Japanese PWR utilities and Nuclear Fuel Industries Ltd. designed, built, and performed demonstration tests of on-site inspection equipment that confirms operational readiness of PWR fuel and NFBC and also gathers data for design verification of these components. 4 figs, 3 tabs

  7. Remedial action plan and site conceptual design for stabilization of the inactive uranium mill tailings site at Ambrosia Lake, New Mexico

    International Nuclear Information System (INIS)

    Matthews, M.L.; Mitzelfelt, R.

    1991-11-01

    This Remedial Action Plan (RAP) has been developed to serve a dual purpose. It presents the series of activities that is proposed by the US Department of Energy (DOE) to stabilize and control radioactive materials at the inactive Phillips/United Nuclear uranium processing site designated as the Ambrosia Lake site in McKinley County, New Mexico. It also serves to document the concurrence of both State of New Mexico and the US Nuclear Regulatory Commission (NRC) in the remedial action. This agreement, upon execution by the DOE and the state and concurrence by NRC, becomes Appendix B of the Cooperative Agreement

  8. "Less Clicking, More Watching": Results from the User-Centered Design of a Multi-Institutional Web Site for Art and Culture.

    Science.gov (United States)

    Vergo, John; Karat, Clare-Marie; Karat, John; Pinhanez, Claudio; Arora, Renee; Cofino, Thomas; Riecken, Doug; Podlaseck, Mark

    This paper summarizes a 10-month long research project conducted at the IBM T.J. Watson Research Center aimed at developing the design concept of a multi-institutional art and culture web site. The work followed a user-centered design (UCD) approach, where interaction with prototypes and feedback from potential users of the web site were sought…

  9. Brownfields Green Avenue Sites: Technical Memorandum - Conceptual Design for Sustainable Redevelopment

    Science.gov (United States)

    This technical memorandum briefly describes the site and proposed conceptual site plan, indicates conceptual design considerations, specifies recommended green and sustainable features, and offers other recommendations

  10. Hanford Site sustainable development initiatives

    International Nuclear Information System (INIS)

    Sullivan, C.T.

    1994-05-01

    Since the days of the Manhattan Project of World War II, the economic well being of the Tri-Cities (Pasco, Kennewick, and Richland) of Washington State has been tied to the US Department of Energy missions at the nearby Hanford Site. As missions at the Site changed, so did the economic vitality of the region. The Hanford Site is now poised to complete its final mission, that of environmental restoration. When restoration is completed, the Site may be closed and the effect on the local economy will be devastating if action is not taken now. To that end, economic diversification and transition are being planned. To facilitate the process, the Hanford Site will become a sustainable development demonstration project

  11. Seismic design of circular-section concrete-lined underground openings: Preclosure performance considerations for the Yucca Mountain Site

    International Nuclear Information System (INIS)

    Richardson, A.M.; Blejwas, T.E.

    1992-01-01

    Yucca Mountain, the potential site of a repository for high-level radioactive waste, is situated in a region of natural and man-made seismicity. Underground openings excavated at this site must be designed for worker safety in the seismic environment anticipated for the preclosure period. This includes accesses developed for site characterization regardless of the ultimate outcome of the repository siting process. Experience with both civil and mining structures has shown that underground openings are much more resistant to seismic effects than surface structures, and that even severe dynamic strains can usually be accommodated with proper design. This paper discusses the design and performance of lined openings in the seismic environment of the potential site. The types and ranges of possible ground motions (seismic loads) are briefly discussed. Relevant historical records of underground opening performance during seismic loading are reviewed. Simple analytical methods of predicting liner performance under combined in situ, thermal, and seismic loading are presented, and results of calculations are discussed in the context of realistic performance requirements for concrete-lined openings for the preclosure period. Design features that will enhance liner stability and mitigate the impact of the potential seismic load are reviewed. The paper is limited to preclosure performance concerns involving worker safety because present decommissioning plans specify maintaining the option for liner removal at seal locations, thus decoupling liner design from repository postclosure performance issues

  12. Design and implementation of a computer based site operations log for the ARM Program

    International Nuclear Information System (INIS)

    Tichler, J.L.; Bernstein, H.J.; Bobrowski, S.F.; Melton, R.B.; Campbell, A.P.; Edwards, D.M.; Kanciruk, P.; Singley, P.T.

    1992-01-01

    The Atmospheric Radiation Measurement (ARM) Program is a Department of Energy (DOE) research effort to reduce the uncertainties found in general circulation and other models due to the effects of clouds and solar radiation. ARM will provide an experimental testbed for the study of important atmospheric effects, particularly cloud and radiative processes, and testing of parameterizations of the processes for use in atmospheric models. The design of the testbed known as the Clouds and Radiation Testbed (CART), calls for five, long-term field data collection sites. The first site, located in the Southern Great Plains (SGP) in Lamont, OK began operation in the spring of 1992. The CART Data Environment (CDE) is the element of the testbed which acquires the basic observations from the instruments and processes them to meet the ARM requirements. A formal design was used to develop a description of the logical requirements for the CDE. This paper discusses the design and prototype implementation of a part of the CDE known as the site operations log, which records metadata defining the environment within which the data produced by the instruments is collected

  13. Development of portal web site for fostering of risk literacy 'risk information navigator'

    International Nuclear Information System (INIS)

    Shobu, Nobuhiro; Mitsui, Seiichiro; Nakamura, Hirofumi

    2004-01-01

    Risk communication activities are important for promoting mutual understanding between local communities and Japan Nuclear Cycle Development Institutes (JNC). In addition to conventional public relation activities, the risk communication study team of JNC Tokai Works has started practical studies to promote further mutual understanding with its local communities. This paper reports the design and concept of a web site for the fostering of risk literacy, the 'Risk Information Navigator', that was developed as one of the risk communication methods, and surveys the web site from the user's perspective. (author)

  14. 10 CFR 435.6 - Sustainable principles for siting, design and construction. [Reserved

    Science.gov (United States)

    2010-01-01

    ... 10 Energy 3 2010-01-01 2010-01-01 false Sustainable principles for siting, design and construction. [Reserved] 435.6 Section 435.6 Energy DEPARTMENT OF ENERGY ENERGY CONSERVATION ENERGY EFFICIENCY STANDARDS...-Rise Residential Buildings. § 435.6 Sustainable principles for siting, design and construction...

  15. 10 CFR 433.6 - Sustainable principles for siting, design and construction. [Reserved

    Science.gov (United States)

    2010-01-01

    ... 10 Energy 3 2010-01-01 2010-01-01 false Sustainable principles for siting, design and construction. [Reserved] 433.6 Section 433.6 Energy DEPARTMENT OF ENERGY ENERGY CONSERVATION ENERGY EFFICIENCY STANDARDS... BUILDINGS § 433.6 Sustainable principles for siting, design and construction. [Reserved] ...

  16. Evaluation of the Overall Costs for the Croatian Repository: Varying Site, Design and Financial Parameters

    International Nuclear Information System (INIS)

    Kucar-Dragicevic, S.; Subasic, D.; Lebegner, J.

    2000-01-01

    Preliminary preparations for the construction of a LILW repository in Croatia included a number of activities and projects related to the siting process, safety assessment, disposal technology and repository design, and public acceptance issues. Costs evaluations have always been a part of the developing project documentation. However, only the estimates of the facility construction and equipment acquisition costs had been included, while other costs associated with the project development and management have not been considered up to now. For the first time the infrastructure status at the potential sites has been evaluated, and the costs of the repository operations as well as the post-closure management has been estimated. Cost parameters have been considered from both technical and fiscal points of view, comparing their relative influence on the overall repository costs. Assessment of the total project costs in eight cases for the four preferential sites and two repository designs gave a clearer picture of the development and management costs differences for the considered options. Without considerations of the operational and post-operational repository management expenses, the total project costs appear to have been heavily underestimated. Also, while the construction costs for the tunnel and the surface type repositories are significantly different, this influence of the repository type on the total project costs becomes far less important when the later phases management expenses are added. Finally, the role of fiscal parameters may further diminish the site and technology impacts on the overall costs. (author)

  17. Development of on-site accident criteria for waste transfer casks

    International Nuclear Information System (INIS)

    Uldrich, E.D.

    1989-01-01

    Removal of radioactive waste must withstand the scrutiny of the public and various regulatory offices. Currently, there is no standard accident criteria or methodology for intra-site shipments at the Idaho National Engineering Laboratory (INEL). Since the radioactive waste transfer casks only carry material within the INEL site boundaries and are not used for normal over-the-road transport, the requirements of 10 CFR 71 Packaging and Transportation of Radioactive Material, do not provide suitable requirements for cask design or safety analyses. The objective is to develop realistically conservative accident scenarios consistent with the limited uses at the INEL for which the cask is approved

  18. On-Site Inspection RadioIsotopic Spectroscopy (Osiris) System Development

    Energy Technology Data Exchange (ETDEWEB)

    Caffrey, Gus J. [Idaho National Laboratory, Idaho Falls, ID (United States); Egger, Ann E. [Idaho National Laboratory, Idaho Falls, ID (United States); Krebs, Kenneth M. [Idaho National Laboratory, Idaho Falls, ID (United States); Milbrath, B. D. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Jordan, D. V. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Warren, G. A. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Wilmer, N. G. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

    2015-09-01

    We have designed and tested hardware and software for the acquisition and analysis of high-resolution gamma-ray spectra during on-site inspections under the Comprehensive Nuclear-Test-Ban Treaty (CTBT). The On-Site Inspection RadioIsotopic Spectroscopy—Osiris—software filters the spectral data to display only radioisotopic information relevant to CTBT on-site inspections, e.g.,132I. A set of over 100 fission-product spectra was employed for Osiris testing. These spectra were measured, where possible, or generated by modeling. The synthetic test spectral compositions include non-nuclear-explosion scenarios, e.g., a severe nuclear reactor accident, and nuclear-explosion scenarios such as a vented underground nuclear test. Comparing its computer-based analyses to expert visual analyses of the test spectra, Osiris correctly identifies CTBT-relevant fission product isotopes at the 95% level or better.The Osiris gamma-ray spectrometer is a mechanically-cooled, battery-powered ORTEC Transpec-100, chosen to avoid the need for liquid nitrogen during on-site inspections. The spectrometer was used successfully during the recent 2014 CTBT Integrated Field Exercise in Jordan. The spectrometer is controlled and the spectral data analyzed by a Panasonic Toughbook notebook computer. To date, software development has been the main focus of the Osiris project. In FY2016-17, we plan to modify the Osiris hardware, integrate the Osiris software and hardware, and conduct rigorous field tests to ensure that the Osiris system will function correctly during CTBT on-site inspections. The planned development will raise Osiris to technology readiness level TRL-8; transfer the Osiris technology to a commercial manufacturer, and demonstrate Osiris to potential CTBT on-site inspectors.

  19. On-Site Inspection RadioIsotopic Spectroscopy (Osiris) System Development

    International Nuclear Information System (INIS)

    Caffrey, Gus J.; Egger, Ann E.; Krebs, Kenneth M.; Milbrath, B. D.; Jordan, D. V.; Warren, G. A.; Wilmer, N. G.

    2015-01-01

    We have designed and tested hardware and software for the acquisition and analysis of high-resolution gamma-ray spectra during on-site inspections under the Comprehensive Nuclear-Test-Ban Treaty (CTBT). The On-Site Inspection RadioIsotopic Spectroscopy-Osiris-software filters the spectral data to display only radioisotopic information relevant to CTBT on-site inspections, e.g.,132I. A set of over 100 fission-product spectra was employed for Osiris testing. These spectra were measured, where possible, or generated by modeling. The synthetic test spectral compositions include non-nuclear-explosion scenarios, e.g., a severe nuclear reactor accident, and nuclear-explosion scenarios such as a vented underground nuclear test. Comparing its computer-based analyses to expert visual analyses of the test spectra, Osiris correctly identifies CTBT-relevant fission product isotopes at the 95% level or better.The Osiris gamma-ray spectrometer is a mechanically-cooled, battery-powered ORTEC Transpec-100, chosen to avoid the need for liquid nitrogen during on-site inspections. The spectrometer was used successfully during the recent 2014 CTBT Integrated Field Exercise in Jordan. The spectrometer is controlled and the spectral data analyzed by a Panasonic Toughbook notebook computer. To date, software development has been the main focus of the Osiris project. In FY2016-17, we plan to modify the Osiris hardware, integrate the Osiris software and hardware, and conduct rigorous field tests to ensure that the Osiris system will function correctly during CTBT on-site inspections. The planned development will raise Osiris to technology readiness level TRL-8; transfer the Osiris technology to a commercial manufacturer, and demonstrate Osiris to potential CTBT on-site inspectors.

  20. Catalysis by Design: Well-Defined Single-Site Heterogeneous Catalysts

    KAUST Repository

    Pelletier, Jeremie

    2016-03-09

    ConspectusHeterogeneous catalysis, a field important industrially and scientifically, is increasingly seeking and refining strategies to render itself more predictable. The main issue is due to the nature and the population of catalytically active sites. Their number is generally low to very low, their "acid strengths" or " redox properties" are not homogeneous, and the material may display related yet inactive sites on the same material. In many heterogeneous catalysts, the discovery of a structure-activity reationship is at best challenging. One possible solution is to generate single-site catalysts in which most, if not all, of the sites are structurally identical. Within this context and using the right tools, the catalyst structure can be designed and well-defined, to reach a molecular understanding. It is then feasible to understand the structure-activity relationship and to develop predictable heterogeneous catalysis. Single-site well-defined heterogeneous catalysts can be prepared using concepts and tools of surface organometallic chemistry (SOMC). This approach operates by reacting organometallic compounds with surfaces of highly divided oxides (or of metal nanoparticles). This strategy has a solid track record to reveal structure-activity relationship to the extent that it is becoming now quite predictable. Almost all elements of the periodical table have been grafted on surfaces of oxides (from simple oxides such as silica or alumina to more sophisticated materials regarding composition or porosity).Considering catalytic hydrocarbon transformations, heterogeneous catalysis outcome may now be predicted based on existing mechanistic proposals and the rules of molecular chemistry (organometallic, organic) associated with some concepts of surface sciences. A thorough characterization of the grafted metal centers must be carried out using tools spanning from molecular organometallic or surface chemistry. By selection of the metal, its ligand set, and the

  1. A future for nuclear sites beyond their service life. Nuclear site value development

    International Nuclear Information System (INIS)

    2008-01-01

    As the nuclear industry moves into a new development phase, many facilities built in the fifties and sixties are reaching the end of their service life. Dismantling them and rehabilitating the sites on which they stand is a major industrial challenge which will give rise to a number of new projects. AREVA has more than 20 years' experience in these highly technical fields. As more and more sites reach the end of their service life, AREVA considers nuclear site value development as a fully-fledged industrial activity. The group's competencies in this field have been grouped together to form a dedicated entity: the Nuclear Site Value Development Business Unit, created in 2008. Several billion euros are invested in site value development projects which are far-reaching and complex, and often last for several decades. Long before work actually begins, lengthy studies and preparations are required to schedule operations, select the techniques to be used and optimize costs and deadlines. The Nuclear Site Value Development BU is currently working on four major projects involving its own facilities and those of the CEA: - La Hague: dismantling of the first generation of used fuel recycling facilities. Between 1966 and 1998, almost 5,000 tons of used fuel from graphite-moderated gas-cooled reactors, 4,500 tons of light water reactor fuel, as well as fuel from fast reactors and research reactors, were treated at UP2 400, the very first industrial recycling plant on the La Hague site. - Marcoule: first-time dismantling of a recycling plant. 1,000 rooms to be cleaned up, 30,000 tons of waste to be treated, 30 years of work. - Cadarache: first-time dismantling of a Mox fuel fabrication plant. The Cadarache plant was commissioned in 1962 to fabricate fuel for fast reactors; this was followed by MOX fuel for light water reactors, an activity which continued until the plant was shut down in 2003. - Annecy and Veurey: giving a new lease of life to former industrial sites in built

  2. Umatilla Satellite and Release Sites Project : Final Siting Report.

    Energy Technology Data Exchange (ETDEWEB)

    Montgomery, James M.

    1992-04-01

    This report presents the results of site analysis for the Umatilla Satellite and Release Sites Project. The purpose of this project is to provide engineering services for the siting and conceptual design of satellite and release facilities for the Umatilla Basin hatchery program. The Umatilla Basin hatchery program consists of artificial production facilities for salmon and steelhead to enhance production in the Umatilla River as defined in the Umatilla master plan approved in 1989 by the Northwest Power Planning Council. Facilities identified in the master plan include adult salmon broodstock holding and spawning facilities, facilities for recovery, acclimation, and/or extended rearing of salmon juveniles, and development of river sites for release of hatchery salmon and steelhead. The historic and current distribution of fall chinook, summer chinook, and coho salmon and steelhead trout was summarized for the Umatilla River basin. Current and future production and release objectives were reviewed. Twenty seven sites were evaluated for the potential and development of facilities. Engineering and environmental attributes of the sites were evaluated and compared to facility requirements for water and space. Site screening was conducted to identify the sites with the most potential for facility development. Alternative sites were selected for conceptual design of each facility type. A proposed program for adult holding facilities, final rearing/acclimation, and direct release facilities was developed.

  3. SAFETY BASIS DESIGN DEVELOPMENT CHALLENGES IMECE2007-42747

    Energy Technology Data Exchange (ETDEWEB)

    RYAN GW

    2007-09-24

    'Designing in Safety' is a desired part of the development of any new potentially hazardous system, process, or facility. It is a required part of nuclear safety activities as specified in the U.S. Department of Energy (DOE) Order 420.B, Facility Safety. This order addresses the design of nuclear related facilities developed under federal regulation IOCFR830, Nuclear Safety Management. IOCFR830 requires that safety basis documentation be provided to identify how nuclear safety is being adequately addressed as a condition for system operation (e.g., the safety basis). To support the development of the safety basis, a safety analysis is performed. Although the concept of developing a design that addresses 'Safety is simple, the execution can be complex and challenging. This paper addresses those complexities and challenges for the design activity of a system to treat sludge, a corrosion product of spent nuclear fuel, at DOE's Hanford Site in Washington State. The system being developed is referred to as the Sludge Treatment Project (STP). This paper describes the portion of the safety analysis that addresses the selection of design basis events using the experience gained from the STP and the development of design requirements for safety features associated with those events. Specifically, the paper describes the safety design process and the application of the process for two types of potential design basis accidents associated with the operation of the system, (1) flashing spray leaks and (2) splash and splatter leaks. Also presented are the technical challenges that are being addressed to develop effective safety features to deal with these design basis accidents.

  4. SAFETY BASIS DESIGN DEVELOPMENT CHALLENGES IMECE2007-42747

    International Nuclear Information System (INIS)

    RYAN GW

    2007-01-01

    'Designing in Safety' is a desired part of the development of any new potentially hazardous system, process, or facility. It is a required part of nuclear safety activities as specified in the U.S. Department of Energy (DOE) Order 420.B, Facility Safety. This order addresses the design of nuclear related facilities developed under federal regulation IOCFR830, Nuclear Safety Management. IOCFR830 requires that safety basis documentation be provided to identify how nuclear safety is being adequately addressed as a condition for system operation (e.g., the safety basis). To support the development of the safety basis, a safety analysis is performed. Although the concept of developing a design that addresses 'Safety is simple, the execution can be complex and challenging. This paper addresses those complexities and challenges for the design activity of a system to treat sludge, a corrosion product of spent nuclear fuel, at DOE's Hanford Site in Washington State. The system being developed is referred to as the Sludge Treatment Project (STP). This paper describes the portion of the safety analysis that addresses the selection of design basis events using the experience gained from the STP and the development of design requirements for safety features associated with those events. Specifically, the paper describes the safety design process and the application of the process for two types of potential design basis accidents associated with the operation of the system, (1) flashing spray leaks and (2) splash and splatter leaks. Also presented are the technical challenges that are being addressed to develop effective safety features to deal with these design basis accidents

  5. Probabilistic site dependent design spectra for a NPP

    International Nuclear Information System (INIS)

    Chavez, M.; Arroyo, M.; Romo, M.P.

    1985-01-01

    A methodology is proposed to compute the design spectra for a NPP site. Near field earthquakes are included by using an appropriately scaled sample of response spectra. Site effects are considered through a probabilistic site response analysis in the frequency domain which considers nonlinear behaviour of soils. The uncertainties of the soil shear modulus, G, are introduced by using Rosenblueth's point estimates. Strong motion duration is treated by using sensitivity analysis. The procedure is applied to a NPP site and the results are: a) the USNCR R.G.1.60 underestimate the spectral amplitudes for frequencies of interest; b) the omission of the uncertainties on the G leads to under or over-estimate the spectral amplitudes at certain frequency bands; c) the effect of considering the actual strong motion duration instead of an average value is to reduce the peak spectral amplitudes by a ten per cent. (orig.)

  6. Early Site Permit Demonstration Program: Guidelines for determining design basis ground motions. Volume 2, Appendices

    Energy Technology Data Exchange (ETDEWEB)

    1993-03-18

    This report develops and applies a methodology for estimating strong earthquake ground motion. The motivation was to develop a much needed tool for use in developing the seismic requirements for structural designs. An earthquake`s ground motion is a function of the earthquake`s magnitude, and the physical properties of the earth through which the seismic waves travel from the earthquake fault to the site of interest. The emphasis of this study is on ground motion estimation in Eastern North America (east of the Rocky Mountains), with particular emphasis on the Eastern United States and southeastern Canada. Eastern North America is a stable continental region, having sparse earthquake activity with rare occurrences of large earthquakes. While large earthquakes are of interest for assessing seismic hazard, little data exists from the region to empirically quantify their effects. The focus of the report is on the attributes of ground motion in Eastern North America that are of interest for the design of facilities such as nuclear power plants. This document, Volume II, contains Appendices 2, 3, 5, 6, and 7 covering the following topics: Eastern North American Empirical Ground Motion Data; Examination of Variance of Seismographic Network Data; Soil Amplification and Vertical-to-Horizontal Ratios from Analysis of Strong Motion Data From Active Tectonic Regions; Revision and Calibration of Ou and Herrmann Method; Generalized Ray Procedure for Modeling Ground Motion Attenuation; Crustal Models for Velocity Regionalization; Depth Distribution Models; Development of Generic Site Effects Model; Validation and Comparison of One-Dimensional Site Response Methodologies; Plots of Amplification Factors; Assessment of Coupling Between Vertical & Horizontal Motions in Nonlinear Site Response Analysis; and Modeling of Dynamic Soil Properties.

  7. Veteran Teacher Engagement in Site-Based Professional Development: A Mixed Methods Study

    Science.gov (United States)

    Houston, Biaze L.

    2016-01-01

    This research study examined how teachers self-report their levels of engagement, which factors they believe contribute most to their engagement, and which assumptions of andragogy most heavily influence teacher engagement in site-based professional development. This study employed a convergent parallel mixed methods design to study veteran…

  8. Early Site Permit Demonstration Program: Guidelines for determining design basis ground motions

    International Nuclear Information System (INIS)

    1993-01-01

    This report develops and applies a methodology for estimating strong earthquake ground motion. The motivation was to develop a much needed tool for use in developing the seismic requirements for structural designs. An earthquake's ground motion is a function of the earthquake's magnitude, and the physical properties of the earth through which the seismic waves travel from the earthquake fault to the site of interest. The emphasis of this study is on ground motion estimation in Eastern North America (east of the Rocky Mountains), with particular emphasis on the Eastern United States and southeastern Canada. Eastern North America is a stable continental region, having sparse earthquake activity with rare occurrences of large earthquakes. While large earthquakes are of interest for assessing seismic hazard, little data exists from the region to empirically quantify their effects. Therefore, empirically based approaches that are used for other regions, such as Western North America, are not appropriate for Eastern North America. Moreover, recent advances in science and technology have now made it possible to combine theoretical and empirical methods to develop new procedures and models for estimating ground motion. The focus of the report is on the attributes of ground motion in Eastern North America that are of interest for the design of facilities such as nuclear power plants. Specifically considered are magnitudes M from 5 to 8, distances from 0 to 500 km, and frequencies from 1 to 35 Hz. This document, Volume IV, provides Appendix 8.B, Laboratory Investigations of Dynamic Properties of Reference Sites

  9. Development of uniform hazard response spectra for Tarapur, Trombay and Kakrapar sites

    International Nuclear Information System (INIS)

    Ghosh, A.K.; Rao, K.S.; Kushwaha, H.S.

    2003-08-01

    Traditionally, the seismic design basis ground motion has been specified by normalised response spectral shapes and peak ground acceleration (PGA). The mean recurrence interval (MRI) used to be computed for PGA only. The present work develops uniform hazard response spectra i.e. spectra having the same MRI at all frequencies for Tarapur, Trombay and Kakrapar sites. These results determine the seismic hazard at the given site and the associated uncertainties. Typical examples are given to show the sensitivity of the results to changes in various parameters. (author)

  10. New "persona" concept helps site designers cater to target user segments' needs.

    Science.gov (United States)

    2004-09-01

    Using the relatively new "persona" design concept, Web strategists create a set of archetypical user characters, each one representing one of their site's primary audiences. Then, as their site is constructed or upgraded, they champion the personas, arguing on their behalf and forcing the design team to take each audience's needs and wants into account.

  11. Hard rock excavation at the CSM/OCRD test site using Swedish blast design techniques

    International Nuclear Information System (INIS)

    Holmberg, R.

    1983-09-01

    This report is the third in a series describing research conducted by the Colorado School of Mines for the Office of Crystalline Repository Development (OCRD) to determine the extent of blast damage in rock surrounding an underground opening. A special room, called the CSM/OCRD room, was excavated at the CSM experimental mine for the purpose of assessing blast damage in the rock around the room. Even though this mine is not proposed as a nuclear waste repository site, the instrumentation and methods of blast damage assessment developed in this project are applicable to proposed repository sites. This report describes the application of Swedish blasting technology for the excavation of the test room. The design of the blasting patterns including the selection of explosives, hole sizes and location, explosive loading densities, and delay intervals is based upon the theories of Langefors and Kihlstrom in combination with methods used at the Swedish Detonic Research Foundation for minimizing unwanted rock damage. The practical application of the design procedures to seven rounds and the achieved results is discussed

  12. Conceptual design of a cover system for the degmay uranium tailings site

    Energy Technology Data Exchange (ETDEWEB)

    Vatsidin, Saidov; David, S. Kessel; Kim, Chang Lak [KEPCO International Nuclear Graduate School, Ulsan (Korea, Republic of)

    2016-06-15

    The Republic of Tajikistan has ten former uranium mining sites. The total volume of all tailings is approximately 55 million tonnes, and the covered area is more than 200 hectares. The safe management of legacy uranium mining and tailing sites has become an issue of concern. Depending on the performance requirements and site-specific conditions (location in an arid, semiarid or humid region), a cover system for uranium tailings sites could be constructed using several material layers using both natural and man-made materials. The purpose of this study is to find a feasible cost-effective cover system design for the Degmay uranium tailings site which could provide a long period (100 years) of protection. The HELP computer code was used in the evaluation of potential Degmay cover system designs. As a result of this study, a cover system with 70 cm thick percolation layer, 30 cm thick drainage layer, geomembrane liner and 60 cm thick barrier soil layer is recommended because it minimizes cover thickness and would be the most cost-effective design.

  13. NGA-West 2 GMPE average site coefficients for use in earthquake-resistant design

    Science.gov (United States)

    Borcherdt, Roger D.

    2015-01-01

    Site coefficients corresponding to those in tables 11.4–1 and 11.4–2 of Minimum Design Loads for Buildings and Other Structures published by the American Society of Civil Engineers (Standard ASCE/SEI 7-10) are derived from four of the Next Generation Attenuation West2 (NGA-W2) Ground-Motion Prediction Equations (GMPEs). The resulting coefficients are compared with those derived by other researchers and those derived from the NGA-West1 database. The derivation of the NGA-W2 average site coefficients provides a simple procedure to update site coefficients with each update in the Maximum Considered Earthquake Response MCER maps. The simple procedure yields average site coefficients consistent with those derived for site-specific design purposes. The NGA-W2 GMPEs provide simple scale factors to reduce conservatism in current simplified design procedures.

  14. 2009 Melbourne metropolitan sewerage strategy: a portfolio of decentralised and on-site concept designs.

    Science.gov (United States)

    Brown, V; Jackson, D W; Khalifé, M

    2010-01-01

    The bulk and retail water companies of the greater Melbourne area are developing the 2009 Metropolitan Sewerage Strategy to provide sustainable sewerage services to 2060. The objective of the strategy is to establish long term principles and near term actions to produce a robust sewage management system for Melbourne. Melbourne's existing sewerage system is largely centralised and discharges to two major treatment plants. Several small satellite treatment plants service local urban areas generally more distant from the centralised system. Decentralised and on-site wastewater systems are options for future sewage management and could play a role in local recycling. A portfolio of 18 on-site and decentralised concept designs was developed, applicable to the full range of urban development types in Melbourne. The concepts can be used in evaluation of metropolitan system configurations as part of future integrated water cycle planning. The options included secondary and tertiary treatment systems incorporating re-use of water for non potable uses, urine separation, black and greywater separation and composting toilets. On-site and cluster treatment systems were analysed. Each option is described by its indicative capital and operating costs, energy use and water and nutrient balances. This paper summarises and compares the portfolio mix of decentralized and on-site options in Melbourne's context.

  15. Hanford Site Long-term Surface Barrier Development Program: Fiscal year 1994 highlights

    International Nuclear Information System (INIS)

    Petersen, K.L.; Link, S.O.; Gee, G.W.

    1995-08-01

    The Hanford Site Surface Barrier Development Program was organized in 1985 to test the effectiveness of various barrier designs in minimizing the effects of water infiltration; plant, animal and human intrusion; and wind and water erosion on buried wastes, plus preventing or minimizing the emanation of noxious gases. A team of scientists from the Pacific Northwest Laboratory (PNL) and engineers from Westinghouse Hanford Company (WHC) direct the barrier development effort. ICF Kaiser Hanford Company, in conjunction with WHC and PNL, developed design drawings and construction specifications for a 5-acre prototype barrier. The highlight of efforts in FY 1994 was the construction of the prototype barrier. The prototype barrier was constructed on the Hanford Site at the 200 BP-1 Operable Unit of the 200 East Area. Construction was completed in August 1994 and monitoring instruments are being installed so experiments on the prototype barrier can begin in FY 1995. The purpose of the prototype barrier is to provide insights and experience with issues regarding barrier design, construction, and performance that have not been possible with individual tests and experiments conducted to date. Additional knowledge and experience was gained in FY 1994 on erosion control, physical stability, water infiltration control, model testing, Resource Conservation and Recovery Act (RCRA) comparisons, biointrusion control, long-term performance, and technology transfer

  16. Architecture and Development of DCMP Web Site

    Science.gov (United States)

    Bariakhtar, Irina

    2003-03-01

    The multi-tier implementation of DCMP Web site is discussed. It is based upon newly developed PHP technology. The technology allows for creating dynamic content and scalable solutions for Web site capabilities. There are several aspects as to what type of information is to be on the site. First, it should serve the immediate needs of the researchers in the field, namely, conferences, journals, news, funds, etc. This is currently available on the site, but can be extended and improved if needed. Second, the site will reflect the connection between Condensed matter physics and the technological breakthroughs that drive the economy. Third, the site will carry an educational mission helping educate the general public, and on the other hand, help young people to start their careers in the field. The content of the DCMP Web site is under active development. It depends upon wide involvement of DCMP members.

  17. Developing a Conceptual Design Engineering Toolbox and its Tools

    Directory of Open Access Journals (Sweden)

    R. W. Vroom

    2004-01-01

    Full Text Available In order to develop a successful product, a design engineer needs to pay attention to all relevant aspects of that product. Many tools are available, software, books, websites, and commercial services. To unlock these potentially useful sources of knowledge, we are developing C-DET, a toolbox for conceptual design engineering. The idea of C-DET is that designers are supported by a system that provides them with a knowledge portal on one hand, and a system to store their current work on the other. The knowledge portal is to help the designer to find the most appropriate sites, experts, tools etc. at a short notice. Such a toolbox offers opportunities to incorporate extra functionalities to support the design engineering work. One of these functionalities could be to help the designer to reach a balanced comprehension in his work. Furthermore C-DET enables researchers in the area of design engineering and design engineers themselves to find each other or their work earlier and more easily. Newly developed design tools that can be used by design engineers but have not yet been developed up to a commercial level could be linked to by C-DET. In this way these tools can be evaluated in an early stage by design engineers who would like to use them. This paper describes the first prototypes of C-DET, an example of the development of a design tool that enables designers to forecast the use process and an example of the future functionalities of C-DET such as balanced comprehension.

  18. Development of conceptual nuclear design of 10MWt research reactor core

    International Nuclear Information System (INIS)

    Kim, M. H.; Lim, J. Y.; Win, Naing; Park, J. M.

    2008-03-01

    KAERI has been devoted to develop export-oriented research reactors for a growing world-wide demand of new research reactor construction. Their ambition is that design of Korean research reactor must be competitive in commercial and technological based on the experience of the HANARO core design concept with thermal power of 30MW. They are developing a new research reactor named Advanced HANARO research Reactor (AHR) with thermal power of 20 MW. KAERI has export records of nuclear technology. In 1954-1967 two series of pool type research reactors based on the Russian design, VVR type and IRT type, have been constructed and commissioned in some countries as well as Russia. Nowadays Russian design is introducing again for export to developing countries such as Union of Myanmar. Therefore the objective of this research is that to build and innovative 10 MW research reactor core design based on the concept of HANARO core design to be competitive with Russian research reactor core design. system tool of HELIOS was used at the first stage in both cases which are research reactor using tubular type fuel assemblies and that reactor using pin type fuel assemblies. The reference core design of first kind of research reactor includes one in-core irradiation site at the core center. The neutron flux evaluations for core as well as reflector region were done through logical consistency of neutron flux distributions for individual assemblies. In order to find the optimum design, the parametric studies were carried out for assembly pitch, active fuel length, number of fuel ring in each assembly and so on. Design result shows the feasibility to have high neutron flux at in-core irradiation site. The second kind of research reactor is used the same kind of assemblies as HANARO and hence there is no optimization about basic design parameters. That core has only difference composition of assemblies and smaller specific power than HANARO. Since it is a reference core at first stage

  19. Design of Buoys for Mounting Wind Turbines at Exposed Sites

    Science.gov (United States)

    Erdoğan, Beytullah; Çelıkkol, Barbaros; Swift, Robinson

    2018-04-01

    In this study, two designs for a buoy capable of supporting a 10 kW wind turbine and its tower were developed to operate at the University of New Hampshire's Center of Ocean Renewable Energy testing site located off the Isles of Shoals, New Hampshire. The buoys are to be moored by a catenary chain system. To evaluate wave response, two Froude-scaled models were constructed, tested, and compared at the Ocean Engineering wave tank at the University of New Hampshire. These buoys have been implemented and compared with wave tank measurements of the spar displacement at a reference elevation 2.44 m above the mean water level.

  20. Houdini: Site and locomotion analysis-driven design of an in-tank mobile cleanup robot

    International Nuclear Information System (INIS)

    Schempf, H.

    1995-10-01

    This paper describes design and locomotion analysis efforts to develop a new reconfigurable and collapsible working machine, dubbed Houdini, to remotely clean up hazardous-waste and petroleum storage tanks. The tethered robot system is designed to allow remote entry through man-way openings as small as 0.61 m in diameter, after which it expands its locomotors and opens up its collapsible backhoe/manipulator and plow to subsequently perform waste or material handling operations. The design is optimized to meet stringent site and safety requirements, and represents a viable alternative to (1) the long-reach manipulation systems proposed for hazardous storage tank cleanup, and (2) confined-entry manual cleanup approaches. The system development has been funded to provide waste mobilization and removal solutions for the hazardous waste storage tanks in the Department of Energy (DoE) Fernald and Oak Ridge complexes. Other potential applications areas are the cleanup of heavy-crude petroleum storage tanks. The author has developed a fully operational prototype which is currently undergoing testing

  1. Development of spectral shapes and attenuation relations from accelerograms recorded on rock and soil sites

    International Nuclear Information System (INIS)

    Ghosh, A.K.; Rao, K.S.; Kushwaha, H.S.

    1998-06-01

    Earthquake accelerograms recorded on rock and soil sites have been analysed. Site-specific response spectra and peak ground acceleration attenuation relations have been developed. This report presents the normalised pseudo-absolute acceleration spectra for various values of damping and for various confidence levels. Scaling laws have been developed for the response spectra. The present results are based on a large database and comparison has been made with earlier results. These results will be useful in the earthquake resistant design of structures. (author)

  2. Site characterization plan: Conceptual design report, Volume 1: Chapters 1-3

    International Nuclear Information System (INIS)

    MacDougall, H.R.; Scully, L.W.; Tillerson, J.R.

    1987-09-01

    The site for the prospective repository is located at Yucca Mountain in southwestern Nevada, and the waste emplacement area will be constructed in the underlying volcanic tuffs. The target horizon for waste emplacement is a sloping bed of densely welded tuff more than 650 ft below the surface and typically more than 600 ft above the water table. The conceptual design described in this report is unique among repository designs in that it uses ramps in addition to shafts to gain access to the underground facility, the emplacement horizon is located above the water table, and it is possible that 300- to 400-ft-long horizontal waste emplacement boreholes will be used. This report summarizes the design bases (site and properties of the waste package), design and performance criteria, and the design analyses performed. The current status of meeting the preclosure performance objectives for licensing and of resolving the repository design and preclosure issues is presented. The repository design presented in this report will be expanded and refined during the advanced conceptual design, the license application design, and the final procurement and construction design phases

  3. Remedial action plan and site design for stabilization of the inactive uranium mill tailings site at Tuba City, Arizona

    International Nuclear Information System (INIS)

    1989-08-01

    This Remedial Action Plan (RAP) has been developed to serve a threefold purpose. It presents the series of activities which are proposed by the US Department of Energy (DOE) to accomplish long-term stabilization and control of radioactive materials at the inactive uranium processing site near Tuba City, Arizona. It provides a characterization of the present conditions of the site. It also serves to document the concurrence of the Navajo Nation, the Hopi Tribe, US Bureau of Indian Affairs (BIA), and the US Nuclear Regulatory Commission (NRC) in the remedial action. This agreement, upon execution by DOE, the Navajo Nation, and the Hopi Tribe, and concurrence by NRC, becomes Appendix B of the Cooperative Agreement. Following the introduction, contents are as follows: Section 2.0 presents the EPA standards, including a discussion of their objectives. Section 3.0 summarizes the present site characteristics and provides a definition of site-specific problems. Section 4.0 is the site design for the proposed action. Section 5.0 summarizes the plan for ensuring environmental, health, and safety protection for the surrounding community and the on-site workers. Section 6.0 presents a detailed listing of the responsibilities of the project participants. Section 7.0 describes the features of the long-term surveillance and maintenance plan. Section 8.0 presents the quality assurance aspects of the project. Section 9.0 documents the ongoing activities to keep the public informed and participating in the project

  4. 7 CFR 1948.83 - Performance of site development work.

    Science.gov (United States)

    2010-01-01

    ... 7 Agriculture 13 2010-01-01 2009-01-01 true Performance of site development work. 1948.83 Section 1948.83 Agriculture Regulations of the Department of Agriculture (Continued) RURAL HOUSING SERVICE... Development Assistance Program § 1948.83 Performance of site development work. Site development work will be...

  5. Functional mimicry of a discontinuous antigenic site by a designed synthetic peptide

    NARCIS (Netherlands)

    Villen, J.; Borras, E.; Schaaper, W.M.M.; Meloen, R.H.; Davila, M.; Domingo, E.; Giralt, E.; Andreu, D.

    2002-01-01

    Functional reproduction of the discontinuous antigenic site D of foot-and-mouth disease virus (FMDV) has been achieved by means of synthetic peptide constructions that integrate each of the three protein loops that define the antigenic site into a single molecule. The site D mimics were designed on

  6. Arid-site SLB technology development at the Los Alamos National Laboratory

    International Nuclear Information System (INIS)

    DePoorter, G.L.

    1981-01-01

    The program goal for shallow land burial (SLB) Technology Development at the Los Alamos National Laboratory is to field test new disposal concepts and strategies for all aspects of arid SLB on an accelerated basis and on a reasonable scale. The major accomplishments during FY-1981 were the development of the Los Alamos Experimental Engineered Test Facility, the emplacement of the biointrusion barrier testing experiments, the design and emplacement of the moisture cycling experiments, the design and construction of the experiment clusters, and the planning for the experiments to be emplaced in these units. This paper will describe the site development work, the design and construction of the experiment clusters, and the experiments planned for these units. The experimental Engineered Test Facility was brought from idea to reality and two experiments were emplaced (biointrusion barrier and moisture cycling). The experiment clusters were designed and constructed, and are now available for experimentation. These units are reusable. After an experiment is complete it can be removed and another experiment put in its place. Several of the experiments were planned and designed while some of the other experiments are still in the planning stage. Based on the work done in FY-1981, significant progress toward Milestones, C, D, and E should be made in FY-1982

  7. Long-term climate change assessment study plan for the Hanford Site permanent isolation Barrier Development Program

    International Nuclear Information System (INIS)

    Petersen, K.L.; Chatters, J.C.; Waugh, W.J.

    1992-07-01

    The Hanford Site Permanent Isolation Barrier Development Program (Barrier Development Program) was organized to develop the technology needed to provide an in-place disposal capability for the Hanford Site (Adams and Wing 1986; Wig and Gee 1990). The goal of the Barrier Development Program is to provide defensible evidence that final barrier design(s) will adequately control water infiltration; plant and animal intrusion; and wind and water erosion for a minimum of 1,000 yr and isolate wastes from the accessible environment and warm inadvertent human intruders using markers. This document describes the long-term climate change studies planned to support the Barrier Development Program. The plan outlines a multi-year and multi-discipline approach to assess long-term climate change issues and to help optimize the design of the permanent isolation barriers. A multi-disciplinary approach to climatic data acquisition will be responsible for obtaining needed information for concurrent barrier tasks and for developing a local climate forecast model. This model will couple past climate patterns with models of regional and global climate drivers to provide bounding conditions for barrier performance assessment analyses

  8. 1994 Site Development Plan: A plan with vision

    Energy Technology Data Exchange (ETDEWEB)

    1994-07-01

    The 1994 Lawrence Livermore National Laboratory Site Development Plan has been developed during a period of great change and uncertainty. Our goal is to make possible the best use of the Laboratory`s resources to meet shifting national priorities in the post-Cold War world. Site Planning is an important component of the overall Laboratory strategic planning process. This plan focuses on opportunities for the Laboratory as well as on key site development issues including facility construction, redevelopment and reuse, site accessibility, and security. A major challenge is to achieve sufficient stability in the site planning and execution so that the processes of construction can occur efficiently while at the same time providing sufficient flexibility in site facilities so that a range of changing national needs can be accommodated. We are closely coupled to the DOE strategic planning process to meet this challenge.

  9. Development of the radiological protection focus in the site, design and construction of the nuclear power plant in Cuba

    International Nuclear Information System (INIS)

    Rodriguez R, J.M.

    1996-01-01

    The first nuclear station in Cuba NPP Juragua, at present in analysis for starting again the construction, under a multinational economic association, had had as main architect/engineer organization the Design Institute for Nuclear Power Stations of St. Petersburg (former LIAEP). Active participation of Cuban radiation protection specialist of Energoproyecto in the Juragua Project began at the beginning of the site selection works and continued in the design and construction stages up till now, and simultaneously our specialists have been acting as a counterpart of soviet designers, responsible for the general design of the station. Furthermore, some additional works in compliance with the latest safety requirements and the best international practices, which are described, as well as ongoing and planned work were performed. (author). 11 refs., 3 figs

  10. French steam generator design developments

    International Nuclear Information System (INIS)

    Ginier, R.; Campan, J.L.; Pontier, M.; Leridon, A.; Remond, A.; Castello, G.; Holcblat, A.; Paurobally, H.

    1986-01-01

    From the outset of the French nuclear power program, a significant R and D effort has been invested in improvement of the design and operation of Pressurized Water Reactors including a special committment to improving steam generators. The steam generator enhancement program has spawned a wide variety of specific R and D resources, e.g., low temperature hydraulic models for investigation of areas with single-phase flow, and freon-filled models for simulation of areas of steam generators experiencing two-phase flow (tube bundles and moisture separators). For the moisture separators, a large scale research program using freon-filled models and highly sophisticated instrumentation was used. Tests at reactor sites during startup of both 900 MWe and 1300 MWe have been used to validate the assumptions made on the basis of loop tests. These tests also demonstrated the validity of using freon to simulate two-phase flow conditions. The wealth of knowledge accumulated by the steam generator R and D program has been used to develop a new design of steam generators for the N4 plants. The current R and D effort is aimed at qualifying the N4 steam generator model and developing more comprehensive models. One prong of the R and D effort is the Megeve program. Megeve is a 25 MW steam generator which simulates operating conditions of the N4 model. The other prong is Clotaire, a freon-filled steam generator model which will be used to qualify thermal/hydraulic design codes used for multidimensional calculations for design of tube bundles

  11. Advances and Challenges in the Implementation of DiD in Siting, Design, and Construction of Nuclear Installations in Vietnam

    Energy Technology Data Exchange (ETDEWEB)

    Nguyen, H.A., E-mail: nhanh@varans.vn [Vietnam Agency for Radiation and Nuclear Safety, Hanoi (Viet Nam)

    2014-10-15

    Vietnam is embarking on a development of a nuclear power program. The main focus is now on the initial 1000 MWe x 2 units of the nuclear power plant in Ninh Thuan province. Now, the nuclear projects of Vietnam are in the phase of siting approval and investment projects approval. The design assessment will be performed in 2013-2014; the construction and installation will be performed from now until the operating licensing is obtained in 2020-2021. With state of development of a nuclear power program in Vietnam, this paper only focuses on advances and challenges in the implementation of Defence in Depth (DID) in siting, design, and construction of nuclear installations in Vietnam. (author)

  12. National Ignition Facility subsystem design requirements NIF site improvements SSDR 1.2.1

    International Nuclear Information System (INIS)

    Kempel, P.; Hands, J.

    1996-01-01

    This Subsystem Design Requirements (SSDR) document establishes the performance, design, and verification requirements associated with the NIF Project Site at Lawrence Livermore National Laboratory (LLNL) at Livermore, California. It identifies generic design conditions for all NIF Project facilities, including siting requirements associated with natural phenomena, and contains specific requirements for furnishing site-related infrastructure utilities and services to the NIF Project conventional facilities and experimental hardware systems. Three candidate sites were identified as potential locations for the NIF Project. However, LLNL has been identified by DOE as the preferred site because of closely related laser experimentation underway at LLNL, the ability to use existing interrelated infrastructure, and other reasons. Selection of a site other than LLNL will entail the acquisition of site improvements and infrastructure additional to those described in this document. This SSDR addresses only the improvements associated with the NIF Project site located at LLNL, including new work and relocation or demolition of existing facilities that interfere with the construction of new facilities. If the Record of Decision for the PEIS on Stockpile Stewardship and Management were to select another site, this SSDR would be revised to reflect the characteristics of the selected site. Other facilities and infrastructure needed to support operation of the NIF, such as those listed below, are existing and available at the LLNL site, and are not included in this SSDR. Office Building. Target Receiving and Inspection. General Assembly Building. Electro- Mechanical Shop. Warehousing and General Storage. Shipping and Receiving. General Stores. Medical Facilities. Cafeteria services. Service Station and Garage. Fire Station. Security and Badging Services

  13. Technical guidance for siting criteria development

    International Nuclear Information System (INIS)

    Aldrich, D.C.; Sprung, J.L.; Alpert, D.J.

    1982-12-01

    Technical guidance to support the formulation and comparison of possible siting criteria for nuclear power plants has been developed in four areas: (1) consequences of hypothetical severe nuclear-power-plant accidents, (2) characteristics of population distributions about current reactor sites, (3) site availability within the continental United States, and (4) socioeconomic impacts of reactor siting. The impact on consequences of source-term magnitude, meteorology, population distribution, and emergency response have been analyzed. Population distributions about current sites were analyzed to identify statistical characteristics, time trends, and regional differences. A site-availability data bank was constructed for the continential United States. The data bank contains information about population densities, seismicity, topography, water availability, and land-use restrictions. Finally, the socioeconomic impacts of rural-industrialization projects, energy boomtowns, and nuclear power plants were examined to determine their nature, magnitude, and dependence on site demography and remoteness

  14. Technical guidance for siting criteria development

    Energy Technology Data Exchange (ETDEWEB)

    Aldrich, D.C.; Sprung, J.L.; Alpert, D.J.; Diegert, K.; Ostmeyer, R.M.; Ritchie, L.T.; Strip, D.R.; Johnson, J.D.; Hansen, K.; Robinson, J.

    1982-12-01

    Technical guidance to support the formulation and comparison of possible siting criteria for nuclear power plants has been developed in four areas: (1) consequences of hypothetical severe nuclear-power-plant accidents, (2) characteristics of population distributions about current reactor sites, (3) site availability within the continental United States, and (4) socioeconomic impacts of reactor siting. The impact on consequences of source-term magnitude, meteorology, population distribution, and emergency response have been analyzed. Population distributions about current sites were analyzed to identify statistical characteristics, time trends, and regional differences. A site-availability data bank was constructed for the continential United States. The data bank contains information about population densities, seismicity, topography, water availability, and land-use restrictions. Finally, the socioeconomic impacts of rural-industrialization projects, energy boomtowns, and nuclear power plants were examined to determine their nature, magnitude, and dependence on site demography and remoteness.

  15. Hydrogeological Site Descriptive Model - a strategy for its development during Site Investigations

    Energy Technology Data Exchange (ETDEWEB)

    Rhen, Ingvar [SWECO VIAK AB, Goeteborg (Sweden); Follin, Sven [SF GeoLogic AB, Stockholm (Sweden); Hermanson, Jan [Golder Associates, Stockholm (Sweden)

    2003-04-01

    The report is to present a strategy for the development of the Site Descriptive Hydrogeological Model within the SKB Site Investigation Programme. The report, and similar reports from the Geology, Rock Mechanics, Thermal properties, Hydrogeochemistry, Transport Properties and Surface Ecosystem disciplines are intended to guide SKB Site Descriptive Modelling but also to provide the authorities with an overview of how the modelling should be performed. Thus the objectives of this report are to: provide guidelines for the modelling of different sites resulting in consistent handling of modelling issues during the Site Investigations, provide a structure for the modelling sequence that is suitable for the establishment of a Site Descriptive model and provide some necessary details that should be considered in a Site Descriptive model.

  16. Hydrogeological Site Descriptive Model - a strategy for its development during Site Investigations

    International Nuclear Information System (INIS)

    Rhen, Ingvar; Follin, Sven; Hermanson, Jan

    2003-04-01

    The report is to present a strategy for the development of the Site Descriptive Hydrogeological Model within the SKB Site Investigation Programme. The report, and similar reports from the Geology, Rock Mechanics, Thermal properties, Hydrogeochemistry, Transport Properties and Surface Ecosystem disciplines are intended to guide SKB Site Descriptive Modelling but also to provide the authorities with an overview of how the modelling should be performed. Thus the objectives of this report are to: provide guidelines for the modelling of different sites resulting in consistent handling of modelling issues during the Site Investigations, provide a structure for the modelling sequence that is suitable for the establishment of a Site Descriptive model and provide some necessary details that should be considered in a Site Descriptive model

  17. Site characterization requirements for nuclear-cratering design

    International Nuclear Information System (INIS)

    Terhune, R.W.; Carlson, R.C.

    1977-01-01

    A material properties measurement program for the design of large engineering nuclear-excavation projects by computer calculation is presented. Material properties of the site and their relative effect on crater size are analyzed and ordered in relation to their importance in determining the overall cratering efficiency. The measurement program includes both in situ logging and laboratory measurement of core samples, together with the reason for each measurement and its use in the calculations

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

    International Nuclear Information System (INIS)

    1985-05-01

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

  19. Remedial action plan and site conceptual design for stabilization of the inactive uranium mill tailings sites at Rifle, Colorado. Appendix D, Final report

    International Nuclear Information System (INIS)

    1992-02-01

    This appendix assesses the present conditions and data gathered about the two designated inactive uranium mill tailings sites near Rifle, Colorado, and the proposed disposal site six miles north of Rifle in the area of Estes Gulch. It consolidates available engineering, radiological, geotechnical, hydrological, meteorological, and other information pertinent to the design of the Remedial Action Plan (RAP). The data characterize conditions at the mill, tailings, and disposal site so that the Remedial Action Contractor (RAC) may complete final designs for the remedial actions

  20. Remedial action plan and site conceptual design for stabilization of the inactive uranium mill tailings sites at Rifle, Colorado. Appendix D, Final report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1992-02-01

    This appendix assesses the present conditions and data gathered about the two designated inactive uranium mill tailings sites near Rifle, Colorado, and the proposed disposal site six miles north of Rifle in the area of Estes Gulch. It consolidates available engineering, radiological, geotechnical, hydrological, meteorological, and other information pertinent to the design of the Remedial Action Plan (RAP). The data characterize conditions at the mill, tailings, and disposal site so that the Remedial Action Contractor (RAC) may complete final designs for the remedial actions.

  1. Remedial action plan and site design for stabilization of the inactive uranium mill tailings sites at Slick Rock, Colorado: Remedial Action Selection Report. Preliminary final

    Energy Technology Data Exchange (ETDEWEB)

    1994-03-01

    This proposed remedial action plan incorporates the results of detailed investigation of geologic, geomorphic, and seismic conditions at the proposed disposal site. The proposed remedial action will consist of relocating the uranium mill tailings, contaminated vicinity property materials, demolition debris, and windblown/waterborne materials to a permanent repository at the proposed Burro Canyon disposal cell. The proposed disposal site will be geomorphically stable. Seismic design parameters were developed for the geotechnical analyses of the proposed cell. Cell stability was analyzed to ensure long-term performance of the disposal cell in meeting design standards, including slope stability, settlement, and liquefaction potential. The proposed cell cover and erosion protection features were also analyzed and designed to protect the RRM (residual radioactive materials) against surface water and wind erosion. The location of the proposed cell precludes the need for permanent drainage or interceptor ditches. Rock to be used on the cell top-, side-, and toeslopes was sized to withstand probable maximum precipitation events.

  2. Nonlinear Time Domain Seismic Soil-Structure Interaction (SSI) Deep Soil Site Methodology Development

    International Nuclear Information System (INIS)

    Spears, Robert Edward; Coleman, Justin Leigh

    2015-01-01

    Currently the Department of Energy (DOE) and the nuclear industry perform seismic soil-structure interaction (SSI) analysis using equivalent linear numerical analysis tools. For lower levels of ground motion, these tools should produce reasonable in-structure response values for evaluation of existing and new facilities. For larger levels of ground motion these tools likely overestimate the in-structure response (and therefore structural demand) since they do not consider geometric nonlinearities (such as gaping and sliding between the soil and structure) and are limited in the ability to model nonlinear soil behavior. The current equivalent linear SSI (SASSI) analysis approach either joins the soil and structure together in both tension and compression or releases the soil from the structure for both tension and compression. It also makes linear approximations for material nonlinearities and generalizes energy absorption with viscous damping. This produces the potential for inaccurately establishing where the structural concerns exist and/or inaccurately establishing the amplitude of the in-structure responses. Seismic hazard curves at nuclear facilities have continued to increase over the years as more information has been developed on seismic sources (i.e. faults), additional information gathered on seismic events, and additional research performed to determine local site effects. Seismic hazard curves are used to develop design basis earthquakes (DBE) that are used to evaluate nuclear facility response. As the seismic hazard curves increase, the input ground motions (DBE's) used to numerically evaluation nuclear facility response increase causing larger in-structure response. As ground motions increase so does the importance of including nonlinear effects in numerical SSI models. To include material nonlinearity in the soil and geometric nonlinearity using contact (gaping and sliding) it is necessary to develop a nonlinear time domain methodology. This

  3. Novel approaches for an enhanced geothermal development of residential sites

    Science.gov (United States)

    Schelenz, Sophie; Firmbach, Linda; Shao, Haibing; Dietrich, Peter; Vienken, Thomas

    2015-04-01

    An ongoing technological enhancement drives an increasing use of shallow geothermal systems for heating and cooling applications. However, even in areas with intensive shallow geothermal use, planning of geothermal systems is in many cases solely based on geological maps, drilling databases, and literature references. Thus, relevant heat transport parameters are rather approximated than measured for the specific site. To increase the planning safety and promote the use of renewable energies in the domestic sector, this study investigates a novel concept for an enhanced geothermal development of residential neighbourhoods. This concept is based on a site-specific characterization of subsurface conditions and the implementation of demand-oriented geothermal usage options. Therefore, an investigation approach has been tested that combines non-invasive with minimum-invasive exploration methods. While electrical resistivity tomography has been applied to characterize the geological subsurface structure, Direct Push soundings enable a detailed, vertical high-resolution characterization of the subsurface surrounding the borehole heat exchangers. The benefit of this site-specific subsurface investigation is highlighted for 1) a more precise design of shallow geothermal systems and 2) a reliable prediction of induced long-term changes in groundwater temperatures. To guarantee the financial feasibility and practicability of the novel geothermal development, three different options for its implementation in residential neighbourhoods were consequently deduced.

  4. Development of spectral shapes and attenuation relations from accelerograms recorded on rock and soil sites

    Energy Technology Data Exchange (ETDEWEB)

    Ghosh, A K; Rao, K S; Kushwaha, H S [Reactor Safety Div., Bhabha Atomic Research Centre, Mumbai (India)

    1998-06-01

    Earthquake accelerograms recorded on rock and soil sites have been analysed. Site-specific response spectra and peak ground acceleration attenuation relations have been developed. This report presents the normalised pseudo-absolute acceleration spectra for various values of damping and for various confidence levels. Scaling laws have been developed for the response spectra. The present results are based on a large database and comparison has been made with earlier results. These results will be useful in the earthquake resistant design of structures. (author) 22 refs., 7 figs., 5 tabs.

  5. Remedial design of the Fultz Landfill Site, Byesville, Ohio

    International Nuclear Information System (INIS)

    Rajaram, V.; Riesing, R.; Bloom, T.

    1994-01-01

    The Fultz Landfill Superfund (Fultz) site is a 30-acre hazardous waste landfill located near Byesville, Ohio. The site is approximately 75 miles east of Columbus and 3 miles southwest of Cambridge, the largest city in Guernsey County, Ohio. The landfill is situated on the north slope of a ridge that overlies abandoned coal mines in the Upper Freeport Coal seam. The north half of the landfill lies in an unreclaimed strip mine in the Upper Freeport Coal seam, where saturated portions of surface mine spoils and natural soils form the ''shallow aquifer''. The south half of the landfill lies 40 to 50 feet (ft.) above an abandoned, flooded deep mine in the same coal seam. The flooded deep mine forms an aquifer referred to as the ''coal mine aquifer''. This paper presents the results of design studies completed by PRC Environmental Management, Inc. (PRC), during 1993, and the remedial design (RD) of the components specified by the US Environmental Protection Agency (EPA) Record of Decision (ROD) for the Fultz site (EPA 1991). The remedy specified in the ROD includes a multilayer landfill cap that is compliant with Resource Conservation and Recovery Act (RCRA) Subtitle C guidelines, a leachate collection and groundwater extraction and treatment system, and stabilizing mine voids underlying the southern portion of the site. Vinyl chloride is the only contaminant exceeding a maximum contaminant limit (MCL) in the coal mine aquifer

  6. Site characterization plan: Yucca Mountain site, Nevada research and development area, Nevada: Consultation draft, Nuclear Waste Policy Act: Volume 4

    International Nuclear Information System (INIS)

    1988-01-01

    The Yucca Mountain site in Nevada is one of three candidate sites for the first geologic repository for radioactive waste. On May 28, 1986, it was recommended and approved by the President for detailed study in a program of site characterization. This site characterization plan (SCP) has been prepared in accordance with the requirements of the Nuclear Waste Policy Act to summarize the information collected to date about the geologic conditions at the site; to describe the conceptual designs for the repository and the waste package; and to present the plans for obtaining the geologic information necessary to demonstate the suitability of the site for a repository, to desin the repository and the waste package, to prepare an environmental impact statement, and to obtain from the US Nuclear Regulatory Commission (NRC) an authorization to construct the repository. This introduction begins with a brief section on the process for siting and developing a repository, followed by a discussion of the pertinent legislation and regulations. A description of site characterization is presented next; it describes the facilities to be constructed for the site characterization program and explains the principal activities to be conducted during the program. Finally, the purpose, content, organizing principles, and organization of this site characterization plan are outlined, and compliance with applicable regulations is discussed

  7. Site characterization plan: Yucca Mountain site, Nevada research and development area, Nevada: Consultation draft, Nuclear Waste Policy Act: Volume 4

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1988-01-01

    The Yucca Mountain site in Nevada is one of three candidate sites for the first geologic repository for radioactive waste. On May 28, 1986, it was recommended and approved by the President for detailed study in a program of site characterization. This site characterization plan (SCP) has been prepared in accordance with the requirements of the Nuclear Waste Policy Act to summarize the information collected to date about the geologic conditions at the site; to describe the conceptual designs for the repository and the waste package; and to present the plans for obtaining the geologic information necessary to demonstate the suitability of the site for a repository, to desin the repository and the waste package, to prepare an environmental impact statement, and to obtain from the US Nuclear Regulatory Commission (NRC) an authorization to construct the repository. This introduction begins with a brief section on the process for siting and developing a repository, followed by a discussion of the pertinent legislation and regulations. A description of site characterization is presented next; it describes the facilities to be constructed for the site characterization program and explains the principal activities to be conducted during the program. Finally, the purpose, content, organizing principles, and organization of this site characterization plan are outlined, and compliance with applicable regulations is discussed.

  8. Thematic report on community development and siting

    International Nuclear Information System (INIS)

    Vari, A.

    2002-01-01

    The paper analyses the Finnish spent fuel disposal facility siting from the perspective of community development, issues of fairness, and general factors of success. We found that anticipated positive impacts on host community development were the most important factors of local support. Second, the willingness of main stakeholders to adopt and combine several competing and changing concepts of fairness helped making legitimate decisions. Finally, we can conclude that in addition to important cultural factors which are unique in Finland, a number of siting elements have contributed to the success that are of cross-cultural nature. The paper summarises the lessons learned about the Finnish spent fuel disposal facility siting process regarding the issues of community development, fairness, and the transferability of siting approaches across cultures. It is largely based on information presented within the framework of the OECD Forum of Stakeholder Confidence Workshop held in Turku, Finland, on 15-16 November 2001. (author)

  9. Regulatory principles, criteria and guidelines for site selection, design, construction and operation of uranium tailings retention systems

    International Nuclear Information System (INIS)

    Coady, J.R.; Henry, L.C.

    1978-01-01

    Principles, criteria and guidelines developed by the Atomic Energy Control Board for the management of uranium mill tailings are discussed. The application of these concepts is considered in relation to site selection, design and construction, operation and decommissioning of tailings retention facilities

  10. Energy-conserving site-design case study, Radisson, New York. Final report

    Energy Technology Data Exchange (ETDEWEB)

    1979-12-01

    Radisson is a 2,950-acre new community currently being developed by the New York State Urban Development Corporation and located in central New York, 12 miles north-west of Syracuse. Case-study sites selected for this project are a 95-acre residential site and the 51-acre Town Center of the new community. Development on the Residential Site is a low-density (2.8 dwelling units/acre) mixture of single-family, townhouse and multi-family units. Development on the Town Center site is a mixture of small-scale commercial use (144,000 sq. ft.) and 330+ multi-family dwelling units. Energy-conserving plans developed for both sites have focused on passive measures to reduce energy use for space heating. Utility-system options have been identified for both sites, but require further study as to feasibility and cost. This report summarizes energy savings and cost differentials due to passive measures incorporated in both the residential and Town Center Plans. The future implementation schedule, also discussed, summarizes the procedures an schedule required for implementation of the passive measures, as well as further study required for the development of utility-system options. 4 tables.

  11. Solid waste management complex site development plan

    International Nuclear Information System (INIS)

    Greager, T.M.

    1994-01-01

    The main purpose of this Solid Waste Management Complex Site Development Plan is to optimize the location of future solid waste treatment and storage facilities and the infrastructure required to support them. An overall site plan is recommended. Further, a series of layouts are included that depict site conditions as facilities are constructed at the SWMC site. In this respect the report serves not only as the siting basis for future projects, but provides siting guidance for Project W-112, as well. The plan is intended to function as a template for expected growth of the site over the next 30 years so that future facilities and infrastructure will be properly integrated

  12. Solid waste management complex site development plan

    Energy Technology Data Exchange (ETDEWEB)

    Greager, T.M.

    1994-09-30

    The main purpose of this Solid Waste Management Complex Site Development Plan is to optimize the location of future solid waste treatment and storage facilities and the infrastructure required to support them. An overall site plan is recommended. Further, a series of layouts are included that depict site conditions as facilities are constructed at the SWMC site. In this respect the report serves not only as the siting basis for future projects, but provides siting guidance for Project W-112, as well. The plan is intended to function as a template for expected growth of the site over the next 30 years so that future facilities and infrastructure will be properly integrated.

  13. Remedial Action Plan and site design for stabilization of the inactive uranium mill tailings site at Durango, Colorado: Remedial action selection report

    International Nuclear Information System (INIS)

    1991-12-01

    The uranium mill tailings site near Durango, Colorado, was one of 24 inactive uranium mill sites designated to be remediated by the US Department of Energy (DOE) under the Uranium Mill Tailings Radiation Control Act of 1978 (UMTRCA). Part of the UMTRCA requires that the US Nuclear Regulatory Commission (NRC) concur with the DOE's Remedial Action Plan (RAP) and certify that the remedial action conducted at the site complies with the standards promulgated by the US Environmental Protection Agency (EPA). Included in the RAP is this Remedial Action Selection Report (RAS), which has been developed to serve a two-fold purpose. First, it describes the activities that have been conducted by the DOE to accomplish remediation and long-term stabilization and control of the radioactive materials at the inactive uranium mill processing site near Durango, Colorado. Secondly, this document and the rest of the RAP, upon concurrence and execution by the DOE, the State of Colorado, and the NRC, become Appendix B of the Cooperative Agreement between the DOE and the State of Colorado

  14. Remedial action plan and site design for stabilization of the inactive uranium mill tailings sites at Slick Rock, Colorado

    International Nuclear Information System (INIS)

    1993-07-01

    The Slick Rock uranium mill tailings sites are located near the small town of Slick Rock, in San Miguel County, Colorado. There are two designated UMTRA sites at Slick Rock, the Union Carbide (UC) site and the North Continent (NC) site. Both sites are adjacent to the Dolores River. The UC site is approximately 1 mile (mi) [2 kilometers (km)] downstream of the NC site. Contaminated materials cover an estimated 55 acres (ac) [22 hectares (ha)] at the UC site and 12 ac (4.9 ha) at the NC site. The sites contain former mill building concrete foundations, tailings piles, demolition debris, and areas contaminated by windblown and waterborne radioactive materials. The total estimated volume of contaminated materials is approximately 620, 000 cubic yards (yd 3 ) [470,000 cubic meters (m 3 )]. In addition to the contamination at the two processing site areas, four vicinity properties were contaminated. Contamination associated with the UC and NC sites has leached into groundwater

  15. Overview of adaptive phased management repository design development

    International Nuclear Information System (INIS)

    Russell, S.

    2011-01-01

    The Nuclear Waste Management Organization is implementing Adaptive Phased Management, Canada's plan for long-term management of used nuclear fuel. The organization is proceeding with the process for selecting a site in partnership with an informed and willing host community to safely and securely container and isolate used nuclear fuel in a deep geological repository in a suitable rock formation. Adaptive Phased Management is the culmination of more than 30 years of research, development and demonstration of repository concepts in Canada. Adaptive Phased Management uses a phased and adaptive step-wise approach to the multi-barrier system which is consistent with the long-term waste management approaches being developed in many other countries with nuclear power programs such as Sweden, Finland, Switzerland, the United Kingdom and France. The Nuclear Waste Management Organization is examining and developing conceptual designs for a deep geological repository and associated facilities for the placement of used nuclear fuel in long-lived containers. This paper will examine two of these generic conceptual designs which have recently been refined and updated. These conceptual designs will be used to support a pre-project review of repository design and safety by the Canadian Nuclear Safety Commission. (author)

  16. Remedial action plan and site design for stabilization of the inactive uranium mill tailings site at Lowman, Idaho: Attachment 2, Geology report

    International Nuclear Information System (INIS)

    1991-09-01

    Detailed investigations of geologic, geomorphic, and seismic conditions at the Lowman site in central Idaho were conducted by the Technical Assistance Contractor. The purpose of these investigations was basic site characterization and the identification of potential geologic hazards that could affect long-term site stability. Subsequent engineering studies (e.g., analyses of the hydrologic regime and liquefaction potential) use this data . The geomorphic analysis is employed in the design of effective erosion protection. Studies of the regional and local seismotectonic setting, which included a detailed search for possible capable faults within a 65-km (40-mile) radius of the site, provided the basis for estimating seismic design parameters

  17. Examination of CRISPR/Cas9 design tools and the effect of target site accessibility on Cas9 activity.

    Science.gov (United States)

    Lee, Ciaran M; Davis, Timothy H; Bao, Gang

    2018-04-01

    What is the topic of this review? In this review, we analyse the performance of recently described tools for CRISPR/Cas9 guide RNA design, in particular, design tools that predict CRISPR/Cas9 activity. What advances does it highlight? Recently, many tools designed to predict CRISPR/Cas9 activity have been reported. However, the majority of these tools lack experimental validation. Our analyses indicate that these tools have poor predictive power. Our preliminary results suggest that target site accessibility should be considered in order to develop better guide RNA design tools with improved predictive power. The recent adaptation of the clustered regulatory interspaced short palindromic repeats (CRISPR)/CRISPR-associated protein 9 (Cas9) system for targeted genome engineering has led to its widespread application in many fields worldwide. In order to gain a better understanding of the design rules of CRISPR/Cas9 systems, several groups have carried out large library-based screens leading to some insight into sequence preferences among highly active target sites. To facilitate CRISPR/Cas9 design, these studies have spawned a plethora of guide RNA (gRNA) design tools with algorithms based solely on direct or indirect sequence features. Here, we demonstrate that the predictive power of these tools is poor, suggesting that sequence features alone cannot accurately inform the cutting efficiency of a particular CRISPR/Cas9 gRNA design. Furthermore, we demonstrate that DNA target site accessibility influences the activity of CRISPR/Cas9. With further optimization, we hypothesize that it will be possible to increase the predictive power of gRNA design tools by including both sequence and target site accessibility metrics. © 2017 The Authors. Experimental Physiology © 2017 The Physiological Society.

  18. DESIGN AND DEVELOPMENT OF A REMOTE MEDICAL CONSULTATION SYSTEM

    Directory of Open Access Journals (Sweden)

    "A. Delrobaee

    2006-05-01

    Full Text Available Telemedicine is an indispensable tool in the hands of doctors to accelerate and facilitate the process of data interchange. To publicize and distribute the culture of utilizing this technology and providing the necessary equipment for this purpose and also to commence some useful activities in this field of science in Iran, the researchers group have designed and performed a telemedicine internet site with the goal of medical consultation. Software was designed and prepared, which is accessible to three groups of users with definite level of access for each one: normal users, doctors and site administrators. There are four main forums on this website with the following titles: medical consultation (Q&A, doctors’ special forum, scientific and research centers and also special disease groups, and the forum of graduates and medical students. Ultimately, we could achieve a new horizon to expand telemedicine activities in the field of medical consultation. A free web-based system was developed through the address of www.teleteb.com with the aim of remote medical consultation, developing the public health services and creating a powerful scientific and research link in the society of medicine.

  19. How to open & operate a financially successful web site design business

    CERN Document Server

    Evans, Charlotte

    2009-01-01

    The Pricing & Ethical Guidelines Handbook published by the Graphic Arts Guild reports that the average cost of designing a Web site for a small corporation can range from 7,750 to 15,000. It is incredibly easy to see the enormous profit potential. Web design businesses can be run part- or full-time and can easily be started in your own home. As such, they are one of the fastest growing segments of the Internet economy. Here is the manual you need to cash in on this highly profitable segment of the industry. This book is a comprehensive and detailed study of the business side of Web site des

  20. Design issues in adaptive web-site development

    NARCIS (Netherlands)

    De Bra, P.M.E.; Brusilovsky, P.; De Bra, P.M.E.

    1999-01-01

    For almost a decade people have been developing hypertext or hypermedia applications that adapt to some "features" of their users, like knowledge or preferences [Brusilovsky, 1996]. Recently some adaptive application environments have become available that use World Wide Web technology. Examples of

  1. Reactor safety under design basis flood condition for inland sites

    International Nuclear Information System (INIS)

    Hajela, S.; Bajaj, S.S.; Samota, A.; Verma, U.S.P.; Warudkar, A.S.

    2002-01-01

    Full text: In June 1994, there was an incident of flooding at Kakrapar Atomic Power Station (KAPS) due to combination of heavy rains and mechanical failure in the operation of gates at the adjoining weir. An indepth review of the incident was carried out and a number of flood protection measures were recommended and were implemented at site. As part of this review, a safety analysis was also done to demonstrate reactor safety with a series of failures considered in the flood protection features. For each inland NPP site, as part of design, different flood scenarios are analysed to arrive at design basis flood (DBF) level. This level is estimated based on worst combination of heavy local precipitation, flooding in river, failure of upstream/downstream water control structures

  2. Site characterization plan: Yucca Mountain Site, Nevada Research and Development Area, Nevada: Volume 4, Part B: Chapter 8, Sections 8.0 through 8.3.1.4

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1988-12-01

    This site characterization plan (SCP) has been developed for the candidate repository site at Yucca Mountain in the State of Nevada. The SCP includes a description of the Yucca Mountain site (Chapters 1-5), a conceptual design for the repository (Chapter 6), a description of the packaging to be used for the waste to be emplaced in the repository (Chapter 7), and a description of the planned site characterization activities (Chapter 8). The schedules and milestones presented in Sections 8.3 and 8.5 of the SCP were developed to be consistent with the June 1988 draft Amendment to the DOE`s Mission Plan for the Civilian Radioactive Waste Management Program. The five month delay in the scheduled start of exploratory shaft construction that was announced recently is not reflected in these schedules. 74 figs., 32 tabs.

  3. Development of a comprehensive management site evaluation methodology

    International Nuclear Information System (INIS)

    Rodgers, J.C.; Onishi, Y.

    1981-01-01

    The Nuclear Regulatory Commission is in the process of preparing regulations that will define the necessary conditions for adequate disposal of low-level waste (LLW) by confinement in an LLW disposal facility. These proposed regulations form the context in which the motivation for the joint Los Alamos National Laboratory Battelle Pacific Northwest Laboratory program to develop a site-specific, LLW site evaluation methodology is discussed. The overall effort is divided into three development areas: land-use evaluation, environmental transport modelling, and long term scenario development including long-range climatology projections. At the present time four steps are envisioned in the application of the methodology to a site: site land use suitability assessment, land use-ecosystem interaction, contaminant transport simulation, and sensitivity analysis. Each of these steps is discussed in the paper. 12 refs

  4. Engineered surface barriers for waste disposal sites: lysimeter facility design and construction

    International Nuclear Information System (INIS)

    Phillips, S.J.; Ruben, M.S.; Kirkham, R.R.

    1988-01-01

    A facility to evaluate performance of engineered surface carriers for confinement of buried wastes has been designed, constructed, and operations initiated. The Field Lysimeter Test Facility is located at the US Department of Energy's Hanford Site in Richland, Washington. The facility consists of 18 one-dimensional drainage and weighing lysimeters used to evaluate 7 replicated barrier treatments. Distinct layers of natural earth materials were used to construct layered soil and rock barriers in each lysimeter. These barrier designs are capable in principal of significantly reducing or precluding infiltration of meteoric water through barriers into underlying contaminated zones. This paper summarizes salient facility design and construction features used in testing of the Hanford Site's engineered surface barriers

  5. Developing a Hierarchical Decision Model to Evaluate Nuclear Power Plant Alternative Siting Technologies

    Science.gov (United States)

    Lingga, Marwan Mossa

    A strong trend of returning to nuclear power is evident in different places in the world. Forty-five countries are planning to add nuclear power to their grids and more than 66 nuclear power plants are under construction. Nuclear power plants that generate electricity and steam need to improve safety to become more acceptable to governments and the public. One novel practical solution to increase nuclear power plants' safety factor is to build them away from urban areas, such as offshore or underground. To date, Land-Based siting is the dominant option for siting all commercial operational nuclear power plants. However, the literature reveals several options for building nuclear power plants in safer sitings than Land-Based sitings. The alternatives are several and each has advantages and disadvantages, and it is difficult to distinguish among them and choose the best for a specific project. In this research, we recall the old idea of using the alternatives of offshore and underground sitings for new nuclear power plants and propose a tool to help in choosing the best siting technology. This research involved the development of a decision model for evaluating several potential nuclear power plant siting technologies, both those that are currently available and future ones. The decision model was developed based on the Hierarchical Decision Modeling (HDM) methodology. The model considers five major dimensions, social, technical, economic, environmental, and political (STEEP), and their related criteria and sub-criteria. The model was designed and developed by the author, and its elements' validation and evaluation were done by a large number of experts in the field of nuclear energy. The decision model was applied in evaluating five potential siting technologies and ranked the Natural Island as the best in comparison to Land-Based, Floating Plant, Artificial Island, and Semi-Embedded plant.

  6. Source removal strategy development for manufactured gas plant sites

    International Nuclear Information System (INIS)

    Golchin, J.; Nelson, S.

    1994-01-01

    A source removal action plan was developed by Midwest Gas and the Iowa Department of Natural Resources to address the source coal tar contamination within the underground gas holder basin at former Manufactured Gas Plant (MGP) sites. The procedure utilizes a mixture of coal, contaminated soil and coal rat sludge to provide a material that had suitable material handling characteristics for shipment and burning in high efficiency utility boilers. Screening of the mixture was required to remove oversized debris and ferrous metal. The resulting mixture did not exhibit toxic characteristics when tested under the Toxicity Characteristics Leaching Procedure (TCLP). Test results on the coal tar sludges have indicated that the more pure coal tar materials may fail the TCLP test and be classified as a RCRA hazardous waste. The processing procedure was designed to stabilize the coal tar sludges and render those sludges less hazardous and, as a result, able to pass the TCLP test. This procedure was adopted by the Edison Electric Institute to develop a national guidance document for remediation of MGP sites. The EPA Office of Solid Waste and Emergency Response recommended this strategy to the Regional Waste Management Directors as a practical tool for handling wastes that may exhibit the RCRA characteristics

  7. Strategy for safety case development: impact of a volunteering approach to siting a japanese HLW repository

    International Nuclear Information System (INIS)

    Kitayama, K.; Ishiguro, K.; Takeuchi, M.; Tsuchi, H.; Kato, T.; Sakabe, Y.; Wakasugi, K.

    2008-01-01

    NUMO strategy for safety case development is constrained by a staged siting approach, which has been initiated by a call for volunteer municipalities to host the HLW repository. For each site, the safety case is an important factor to be considered at the selection steps which narrow down towards the preferred repository location. This is particularly challenging, however, as every site requires a tailored repository concept, with associated performance assessment and an individual site evaluation programme all of which evolve with gradually increasing understanding of the host environment. In order to maintain flexibility without losing focus, NUMO has developed a formalized tailoring procedure, termed the NUMO Structured Approach (NSA). The NSA guides the interaction of the key site characterisation, repository design and performance assessment groups and is facilitated by tools to help the decision making associated with the tailoring process (e.g. a requirements management system) and with comparison of siting and design options (e.g. multi-attribute analysis). Pragmatically, the post-closure safety case will initially emphasize near-field processes and a robust engineering barrier system, considering the limited geological information at early stages. This will be complemented by a more realistic assessment of total system performance, as needed to compare options. In addition, efforts to rigorously assess operational phase safety and the practicality of assuring quality of the constructed engineered barriers are components of the total safety case which are receiving particular attention now, as they may better discriminate between sites while information is still limited. (authors)

  8. A peer review of the Hanford Site Permanent Isolation Surface Barrier Development Program

    International Nuclear Information System (INIS)

    Wing, N.R.

    1992-09-01

    A panel of technical experts was organized to peer review the Hanford Site Permanent Isolation Surface Barrier Development Program (BDP) and to provide a specific review of a preconceptual prototype barrier design initiated during fiscal year (FY) 1990. The technical peer review of the BDP and the prototype is being conducted in three phases, two of which have been completed. This document presents the peer review panel's findings on the first two phases of the peer review process. Biointrusion and water intrusion control are discussed, along with design life, vegetation, and climate impact

  9. Nevada test site low-level and mixed waste repository design in the unsaturated zone

    International Nuclear Information System (INIS)

    Kawamura, T.A.; Warren, D.M.

    1989-01-01

    The Area 5 Radioactive Waste Management Site (RWMS) at the Nevada Test Site (NTS) is used for shallow land disposal of Low-Level Radioactive (LLW) and for retrievable disposal of Mixed Wastes (MW) from various Department of Energy (DOE) facilities. The site is situated in southern Nevada, one of the most arid regions of the United States. Design considerations include vadose zone monitoring in lieu of groundwater monitoring, stringent waste acceptance and packaging criteria, a waste examination and real-time radiography facility, and trench design. 4 refs

  10. Development of uniform hazard response spectra from accelerograms recorded on rock sites

    International Nuclear Information System (INIS)

    Ghosh, A.K.; Kushwaha, H.S.

    2000-05-01

    Traditionally, the seismic design basis ground motion has been specified by response spectral shapes and the peak ground acceleration (PGA). The mean recurrence interval (MRI) is evaluated for PGA only. The present work has developed response spectra having the same MRI at all frequencies. This report extends the work of Cornell (on PGA) to consider an aerial source model and a general form of the spectral acceleration at various frequencies. The latter has been derived from a number of strong motion earthquake recorded on rock sites. Sensitivity of the results to the changes in various parameters has also been presented. These results will help to determine the seismic hazard at a given site and the associated uncertainties. (author)

  11. Design Optimization and Site Matching of Direct-Drive Permanent Magnet Wind Generator Systems

    DEFF Research Database (Denmark)

    Li, H.; Chen, Zhe

    2009-01-01

    This paper investigates the possible site matching of the direct-drive wind turbine concepts based on the electromagnetic design optimization of permanent magnet (PM) generator systems. Firstly, the analytical models of a three-phase radial-flux PM generator with a back-to-back power converter...... of the maximum wind energy capture, the rotor diameter and the rated wind speed of a direct-drive wind turbine with the optimum PM generator are determined. The annual energy output (AEO) is also presented using the Weibull density function. Finally, the maximum AEO per cost (AEOPC) of the optimized wind...... are presented. The optimum design models of direct-drive PM wind generation system are developed with an improved genetic algorithm, and a 500-kW direct-drive PM generator for the minimal generator active material cost is compared to demonstrate the effectiveness of the design optimization. Forty-five PM...

  12. Development of the NUMO pre-selection, site-specific safety case

    International Nuclear Information System (INIS)

    Fujiyama, Tetsuo; Suzuki, Satoru; Deguchi, Akira; Umeki, Hiroyuki

    2016-01-01

    Key conclusions: ◆ “The NUMO pre-selection, site-specific safety case” provides the basic structure for subsequent safety cases that will be applied to any selected site, emphasising practical approaches and methodology which will be applicable for the conditions/constraints during an actual siting process. ◆ The preliminary results of the design and safety assessment would underpin the feasibility and safety of geological disposal in Japan.

  13. Three types of children’s informational web sites: an inventory of design conventions

    NARCIS (Netherlands)

    Jochmann-Mannak, Hanna; Lentz, Leo; Huibers, Theo W.C.; Sanders, Ted

    2012-01-01

    "Purpose: Research on Web design conventions has an almost exclusive focus on Web design for adults. There is far less knowledge about Web design for children. For the first time, an overview is presented of the current design conventions for children's informational Web sites. Method: In this study

  14. Development of the remedial action priority system: An improved risk assessment tool for prioritizing hazardous and radioactive-mixed waste disposal sites

    International Nuclear Information System (INIS)

    Whelan, G.; Strenge, D.L.; Steelman, B.L.; Hawley, K.A.

    1985-01-01

    The Remedial Action Priority System (RAPS) represents a methodology that prioritizes inactive hazardous and radioactive mixed-waste disposal sites in a scientific and objective manner based on limited site information. This methodology is intended to bridge the technology gap that exists between the initial site evaluation using the Hazard Ranking System (HRS) and the time-consuming process of actual field site characterization, assessment and remediation efforts. The HRS was designed as an initial screening tool to discriminate between hazardous waste sites that do not and those that are likely to power significant problems to human health, safety and/or the environment. The HRS is used by the U.S. EPA to identify sites for nomination to the National Priorities List (NPL). Because the HRS is not designed to evaluate sites containing radionuclides, a modified Hazard Ranking System (mHRS) addressing both hazardous and radioactive mixed wastes was developed by Pacific Northwest Laboratory (PNL) for the U.S. Department of Energy (DOE). Neither the HRS nor the mHRS was designed to prioritize sites that are nominated to the NPL according to their potential risks. To provide DOE with a better management tool for prioritizing funding and human resource allocations for further investigations and possible remediations at its inactive waste sites, PNL is developing the risk assessment methodology called RAPS. Use of RAPS will help DOE ensure that those sites posing the highest potential risk are addressed first

  15. Geohydrologic aspects for siting and design of low-level radioactive-waste disposal

    Science.gov (United States)

    Bedinger, M.S.

    1989-01-01

    The objective for siting and design of low-level radioactive-waste repository sites is to isolate the waste from the biosphere until the waste no longer poses an unacceptable hazard as a result of radioactive decay. Low-level radioactive waste commonly is isolated at shallow depths with various engineered features to stabilize the waste and to reduce its dissolution and transport by ground water. The unsaturated zone generally is preferred for isolating the waste. Low-level radioactive waste may need to be isolated for 300 to 500 years. Maintenance and monitoring of the repository site are required by Federal regulations for only the first 100 years. Therefore, geohydrology of the repository site needs to provide natural isolation of the waste for the hazardous period following maintenance of the site. Engineering design of the repository needs to be compatible with the natural geohydrologic conditions at the site. Studies at existing commercial and Federal waste-disposal sites provide information on the problems encountered and the basis for establishing siting guidelines for improved isolation of radioactive waste, engineering design of repository structures, and surveillance needs to assess the effectiveness of the repositories and to provide early warning of problems that may require remedial action.Climate directly affects the hydrology of a site and probably is the most important single factor that affects the suitability of a site for shallow-land burial of low-level radioactive waste. Humid and subhumid regions are not well suited for shallow isolation of low-level radioactive waste in the unsaturated zone; arid regions with zero to small infiltration from precipitation, great depths to the water table, and long flow paths to natural discharge areas are naturally well suited to isolation of the waste. The unsaturated zone is preferred for isolation of low-level radioactive waste. The guiding rationale is to minimize contact of water with the waste and to

  16. Siting Practices and Site Licensing Process for New Reactors in Canada

    International Nuclear Information System (INIS)

    Vos, Marcel de

    2011-01-01

    'Siting' in Canada is composed of Site Evaluation and Site Selection. As outlined in CNSC Regulatory Document RD-346 Site Evaluation for New Nuclear Power Plants (based on IAEA NS-R-3), prior to the triggering of the Environmental Assessment (EA) and licensing processes, the proponent is expected to use a robust process to characterize proposed sites over the full life cycle of the facility, and then develop a fully documented defense of the site selection case. This case forms the backbone for submissions in support of the EA and the application for a License to Prepare Site which will be reviewed by the CNSC and other applicable federal authorities. The Environmental Assessment process and License to Prepare Site in Canada do not require a proponent to select a specific design; however, CNSC does not accept a 'black box' approach to siting. CNSC balances the level of design information required with the extent of safety assurance desired for any designs being contemplated for the proposed site. Nevertheless, the design information submitted must be sufficient to justify the site as suitable for all future licensing stages. The depth of plant design information contributes significantly to the credibility of the applicant's case for both the EA and application for License to Prepare Site. The review process utilizes an assessment plan with defined review stages and timelines. The outcome of these reviews is a series of recommendations to a federal government appointed Joint Review Panel (which also serves as a panel of the 'Commission') which, following public hearings, renders a decision regarding the EA, and subsequently, the application for a License to Prepare Site. (author)

  17. Site characterization plan: Yucca Mountain Site, Nevada Research and Development Area, Nevada: Volume 8, Part B: Chapter 8, Sections 8.3.5 through 8.3.5.20

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1988-12-01

    This site characterization plan (SCP) has been developed for the candidate repository site at Yucca Mountain in the State of Nevada. The SCP includes a description of the Yucca Mountain site (Chapters 1-5), a conceptual design for the repository (Chapter 6), a description of the packaging to be used for the waste to be emplaced in the repository (Chapter 7), and a description of the planned site characterization activities (Chapter 8). The schedules and milestones presented in Sections 8.3 and 8.5 of the SCP were developed to be consistent with the June 1988 draft Amendment to the DOE`s Mission Plan for the Civilian Radioactive Waste Management Program. The five month delay in the scheduled start of exploratory shaft construction that was announced recently is not reflected in these schedules. 68 figs., 102 tabs.

  18. Site characterization plan: Yucca Mountain Site, Nevada Research and Development Area, Nevada: Volume 8, Part B: Chapter 8, Sections 8.4 through 8.7; Glossary and Acronyms

    International Nuclear Information System (INIS)

    1988-12-01

    This site characterization plan (SCP) has been developed for the candidate repository site at Yucca Mountain in the State of Nevada. The SCP includes a description of the Yucca Mountain site (Chapters 1-5), a conceptual design for the repository (Chapter 6), a description of the packaging to be used for the waste to be emplaced in the repository (Chapter 7), and a description of the planned site characterization activities (Chapter 8). The schedules and milestones presented in Section 8.3 and 8.5 of the SCP were developed to be consistent with the June 1988 draft Amendment to the DOE's Mission Plan for the Civilian Radioactive Waste Management Program. The five month delay in the scheduled start of exploratory shaft construction that was announced recently is not reflected in these schedules. 88 figs., 42 tabs

  19. Site characterization plan: Yucca Mountain Site, Nevada Research and Development Area, Nevada: Volume 6, Part B: Chapter 8, Sections 8.3.2 through 8.3.4.4

    International Nuclear Information System (INIS)

    1988-12-01

    This site characterization plan (SCP) has been developed for the candidate repository site at Yucca Mountain in the State of Nevada. The SCP includes a description of the Yucca Mountain site (Chapters 1-5), a conceptual design for the repository (Chapter 6), a description of the packaging to be used for the waste to be emplaced in the repository (Chapter 7), and a description of the planned site characterization activities (Chapter 8). The schedules and milestones presented in Sections 8.3 and 8.5 of the SCP were developed to be consistent with the June 1988 draft Amendment to the DOE's Mission Plan for the Civilian Radioactive Waste Management Program. The five month delay in the scheduled start of exploratory shaft construction that was announced recently is not reflected in these schedules. 35 figs., 70 tabs

  20. Site characterization plan: Yucca Mountain Site, Nevada Research and Development Area, Nevada: Volume 8, Part B: Chapter 8, Sections 8.3.5 through 8.3.5.20

    International Nuclear Information System (INIS)

    1988-12-01

    This site characterization plan (SCP) has been developed for the candidate repository site at Yucca Mountain in the State of Nevada. The SCP includes a description of the Yucca Mountain site (Chapters 1-5), a conceptual design for the repository (Chapter 6), a description of the packaging to be used for the waste to be emplaced in the repository (Chapter 7), and a description of the planned site characterization activities (Chapter 8). The schedules and milestones presented in Sections 8.3 and 8.5 of the SCP were developed to be consistent with the June 1988 draft Amendment to the DOE's Mission Plan for the Civilian Radioactive Waste Management Program. The five month delay in the scheduled start of exploratory shaft construction that was announced recently is not reflected in these schedules. 68 figs., 102 tabs

  1. Site characterization plan: Yucca Mountain Site, Nevada Research and Development Area, Nevada: Volume 8, Part B: Chapter 8, Sections 8.4 through 8.7; Glossary and Acronyms

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1988-12-01

    This site characterization plan (SCP) has been developed for the candidate repository site at Yucca Mountain in the State of Nevada. The SCP includes a description of the Yucca Mountain site (Chapters 1-5), a conceptual design for the repository (Chapter 6), a description of the packaging to be used for the waste to be emplaced in the repository (Chapter 7), and a description of the planned site characterization activities (Chapter 8). The schedules and milestones presented in Section 8.3 and 8.5 of the SCP were developed to be consistent with the June 1988 draft Amendment to the DOE`s Mission Plan for the Civilian Radioactive Waste Management Program. The five month delay in the scheduled start of exploratory shaft construction that was announced recently is not reflected in these schedules. 88 figs., 42 tabs.

  2. A future for nuclear sites beyond their service life. Nuclear site value development; Un avenir pour les sites nucleaires en fin de cycle. Valorisation des sites nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2008-07-01

    As the nuclear industry moves into a new development phase, many facilities built in the fifties and sixties are reaching the end of their service life. Dismantling them and rehabilitating the sites on which they stand is a major industrial challenge which will give rise to a number of new projects. AREVA has more than 20 years' experience in these highly technical fields. As more and more sites reach the end of their service life, AREVA considers nuclear site value development as a fully-fledged industrial activity. The group's competencies in this field have been grouped together to form a dedicated entity: the Nuclear Site Value Development Business Unit, created in 2008. Several billion euros are invested in site value development projects which are far-reaching and complex, and often last for several decades. Long before work actually begins, lengthy studies and preparations are required to schedule operations, select the techniques to be used and optimize costs and deadlines. The Nuclear Site Value Development BU is currently working on four major projects involving its own facilities and those of the CEA: - La Hague: dismantling of the first generation of used fuel recycling facilities. Between 1966 and 1998, almost 5,000 tons of used fuel from graphite-moderated gas-cooled reactors, 4,500 tons of light water reactor fuel, as well as fuel from fast reactors and research reactors, were treated at UP2 400, the very first industrial recycling plant on the La Hague site. - Marcoule: first-time dismantling of a recycling plant. 1,000 rooms to be cleaned up, 30,000 tons of waste to be treated, 30 years of work. - Cadarache: first-time dismantling of a Mox fuel fabrication plant. The Cadarache plant was commissioned in 1962 to fabricate fuel for fast reactors; this was followed by MOX fuel for light water reactors, an activity which continued until the plant was shut down in 2003. - Annecy and Veurey: giving a new lease of life to former industrial sites

  3. Site characterization plan: Yucca Mountain Site, Nevada Research and Development Area, Nevada: Volume 5, Part B: Chapter 8, Sections 8.3.1.5 through 8.3.1.17

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1988-12-01

    This site characterization plan (SCP) has been developed for the candidate repository site at Yucca Mountain in the State of Nevada. The SCP includes a description of the Yucca Mountain site (Chapters 1-5), a conceptual design for the repository (Chapter 6), a description of the packaging to be used for the waste to be emplaced in the repository (Chapter 7), and a description of the planned site characterization activities (Chapter 8). The schedules and milestones presented in Sections 8.3 and 8.5 of the SCP were developed to be consistent with the June 1988 draft Amendment to the SOE`s Mission Plan for the Civilian Radioactive Waste Management Program. The five month delay in the scheduled start of exploratory shaft construction that was announced recently is not reflected in these schedules.

  4. Site characterization plan: Yucca Mountain Site, Nevada Research and Development Area, Nevada: Volume 5, Part B: Chapter 8, Sections 8.3.1.5 through 8.3.1.17

    International Nuclear Information System (INIS)

    1988-12-01

    This site characterization plan (SCP) has been developed for the candidate repository site at Yucca Mountain in the State of Nevada. The SCP includes a description of the Yucca Mountain site (Chapters 1-5), a conceptual design for the repository (Chapter 6), a description of the packaging to be used for the waste to be emplaced in the repository (Chapter 7), and a description of the planned site characterization activities (Chapter 8). The schedules and milestones presented in Sections 8.3 and 8.5 of the SCP were developed to be consistent with the June 1988 draft Amendment to the SOE's Mission Plan for the Civilian Radioactive Waste Management Program. The five month delay in the scheduled start of exploratory shaft construction that was announced recently is not reflected in these schedules

  5. The Potential Impacts of OTEC Intakes on Aquatic Organisms at an OTEC Site under Development on Kauai, HI

    Energy Technology Data Exchange (ETDEWEB)

    Oney, Stephen K. [OTE Corporation; Hogan, Timothy [Alden Research Laboratory; Steinbeck, John [Tenera Environmental

    2013-08-31

    Ocean thermal energy conversion (OTEC) is a marine renewable energy technology with the potential to contribute significantly to the baseload power needs of tropical island communities and remote U.S. military installations. As with other renewable energy technologies, however, there are potential challenges to its commercialization: technological, financial, social, and environmental. Given the large volumes of seawater required to drive the electricity-producing cycle, there is potential for the intakes to negatively impact the marine resources of the source waterbody through the impingement and entrainment of marine organisms. The goal of this project was to identify feasible warm water intake designs for a land-based OTEC facility proposed for development in Port Allen, Kauai and to characterize the populations of ichthyoplankton near the proposed warm water intake location that could be at risk of entrainment. The specific objectives of this project were to: • Complete a site-specific assessment of available and feasible warm water intake technologies to determine the best intake designs for minimizing impacts to aquatic organisms at the proposed land-based OTEC site in Port Allen, Kauai. • Complete a field sampling program to collect biological data to characterize the baseline populations of ichthyoplankton near the sites being considered for the warm water intake at the proposed land-based OTEC site in Port Allen, Kauai. Various intake design options are presented with the focus on providing adequate environmental protection to the local ichthyoplankton population while providing an economically viable intake option to the OTEC developer. Further definition by NOAA and other environmental regulators is required to further refine the designs presented to meet all US regulations for future OTEC development.

  6. Development of site-specific soil cleanup criteria: New Brunswick Laboratory, New Jersey site

    Energy Technology Data Exchange (ETDEWEB)

    Veluri, V.R.; Moe, H.J.; Robinet, M.J.; Wynveen, R.A.

    1983-03-01

    The potential human exposure which results from the residual soil radioactivity at a decommissioned site is a prime concern during D and D projects. To estimate this exposure, a pathway analysis approach is often used to arrive at the residual soil radioactivity criteria. The development of such a criteria for the decommissioning of the New Brunswick Laboratory, New Jersey site is discussed. Contamination on this site was spotty and located in small soil pockets spread throughout the site area. Less than 1% of the relevant site area was contaminated. The major contaminants encountered at the site were /sup 239/Pu, /sup 241/Am, normal and natural uranium, and natural thorium. During the development of the pathway analysis to determine the site cleanup criteria, corrections for the inhomogeneity of the contamination were made. These correction factors and their effect upon the relevant pathway parameters are presented. Major pathways by which radioactive material may reach an individual are identified and patterns of use are specified (scenario). Each pathway is modeled to estimate the transfer parameters along the given pathway, such as soil to air to man, etc. The transfer parameters are then combined with dose rate conversion factors (ICRP 30 methodology) to obtain soil concentration to dose rate conversion factors (pCi/g/mrem/yr). For an appropriate choice of annual dose equivalent rate, one can then arrive at a value for the residual soil concentration. Pathway modeling, transfer parameters, and dose rate factors for the three major pathways; inhalation, ingestion and external exposure, which are important for the NBL site, are discussed.

  7. Siting, design and construction of a deep geological repository for the disposal of high level and alpha bearing wastes

    International Nuclear Information System (INIS)

    1990-06-01

    The main objective of this document is to summarize the basic principles and approaches to siting, design and construction of a deep geological repository for disposal of high level and alpha bearing radioactive wastes, as commonly agreed upon by Member States. This report is addressed to decision makers and technical managers as well as to specialists planning for siting, design and construction of geological repositories for disposal of high level and alpha bearing wastes. This document is intended to provide Member States of the IAEA with a summary outline for the responsible implementing organizations to use for siting, designing and constructing confinement systems for high level and alpha bearing radioactive waste in accordance with the protection objectives set by national regulating authorities or derived from safety fundamentals and standards of the IAEA. The protection objectives will be achieved by the isolation of the radionuclides from the environment by a repository system, which consists of a series of man made and natural safety barriers. Engineered barriers are used to enhance natural geological containment in a variety of ways. They must complement the natural barriers to provide adequate safety and necessary redundancy to the barrier system to ensure that safety standards are met. Because of the long timescales involved and the important role of the natural barrier formed by the host rock, the site selection process is a key activity in the repository design and development programme. The choice of the site, the investigation of its geological setting, the exploration of the regional hydrogeological setting and the primary underground excavations are all considered to be part of the siting process. 16 refs

  8. Evaluation of dynamic properties, local site effects and design ground motions: recent advances

    International Nuclear Information System (INIS)

    Sitharam, T.G.; Vipin, K.S.; James, Naveen

    2011-01-01

    Evidences from past earthquakes clearly shows that the damages due to an earthquake and its severity at a site are controlled mainly by three factors i.e., earthquake source and path characteristics, local geological and geotechnical characteristics, structural design and quality of the construction. Seismic ground response at a site is strongly influenced by local geological and soil conditions. The exact information of the geological, geomorphological and geotechnical data along with seismotectonic details are necessary to evaluate the ground response. The geometry of the subsoil structure, the soil type, the lateral discontinuities and the surface topography will also influence the site response at a particular location. In the case of a nuclear power plant, the details obtained from the site investigation will have multiple objectives: (i) for the effective design of the foundation (ii) assessment of site amplification (iii) for liquefaction potential evaluation. Since the seismic effects on the structure depend fully on the site conditions and assessment of site amplification. The first input required in evaluation of geotechnical aspect of seismic hazard is the rock level peak horizontal acceleration (PHA) values. The surface level acceleration values need to be calculated based on the site conditions and site amplification values. This paper discusses various methods for evaluating the site amplification values, dynamic soil properties, different field and laboratory tests required and various site classification schemes. In addition to these aspects, the evaluation of liquefaction potential of the site is also presented. The paper highlights on the latest testing methods to evaluate dynamic properties (shear modulus and damping ratio) of soils and techniques for estimating local site effects. (author)

  9. Development of site specific response spectra

    International Nuclear Information System (INIS)

    Bernreuter, D.L.; Chen, J.C.; Savy, J.B.

    1987-03-01

    For a number of years the US Nuclear Regulatory Commission (NRC) has employed site specific spectra (SSSP) in their evaluation of the adequacy of the Safe Shutdown Earthquake (SSE). These spectra were developed only from the spectra of the horizontal components of the ground motion and from a very limited data set. As the data set has considerably increased for Eastern North America (ENA) and as more relevant data has become available from earthquakes occurring in other parts of the world (e.g., Italy), together with the fact that recent data indicated the importance of the vertical component, it became clear that an update of the SSSP's for ENA was desirable. The methodology used in this study is similar to the previous ones in that it used actual earthquake ground motion data with magnitudes within a certain range and recorded at distances and at sites similar to those that would be chosen for the definition of an SSE. An extensive analysis of the origin and size of the uncertainty is an important part of this study. The results of this analysis of the uncertainties is used to develop criteria for selecting the earthquake records to be used in the derivation of the SSSP's. We concluded that the SSSPs were not very sensitive to the distribution of the source to site distance of the earthquake records used in the analysis. That is, the variability (uncertainty) introduced by the range of distances was relatively small compared to the variability introduced by other factors. We also concluded that the SSSP are somewhat sensitive to the distribution of the magnitudes of these earthquakes, particularly at rock sites and, by inference, at shallow soil sites. We found that one important criterion in selecting records to generate SSSP is the depth of soil at the site

  10. 41 CFR 102-76.20 - What issues must Federal agencies consider in providing site planning and landscape design services?

    Science.gov (United States)

    2010-07-01

    ... agencies consider in providing site planning and landscape design services? 102-76.20 Section 102-76.20... What issues must Federal agencies consider in providing site planning and landscape design services? In providing site planning and design services, Federal agencies must— (a) Make the site planning and landscape...

  11. Idaho National Engineering Laboratory site development plan

    International Nuclear Information System (INIS)

    1994-09-01

    This plan briefly describes the 20-year outlook for the Idaho National Engineering Laboratory (INEL). Missions, workloads, worker populations, facilities, land, and other resources necessary to fulfill the 20-year site development vision for the INEL are addressed. In addition, the plan examines factors that could enhance or deter new or expanded missions at the INEL. And finally, the plan discusses specific site development issues facing the INEL, possible solutions, resources required to resolve these issues, and the anticipated impacts if these issues remain unresolved

  12. Remedial action plan and site design for stabilization of the inactive uranium mill tailings sites at Rifle, Colorado. Volume 2, Appendices D and E: Final report

    Energy Technology Data Exchange (ETDEWEB)

    1992-02-01

    This appendix assesses the present conditions and data gathered about the two inactive uranium mill tailings sites near Rifle, Colorado, and the designated disposal site six miles north of Rifle in the area of Estes Gulch. It consolidates available engineering, radiological, geotechnical, hydrological, meteorological, and other information pertinent to the design of the Remedial Action Plan (RAP). The data characterize conditions at the mill, tailings, and disposal site so that the Remedial Action Contractor (RAC) may complete final designs for the remedial actions.

  13. Development of an integrated economic decision-support tool for the remediation of contaminated sites. Overview note

    International Nuclear Information System (INIS)

    Samson, R.; Bage, G.

    2004-05-01

    This report concludes the first design phase of an innovative software tool which, when completed, will allow managers of contaminated sites to make optimal decisions with respect to site remediation. The principal objective of the project was to develop the foundations for decision-support software (SITE VII) which will allow a comprehensive and rigorous approach to the comparison of remediation scenarios for sites contaminated with petroleum hydrocarbons. During this first phase of the project, the NSERC Industrial Chair in Site Remediation and Management of the Ecole Polytechnique de Montreal has completed four stages in the design of a decision-support tool that could be applied by any site manager using a simple computer. These four stages are: refinement of a technico-economic evaluation model; development of databases for five soil remediation technologies; design of a structure for integration of the databases with the technico-economic model; and simulation of the remediation of a contaminated site using the technico-economic model and a subset of the databases. In the interim report, the emphasis was placed on the development of the technico-economic model, supported by a very simple, single-technology simulation of remediation. In the present report, the priority is placed on the integration of the different components required for the creation of decision-support software based on the technico-economic model. An entire chapter of this report is devoted to elaborating the decision structure of the software. The treatment of information within the software is shown schematically and explained step-by-step. Five remediation technologies are handled by the software: three in-situ technologies (bio-venting, bio-slurping, bio-sparging) and two ex-situ technologies (thermal desorption, Bio-pile treatment). A technology file has been created for each technology, containing a brief description of the technology, its performance, its criteria of applicability

  14. Conceptual Design Report: Nevada Test Site Mixed Waste Disposal Facility Project

    International Nuclear Information System (INIS)

    2009-01-01

    Environmental cleanup of contaminated nuclear weapons manufacturing and test sites generates radioactive waste that must be disposed. Site cleanup activities throughout the U.S. Department of Energy (DOE) complex are projected to continue through 2050. Some of this waste is mixed waste (MW), containing both hazardous and radioactive components. In addition, there is a need for MW disposal from other mission activities. The Waste Management Programmatic Environmental Impact Statement Record of Decision designates the Nevada Test Site (NTS) as a regional MW disposal site. The NTS has a facility that is permitted to dispose of onsite- and offsite-generated MW until November 30, 2010. There is not a DOE waste management facility that is currently permitted to dispose of offsite-generated MW after 2010, jeopardizing the DOE environmental cleanup mission and other MW-generating mission-related activities. A mission needs document (CD-0) has been prepared for a newly permitted MW disposal facility at the NTS that would provide the needed capability to support DOE's environmental cleanup mission and other MW-generating mission-related activities. This report presents a conceptual engineering design for a MW facility that is fully compliant with Resource Conservation and Recovery Act (RCRA) and DOE O 435.1, 'Radioactive Waste Management'. The facility, which will be located within the Area 5 Radioactive Waste Management Site (RWMS) at the NTS, will provide an approximately 20,000-cubic yard waste disposal capacity. The facility will be licensed by the Nevada Division of Environmental Protection (NDEP)

  15. Development of Onsite Transportation Safety Documents for Nevada Test Site

    International Nuclear Information System (INIS)

    Frank Hand; Willard Thomas; Frank Sciacca; Manny Negrete; Susan Kelley

    2008-01-01

    Department of Energy (DOE) Orders require each DOE site to develop onsite transportation safety documents (OTSDs). The Nevada Test Site approach divided all onsite transfers into two groups with each group covered by a standalone OTSD identified as Non-Nuclear and Nuclear. The Non-Nuclear transfers involve all radioactive hazardous material in less than Hazard Category (HC)-3 quantities and all chemically hazardous materials. The Nuclear transfers involve all radioactive material equal to or greater than HC-3 quantities and radioactive material mated with high explosives regardless of quantity. Both OTSDs comply with DOE O 460.1B requirements. The Nuclear OTSD also complies with DOE O 461.1A requirements and includes a DOE-STD-3009 approach to hazard analysis (HA) and accident analysis as needed. All Nuclear OTSD proposed transfers were determined to be non-equivalent and a methodology was developed to determine if 'equivalent safety' to a fully compliant Department of Transportation (DOT) transfer was achieved. For each HA scenario, three hypothetical transfers were evaluated: a DOT-compliant, uncontrolled, and controlled transfer. Equivalent safety is demonstrated when the risk level for each controlled transfer is equal to or less than the corresponding DOT-compliant transfer risk level. In this comparison the typical DOE-STD-3009 risk matrix was modified to reflect transportation requirements. Design basis conditions (DBCs) were developed for each non-equivalent transfer. Initial DBCs were based solely upon the amount of material present. Route-, transfer-, and site-specific conditions were evaluated and the initial DBCs revised as needed. Final DBCs were evaluated for each transfer's packaging and its contents

  16. Convective boiling in a parallel microchannel heat sink with a diverging cross-section design and artificial nucleation sites

    International Nuclear Information System (INIS)

    Lu, Chun Ting; Pan, Chin

    2009-01-01

    To develop a highly stable boiling heat transfer microchannel heat sink, the three types of diverging microchannels, namely Type-1, Type-2 and Type-3, were designed to explore experimentally the effect of different distribution of artificial nucleation sites on enhancing boiling heat transfer in 10 parallel diverging microchannels with a mean hydraulic diameter of 120 μm. The Type-1 system is with no cavities, Type-2 is with cavities distributed uniformly along the downstream half of the channel, while Type-3 is with cavities distributed uniformly along the whole channel. The artificial nucleation sites are laser-etched pits on the channel bottom wall with a mouth diameter of about 20-22 μm based on the heterogeneous nucleation theory. The results of the present study reveal the presence of the artificial nucleation sites for flow boiling in parallel diverging microchannel significantly reduces the wall superheat and enhances the boiling heat transfer performance. Additionally, the Type-3 design demonstrates the best boiling heat transfer performance. (author)

  17. Remedial action plan and site design for stabilization of the inactive uranium processing site at Naturita, Colorado

    International Nuclear Information System (INIS)

    1994-03-01

    The uranium processing site near Naturita, Colorado, is one of 24 inactive uranium mill sites designated to be cleaned up by the US Department of Energy (DOE) under the Uranium Mill Tailings Radiation Control Act of 1978 (UMTRCA), 42 USC section 7901 et seq. Part of the UMTRCA requires that the US Nuclear Regulatory Commission (NRC) concur with the DOE's remedial action plan (RAP) and certify that the remedial action conducted at the site complies with the standards promulgated by the US Environmental Protection Agency (EPA). Included in the RAP is this Remedial Action Selection Report (RAS), which describes the proposed remedial action for the Naturita site. An extensive amount of data and supporting information has been generated and evaluated for this remedial action. These data and supporting information are not incorporated into this single document but are included or referenced in the supporting documents. The RAP consists of this RAS and four supporting documents or attachments. This Attachment 2, Geology Report describes the details of geologic, geomorphic, and seismic conditions at the Dry Flats disposal site

  18. Remedial action plan and site design for stabilization of the inactive uranium mill tailings site at Lowman, Idaho: Remedial action selection report for the Lowman UMTRA project site, Idaho

    International Nuclear Information System (INIS)

    Matthews, M.L.; Nagel, J.

    1991-09-01

    The inactive uranium mill tailings site near Lowman, Idaho, was designated as one of 24 abandoned uranium tailings sites to be remediated by the US Department of Energy (DOE) under the Uranium Mill Tailings Radiation Control Act of 1978 (UMTRCA). The UMTRCA requires that the US Nuclear Regulatory Commission (NRC) concur with the DOE's remedial action plan and certify that the remedial action complies with the standards promulgated by the US Environmental Protection Agency (EPA). The remedial action plan (RAP), which includes this remedial action selection report (RAS), has been developed to serve a two-fold purpose. First, it describes the activities that are proposed by the DOE to accomplish long-term stabilization and control of residual radioactive materials at the inactive uranium processing site near Lowman, Idaho. Second, this document and the remainder of the RAP, upon concurrence and execution by the DOE, the State of Idaho, and the NRC, becomes Appendix B of the Cooperative Agreement (No. DE-FC04-85AL20535) between the DOE and the State of Idaho

  19. Thermal Site Descriptive Model. A strategy for the model development during site investigations. Version 1.0

    International Nuclear Information System (INIS)

    Sundberg, Jan

    2003-04-01

    Site investigations are in progress for the siting of a deep repository for spent nuclear fuel. As part of the planning work, strategies are developed for site descriptive modelling regarding different disciplines, amongst them the thermal conditions. The objective of the strategy for a thermal site descriptive model is to guide the practical implementation of evaluating site specific data during the site investigations. It is understood that further development may be needed. The model describes the thermal properties and other thermal parameters of intact rock, fractures and fracture zones, and of the rock mass. The methodology is based on estimation of thermal properties of intact rock and discontinuities, using both empirical and theoretical/numerical approaches, and estimation of thermal processes using mathematical modelling. The methodology will be used and evaluated for the thermal site descriptive modelling at the Aespoe Hard Rock Laboratory

  20. Design report for the interim waste containment facility at the Niagara Falls Storage Site

    International Nuclear Information System (INIS)

    1986-05-01

    Low-level radioactive residues from pitchblende processing and thorium- and radium-contaminated sand, soil, and building rubble are presently stored at the Niagara Falls Storage Site (NFSS) in Lewiston, New York. These residues and wastes derive from past NFSS operations and from similar operations at other sites in the United States conducted during the 1940s by the Manhattan Engineer District (MED) and subsequently by the Atomic Energy Commission (AEC). The US Department of Energy (DOE), successor to MED/AEC, is conducting remedial action at the NFSS under two programs: on-site work under the Surplus Facilities Managemnt Program and off-site cleanup of vicinity properties under the Formerly Utilized Sites Remedial Action Program. On-site remedial action consists of consolidating the residues and wastes within a designated waste containment area and constructing a waste containment facility to prevent contaminant migration. The service life of the system is 25 to 50 years. Near-term remedial action construction activities will not jeopardize or preclude implementation of any other remedial action alternative at a later date. Should DOE decide to extend the service life of the system, the waste containment area would be upgraded to provide a minimum service life of 200 years. This report describes the design for the containment system. Pertinent information on site geology and hydrology and on regional seismicity and meteorology is also provided. Engineering calculations and validated computer modeling studies based on site-specific and conservative parameters confirm the adequacy of the design for its intended purposes of waste containment and environmental protection

  1. Molecular dynamics explorations of active site structure in designed and evolved enzymes.

    Science.gov (United States)

    Osuna, Sílvia; Jiménez-Osés, Gonzalo; Noey, Elizabeth L; Houk, K N

    2015-04-21

    This Account describes the use of molecular dynamics (MD) simulations to reveal how mutations alter the structure and organization of enzyme active sites. As proposed by Pauling about 70 years ago and elaborated by many others since then, biocatalysis is efficient when functional groups in the active site of an enzyme are in optimal positions for transition state stabilization. Changes in mechanism and covalent interactions are often critical parts of enzyme catalysis. We describe our explorations of the dynamical preorganization of active sites using MD, studying the fluctuations between active and inactive conformations normally concealed to static crystallography. MD shows how the various arrangements of active site residues influence the free energy of the transition state and relates the populations of the catalytic conformational ensemble to the enzyme activity. This Account is organized around three case studies from our laboratory. We first describe the importance of dynamics in evaluating a series of computationally designed and experimentally evolved enzymes for the Kemp elimination, a popular subject in the enzyme design field. We find that the dynamics of the active site is influenced not only by the original sequence design and subsequent mutations but also by the nature of the ligand present in the active site. In the second example, we show how microsecond MD has been used to uncover the role of remote mutations in the active site dynamics and catalysis of a transesterase, LovD. This enzyme was evolved by Tang at UCLA and Codexis, Inc., and is a useful commercial catalyst for the production of the drug simvastatin. X-ray analysis of inactive and active mutants did not reveal differences in the active sites, but relatively long time scale MD in solution showed that the active site of the wild-type enzyme preorganizes only upon binding of the acyl carrier protein (ACP) that delivers the natural acyl group to the active site. In the absence of bound ACP

  2. Designing chemical soil characterization programs for mixed waste sites

    International Nuclear Information System (INIS)

    Meyers, K.A. Jr.

    1989-01-01

    The Weldon Spring Site Remedial Action Project is a remedial action effort funded by the U.S. Department of Energy. The Weldon Spring Site, a former uranium processing facility, is located in east-central Missouri on a portion of a former ordnance works facility which produced trinitrotoluene during World War II. As a result of both uranium and ordnance production, the soils have become both radiologically and chemically contaminated. As a part of site characterization efforts in support of the environmental documentation process, a chemical soil characterization program was developed. This program consisted of biased and unbiased sampling program which maximized areal coverage, provided a statistically sound data base and maintained cost effectiveness. This paper discusses how the general rationale and processes used at the Weldon Spring Site can be applied to other mixed and hazardous waste sites

  3. The discussion of nuclear power plant's cooling chain design for freezing site

    International Nuclear Information System (INIS)

    Hu Jian; Yang Ting; Jiang Xulun

    2014-01-01

    The Component cooling water system (RRI) and Essential service water system (SEC) are composed of Nuclear Power Plant's (NPP) cooling chain, which has its special requirement for freezing site from system design and safety point of view. The feature and difficulty of cooling chain design at freezing condition (when the intake water temperature is below O ℃) are represented. At present, several NPPs are in operation or under construction at freezing site in the world, including Pressurized Water Reactor (PWR) and Canadian Deuterium Uranium reactor (CANDU). By analyzing the thoughts and applicability of different kinds of cooling chain design at freezing site, one solution called 'SEC thermal discharge reflux' is proposed to remove the residual heat from Nuclear Island (NI) into heat sink safely in winter. The solution has been approved by National Nuclear Safety Administration (NNSA) in China and applied in one of CPR NPP in the north of China, which is able to solve several problems compared with the traditional solutions, such as 'Reactor low power operation', 'Reactor start-up for the first time', and 'Changeover of RRI/SEC trains in winter'. The solution is also able to prevent RRI/SEC heat exchanger from icing and avoid low flowrate in SEC pipes. Besides, considering of the economical efficiency, simple operation and control strategy is designed. (authors)

  4. Perceptions of Web Site Design Characteristics: A Malaysian/Australian Comparison.

    Science.gov (United States)

    Fink, Dieter; Laupase, Ricky

    2000-01-01

    Compares the perceptions of Malaysians and Australians for four Web site design characteristics--atmospherics, news stories, signs, and products and services--as part of the integrated Internet marketing model. Hypothesizes that the predominant culture is not generalized to another culture, discusses validity and reliability, and suggest further…

  5. Drift design methodology and preliminary application for the Yucca Mountain Site Characterization Project

    International Nuclear Information System (INIS)

    Hardy, M.P.; Bauer, S.J.

    1991-12-01

    Excavation stability in an underground nuclear waste repository is required during construction, emplacement, retrieval (if required), and closure phases to ensure worker health and safety, and to prevent development of potential pathways for radionuclide migration in the post-closure period. Stable excavations are developed by appropriate excavation procedures, design of the room shape, design and installation of rock support reinforcement systems, and implementation of appropriate monitoring and maintenance programs. In addition to the loads imposed by the in situ stress field, the repository drifts will be impacted by thermal loads developed after waste emplacement and, periodically, by seismic loads from naturally occurring earthquakes and underground nuclear events. A priori evaluation of stability is required for design of the ground support system, to confirm that the thermal loads are reasonable, and to support the license application process. In this report, a design methodology for assessing drift stability is presented. This is based on site conditions, together with empirical and analytical methods. Analytical numerical methods are emphasized at this time because empirical data are unavailable for excavations in welded tuff either at elevated temperatures or under seismic loads. The analytical methodology incorporates analysis of rock masses that are systematically jointed, randomly jointed, and sparsely jointed. In situ thermal and seismic loads are considered. Methods of evaluating the analytical results and estimating ground support requirements for all the full range of expected ground conditions are outlines. The results of a preliminary application of the methodology using the limited available data are presented. 26 figs., 55 tabs

  6. KAJIAN ZONASI PENGEMBANGAN KAWASAN PUSAKA. STUDI KASUS: SITUS SANGIRAN, SRAGEN (Zoning Study of Heritage Site Development Case Study: Sangiran Site, Sragen

    Directory of Open Access Journals (Sweden)

    Wiendu Nuryanti

    2008-11-01

    Full Text Available ABSTRAK Sebagai Warisan Budaya Dunia (World Culture Heritage yang ditetapkan oleh UNESCO pada tanggal 5 Desember 1996, Situs Sangiran merupakan bagian penting dalam sejarah manusia di dunia. Sesuai dengan keputusan Menteri Pendidikan dan Kebudayaan (Nomor 0701011977, situs tersebut telah ditetapkan sebagai cagar budaya (Widianto, et al.,1996. Penelitian ini memiliki dua tujuan utama: (1 menyusun konsepsi dasar pelestarian, dan (2 menyusun arahan desain (guidelines pelestarian Situs Sangiran. Permasalahan utama dari kajian ini adalah perubahan lahan karena faktor alam dan aktivitas manusia (pertanian, pembangunan, penambangan, ancaman pencurian, penggelapan, dan jual beli fosil, rendahnya partisipasi masyarakat dalam upaya pelestarian Situs Sangiran, dan belum adanya panduan/arahan pelestarian dan pemanfaatan wisata yang jelas. Dengan metoda kualitatif naturalistik, dihasilkan konsepsi (prinsip dasar pelestarian Situs Sangiran Sragen, dalanr masing-masing zona (zona I -3 sesuai dengan potensi tiap zona yang perlu dilestarikan dan dikernbangkan. Analisis yang digunakan dalam hal ini adalah analisis makro, meso, dan mikro. Dari kajian ini dapat disimpulkan bahwa dalam merencanakan pelestarian Situs Sangiran, hal terpenting adalah mentaati zonasi dasar situs, di mana setiap zona akan merniliki guidelines  tersendiri. Guidelines terdiri atas pengembangan produk (Klaster Ngebung, Bukuran, Dayu, street furniture, serta pemberdayaan masyarakat.   ABSTRACT  UNESCO has established Sangiran Site as a World Culture Heritage in December 5th 1996. Its present is important to the history of mankind in the world. Widianto, et al., 1996, stated that Sangiran site has become a Cultural Site regarding to the declaration of Minister of Culture and Education (No. 070/0/1977. This Research has two main purposes, (1 to arrange a conception of basic preservation, and (2 to arrange a design guidelines of Sangiran Site Preservation. There are several major issues in

  7. Geological evolution, palaeoclimate and historical development of the Forsmark and Laxemar-Simpevarp areas. Site descriptive modelling SDM-Site

    Energy Technology Data Exchange (ETDEWEB)

    Soederbaeck, Bjoern [ed.

    2008-06-15

    The Swedish Nuclear Fuel and Waste Management Company (SKB) is undertaking site characterization at two different locations, the Forsmark and Laxemar-Simpevarp areas, with the objective of siting a geological repository for spent nuclear fuel. The site investigations started in 2002 and were completed in 2007. The analysis and modelling of data from the site investigations, which have taken place during and after these investigations, provide a foundation for the development of an integrated, multidisciplinary site descriptive model (SDM) for each of the two sites. A site descriptive model constitutes a description of the site and its regional setting, covering the current state of the geosphere and the biosphere, as well as those natural processes that affect or have affected their long-term development. Hitherto, a number of reports presenting preliminary site descriptive models for Forsmark and Laxemar-Simpevarp have been published. In these reports, the evolutionary and historical aspects of the site were included in a separate chapter. The present report comprises a further elaboration of the evolutionary and historical information included in the preliminary SDM reports, but presented here in a separate, supplementary report to the final site description, SDM-Site. The report is common to the two investigated areas, and the overall objective is to describe the long-term geological evolution, the palaeoclimate, and the post-glacial development of ecosystems and of the human population at the two sites. The report largely consists of a synthesis of information derived from the scientific literature and other sources not related to the site investigations. However, considerable information from the site investigations that has contributed to our understanding of the past development at each site is also included. This unique synthesis of both published information in a regional perspective and new site-specific information breaks new ground in our understanding

  8. Geological evolution, palaeoclimate and historical development of the Forsmark and Laxemar-Simpevarp areas. Site descriptive modelling SDM-Site

    International Nuclear Information System (INIS)

    Soederbaeck, Bjoern

    2008-06-01

    The Swedish Nuclear Fuel and Waste Management Company (SKB) is undertaking site characterization at two different locations, the Forsmark and Laxemar-Simpevarp areas, with the objective of siting a geological repository for spent nuclear fuel. The site investigations started in 2002 and were completed in 2007. The analysis and modelling of data from the site investigations, which have taken place during and after these investigations, provide a foundation for the development of an integrated, multidisciplinary site descriptive model (SDM) for each of the two sites. A site descriptive model constitutes a description of the site and its regional setting, covering the current state of the geosphere and the biosphere, as well as those natural processes that affect or have affected their long-term development. Hitherto, a number of reports presenting preliminary site descriptive models for Forsmark and Laxemar-Simpevarp have been published. In these reports, the evolutionary and historical aspects of the site were included in a separate chapter. The present report comprises a further elaboration of the evolutionary and historical information included in the preliminary SDM reports, but presented here in a separate, supplementary report to the final site description, SDM-Site. The report is common to the two investigated areas, and the overall objective is to describe the long-term geological evolution, the palaeoclimate, and the post-glacial development of ecosystems and of the human population at the two sites. The report largely consists of a synthesis of information derived from the scientific literature and other sources not related to the site investigations. However, considerable information from the site investigations that has contributed to our understanding of the past development at each site is also included. This unique synthesis of both published information in a regional perspective and new site-specific information breaks new ground in our understanding

  9. Conceptual design analyses for Hanford Site deployable remote spectroscopy systems

    International Nuclear Information System (INIS)

    Philipp, B.L.; Reich, F.R.

    1994-09-01

    This document identifies potential remote, NIR spectroscopic waste surface moisture monitoring system design alternatives to be operated inside one of the Hanford Site, high level, nuclear waste storage tanks. Potential tank waste moisture data impacts from the remote NIR signal transfer through high humidity vapor space is evaluated

  10. Development of impact design methods for ceramic gas turbine components

    Science.gov (United States)

    Song, J.; Cuccio, J.; Kington, H.

    1990-01-01

    Impact damage prediction methods are being developed to aid in the design of ceramic gas turbine engine components with improved impact resistance. Two impact damage modes were characterized: local, near the impact site, and structural, usually fast fracture away from the impact site. Local damage to Si3N4 impacted by Si3N4 spherical projectiles consists of ring and/or radial cracks around the impact point. In a mechanistic model being developed, impact damage is characterized as microcrack nucleation and propagation. The extent of damage is measured as volume fraction of microcracks. Model capability is demonstrated by simulating late impact tests. Structural failure is caused by tensile stress during impact exceeding material strength. The EPIC3 code was successfully used to predict blade structural failures in different size particle impacts on radial and axial blades.

  11. Development of Probabilistic Design Basis Earthquake (DBE) Parameters for Moderate and High Hazard Facilities at INEEL

    International Nuclear Information System (INIS)

    Payne, S. M.; Gorman, V. W.; Jensen, S. A.; Nitzel, M. E.; Russell, M. J.; Smith, R. P.

    2000-01-01

    Design Basis Earthquake (DBE) horizontal and vertical response spectra are developed for moderate and high hazard facilities or Performance Categories (PC) 3 and 4, respectively, at the Idaho National Engineering and Environmental Laboratory (INEEL). The probabilistic DBE response spectra will replace the deterministic DBE response spectra currently in the U.S. Department of Energy Idaho Operations Office (DOE-ID) Architectural Engineering Standards that govern seismic design criteria for several facility areas at the INEEL. Probabilistic DBE response spectra are recommended to DOE Naval Reactors for use at the Naval Reactor Facility at INEEL. The site-specific Uniform Hazard Spectra (UHS) developed by URS Greiner Woodward Clyde Federal Services are used as the basis for developing the DBE response spectra. In 1999, the UHS for all INEEL facility areas were recomputed using more appropriate attenuation relationships for the Basin and Range province. The revised UHS have lower ground motions than those produced in the 1996 INEEL site-wide probabilistic ground motion study. The DBE response spectra were developed by incorporating smoothed broadened regions of the peak accelerations, velocities, and displacements defined by the site-specific UHS. Portions of the DBE response spectra were adjusted to ensure conservatism for the structural design process

  12. Central repository for low- and intermediate-level waste (ALMA) conceptual design, siting and safety study

    International Nuclear Information System (INIS)

    Kjellbert, N.; Haeggblom, H.; Cederstroem, M.; Lundgren, T.

    1980-07-01

    A generic design, siting and safety study of a proposed repository for low- and intermediate-level waste has been made. Special emphasis has been placed on safety characterostics. The conceptual design and the generic site, on which the study is based, are realistically chosen in accordance with present construction techniques and the existing geohydrological conditions in Sweden. (Auth.)

  13. Study of seismic design bases and site conditions for nuclear power plants

    International Nuclear Information System (INIS)

    1980-04-01

    This report presents the results of an investigation of four topics pertinent to the seismic design of nuclear power plants: Design accelerations by regions of the continental United States; review and compilation of design-basis seismic levels and soil conditions for existing nuclear power plants; regional distribution of shear wave velocity of foundation materials at nuclear power plant sites; and technical review of surface-founded seismic analysis versus embedded approaches

  14. Study of seismic design bases and site conditions for nuclear power plants

    Energy Technology Data Exchange (ETDEWEB)

    1980-04-01

    This report presents the results of an investigation of four topics pertinent to the seismic design of nuclear power plants: Design accelerations by regions of the continental United States; review and compilation of design-basis seismic levels and soil conditions for existing nuclear power plants; regional distribution of shear wave velocity of foundation materials at nuclear power plant sites; and technical review of surface-founded seismic analysis versus embedded approaches.

  15. From heat integration targets toward implementation – A TSA (total site analysis)-based design approach for heat recovery systems in industrial clusters

    International Nuclear Information System (INIS)

    Hackl, Roman; Harvey, Simon

    2015-01-01

    The European process industry is facing major challenges to decrease production costs. One strategy to achieve this is by increasing energy efficiency. Single chemical processes are often well-integrated and the tools to target and design such measures are well developed. Site-wide heat integration based on total site analysis tools can be used to identify opportunities to further increase energy efficiency. However, the methodology has to be developed further in order to enable identification of practical heat integration measures in a systematic way. Designing site-wide heat recovery systems across an industrial cluster is complex and involves aspects apart from thermal process and utility flows. This work presents a method for designing a roadmap of heat integration investments based on total site analysis. The method is applied to a chemical cluster in Sweden. The results of the case study show that application of the proposed method can achieve up to 42% of the previously targeted hot utility savings of 129 MW. A roadmap of heat integration systems is suggested, ranging from less complex systems that achieve a minor share of the heat recovery potential to sophisticated, strongly interdependent systems demanding large investments and a high level of collaboration. - Highlights: • Methodology focused on the practical implementation of site-wide heat recovery. • Algorithm to determine a roadmap of heat integration investments. • Case study: 42% hot utility savings potential at a pay-back period of 3.9y.

  16. Development of the Remedial Action Priority System: an improved risk assessment tool for prioritizing hazardous and radioactive-mixed waste disposal sites

    International Nuclear Information System (INIS)

    Whelan, G.; Strenge, D.L.; Steelman, B.L.; Hawley, K.A.

    1985-08-01

    The Remedial Action Priority System (RAPS) represents a methodology that prioritizes inactive hazardous and radioactive mixed-waste disposal sites in a scientific and objective manner based on limited site information. This methodology is intended to bridge the technology gap that exists between the initial site evaluation using the Hazard Ranking System (HRS) and the time-consuming process of actual field site characterization, assessment, and remediation efforts. The HRS was designed as an initial screening tool to discriminate between hazardous waste sites that do not and those that are likely to pose significant problems to human health, safety, and/or the environment. The HRS is used by the US Environmental Protection Agency to identify sites for nomination to the National Priorites List (NPL). Because the HRS is not designed to evaluate sites containing radionuclides, a modified Hazard Ranking System (mHRS) addressing both hazardous and radioactive mixed wastes was developed by Pacific Northwest Laboratory (PNL) for the US Department of Energy (DOE). Neither the HRS nor the mHRS was designed to prioritize sites that are nominated to the NPL according to their potential risks. 15 refs., 6 figs., 3 tabs

  17. Bedrock hydrogeology Forsmark. Site descriptive modelling, SDM-Site Forsmark

    Energy Technology Data Exchange (ETDEWEB)

    Follin, Sven (SF GeoLogic AB, Taeby (Sweden))

    2008-12-15

    The Swedish Nuclear Fuel and Waste Management Company (SKB) has conducted site investigations at two different locations, the Forsmark and Laxemar-Simpevarp areas, with the objective of siting a final repository for spent nuclear fuel according to the KBS-3 concept. Site characterisation should provide all data required for an integrated evaluation of the suitability of the investigated site and an important component in the characterisation work is the development of a hydrogeological model. The hydrogeological model is used by repository engineering to design the underground facility and to develop a repository layout adapted to the site. It also provides input to the safety assessment. Another important use of the hydrogeological model is in the environmental impact assessment. This report presents the understanding of the hydrogeological conditions of the bedrock at Forsmark reached following the completion of the surface-based investigations and provides a summary of the bedrock hydrogeological model and the underlying data supporting its development. It constitutes the main reference on bedrock hydrogeology for the site descriptive model concluding the surface-based investigations at Forsmark, SDM-site, and is intended to describe the hydraulic properties and hydrogeological conditions of the bedrock at the site and to give the information essential for demonstrating understanding

  18. Early Site Permit Demonstration Program: Guidelines for determining design basis ground motions

    International Nuclear Information System (INIS)

    1993-01-01

    This report develops and applies a methodology for estimating strong earthquake ground motion. The motivation was to develop a much needed tool for use in developing the seismic requirements for structural designs. An earthquake's ground motion is a function of the earthquake's magnitude, and the physical properties of the earth through which the seismic waves travel from the earthquake fault to the site of interest. The emphasis of this study is on ground motion estimation in Eastern North America (east of the Rocky Mountains), with particular emphasis on the Eastern United States and southeastern Canada. Eastern North America is a stable continental region, having sparse earthquake activity with rare occurrences of large earthquakes. While large earthquakes are of interest for assessing seismic hazard, little data exists from the region to empirically quantify their effects. Therefore, empirically based approaches that are used for other regions, such as Western North America, are not appropriate for Eastern North America. Moreover, recent advances in science and technology have now made it possible to combine theoretical and empirical methods to develop new procedures and models for estimating ground motion. The focus of the report is on the attributes of ground motion in Eastern North America that are of interest for the design of facilities such as nuclear power plants. Specifically considered are magnitudes M from 5 to 8, distances from 0 to 500 km, and frequencies from 1 to 35 Hz

  19. Site characterization plan: Yucca Mountain site, Nevada research and development area, Nevada: Consultation draft, Nuclear Waste Policy Act: Volume 1

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1988-01-01

    The Yucca Mountain site in Nevada is one of three candidate sites for the first geologic repository for radioactive waste. On May 28, 1986, it was recommended for detailed study in a program of site characterization. This site characterization plan (SCP) has been prepared in acordance with the requirements of the Nuclear Waste Policy Act to summarize the information collected to date about the geologic conditions at the site;to describe the conceptual designs for the repository and the waste package and to present the plans for obtaining the geologic information necessary to demonstrate the suitability of the site for a repository, to design the repository and the waste package, to prepare an environmental impact statement, and to obtain from the US Nuclear Regulatory Commission (NRC) an authorization to construct the repository. This introduction begins with a brief section on the process for siting and eveloping a repository, followed by a discussion of the pertinent legislation and regulations. A description of site characterization is presented next;it describes the facilities to be constructed for the site characterization program and explains the principal activities to be conducted during the program. Finally, the purpose, content, organizing prinicples, and organization of this site characterization plan are outlined, and compliance with applicable regulations is discussed. 880 refs., 130 figs., 25 tabs.

  20. State-of-the-Art Report for the Deep URL Facility Development : Aspo Hard Rock Laboratory, Grimsel Test Site

    International Nuclear Information System (INIS)

    Kim, Kyung Su; Bae, Dae Seok; Kim, Geon Young

    2012-01-01

    This report analysed the development status on the SKB's Hard Rock Laboratory and Nagra's Grimsel Test Site facilities to investigate their facility overview, operation system, site condition, project history and procedure, and current experiment programmes of underground research laboratory. SKB and Nagra had launched high level radioactive waste disposal project around 1970's. Actual site investigation activities were initiated since 1990's and the time schedule for siting programmes to determine the final disposal site were taken fifteen to thirty years. Furthermore, ten to twenty years will be needed to site characterization, facility design, construction, and operation commissioning. Nagra had constructed Grimsel Test Site facility in southern Switzerland Apls with the collaboration of KWO electrical company in early 1980's. This facility is characterized of a centre of excellence for underground Research and Development (R and D) to support projects for the disposal of radioactive and chemo-toxic waste and not a potential repository site. The SKB's Aspo HRL constructed in outside Oskarshamn is a unique PBG-URL facility. SKB is conducting full-scale research and development here in preparation for the construction of a final repository for spent nuclear fuel. The research programmes for the development of disposal technologies is performed over thirty to fifty years prior to repository operation. In 2000's, research on long-term phenomena, i.e., optimization of disposal concept, understanding of coupling process, validation of mathematical model, test and development of safety assessment models, characterization of deep geochemical environment, and long-term demonstration experiments have been leading the issues of research and development

  1. Design and control strategy for a hybrid green energy system for mobile telecommunication sites

    Science.gov (United States)

    Okundamiya, Michael S.; Emagbetere, Joy O.; Ogujor, Emmanuel A.

    2014-07-01

    The rising energy costs and carbon footprint of operating mobile telecommunication sites in the emerging world have increased research interests in green technology. The intermittent nature of most green energy sources creates the problem of designing the optimum configuration for a given location. This study presents the design analysis and control strategy for a cost effective and reliable operation of the hybrid green energy system (HGES) for GSM base transceiver station (BTS) sites in isolated regions. The design constrains the generation and distribution of power to reliably satisfy the energy demand while ensuring safe operation of the system. The overall process control applies the genetic algorithm-based technique for optimal techno-economic sizing of system's components. The process simulation utilized meteorological data for 3 locations (Abuja, Benin City and Sokoto) with varying climatic conditions in Nigeria. Simulation results presented for green GSM BTS sites are discussed and compared with existing approaches.

  2. Mechanisation and automation technologies development in work at construction sites

    Science.gov (United States)

    Sobotka, A.; Pacewicz, K.

    2017-10-01

    Implementing construction work that creates buildings is a very complicated and laborious task and requires the use of various types of machines and equipment. For years there has been a desire for designers and technologists to introduce devices that replace people’s work on machine construction, automation and even robots. Technologies for building construction are still being developed and implemented to limit people’s hard work and improve work efficiency and quality in innovative architectonical and construction solutions. New opportunities for improving work on the construction site include computerisation of technological processes and construction management for projects and processes. The aim of the paper was to analyse the development of mechanisation, automation and computerisation of construction processes and selected building technologies, with special attention paid to 3D printing technology. The state of mechanisation of construction works in Poland and trends in its development in construction technologies are presented. These studies were conducted on the basis of the available literature and a survey of Polish construction companies.

  3. HTP-OligoDesigner: An Online Primer Design Tool for High-Throughput Gene Cloning and Site-Directed Mutagenesis.

    Science.gov (United States)

    Camilo, Cesar M; Lima, Gustavo M A; Maluf, Fernando V; Guido, Rafael V C; Polikarpov, Igor

    2016-01-01

    Following burgeoning genomic and transcriptomic sequencing data, biochemical and molecular biology groups worldwide are implementing high-throughput cloning and mutagenesis facilities in order to obtain a large number of soluble proteins for structural and functional characterization. Since manual primer design can be a time-consuming and error-generating step, particularly when working with hundreds of targets, the automation of primer design process becomes highly desirable. HTP-OligoDesigner was created to provide the scientific community with a simple and intuitive online primer design tool for both laboratory-scale and high-throughput projects of sequence-independent gene cloning and site-directed mutagenesis and a Tm calculator for quick queries.

  4. Remedial Action Plan and site design for stabilization of the inactive uranium mill tailings site at Rifle, Colorado

    International Nuclear Information System (INIS)

    1990-02-01

    This document has been structured to provide a comprehensive understanding of the remedial action proposed for the Rifle sites. That remedial action consists of removing approximately 4,185,000 cubic yards (cy) of tailings and contaminated materials from their current locations, transporting, and stabilizing the tailings material at the Estes Gulch disposal site, approximately six miles north of Rifle. The tailings and contaminated materials are comprised of approximately 597,000 cy from Old Rifle, 3,232,000 cy from New Rifle, and 322,000 cy from vicinity properties and about 34,000 cy from demolition. The remedial action plan includes specific design requirements for the detailed design and construction of the remedial action. An extensive amount of data and supporting information have been generated for this remedial action and cannot all be incorporated into this document. Pertinent information and data are included with reference given to the supporting documents

  5. Remedial action plan and site design for stabilization of the inactive uranium processing site at Naturita, Colorado

    International Nuclear Information System (INIS)

    1993-08-01

    The US Environmental Protection Agency (EPA) has established health and environmental protection regulations to correct and prevent groundwater contamination resulting from processing activities at inactive uranium milling sites (40 CFR 192). The Uranium Mill Tailings Radiation Control Act (UMTRCA) of 1978 designated responsibility to the US Department of Energy (DOE) for assessing the inactive uranium milling sites. The DOE has determined that each assessment shall include information on site characterization, a description of the proposed action, and a summary of the water resources protection strategy that describes how the proposed action will comply with the EPA groundwater protection standards. To achieve compliance with the proposed US Environmental Protection Agency (EPA) groundwater protection standards, the US Department of Energy (DOE) proposes that supplemental standards be applied at the Dry Flats disposal site because of Class III (limited use) groundwater in the uppermost aquifer (the basal sandstone of the Cretaceous Burro Canyon Formation) based on low yield. The proposed remedial action will ensure protection of human health and the environment

  6. Remedial action plan and site design for stabilization of the inactive uranium processing site at Naturita, Colorado

    International Nuclear Information System (INIS)

    1993-08-01

    The uranium processing site near Naturita, Colorado, is one of 24 inactive uranium mill sites designated to be cleaned up by the US Department of Energy (DOE) under the Uranium Mill Tailings Radiation Control Act of 1978 (UMTRCA), Public Law 95-604. Part of the UMTRCA requires that the US Nuclear Regulatory Commission (NRC) concur with the DOE's remedial action plan (RAP) and certify that the remedial action conducted at the site complies with the standards promulgated by the US Environmental Protection Agency (EPA). Included in the RAP is this Remedial Action Selection Report (RAS), which serves two purposes. First, it describes the activities that are proposed by the DOE to accomplish remediation and long-term stabilization and control of the radioactive materials at the inactive uranium processing site near Naturita, Colorado. Second, this document and the rest of the RAP, upon concurrence and execution by the DOE, the state of Colorado, and the NRC, become Appendix B of the cooperative agreement between the DOE and the State of Colorado

  7. Remedial design process for Montclair/West Orange and Glen Ridge radium sites

    International Nuclear Information System (INIS)

    MacIndoe, M.; Johnson, R.; Paez-Restrepo, A.; Wilkinson, S.; Hyman, M.

    1994-01-01

    The Montclair/West Orange and Glen Ridge Superfund Sites, located in Essex County, New Jersey, are contaminated to varying degrees with radioactive materials. The waste materials originated from radium processing facilities prevalent in the area during the early 1900's. The two sites consist of 769 residential and commercial properties having a combined land area of approximately 210 acres. Historically, radioactive waste materials were disposed as landfill material in what were once rural areas. As development flourished, homes and streets were constructed over the landfilled waste. In 1981 the EPA conducted an aerial gamma radiation survey of the area to determine the presence of radioactive materials. It was from this survey that subsequent ground studies where initiated, and elevated gamma radiation and radon levels were discovered. The paper will discuss the methods used to obtain data through field investigations; the relationship between the interpretation of data to define the vertical and lateral limits of contamination and the selection of remedial design methods used to develop excavation plans; the evolution of remediation methods and technologies relative to the remediation of structures by underpinning basements, on-grade structures, and chimneys; removal of contaminated material beneath footings without cribbing; and demolition of basement foundation walls (where contaminated) without use of traditional support methods. Finally, the paper will discuss remedial action execution of the work

  8. DESIGN VERSUS PRODUCT DEVELOPMENT?

    Directory of Open Access Journals (Sweden)

    Edu Grieco Mazzini Junior

    2015-03-01

    Full Text Available Design or product development? The questioning in relation to the employment of such terminology dates back to possible misconceptions regarding interpretation and approach them. Therefore, it can be stated that there are differences between these two terms? In this context, we highlight two views concerning the origin of the design. The first character creative and based on pre-industrial revolution, based on projective and methodologies directed towards the practice of designing products. And second, where design is understood as an industrial process: the development of new products includes, besides a creative procedure are developed, and symbolic formal solutions for products, but also a technical procedure based on the definition of the requirements concerning the product engineering. Is this the most widely accepted interpretation? theoretical studies were conducted from interpretations of the concept of the design proposed by the International Council of Societies of Industrial Design – ICSDI (2012, and for the characterization of the process of product development, we sought to develop an analogy between these two terminologies and can be proved that the use of one of terminology will not cause deviations of interpretation, since both deal with the life cycle of the product. The main results obtained until now the definition of design proposed by the ICSID where it is characterized as a creative activity focused on the complete life cycle of products is the more approaches of the concept of product development.

  9. Comment and response document for the final remedial action plan and site design for stabilization of the inactive uranium mill tailings sites at Slick Rock, Colorado. Revision 2

    International Nuclear Information System (INIS)

    1996-05-01

    This document for the final remedial action plan and site design has been prepared for US Department of Energy Environmental Restoration Division as part of the Uranium Mill Tailings Remedial Action plan. Comments and responses are included for the site design for stabilization of the inactive uranium mill tailings sites at Slick Rock, Colorado

  10. Third report, development of site suitability and design performance data base for a high level nuclear waste repository

    International Nuclear Information System (INIS)

    1978-05-01

    This report presents the results of mining and geotechnical studies provided as support for the development of a technical data base suitable for the generation of a regulatory framework governing high-level nuclear waste disposal: flow path models for basalts, salt domes, and crystalline rocks; simplistic model evaluations; loss of administrative control; repository conceptual designs; repository design considerations; and design performance criteria

  11. Guide to radiological accident considerations for siting and design of DOE nonreactor nuclear facilities

    International Nuclear Information System (INIS)

    Elder, J.; Graf, J.M.

    1984-01-01

    DOE Office of Nuclear Safety has sponsored preparation of a guidance document to aid field offices and contractors in their analyses of consequences of postulated major accidents. The guide addresses the requirements of DOE Orders 5480.1A, Chapter V, and 6430.1, including the general requirement that DOE nuclear facilities be sited, designed, and operated in accordance with standards, codes, and guides consistent with those applied to comparable licensed nuclear facilities. The guide includes both philosophical and technical information in the areas of: siting guidelines doses applied to an offsite reference person; consideration also given to an onsite reference person; physical parameters, models, and assumptions to be applied when calculating doses for comparison to siting criteria; and potential accident consequences other than radiological dose to a reference person which might affect siting and major design features of the facility, such as environmental contamination, population dose, and associated public health effects. Recommendations and/or clarifications are provided where this could be done without adding new requirements. In this regard, the guide is considered a valuable aid to the safety analyst, especially where requirements have been subject to inconsistent interpretation or where analysis methods are in transition, such as use of dose model (ICRP 2 or ICRP 30) or use of probabilistic methods of risk analysis in the siting and design of nuclear facilities

  12. SITE-94. Scenario development FEP audit list preparation: methodology and presentation

    International Nuclear Information System (INIS)

    Stenhouse, M.; Chapman, N.; Sumerling, T.

    1993-04-01

    This report concerns a study which is part of the SKI performance assessment project SITE-94. SITE-94 is a performance assessment of a hypothetical repository at a real site. The main objective of the project is to determine how site specific data should be assimilated into the performance assessment process and to evaluate how uncertainties inherent in site characterization will influence performance assessment results. Other important elements of SITE-94 are the development of a practical and defensible methodology for defining, constructing and analyzing scenarios, the development of approaches for treatment of uncertainties , evaluation of canister integrity, and the development and application of an appropriate quality assurance plan for performance assessments

  13. Current plans to characterize the design basis ground motion at the Yucca Mountain, Nevada Site

    International Nuclear Information System (INIS)

    Simecka, W.B.; Grant, T.A.; Voegele, M.D.; Cline, K.M.

    1992-01-01

    A site at Yucca Mountain Nevada is currently being studied to assess its suitability as a potential host site for the nation's first commercial high level waste repository. The DOE has proposed a new methodology for determining design-basis ground motions that uses both deterministic and probabilistic methods. The role of the deterministic approach is primary. It provides the level of detail needed by design engineers in the characterization of ground motions. The probabilistic approach provides a logical structured procedure for integrating the range of possible earthquakes that contribute to the ground motion hazard at the site. In addition, probabilistic methods will be used as needed to provide input for the assessment of long-term repository performance. This paper discusses the local tectonic environment, potential seismic sources and their associated displacements and ground motions. It also discusses the approach to assessing the design basis earthquake for the surface and underground facilities, as well as selected examples of the use of this type of information in design activities

  14. Are Biophilic-Designed Site Office Buildings Linked to Health Benefits and High Performing Occupants?

    Directory of Open Access Journals (Sweden)

    Tonia Gray

    2014-11-01

    Full Text Available This paper discusses the first phase of a longitudinal study underway in Australia to ascertain the broad health benefits of specific types of biophilic design for workers in a building site office. A bespoke site design was formulated to include open plan workspace, natural lighting, ventilation, significant plants, prospect and views, recycled materials and use of non-synthetic materials. Initial data in the first three months was gathered from a series of demographic questions and from interviews and observations of site workers. Preliminary data indicates a strong positive effect from incorporating aspects of biophilic design to boost productivity, ameliorate stress, enhance well-being, foster a collaborative work environment and promote workplace satisfaction, thus contributing towards a high performance workspace. The longitudinal study spanning over two years will track human-plant interactions in a biophilic influenced space, whilst also assessing the concomitant cognitive, social, psychological and physical health benefits for workers.

  15. Creating Virtual Fieldwork Experiences of Geoheritage Sites as Educator Professional Development (Invited)

    Science.gov (United States)

    Duggan-Haas, D.

    2013-12-01

    Geoheritage sites are identified as such because they include excellent examples of geologic features or processes, or they have played an important role in the development of geologic understandings. These characteristics also make them excellent sites for teaching in the field, for teaching educators about the nature of fieldwork, and for making Virtual Fieldwork Experiences (VFEs, multimedia representations of field sites). Through the NSF-funded Regional and Local Earth (ReaL) Earth Inquiry Project, we have engaged educators in these practices. The nature of geoheritage sites is anomalous -- if this were not the case, the sites would not gain recognition. Anomalous features or processes can be powerful learning tools when placed into comparison with the more mundane, and the Earth system science of sites local to schools is likely to be mundane. By comparing the mundane and the extraordinary, it is hoped we can learn more about both. The professional development (PD) in ReaL Earth Inquiry begins with a face-to-face workshop within the teachers' region at a site that is interesting from an Earth system science perspective. Though we recognize and emphasize that all sites are interesting from an ESS perspective if you know how to look, the sites typically have features worthy of geoheritage designation. PD does not end with the end of the workshop but continues with online study groups where teachers work together to complete the workshop site VFE, and transition to work on VFEs of sites local to their schools. Throughout the program, participants engage in: - mentored fieldwork that pays attention to the skills and knowledge needed to lead fieldwork; - instruction in and use of a wide range of technologies for making VFEs; - study of a coherent conceptual framework connected to the project's driving question: Why does this place look the way it does? - and, use of resources for supporting all of the above The resources include templates for making VFEs and a

  16. The Concept of Historical Landscape Design at Watugong Archaeological Site Area in Malang City

    Science.gov (United States)

    Setyabudi, I.; Alfian, R.; Hastutiningtyas, W. R.

    2017-10-01

    Malang city has the high historical value. It showed by many archaeological situses found, such as: The Dutch Colonial Building until kingdom era on classical history period. Generally, it could be seen at urban affairs like government building even the ancient house. But the last kingdom archaeological site only found at the village. The oldest archaeological site in Malang city was found on Kanjuruhan Kingdom, which is concentrated in Tlogomas. The Watu Gong Hamlet that was located in Tlogomas Political District had an archaeological site. It was a big stone in which the stone looked like a traditional music instrument, it was called Gong. As the archaeological site in megalithicum, before the Hindu and Budha came in from India, that stone was predicted as the foundation structure of the big building. The Watu Gong Hamlet was located in Tlogomas archeological site area, also Merjosari and Karang Besuki. Three of them are the archeological sites for Kanjuruhan Kingdom at eigth century, until Kahuripan Kingdom around the eleventh century, as the heir of the Ancient Mataram Kingdom. The urban government has a program to improve the village required to their region potential and it was possible to revitalize the Tlogomas village, so that the historical character can be seen well. The modernity of a hamlet has impact on the local identity blured. In which, they did not think about economic only and it can be minimized, also the hamlet will be a characterized tourism object. The revitalization purposed to continuing the past, then it’s connected to present. It’s performed as corridored garden planning. The landscape development appropriated to promote about the characters of Kacapiring flower, Rose, Jasmine and Puring. They are the special plants from Kanjuruhan Kingdom, beside the other furniture street model. This research was descriptive explorative and discussed about the concept with architecture design approach, started from data collecting, precedent study

  17. Development of rail access to the proposed repository site at Yucca Mountain

    International Nuclear Information System (INIS)

    Standish, P.N.; Seidler, P.E.; Andrews, W.B.; Shearin, G.

    1991-01-01

    In accordance with the Nuclear Waste Policy Amendment Act of 1987, Yucca Mountain was designated as the initial site to be investigated as a potential repository for the disposal of high-level radioactive waste. The Yucca Mountain site is an undeveloped area located on the southwestern edge of the Nevada Test Site (NTS), about 100 miles northwest of Las Vegas. The site currently lacks rail service or an existing right-of-way. If the Yucca Mountain site is found suitable for the repository, rail service is considered desirable by the Office of Civilian Radioactive Waste Management (OCRWM) program because of the potential of rail transportation to reduce (1) costs and (2) number of shipments, relative to highway transportation. Therefore, it is necessary to conduct a study to determine (1) that there are alignments for a potential rail line from existing mainline railroads to Yucca Mountain and (2) that these are consistent with present rail design standards and are acceptable relative to environmental and land access considerations

  18. Characterization Report for the 92-Acre Area of the Area 5 Radioactive Waste Management Site, Nevada Test Site, Nevada

    International Nuclear Information System (INIS)

    Bechtel Nevada; U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office

    2006-01-01

    The U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office manages two low-level Radioactive Waste Management Sites at the Nevada Test Site. The Area 5 RWMS uses engineered shallow-land burial cells to dispose of packaged waste. This report summarizes characterization and monitoring work pertinent to the 92-Acre Area in the southeast part of the Area 5 Radioactive Waste Management Sites. The decades of characterization and assessment work at the Area 5 RWMS indicate that the access controls, waste operation practices, site design, final cover design, site setting, and arid natural environment contribute to a containment system that meets regulatory requirements and performance objectives for the short- and long-term protection of the environment and public. The available characterization and Performance Assessment information is adequate to support design of the final cover and development of closure plans. No further characterization is warranted to demonstrate regulatory compliance. U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office is proceeding with the development of closure plans for the six closure units of the 92-Acre Area

  19. Characterization Report for the 92-Acre Area of the Area 5 Radioactive Waste Management Site, Nevada Test Site, Nevada

    Energy Technology Data Exchange (ETDEWEB)

    Bechtel Nevada; U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office

    2006-06-01

    The U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office manages two low-level Radioactive Waste Management Sites at the Nevada Test Site. The Area 5 RWMS uses engineered shallow-land burial cells to dispose of packaged waste. This report summarizes characterization and monitoring work pertinent to the 92-Acre Area in the southeast part of the Area 5 Radioactive Waste Management Sites. The decades of characterization and assessment work at the Area 5 RWMS indicate that the access controls, waste operation practices, site design, final cover design, site setting, and arid natural environment contribute to a containment system that meets regulatory requirements and performance objectives for the short- and long-term protection of the environment and public. The available characterization and Performance Assessment information is adequate to support design of the final cover and development of closure plans. No further characterization is warranted to demonstrate regulatory compliance. U.S. Department of Energy, National Nuclear Security Administration Nevada Site Office is proceeding with the development of closure plans for the six closure units of the 92-Acre Area.

  20. Hanford Site waste tank farm facilities design reconstitution program plan

    International Nuclear Information System (INIS)

    Vollert, F.R.

    1994-01-01

    Throughout the commercial nuclear industry the lack of design reconstitution programs prior to the mid 1980's has resulted in inadequate documentation to support operating facilities configuration changes or safety evaluations. As a result, many utilities have completed or have ongoing design reconstitution programs and have discovered that without sufficient pre-planning their program can be potentially very expensive and may result in end-products inconsistent with the facility needs or expectations. A design reconstitution program plan is developed here for the Hanford waste tank farms facility as a consequence of the DOE Standard on operational configuration management. This design reconstitution plan provides for the recovery or regeneration of design requirements and basis, the compilation of Design Information Summaries, and a methodology to disposition items open for regeneration that were discovered during the development of Design Information Summaries. Implementation of this plan will culminate in an end-product of about 30 Design Information Summary documents. These documents will be developed to identify tank farms facility design requirements and design bases and thereby capture the technical baselines of the facility. This plan identifies the methodology necessary to systematically recover documents that are sources of design input information, and to evaluate and disposition open items or regeneration items discovered during the development of the Design Information Summaries or during the verification and validation processes. These development activities will be governed and implemented by three procedures and a guide that are to be developed as an outgrowth of this plan

  1. Energy conserving site design case study: Shenandoah, Georgia. Final report

    Energy Technology Data Exchange (ETDEWEB)

    1980-01-01

    The case study examines the means by which energy conservation can be achieved at an aggregate community level by using proper planning and analytical techniques for a new town, Shenandoah, Georgia, located twenty-five miles southwest of Atlanta's Hartsfield International Airport. A potentially implementable energy conservation community plan is achieved by a study team examining the land use options, siting characteristics of each building type, alternate infrastructure plans, possible decentralized energy options, and central utility schemes to determine how community energy conservation can be achieved by use of pre-construction planning. The concept for the development of mixed land uses as a passively sited, energy conserving community is based on a plan (Level 1 Plan) that uses the natural site characteristics, maximizes on passive energy siting requirement, and allows flexibility for the changing needs of the developers. The Level 2 Plan is identical with Level 1 plan plus a series of decentraized systems that have been added to the residential units: the single-family detached, the apartments, and the townhouses. Level 3 Plan is similar to the Level 1 Plan except that higher density dwellings have been moved to areas adjacent to central site. The total energy savings for each plan relative to the conventional plan are indicated. (MCW)

  2. Site characterization plan:

    International Nuclear Information System (INIS)

    1988-01-01

    The Yucca Mountain site in Nevada is one of three candidate sites for the first geologic repository for radioactive waste. On May 28, 1986, it was recommended for detailed study in a program of site characterization. This site characterization plan (SCP) has been prepared in accordance with the requirements of the Nuclear Waste Policy Act to summarize the information collected to date about the geologic conditions at the site;to describe the conceptual designs for the repository and the waste package;and to present the plans for obtaining the geologic information necessary to demonstrate the suitability of the site for repository, to design the repository and the waste package, to prepare an environmental impact statement, and to obtain from the US Nuclear Regulatory Commission (NRC) an authorization to construct the repository. This introduction begins with a brief section on the process for siting and developing a repository, followed by a discussion of the pertinent legislation and regulations. A description of site characterization is presented next;it describes the facilities to be constructed for the site characterization program and explains the principal activities to be conducted during the program. Finally, the purpose, content, organizing principles, and organization of this site characterization plan are outlined, and compliance with applicable regulations is discussed

  3. Small Reactors without On-site Refuelling: Neutronic Characteristics, Emergency Planning and Development Scenarios. Final Report of an IAEA Coordinated Research Project

    International Nuclear Information System (INIS)

    2010-09-01

    Small reactors without on-site refuelling have a capability to operate without reloading or shuffling of fuel in their cores for reasonably long periods of time consistent with plant economy and considerations of energy security, with no fresh or spent fuel being stored at the site during reactor operation. In 2009, more than 25 design concepts of such reactors were analyzed or developed in IAEA Member States, representing both developed and developing countries. Small reactors without on-site refuelling are being developed for several reactor lines, including water cooled reactors, sodium cooled fast reactors, lead and lead bismuth cooled reactors, and also include some non-conventional concepts. Most of the concepts of small reactors without on-site refuelling reactors are at early design stages. To make such reactors viable, further research and development (R and D) is necessary, inter alia, to validate long-life core operation, define and validate new robust types of fuel, justify an option of plant location in the proximity to its users, and examine possible niches that such reactors could fill in future energy systems. To further research and development (R and D) in the areas mentioned above and several others, and to facilitate progress in Member States in design and technology development for small reactors without on-site refueling, the IAEA has conducted a dedicated Coordinated Research Project (CRP) entitled 'Small Reactors without On-site Refuelling' (CRPi25001). The project started late in 2004 and, after a review in 2008, was extended for one more year to be ended in 2009. The project has created a network of 18 research institutions from 10 Member States, representing both developed and developing countries. Over the CRP period, collaborative results were achieved for many of the abovementioned research areas. Some studies highlighted new directions of research to be furthered after the CRP completion. Some studies remained the efforts of

  4. Inventory of sites used to develop residual radioactivity criteria

    International Nuclear Information System (INIS)

    Ronca-Battista, M.; Hardeman, J.C. Jr.

    1986-01-01

    The US Environmental Protection Agency (EPA), in conjunction with the National Conference of Radiation Control Program Directors (CRCPD), has compiled an inventory of never licensed or otherwise poorly documented sites that may be contaminated with radioactive materials. This effort is in support of the EPA's development of radiation protection criteria for residual radioactivity at decommissioned sites. The inventory will help to establish the range of circumstances for which criteria are needed, as well as the suitability of candidate criteria for actual situations. The information will also be used to develop model sites and facilities for analyzing technical and economic feasibility of residual radioactivity criteria and to assess costs and benefits of alternate criteria. Relevant information about each site, such as radionuclides, waste forms, and quantities present will be included in the inventory when such information is available. The CRCPD has requested that each State radiation control agency furnish the information for the inventory. The inventory supplements the relatively extensive documentation of sites regulated by Federal or State agencies with information on old or unlicensed sites, such as old waste storage sites or radium ore processing facilities

  5. Geological Site Descriptive Model. A strategy for the model development during site investigations

    Energy Technology Data Exchange (ETDEWEB)

    Munier, Raymond; Stenberg, Leif [Swedish Nuclear Fuel and Waste Management Co., Stockholm (Sweden); Stanfors, Roy [Roy Stanfors Consulting, Lund (Sweden); Milnes, Allan Geoffrey [GEA Consulting, Uppsala (Sweden); Hermanson, Jan [Golder Associates, Stockholm (Sweden); Triumf, Carl-Axel [Geovista, Luleaa (Sweden)

    2003-04-01

    The Swedish Nuclear Fuel and Waste Management Company (SKB) is at present conducting site investigations as a preliminary to building an underground nuclear waste disposal facility in Sweden. This report presents a methodology for constructing, visualising and presenting 3-dimensional geological models, based on data from the site investigations. The methodology integrates with the overall work-flow of the site investigations, from the collection of raw data to the complete site description, as proposed in several earlier technical reports. Further, it is specifically designed for interaction with SICADA - SKB's Site Characterisation Database - and RVS - SKB's Rock Visualisation System. This report is one in a series of strategy documents intended to demonstrate how modelling is to be performed within each discipline. However, it also has a wider purpose, since the geological site descriptive model provides the basic geometrical framework for all the other disciplines. Hence, the wider aim is to present a practical and clear methodology for the analysis and interpretation of input data for use in the construction of the geology-based 3D geometrical model. In addition to the various aspects of modelling described above, the methodology presented here should therefore also provide: guidelines and directives on how systematic interpretation and integration of geo-scientific data from the different investigation methods should be carried out; guidelines on how different geometries should be created in the geological models; guidelines on how the assignment of parameters to the different geological units in RVS should be accomplished; guidelines on the handling of uncertainty at different points in the interpretation process. In addition, it should clarify the relation between the geological model and other models used in the processes of site characterisation, repository layout and safety analysis. In particular, integration and transparency should be

  6. Geological Site Descriptive Model. A strategy for the model development during site investigations

    International Nuclear Information System (INIS)

    Munier, Raymond; Stenberg, Leif; Stanfors, Roy; Milnes, Allan Geoffrey; Hermanson, Jan; Triumf, Carl-Axel

    2003-04-01

    The Swedish Nuclear Fuel and Waste Management Company (SKB) is at present conducting site investigations as a preliminary to building an underground nuclear waste disposal facility in Sweden. This report presents a methodology for constructing, visualising and presenting 3-dimensional geological models, based on data from the site investigations. The methodology integrates with the overall work-flow of the site investigations, from the collection of raw data to the complete site description, as proposed in several earlier technical reports. Further, it is specifically designed for interaction with SICADA - SKB's Site Characterisation Database - and RVS - SKB's Rock Visualisation System. This report is one in a series of strategy documents intended to demonstrate how modelling is to be performed within each discipline. However, it also has a wider purpose, since the geological site descriptive model provides the basic geometrical framework for all the other disciplines. Hence, the wider aim is to present a practical and clear methodology for the analysis and interpretation of input data for use in the construction of the geology-based 3D geometrical model. In addition to the various aspects of modelling described above, the methodology presented here should therefore also provide: guidelines and directives on how systematic interpretation and integration of geo-scientific data from the different investigation methods should be carried out; guidelines on how different geometries should be created in the geological models; guidelines on how the assignment of parameters to the different geological units in RVS should be accomplished; guidelines on the handling of uncertainty at different points in the interpretation process. In addition, it should clarify the relation between the geological model and other models used in the processes of site characterisation, repository layout and safety analysis. In particular, integration and transparency should be promoted. The

  7. Metallic fuel design development

    International Nuclear Information System (INIS)

    Hwang, Woan; Kang, H. Y.; Lee, B. O. and others

    1999-04-01

    This report describes the R and D results of the ''Metallic Fuel Design Development'' project that performed as a part of 'Nuclear Research and Development Program' during the '97 - '98 project years. The objectives of this project are to perform the analysis of thermo-mechanical and irradiation behaviors, and preliminary conceptual design for the fuel system of the KALIMER liquid metal reactor. The following are the major results that obtained through the project. The preliminary design requirements and design criteria which are necessary in conceptual design stage, are set up. In the field of fuel pin design, the pin behavior analysis, failure probability prediction, and sensitivity analysis are performed under the operation conditions of steady-state and transient accidents. In the area of assembly duct analysis; 1) KAFACON-2D program is developed to calculate an array configuration of inner shape of assembly duct, 2) Stress-strain analysis are performed for the components of assembly such as, handling socket, mounting rail and wire wrap, 3) The BDI program is developed to analyze mechanical interaction between pin bundle and duct, 4) a vibration analysis is performed to understand flow-induced vibration of assembly duct, 5) The NUBOW-2D, which is bowing and deformation analysis code for assembly duct, is modified to be operated in KALIMER circumstance, and integrity evaluation of KALIMER core assembly is carried out using the modified NUBOW-2D and the CRAMP code in U.K., and 6) The KALIMER assembly duct is manufactured to be used in flow test. In the area of non-fuel assembly, such as control, reflector, shielding, GEM and USS, the states-of-the-arts and the major considerations in designing are evaluated, and the design concepts are derived. The preliminary design description and their design drawing of KALIMER fuel system are prepared based upon the above mentioned evaluation and analysis. The achievement of conceptual design technology on metallic fuel

  8. Design methodology for the physical protection upgrade rule requirements for fixed sites. Technical report

    International Nuclear Information System (INIS)

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

    1980-06-01

    This Design Methodology document aids the licensee in understanding how the fixed site requirements of the Physical Protection Upgrade Rule affect the design of physical protection systems for fuel processing plants, fuel manufacturing plants, or other fixed site special nuclear material operations involving possession or use of formula quantities of strategic special nuclear material. The document consists of three major elements: Logic Trees, Safeguards Jobs and Component Matrices, and Effectiveness Test Questionnaires. The work is based upon a previous study conducted by Sandia Laboratories for the Nuclear Regulatory Commission

  9. Comments and responses on the Remedial Action Plan and site design for stabilization of the Inactive Uranium Mill Tailings Site, Grand Junction, Colorado. Revision 1

    International Nuclear Information System (INIS)

    1994-01-01

    This report contains information concerning public comments and responses on the remedial action plan and site design for stabilization of the inactive uranium mill tailings site in Grand Junction, Colorado

  10. Implementing ‘Site BIM’

    DEFF Research Database (Denmark)

    Davies, Richard; Harty, Chris

    2013-01-01

    Numerous Building Information Modelling (BIM) tools are well established and potentially beneficial in certain uses. However, issues of adoption and implementation persist, particularly for on-site use of BIM tools in the construction phase. We describe an empirical case-study of the implementation...... of an innovative ‘Site BIM’ system on a major hospital construction project. The main contractor on the project developed BIM-enabled tools to allow site workers using mobile tablet personal computers to access design information and to capture work quality and progress data on-site. Accounts show that ‘Site BIM...

  11. Sampling design and procedures for fixed surface-water sites in the Georgia-Florida coastal plain study unit, 1993

    Science.gov (United States)

    Hatzell, H.H.; Oaksford, E.T.; Asbury, C.E.

    1995-01-01

    The implementation of design guidelines for the National Water-Quality Assessment (NAWQA) Program has resulted in the development of new sampling procedures and the modification of existing procedures commonly used in the Water Resources Division of the U.S. Geological Survey. The Georgia-Florida Coastal Plain (GAFL) study unit began the intensive data collection phase of the program in October 1992. This report documents the implementation of the NAWQA guidelines by describing the sampling design and procedures for collecting surface-water samples in the GAFL study unit in 1993. This documentation is provided for agencies that use water-quality data and for future study units that will be entering the intensive phase of data collection. The sampling design is intended to account for large- and small-scale spatial variations, and temporal variations in water quality for the study area. Nine fixed sites were selected in drainage basins of different sizes and different land-use characteristics located in different land-resource provinces. Each of the nine fixed sites was sampled regularly for a combination of six constituent groups composed of physical and chemical constituents: field measurements, major ions and metals, nutrients, organic carbon, pesticides, and suspended sediments. Some sites were also sampled during high-flow conditions and storm events. Discussion of the sampling procedure is divided into three phases: sample collection, sample splitting, and sample processing. A cone splitter was used to split water samples for the analysis of the sampling constituent groups except organic carbon from approximately nine liters of stream water collected at four fixed sites that were sampled intensively. An example of the sample splitting schemes designed to provide the sample volumes required for each sample constituent group is described in detail. Information about onsite sample processing has been organized into a flowchart that describes a pathway for each of

  12. Using Collaborative Technology in CS Education to facilitate Cross-Site Software Development

    Directory of Open Access Journals (Sweden)

    Marie Devlin

    2008-12-01

    Full Text Available With offshore computing becoming more prevalent, it is essential that we increase our students' employability by providing new and relevant experiences in software development and project management; giving them valuable skills that are essential in an ever-increasing and changing global market. What is new about the work we discuss here is how collaborative technologies have facilitated a year-long cross-site software engineering project between Durham University and Newcastle University students. Our use of various collaboration technologies such as online discussion forums, video-conferencing, company repositories, version control software etc., as part of the collaborative team project has not only encouraged students to develop technical 'transferable' skills but also gain an understanding, through realistic experiences, of how the use of these technologies involves more than just learning their technical aspects and operation, but that it is essential to develop and implement the soft processes and skills required to use them successfully and effectively and hence optimize their cross-site working partnerships and productivity. In this paper we describe the project, the technologies employed by the student teams and the results and anecdotal evidence of staff and students that show the successes and, it must be admitted, occasional failures of this work. We discuss how we have tried to manage the expectations of the students throughout the project, how the technologies we have provided have affected the students' experience of cross-site collaboration and the impact of crosssite collaboration on our assessment strategies and curriculum design.

  13. Methodology applied in Cuba for siting, designing, and building a radioactive waste repository under safety conditions

    International Nuclear Information System (INIS)

    Orbera, L.; Peralta, J.L.; Franklin, R.; Gil, R.; Chales, G.; Rodriguez, A.

    1993-01-01

    The work presents the methodology used in Cuba for siting, designing, and building a radioactive waste repository safely. This methodology covers both the technical and socio-economic factors, as well as those of design and construction so as to have a safe siting for this kind of repository under Cuba especial condition. Applying this methodology will results in a safe repository

  14. Development of a low level radioactive waste disposal site in Texas - 1994 status

    International Nuclear Information System (INIS)

    Jacobi, L.R. Jr.

    1995-01-01

    The Texas Low Level Radioactive Waste Disposal Authority, an agency of the State of Texas, has been trying to develop a site for the disposal of low level radioactive waste in Texas for over ten years. Since 1991, the agency has been evaluating a site near Sierra Blanca, in far west Texas. Site characterization has been completed and a license application has been filed with the Texas Natural Resource Conservation Commission. Construction plans were completed in 1993, and the agency is prepared to begin construction and operations as soon as a license can be issued. Development costs for the site are borne by the utility companies and other major generators in Texas through the assessment of a planning and implementation fee. Total costs to date are approximately $26 million. As the project moves toward completion, state and national anti-nuclear activist groups have become more involved in attempts to thwart the Texas government's effort to solve the radioactive waste problem. To counter this increased opposition, the Texas utility companies and medical radioactive waste generators have also become more active in responding to these groups. This has been very helpful and is in keeping with the elements of building block 12 of the Nuclear Power Oversight Committee's Strategic Plan for Building New Nuclear Power Plants. This paper and poster session look at the schedule, design, and long term prospects for ultimate success of the project

  15. Development of a mixed waste management facility at the Nevada Test Site

    International Nuclear Information System (INIS)

    Dolenc, M.R.; Kendall, E.W.

    1989-01-01

    The US Department of Energy (DOE) produces some radioactive low-level wastes (LLW) which contain hazardous components. By definition, the management of those mixed wastes (MW) at the Nevada Test Site (NTS) requires compliance with US Environmental Protection Agency (EPA) and state of Nevada regulations for hazardous wastes, and DOE regulations for LLW. Preparations for operation of a separate Mixed Waste Management Unit (MWMU) in the 1990s are underway. The 167-acre MWMU will be a part of the 732-acre Area 5 Radioactive Waste Management Site (RWMS). The MWMU is being developed in response to a DOE Office of Defense Waste and Transporation Management need to provide enhanced capabilities and facilities for safe, secure, and efficient disposal of defense-related MW in accordance with DOE, EPA, and state of Nevada requirements. Planned activities relating to the development of the MWMU include completing National Environmental Policy Act (NEPA) requirements; responding to any notices of deficiencies (NODs) on the NTS Part B Permit application; conducting generator audits as part of the NTS MW certification program; optimizing the design and operation of the vadose zone monitoring system; developing protocols for the sampling and analysis of MW, and facility construction. This paper describes the permitting and regulatory environment, the specific application of the permit process to the NTS, and the phased development of an MWMU at the NTS

  16. Seismic site evaluation practice and seismic design guide for NPP in Continent of China

    Energy Technology Data Exchange (ETDEWEB)

    Yuxian, Hu [State Seismological Bureau, Beijing, BJ (China). Inst. of Geophysics

    1997-03-01

    Energy resources, seismicity, NPP and related regulations of the Continent of China are briefly introduced in the beginning and two codes related to the seismic design of NPP, one on siting and another on design, are discussed in some detail. The one on siting is an official code of the State Seismological Bureau, which specifies the seismic safety evaluation requirements of various kinds of structures, from the most critic and important structures such as NPP to ordinary buildings, and including also engineering works in big cities. The one on seismic design of NPP is a draft subjected to publication now, which will be an official national code. The first one is somewhat unique but the second one is quite similar to those in the world. (author)

  17. Seismic site evaluation practice and seismic design guide for NPP in Continent of China

    International Nuclear Information System (INIS)

    Hu Yuxian

    1997-01-01

    Energy resources, seismicity, NPP and related regulations of the Continent of China are briefly introduced in the beginning and two codes related to the seismic design of NPP, one on siting and another on design, are discussed in some detail. The one on siting is an official code of the State Seismological Bureau, which specifies the seismic safety evaluation requirements of various kinds of structures, from the most critic and important structures such as NPP to ordinary buildings, and including also engineering works in big cities. The one on seismic design of NPP is a draft subjected to publication now, which will be an official national code. The first one is somewhat unique but the second one is quite similar to those in the world. (author)

  18. Geothermal energy in Washington: site data base and development status

    Energy Technology Data Exchange (ETDEWEB)

    Bloomquist, R.G.

    1979-04-01

    This is an attempt to identify the factors which have affected and will continue to affect geothermal assessment and development in the state. The eight potential sites chosen for detailed analysis include: Indian Heaven KGRA, Mount St. Helens KGRA, Kennedy Hot Springs KGRA, Mount Adams PGRA (Potential Geothermal Resource Area), Mount Rainier PGRA, Mount Baker PGRA, Olympic-Sol Duc Hot Springs, and Yakima. The following information is included for each site: site data, site location and physical description, geological/geophysical description, reservoir characteristics, land ownership and leasing, geothermal development status, institutional characteristics, environmental factors, transportation and utilities, and population. A number of serious impediments to geothermal development were identified which can be solved only by legislative action at the state or federal level and/or changes in attitudes by regulatory agencies. (MHR)

  19. Subsoil exploration of the estimated building site for nuclear fuel development and fabrication facility

    Energy Technology Data Exchange (ETDEWEB)

    Song, In Taek [Korea Atomic Energy Research Institute, Taejeon (Korea)

    2000-01-01

    The objective of this report, as the result of subsoil exploration, is to provide basic design data of structural plan for nuclear fuel development and fabrication facility that is builded on Duckjin 150, Yusong, Taejeon, Korea, and provide basic data for execution of work. The soft rock level of estimated building site is deep(18.0m:BH-1, 20.5m:BH-2, 25.5m:BH-3) and the hard rock level of it is very deep (33.0m:BH-1, 46.0m:BH-2, 34.5m:BH-3) , for structural design, the hard rock shall be the bottom of foundation. 9 figs., 19 tabs. (Author)

  20. Aerosol measurements at the Southern Great Plains Site: Design and surface installation

    Energy Technology Data Exchange (ETDEWEB)

    Leifer, R.; Knuth, R.H.; Guggenheim, S.F.; Albert, B. [Department of Energy, New York, NY (United States)

    1996-04-01

    To impropve the predictive capabilities of the Atmospheric Radiation Measurements (ARM) program radiation models, measurements of awserosol size distributions, condensation particle concentrations, aerosol scattering coefficients at a number of wavelenghts, and the aerosol absorption coefficients are needed at the Southern Great Plains (SGP) site. Alos, continuous measurements of ozone concnetrations are needed for model validation. The environmental Measuremenr Laboratory (EMK) has the responsibility to establish the surface aerosol measurements program at the SGP site. EML has designed a special sampling manifold.

  1. Development of site index curves for Pinus kesiya in the Philippines ...

    African Journals Online (AJOL)

    Development of site index curves for Pinus kesiya in the Philippines. RIC Lumbres, YJ Lee, YO Seo, FG Calora JR. Abstract. This study was conducted to develop a height–age growth model and site index curves for site quality evaluation of old secondary-growth stands of Pinus kesiya in the northern Philippines.

  2. Metallic fuel design development

    Energy Technology Data Exchange (ETDEWEB)

    Hwang, Woan; Kang, H. Y.; Lee, B. O. and others

    1999-04-01

    This report describes the R and D results of the ''Metallic Fuel Design Development'' project that performed as a part of 'Nuclear Research and Development Program' during the '97 - '98 project years. The objectives of this project are to perform the analysis of thermo-mechanical and irradiation behaviors, and preliminary conceptual design for the fuel system of the KALIMER liquid metal reactor. The following are the major results that obtained through the project. The preliminary design requirements and design criteria which are necessary in conceptual design stage, are set up. In the field of fuel pin design, the pin behavior analysis, failure probability prediction, and sensitivity analysis are performed under the operation conditions of steady-state and transient accidents. In the area of assembly duct analysis; 1) KAFACON-2D program is developed to calculate an array configuration of inner shape of assembly duct, 2) Stress-strain analysis are performed for the components of assembly such as, handling socket, mounting rail and wire wrap, 3) The BDI program is developed to analyze mechanical interaction between pin bundle and duct, 4) a vibration analysis is performed to understand flow-induced vibration of assembly duct, 5) The NUBOW-2D, which is bowing and deformation analysis code for assembly duct, is modified to be operated in KALIMER circumstance, and integrity evaluation of KALIMER core assembly is carried out using the modified NUBOW-2D and the CRAMP code in U.K., and 6) The KALIMER assembly duct is manufactured to be used in flow test. In the area of non-fuel assembly, such as control, reflector, shielding, GEM and USS, the states-of-the-arts and the major considerations in designing are evaluated, and the design concepts are derived. The preliminary design description and their design drawing of KALIMER fuel system are prepared based upon the above mentioned evaluation and analysis. The achievement of conceptual

  3. Study of site layout in the Rokkasho site

    International Nuclear Information System (INIS)

    Sato, Kazuyoshi; Tamura, Kousaku; Yagenji, Akira; Sekiya, Shigeki; Takahashi, Hideo; Neyatani, Yuzuru; Uehara, Masaharu; Motohashi, Keiichi; Hashimoto, Masayoshi; Ogino, Shunji; Nagamatsu, Nobuhide

    2006-03-01

    The Final Design Report (FDR) of the International Thermonuclear Experimental Reactor (ITER) was published on July 2001 as a summary of the Engineering Design Activity (EDA). After the EDA, site dependent design has been investigated for the invitation of ITER toward Rokkasho Site (Iyasakadai area) in Aomori prefecture. This report describes the results of site layout of major buildings and structures of ITER in the Rokkasho-Site. The data of the ground near the site and the results of site dependent design in Japan were applied to this study. Through this study, the most appropriate site layout has been constructed with satisfaction of following conditions. (1) Bedrock level at the tokamak complex building is relatively high and it can be reduced the cost of excavation and foundation work. (2) Total amount of excavation soil for site preparation is minimized and the flexibility of the layout is ensured with flat ground level. (3) Accessibility of human and equipments, reduction of noise and vibration to the environment can be obtained. Total length of ducts and piping between buildings in site is minimized. (author)

  4. Design criteria development for the structural stability of nuclear waste repository

    Energy Technology Data Exchange (ETDEWEB)

    Yun, C H [Korea Institute of Nuclear Safety, Taejon (Korea, Republic of); Yu, T S [Daewoo Engineering Company, Sungnam (Korea, Republic of); Ko, H M [Seoul National Univ., Seoul (Korea, Republic of)

    1990-11-15

    The objective of the present project is to develop design criteria for the structural stability of rock cavity for the underground repository are defined, according to which detailed descriptions for design methodologies, design stages and stability analysis of the cavity are made. The proposed criteria can be used as a guide for the preparation of design codes which are to be established as the site condition and technical emplacement procedure are fixed. The present report first reviews basic safety requirements and criteria of the underground disposal of nuclear wastes for the establishment of design concepts and stability analysis of the rock cavity. Important factors for the design are also described by considering characteristics of the wastes and underground facilities. The present project has investigated technical aspects on the design of underground structures based on the currently established underground construction technologies, and presented a proposal for design criteria for the structural stability of the nuclear waste repository. The proposed criteria consist of general provisions, geological exploration, rock classification, design process and methods, supporting system, analyses and instrumentation.

  5. Remedial Action Plan and site design for stabilization of the inactive uranium mill tailings site at Falls City, Texas

    International Nuclear Information System (INIS)

    Chernoff, A.R.; Lacker, D.K.

    1992-09-01

    The uranium processing site near Falls City, Texas, was one of 24 inactive uranium mill sites designated to be remediated by the US Department of Energy (DOE) under Title I of the Uranium Mill Tailings Radiation Control Act of 1978 (UMTRCA). The UMTRCA requires that the US Nuclear Regulatory Commission (NRC) concur with the DOE's remedial action plan (RAP) and certify that the remedial action conducted at the site complies with the standards promulgated by the US Environmental Protection Agency (EPA). The RAP, which includes this summary remedial action selection report (RAS), serves a two-fold purpose. First, it describes the activities proposed by the DOE to accomplish long-term stabilization and control of the residual radioactive materials at the inactive uranium processing site near Falls City, Texas. Second, this document and the remainder of the RAP, upon concurrence and execution by the DOE, the State of Texas, and the NRC, becomes Appendix B of the Cooperative Agreement between the DOE and the State of Texas

  6. Remedial Action Plan and site design for stabilization of the inactive uranium mill tailings site at Gunnison, Colorado

    International Nuclear Information System (INIS)

    1992-10-01

    Diffusion coefficients for radon gas in earthen materials are required to design suitable radon-barrier covers for uranium tailings impoundments and other materials that emit radon gas. Many early measurements of radon diffusion coefficients relied on the differences in steady-state radon fluxes measured from radon source before and after installation of a cover layer of the material being tested. More recent measurements have utilized the small-sample transient (SST) technique for greater control on moistures and densities of the test soils, greater measurement precision, and reduced testing time and costs. Several of the project sites for the US Department of Energy's Uranium Mill Tailings Remedial Action (UMTRA) Program contain radiologically contaminated subsurface material composed predominantly of cobbles, gravels andsands. Since remedial action designs require radon diffusion coefficients for the source materials as well as the cover materials, these cobbly and gravelly materials also must be tested. This report contains the following information: a description of the test materials used and the methods developed to conduct the SST radon diffusion measurements on cobbly soils; the protocol for conducting radon diffusion tests oncobbly soils; the results of measurements on the test samples; and modifications to the FITS computer code for analyzing the time-dependent radon diffusion data

  7. GEOTECHNICAL DESIGN OF SOLID WASTE LANDFILL SITES

    Directory of Open Access Journals (Sweden)

    Suat AKBULUT

    2003-02-01

    Full Text Available Solid waste landfills are important engineering structures for protection of wastes, decrease of environmental pollution, and especially prevention of soil and water pollution. Solid wastes should conveniently be maintained in landfill areas to control environmental pollution caused by waste disposals. Until the middle of this century clay liners were used for maintenance of waste disposal, but it was observed that these liner systems were insufficient. Today thinner and less permeable liner systems are constructed by using synthetic materials. In this study, by evaluating the waste landfills, site assessment of landfills and construction of natural and synthetic liner systems were summarized respectively, and especially the design properties of these systems were examined intensively. Also, leachate collection and removal facilities, landfill gas collection unites, and final cover unites were evaluated in a detailed way.

  8. Development of emergency response training program for on-site commanders (1)

    International Nuclear Information System (INIS)

    Hikono, Masaru; Matsui, Yuko; Kanayama, Masaki

    2017-01-01

    Since the Great East Japan Earthquake of 2011, there have been increasing calls for developing the leadership capabilities of managers who are in charge of command and control of the on-site emergency response center at nuclear power plants. Training programs to improve non-technical skills are being developed and introduced. The authors developed an active learning exercise that can be repeatedly performed on-site, targeting on-site commander teams in charge of the initial response in an emergency situation. The exercise forms the core element of a non-technical skills training curriculum. This paper outlines the developed exercise, evaluates the stress on the participants caused by the exercise, and identifies any issues before actually introducing it to a site. (author)

  9. Multi-Site Project Management A Program for Reducing the Cost of Technology Deployment at Department of Energy Sites

    International Nuclear Information System (INIS)

    Davis, N.R.; Selden, E.R.; Little, D.B.; Coleman, M.C.; Bennett, J.T.

    2009-01-01

    Retrieval and processing of High Level Waste (HLW) stored in Department of Energy (DOE) waste tanks is performed to support closure of the tanks as required by site specific regulatory agreements. Currently, there are four sites in the DOE Complex that have HLW tanks and must process and disposition HLW. As such, there is an opportunity to achieve an economy of scale and reduce duplication of efforts. Two or more sites typically have similar technology development and deployment needs. Technology development is already executed at the national level. As the technology is matured, the next step is to commission a design/build project. Typically each site performs this separately due to differences in waste type, tank design, site specific considerations such as proximity to the water table or to the site boundary. The focus of the individual sites tends to be on the differences between sites versus on the similarities thus there is an opportunity to minimize the cost for similar deployments. A team of engineers and project management professionals from the Savannah River Site has evaluated technology needs at the four HLW sites and determined that there is an economy of scale that can be achieved by specific technology deployments in the area of waste retrieval, waste pretreatment and waste disposition. As an example, the Waste on Wheels tank retrieval system (presented in the 2006 Waste Management Symposium) was designed and fabricated in portable modules that could be installed in HLW tanks at Hanford, Savannah River or Idaho. This same concept could be used for modular in-tank cesium removal process and equipment, tank cleaning mechanical equipment, and chemical tank cleaning process and equipment. The purpose of this paper is to present a multi-site project management approach that will reduce deployment costs and be consistent with DOE Order 413.3 project management principles. The approach will describe how projects can be managed by a lead site with

  10. Risk assessment data bank design at the Savannah River Site

    International Nuclear Information System (INIS)

    Townsend, C.S.; Johnson, K.B.

    1992-01-01

    The Savannah River Site has designed and implemented a database system containing a series of compilations of incidents used primarily for risk assessment. Four databases have been designed and implemented using advanced database management system computer software. These databases exist for reprocessing, fuel fabrication, waste management, and the Savannah River Technology Center. They are combined into one system caged the Risk Assessment Methodology (RAM) Fault Tree Data Banks. This paper will discuss the logical design of the data, the menus, and the operating platform. Built-in updating features, such as batch and on-line data entry; data validation methods; automatic update features; and expert system programs, will also be discussed. User functions, such as on-line search/view/report and statistical functions, will be presented. Security features and backup and recovery methods will also be covered

  11. The Clinch Bend Regional Industrial Site and economic development opportunities

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-12-31

    This effort focuses initially on the Clinch Bend site. Other sites and developable tracts of land are identified with the assistance of communities in proximity to Oak Ridge, the State of Tennessee, and others, and compared with the projected site requirements for large industrial facilities.

  12. Development of the web-based site investigation flow diagram in repository development program

    International Nuclear Information System (INIS)

    Yamamoto, Shuichi; Yoshimura, Kimitaka; Ohuchi, Jin; Tsuboya, Takao; Ando, Kenichi

    2005-01-01

    In siting a repository for high level radioactive wastes (HLW), it is essential for consensus building intelligibly and visually present why and how the area is selected as a suitable site. However 'information asymmetry' exists especially between society and an implementation body because various types of investigation, analysis and assessment are implemented in site characterization on the basis of a wide variety of advanced science and technology. Communication between experts (e.g. surveyors and modelers) is also important for efficient and reliable site investigation/ characterization. The Web-based Site Investigation Flow Diagram (SIFD) has been developed as a tool for information sharing among stake holders and society-jointed decision making. To test applicability of the SIFD, virtual site characterization ('dry run') is performed using the existing site investigation data. It is concluded that the web-based SIFD enhance traceability and transparency of the site investigation/ characterization, and therefore it would be a powerful communication tool among experts for efficient and reliable site investigation/characterization and among stake holders for consensus building

  13. Design and Construction of Deinococcus Radiodurans for Biodegradation of Organic Toxins at Radioactive DOE Waste Sites

    International Nuclear Information System (INIS)

    Daly, Michael J.; Wackett, Lawrence P.; Fredrickson, James K.

    2001-01-01

    Seventy million cubic meters of ground and three trillion liters of groundwater have been contaminated by leaking radioactive waste generated in the United States during the Cold War. A cleanup technology is being developed based on the extremely radiation resistant bacterium Deinococcus radiodurans that is being engineered to express bioremediating functions. Research aimed at developing D. radiodurans for organic toxin degradation in highly radioactive waste sites containing radionuclides, heavy metals, and toxic organic compounds was started by this group.Work funded by the existing grant has already contributed to eleven papers on the fundamental biology of D. radiodurans and its design for bioremediation of highly radioactive waste environments

  14. Development of corrective measures and site stabilization technologies for shallow land burial facilities at semiarid sites

    International Nuclear Information System (INIS)

    Nyhan, J.W.; Abeele, W.V.

    1986-01-01

    The overall purpose of the corrective measures task performed for the National Low-Level Waste Management Program has been to develop and test methods that can be used to correct any actual or anticipated problems with new and existing shallow land burial (SLB) sites in a semiarid environment. These field tests have not only evaluated remedial actions, but have also investigated phenomena suspected of being a possible problem at semiarid SLB sites. The approach we have taken in developing remedial action and site closure technologies for low-level waste sites is to recognize that physical and biological processes affecting site integrity are interdependent, and therefore, cannot be treated as separate problems. The field experiments performed for this task were to identify, evaluate, and model erosion control technologies, field test second generation biointrusion barriers, determine by field experiments the extent of upward radionuclide migration due to moisture cycling, and measure the effects of subsidence on remedial action of other system components. Progress made in each of these research areas is described

  15. Radiation Protection training WEB site to hold pedagogical material for developing courses a distance way

    International Nuclear Information System (INIS)

    Marco, M.; Rodriguez, M.; Hernando, E.; Falcon, S.; Rodriguez, M.; Villarroel, R.

    2003-01-01

    Radiation Protection Training (RPT) System in Spain are is well defined in the local local regulations related to radioactive facilities licensing and radiation protection. A system of personnel licenses is established considering two levels of required radiation protection training-supervisor and operator according to responsibilities assigned during the operation of the radioactive facilities. This paper present the major advances already done in the educational web site maintained on the CIEMAT server and accessible through the CSN web. The project includes training material for sixteen applied courses and the design of a educational web site to hold pedagogical material for developing distant learning courses. The main objective of this project is to provide training materials for course organisers, trainers and for professional participants and to promote the exchange of expertise between workers involved in all activities using radiation sources. The project also aims to provide necessary mechanism for standardisation of the radiation protection knowledge made available to the exposed workers, including theoretical and practical training. The developed training material included in the project will cover all uses of radioactive sources including medical diagnosis. The web site is being developed of provide educational material on a modular design and in Spanish. The paper presents the initial results of this useful tool for practitioners. Courses are based on core modules with basic and specific modules involving different targets groups, and the contents can be easily adapted for other target groups. For each one of the modules should be included in the web site: objectives, syllabus, lessons and practical sessions, demo and lab exercises, etc. The project includes training tools for sixteen courses based in the standard syllabus content in the Spanish legal framework. In the next future complete materials for trainers will be available to case courses

  16. Long-Term Climate Change Assessment Task for the Hanford Site Permanent Isolation Barrier Development Program: Status through FY 1992

    International Nuclear Information System (INIS)

    Petersen, K.L.; Chatters, J.C.

    1993-07-01

    The Hanford Site Permanent Isolation Barrier Development Program (Barrier Development Program) was organized (Adams and Wing 1986) to develop the technology needed to provide an in-place disposal capability for the US Department of Energy at the Hanford Site in southeastern Washington. The goals of the Barrier Development Program are to provide defensible evidence that final barrier design(s) will adequately control water infiltration, plant and animal intrusion, and wind and water erosion for a minimum of 1,000 years; to isolate wastes from the accessible environment; and to use markers to warn inadvertent human intruders. Evidence for barrier performance will be obtained by conducting laboratory experiments, field tests, computer modeling, and other studies that establish confidence in the barrier's ability to meet its 1,000-year design life. The performance and stability of natural barrier analogs that have existed for several millennia and the reconstruction of climate changes during the past 10,000 to 125,000 years also will provide insight into bounding conditions of possible future changes and increase confidence in the barriers design. In the following discussion the term open-quotes long-termclose quotes references periods of time up to 1000's of years, distinguishing it from open-quotes short-termclose quotes weather patterns covering a decade or less. Specific activities focus on planning and conducting a series of studies and tests required to confirm key aspects of the barrier design. The effort is a collaborative one between scientists and engineers from Westinghouse Hanford Company (Westinghouse Hanford) and Pacific Northwest Laboratory (PNL) to design barriers to limit movement of radionuclides and other contaminants to the accessible environment for at least 1,000 years. These activities have been divided into 14 groups of tasks that aid in the complete development of protective barrier and warning marker system

  17. Long-Term Climate Change Assessment Task for the Hanford Site Permanent Isolation Barrier Development Program: Status through FY 1992

    Energy Technology Data Exchange (ETDEWEB)

    Petersen, K.L. [Westinghouse Hanford Co., Richland, WA (US); Chatters, J.C. [Pacific Northwest Lab., Richland, WA (US)

    1993-07-01

    The Hanford Site Permanent Isolation Barrier Development Program (Barrier Development Program) was organized (Adams and Wing 1986) to develop the technology needed to provide an in-place disposal capability for the US Department of Energy at the Hanford Site in southeastern Washington. The goals of the Barrier Development Program are to provide defensible evidence that final barrier design(s) will adequately control water infiltration, plant and animal intrusion, and wind and water erosion for a minimum of 1,000 years; to isolate wastes from the accessible environment; and to use markers to warn inadvertent human intruders. Evidence for barrier performance will be obtained by conducting laboratory experiments, field tests, computer modeling, and other studies that establish confidence in the barrier`s ability to meet its 1,000-year design life. The performance and stability of natural barrier analogs that have existed for several millennia and the reconstruction of climate changes during the past 10,000 to 125,000 years also will provide insight into bounding conditions of possible future changes and increase confidence in the barriers design. In the following discussion the term {open_quotes}long-term{close_quotes} references periods of time up to 1000`s of years, distinguishing it from {open_quotes}short-term{close_quotes} weather patterns covering a decade or less. Specific activities focus on planning and conducting a series of studies and tests required to confirm key aspects of the barrier design. The effort is a collaborative one between scientists and engineers from Westinghouse Hanford Company (Westinghouse Hanford) and Pacific Northwest Laboratory (PNL) to design barriers to limit movement of radionuclides and other contaminants to the accessible environment for at least 1,000 years. These activities have been divided into 14 groups of tasks that aid in the complete development of protective barrier and warning marker system.

  18. Highlights of the SSC Site Development Plan

    International Nuclear Information System (INIS)

    Sanford, J.R.

    1991-10-01

    This paper summarizes highlights of the Site Development Plan for the Superconducting Super Collider Laboratory. The Plan, sometimes called a Master Plan, was prepared by the architectural and engineering firm for the Laboratory: Parsons Brinckerhoff/Morrison Knudsen (PB/MK) working in association with CRSS. Their task was to interpret the SSC project needs in the context of the Ellis County, Texas site. The team effort was under the direction of Lewis May from CRSS, guided by Robert Sims from the SSC Laboratory. Conceptual drawings are presented in this report

  19. Site selection handbook: Workshop on site selection for low-level radioactive waste disposal facilities

    International Nuclear Information System (INIS)

    1987-10-01

    The Low-Level Radioactive Waste Policy Amendments Act of 1985 (LLRWPAA) requires the Department of Energy (DOE) to provide technical assistance to ''...those compact regions, host States and nonmember States determined by the Secretary to require assistance.'' Technical assistance has been defined to include, but not be limited to, ''technical guidelines for site selection.'' This site selection workshop was developed to assist States and Compacts in developing new low-level radioactive waste (LLW) disposal sites in accordance with the requirements of the LLRWPAA. The workshop comprises a series of lectures, discussion topics, and exercises, supported by this Site Selection Workshop Handbook, designed to examine various aspects of a comprehensive site selection program. It is not an exhaustive treatment of all aspects of site selection, nor is it prescriptive. The workshop focuses on the major elements of site selection and the tools that can be used to implement the site selection program

  20. Mock Site Licensing Demonstration Project. Final report

    International Nuclear Information System (INIS)

    Roop, R.D.

    1986-06-01

    The Mock Site Licensing Demonstration Project developed the Low-Level Radioactive Waste Siting Simulation, a role-playing exercise designed to facilitate the process of siting and licensing disposal facilities for low-level waste (LLW). This report describes the development, contant, and usefulness of the siting simulation. The simulation was designed by Harvard University's Program on Negotiation; it can be conducted at a workshop or conference, involves 14 or more participants, and requires about eight hours to complete. The simulation consists of two sessions. In the first, participants negotiate the selection of siting criteria, and in the second, a preferred site for a facility is chosen from three candidate sites. The project sponsored two workshops (in Boston, Massachusetts and Richmond, Virginia) in which the simulation was conducted for persons involved in planning for LLW. It is concluded that the siting simulation can be useful in three ways: (1) as a tool for information dissemination, (2) as a vehicle that can foste communication among parties in conflict, and (3) as a step toward consensus building and conflict resolution. The DOE National Low-Level Waste Management Program is now making the siting simulation available for use by states, regional compacts, and other organizations involved in development of LLW disposal facilities

  1. AECL strategy for surface-based investigations of potential disposal sites and the development of a geosphere model for a site

    International Nuclear Information System (INIS)

    Whitaker, S.H.; Brown, A.; Davison, C.C.; Gascoyne, M.; Lodha, G.S.; Stevenson, D.R.; Thorne, G.A.; Tomsons, D.

    1994-05-01

    The objective of this report is to summarize AECL's strategy for surface-based geotechnical site investigations used in screening and evaluating candidate areas and candidate sites for a nuclear fuel waste repository and for the development of geosphere models of sites. The report is one of several prepared by national nuclear fuel waste management programs for the Swedish Nuclear Fuel and Waste Management Co. (SKB) to provide international background on site investigations for SKB's R and D programme on siting.The scope of the report is limited to surface-based investigations of the geosphere, those done at surface or in boreholes drilled from surface. The report discusses AECL's investigation strategy and the methods proposed for use in surface-based reconnaissance and detailed site investigations at potential repository sites. Site investigations done for AECL's Underground Research Laboratory are used to illustrate the approach. The report also discusses AECL's strategy for developing conceptual and mathematical models of geological conditions at sites and the use of these models in developing a model (Geosphere Model) for use in assessing the performance of the disposal system after a repository is closed. Models based on the site data obtained at the URL are used to illustrate the approach. Finally, the report summarizes the lessons learned from AECL's R and D program on site investigations and mentions some recent developments in the R and D program. 120 refs, 33 figs, 7 tabs

  2. AECL strategy for surface-based investigations of potential disposal sites and the development of a geosphere model for a site

    Energy Technology Data Exchange (ETDEWEB)

    Whitaker, S H; Brown, A; Davison, C C; Gascoyne, M; Lodha, G S; Stevenson, D R; Thorne, G A; Tomsons, D [AECL Research, Whiteshell Labs., Pinawa, MB (Canada)

    1994-05-01

    The objective of this report is to summarize AECL`s strategy for surface-based geotechnical site investigations used in screening and evaluating candidate areas and candidate sites for a nuclear fuel waste repository and for the development of geosphere models of sites. The report is one of several prepared by national nuclear fuel waste management programs for the Swedish Nuclear Fuel and Waste Management Co. (SKB) to provide international background on site investigations for SKB`s R and D programme on siting.The scope of the report is limited to surface-based investigations of the geosphere, those done at surface or in boreholes drilled from surface. The report discusses AECL`s investigation strategy and the methods proposed for use in surface-based reconnaissance and detailed site investigations at potential repository sites. Site investigations done for AECL`s Underground Research Laboratory are used to illustrate the approach. The report also discusses AECL`s strategy for developing conceptual and mathematical models of geological conditions at sites and the use of these models in developing a model (Geosphere Model) for use in assessing the performance of the disposal system after a repository is closed. Models based on the site data obtained at the URL are used to illustrate the approach. Finally, the report summarizes the lessons learned from AECL`s R and D program on site investigations and mentions some recent developments in the R and D program. 120 refs, 33 figs, 7 tabs.

  3. Site characterization plan conceptual design report for a high-level nuclear waste repository in salt, horizontal emplacement mode: Volume 2

    International Nuclear Information System (INIS)

    1987-12-01

    Chapter 6 discusses the repository design features and operating procedures that will be used to ensure compliance with regulatory limits for preclosure releases, performance objectives for waste retrieval, and performance objectives for post closure or long-term waste isolation. Chapter 7 discusses the analyses that were conducted in developing the repository design and the impacts of various external factors on the design of repository elements and the repository as a whole. These discussions are divided into preclosure design analysis, post closure design analysis, and engineering analysis of design. Also discussed are the structures, systems, and components that have been identified as important to safety and the barriers that have been, or need to be, identified as important to waste isolation. Chapter 8 discusses the engineering design information needs that were identified during conceptual design as necessary to advance the current conceptual design to Licence Application Design. These information needs should be resolved during the site characterization program or by other technology development studies. The discussion of these design issues and data needs is arranged according to the major elements of the repository. Chapter describes the quality assurance program. 146 refs., 40 figs., 22 tabs

  4. Evaluation of E-Learning Web Sites Using Fuzzy Axiomatic Design Based Approach

    Directory of Open Access Journals (Sweden)

    2010-04-01

    Full Text Available High quality web site has been generally recognized as a critical enabler to conduct online business. Numerous studies exist in the literature to measure the business performance in relation to web site quality. In this paper, an axiomatic design based approach for fuzzy group decision making is adopted to evaluate the quality of e-learning web sites. Another multi-criteria decision making technique, namely fuzzy TOPSIS, is applied in order to validate the outcome. The methodology proposed in this paper has the advantage of incorporating requirements and enabling reductions in the problem size, as compared to fuzzy TOPSIS. A case study focusing on Turkish e-learning websites is presented, and based on the empirical findings, managerial implications and recommendations for future research are offered.

  5. Site selection and design basis of the National Disposal Facility for LILW. Geological and engineering barriers

    International Nuclear Information System (INIS)

    Boyanov, S.

    2010-01-01

    Content of the presentation: Site selection; Characteristics of the “Radiana” site (location, geological structure, physical and mechanical properties, hydro-geological conditions); Design basis of the Disposal Facility; Migration analysis; Safety assessment approach

  6. Site development and demands on infrastructure

    International Nuclear Information System (INIS)

    Nieke, K.F.

    1976-01-01

    All sub-fields are examined which form the infrastructure, the infrastructure being indispensable for the site development of a nuclear power plant. The main emphasis is put on the technical infrastructure, but the social infrastructure is dealt with, too. The most important sub-fields are: traffic connections, energy supply, external communications, foundation, building mearures. (UA) [de

  7. Paraho oil shale module. Site development plan, Task 4

    Energy Technology Data Exchange (ETDEWEB)

    1981-10-01

    A management plan and schedule which covers all requirements for gaining access to the site and for conducting a Paraho Process demonstration program have been prepared. The oil shale available should represent a regional resource of suitable size and quality for commercial development. Discussed in this report are: proof of ownership; requirements for rights-of-way for access to the site; local zoning restrictions; water rights; site availability verification; and other legal requirements. (DMC)

  8. Development of an arid site closure plan

    International Nuclear Information System (INIS)

    Nyhan, J.W.; Barnes, F.J.

    1987-01-01

    This document describes the development of a prototype plan for the effective closure and stabilization of an arid low-level waste disposal site. This plan will provide demonstrated closure techniques for a trench in a disposal site at Los Alamos. The accuracy of modeling soil water storage by two hydrologic models, CREAMS and HELP, was tested by comparing simulation results with field measurements of soil moisture in eight experimental landfill cover systems having a range of well-defined soil profiles and vegetative covers. Regression analysis showed that CREAMS generally represented soil moisture more accurately than HELP simulations. Precautions for determining parameter values for model input and for interpreting simulation results are discussed. A specific example is presented showing how the field-validated hydrologic models can be used to develop a final prototype closure plan. 15 refs., 13 figs., 3 tabs

  9. Development of Intensity-Duration-Frequency curves at ungauged sites: risk management under changing climate

    Science.gov (United States)

    Liew, San Chuin; Raghavan, Srivatsan V.; Liong, Shie-Yui

    2014-12-01

    The impact of a changing climate is already being felt on several hydrological systems both on a regional and sub-regional scale of the globe. Southeast Asia is one of the regions strongly affected by climate change. With climate change, one of the anticipated impacts is an increase in the intensity and frequency of extreme rainfall which further increase the region's flood catastrophes, human casualties and economic loss. Optimal mitigation measures can be undertaken only when stormwater systems are designed using rainfall Intensity-Duration-Frequency (IDF) curves derived from a long and good quality rainfall data. Developing IDF curves for the future climate can be even more challenging especially for ungauged sites. The current practice to derive current climate's IDF curves for ungauged sites is, for example, to `borrow' or `interpolate' data from regions of climatologically similar characteristics. Recent measures to derive IDF curves for present climate was performed by extracting rainfall data from a high spatial resolution Regional Climate Model driven by ERA-40 reanalysis dataset. This approach has been demonstrated on an ungauged site (Java, Indonesia) and the results were quite promising. In this paper, the authors extend the application of the approach to other ungauged sites particularly in Peninsular Malaysia. The results of the study undoubtedly have significance contribution in terms of local and regional hydrology (Malaysia and Southeast Asian countries). The anticipated impacts of climate change especially increase in rainfall intensity and its frequency appreciates the derivation of future IDF curves in this study. It also provides policy makers better information on the adequacy of storm drainage design, for the current climate at the ungauged sites, and the adequacy of the existing storm drainage to cope with the impacts of climate change.

  10. The design on high slope stabilization in waste rock sites of uranium mines

    International Nuclear Information System (INIS)

    Liu Taoan; Zhou Xinghuo; Liu Jia

    2005-01-01

    Design methods, reinforcement measures, and flood control measures concerning high slope stabilization in harnessing waste rock site are described in brief according to some examples of two uranium mines in Hunan province. (authors)

  11. Development of a Lunar Scintillometer as part of the national large optical telescope site survey

    Science.gov (United States)

    Surendran, Avinash; Parihar, Padmakar S.; Banyal, Ravinder K.; Kalyaan, Anusha

    2018-03-01

    Ground layer turbulence is a very important site characterization parameter used to assess the quality of an astronomical site. The Lunar Scintillometer is a simple and effective site-testing device for measuring the ground layer turbulence. It consists of a linear array of photodiodes which are sensitive to the slight variations in the moon's brightness due to scintillation by the lower layers of the Earth's atmosphere. The covariance of intensity values between the non-redundant photodiode baselines can be used to measure the turbulence profile from the ground up to a height determined by the furthest pair of detectors. The six channel lunar scintillometer that has been developed at the Indian Institute of Astrophysics is based closely on an instrument built by the team led by Andrei Tokovinin of Cerro Tololo Inter-American Observatory (CTIO), Chile (Tokovinin et al., Mon. Not. R. Astron. Soc. 404(3), 1186-1196 2010). We have fabricated the instrument based on the existing electronic design, and have worked on the noise analysis, an EMI (Electromagnetic Induction) resistant PCB design and the software pipeline for analyzing the data from the same. The results from the instrument's multi-year campaign at Mount Saraswati, Hanle is also presented.

  12. The development of permanent isolation surface barriers: Hanford Site, Richland, Washington, U.S.A

    International Nuclear Information System (INIS)

    Wing, N.R.; Gee, G.W.

    1993-01-01

    Permanent isolation surface barriers are being developed to isolate wastes disposed of in situ (in place) at the US Department of Energy's Hanford Site in Washington State (USA). The current focus of development efforts is to design barriers that will function in a semiarid to subhumid climate, Emit infiltration and percolation of water through the waste zone to near-zero amounts, be maintenance free, and last up to 1000 years or more. A series of field tests, experiments, and lysimeter studies have been conducted for several years. The results of tests to date confirm that the Hanford barrier concepts are valid for both present and wetter climatic conditions. The data collected also have provided the foundation for the design of a large prototype barrier to be constructed later in 1993. This paper presents the results of some of the field tests, experiments, and lysimeter studies

  13. Custom-Designed Molecular Scissors for Site-Specific Manipulation of the Plant and Mammalian Genomes

    Science.gov (United States)

    Kandavelou, Karthikeyan; Chandrasegaran, Srinivasan

    Zinc finger nucleases (ZFNs) are custom-designed molecular scissors, engineered to cut at specific DNA sequences. ZFNs combine the zinc finger proteins (ZFPs) with the nonspecific cleavage domain of the FokI restriction enzyme. The DNA-binding specificity of ZFNs can be easily altered experimentally. This easy manipulation of the ZFN recognition specificity enables one to deliver a targeted double-strand break (DSB) to a genome. The targeted DSB stimulates local gene targeting by several orders of magnitude at that specific cut site via homologous recombination (HR). Thus, ZFNs have become an important experimental tool to make site-specific and permanent alterations to genomes of not only plants and mammals but also of many other organisms. Engineering of custom ZFNs involves many steps. The first step is to identify a ZFN site at or near the chosen chromosomal target within the genome to which ZFNs will bind and cut. The second step is to design and/or select various ZFP combinations that will bind to the chosen target site with high specificity and affinity. The DNA coding sequence for the designed ZFPs are then assembled by polymerase chain reaction (PCR) using oligonucleotides. The third step is to fuse the ZFP constructs to the FokI cleavage domain. The ZFNs are then expressed as proteins by using the rabbit reticulocyte in vitro transcription/translation system and the protein products assayed for their DNA cleavage specificity.

  14. Accident consequence assessment and siting criteria development

    International Nuclear Information System (INIS)

    Kollas, J.G.

    1988-01-01

    The methodology developed is based on assessing the average over a large spectrum of meteorological conditions whole body collective dose resulting from a severe reference accident. The assessment of this dose is performed by code CRAC.GAEC, the Greek A.E.C. version of code CRAC2. The collective dose, which is chosen as a measure of the social radiation risk, is compared to the dose corresponding to a level of social risk encountered historically in energy production as a whole. The outcome of the comparison can be the determination of one or more sectors of acceptable sites for a set of specific conditions considered, such as the reactor characteristics. The present approach was aimed to deal with the problems stemming from the demographic idiomorphy of Greece, where one third of the country's population is concentrated in Athens, with the rest of the country exhibiting small population densities. One of the applications of the methodology developed concerned the identification of acceptable sites near Athens. For these sites the risk from the reference severe accident of a standard reactor to the over three millions inhabitants of Athens is less tan the risk corresponding to the same population that is due to energy production

  15. Subsurface moisture regimes and tracer movement under two types of trench-cap designs for shallow land burial sites

    International Nuclear Information System (INIS)

    Perkins, B.A.; Cokal, E.J.

    1986-03-01

    The Los Alamos work has focused on proper design of shallow land burial (SLB) sites in arid and semiarid regions and on applying corrective measures to existing sites. One of the most important design features affecting the probability of movement of radionuclides in SLB sites is the type of trench cap placed over the waste. The cap influences such interdependent parameters as erosion, water infiltration and percolation, and biointrusion. To obtain experimental data for arid and semiarid sites, two different designs of trench caps, one with topsoil underlain with a cobble/gravel biobarrier and one with topsoil underlain with crushed tuff, were compared with respect to (1) seasonal changes in volumetric soil water content, and (2) downward migration of tracers emplaced directly below each type of trench cap. The causes for the large differences in concentrations found in this experiment need to be investigated further. Problems in environmental modeling and monitoring of arid and semiarid SLB sites because of heterogeneities in the soil profiles and their implications for SLB waste management need to be better understood. More work in trench-cap design and its influence on the many pathways available for mobilization is needed

  16. Developments in modelling the economic impact of Off-site accident consequences

    International Nuclear Information System (INIS)

    Haywood, S.M.; Robinson, C.A.; Faude, D.

    1991-01-01

    Models for assessing the economic consequences of accidental releases of radioactivity have application both in accident consequence codes and in decision aiding computer systems for use in emergency response. Such models may be applied in emergency planning, and studies in connection with the siting, design and licensing of nuclear facilities. Several models for predicting economic impact have been developed, in Europe and the US, and these are reviewed. A new model, called COCO-1 (Cost of Consequences Off-site), has been developed under the CEC MARIA programme and the features of the model are summarised. The costs calculated are a measure of the benefit foregone as a result of the accident, and in addition to tangible monetary costs the model attempts to include costs arising from the effect of the accident on individuals, for instance the disruption caused by the loss of homes. COCO-1 includes the cost of countermeasures, namely evacuation, relocation, sheltering, food restrictions and decontamination, and also the cost of health effects in the exposed population. The primary quantity used in COCO-1 to measure the economic value of land subject to restrictions on usage is Gross Domestic Product (GDP). Examples of default data included in the model are presented, as are the results of an illustrative application. The limitations of COCO-1 are discussed, and areas where further data are needed are identified

  17. Event-based soil loss models for construction sites

    Science.gov (United States)

    Trenouth, William R.; Gharabaghi, Bahram

    2015-05-01

    The elevated rates of soil erosion stemming from land clearing and grading activities during urban development, can result in excessive amounts of eroded sediments entering waterways and causing harm to the biota living therein. However, construction site event-based soil loss simulations - required for reliable design of erosion and sediment controls - are one of the most uncertain types of hydrologic models. This study presents models with improved degree of accuracy to advance the design of erosion and sediment controls for construction sites. The new models are developed using multiple linear regression (MLR) on event-based permutations of the Universal Soil Loss Equation (USLE) and artificial neural networks (ANN). These models were developed using surface runoff monitoring datasets obtained from three sites - Greensborough, Cookstown, and Alcona - in Ontario and datasets mined from the literature for three additional sites - Treynor, Iowa, Coshocton, Ohio and Cordoba, Spain. The predictive MLR and ANN models can serve as both diagnostic and design tools for the effective sizing of erosion and sediment controls on active construction sites, and can be used for dynamic scenario forecasting when considering rapidly changing land use conditions during various phases of construction.

  18. Development of a mixed waste management facility at the Nevada Test Site

    International Nuclear Information System (INIS)

    Dodge, R.L.; Brich, R.F.

    1988-01-01

    The U.S. Department of Energy (DOE) produces radioactive low-level wastes (LLW) which contain hazardous components as identified by 40 Code of Federal Regulations (CFR) 261. Management of those mixed wastes (MW) requires compliance with U.S.Environmental Protection Agency (EPA) regulations for hazardous wastes and DOE regulations for LLW. In 1988, DOE's Nevada Operations Office (NV) began disposing of MW at the Nevada Test Site (NTS) under interim status as authorized by the state of Nevada. MW disposal is limited to Pit 3 while operating under interim status. This paper discusses how preparations for operation of a separate mixed waste management facility (MWMF) are underway. Those preparations include revising the NTS Part B Permit application, developing a MW certification program, developing and operating a vadose zone monitoring system, preparing an Environmental Assessment (EA), developing protocols for analysis of MW, and facility design and construction

  19. Building a Spatial Database for Romanian Archaeological Sites

    Directory of Open Access Journals (Sweden)

    Aura-Mihaela MOCANU

    2011-03-01

    Full Text Available Spatial databases are a new technology in the database systems which allow storing, retrieving and maintaining geospatial data. This paper describes the steps which we have followed to model, design and develop a spatial database for Romanian archaeological sites and their assemblies. The system analysis was made using the well known Entity-Relationship model; the system design included the conceptual, the external and the internal schemas design, and the system development meant developing the needed database objects and programs. The designed database allows users to load vector geospatial data about the archaeological sites in two distinct spatial reference systems WGS84 and STEREO70, temporal data about the historical periods and cultures, other descriptive data and documents as references to the archaeological objects.

  20. Guidelines for the development of natural phenomena hazards design criteria for surface facilities

    International Nuclear Information System (INIS)

    Nelson, T.A.; Hossain, Q.A.; Murray, R.C.

    1992-01-01

    This paper discusses the rationale behind the guidelines, criteria, and methodologies that are currently used for natural phenomena hazard design and evaluation of DOE nuclear and non-nuclear facilities. The bases for the performance goals and usage categories specified in UCRL-15910 are examined, and the sources of intentional conservatism in the analyses, design, and evaluation methods and criteria are identified. Outlines of recent developments/changes in DOE Orders related to Natural Phenomena hazard mitigation are also presented. Finally, the authors recommend the use of DOE methodologies as embodied in UCRL-15910 for design and evaluation of surface facilities of the high level nuclear waste repository site

  1. Developing a Parametric Urban Design Tool

    DEFF Research Database (Denmark)

    Steinø, Nicolai; Obeling, Esben

    2014-01-01

    Parametric urban design is a potentially powerful tool for collaborative urban design processes. Rather than making one- off designs which need to be redesigned from the ground up in case of changes, parametric design tools make it possible keep the design open while at the same time allowing...... for a level of detailing which is high enough to facilitate an understan- ding of the generic qualities of proposed designs. Starting from a brief overview of parametric design, this paper presents initial findings from the development of a parametric urban design tool with regard to developing a structural...... logic which is flexible and expandable. It then moves on to outline and discuss further development work. Finally, it offers a brief reflection on the potentials and shortcomings of the software – CityEngine – which is used for developing the parametric urban design tool....

  2. Establishment of advanced integration technology for site characterization of deep geological repository. Development of information synthesis and interpretation system. Annual report 2007

    International Nuclear Information System (INIS)

    Osawa, Hideaki; Umeki, Hiroyuki; Ota, Kunio; Maekawa, Keisuke; Kunimaru, Takanori; Niizato, Tadafumi; Asamori, Koichi; Yamanaka, Yoshiaki; Shigehiro, Michiko; Abe, Hironobu; Hama, Katsuhiro; Takeuchi, Shinji; Amano, Kenji; Saegusa, Hiromitsu; Matsukawa, Toshiyuki; Miyamoto, Tetsuo; Toyoda, Gakuji; Sawada, Atsushi; Shimada, Akiomi

    2008-11-01

    This project is planned as a five-year program aiming to develop an advanced integration technology for characterization of a site for radioactive waste geological disposal. It is carried out by the Geological Isolation Research and Development Directorate of Japan Atomic Energy Agency with the fund of Agency for Natural Resources and Energy of the Ministry of Economy, Trade and Industry. This report summarizes the outcome of the first year (FY 2007) activities of the project. The site characterization is a dynamic and complex process and needs close linkage with repository design and performance assessment (PA). A geosynthesis methodology has been developed for integrating site characterization information into design and PA, and applied for e.g. on-going JAEA's studies at two generic URLs at Mizunami and Horonobe. This methodology explicitly presents an information flow (often referred to as geosynthesis data flow diagram or data flow diagram, in short) from measurements by site investigation to generating data sets for design and PA. It is a useful tool for guiding the site characterization in a transparent and traceable manner. As site investigation proceeds and information being obtained on geological environments of the site increases, the site characterization plan is iteratively reviewed and modified reflecting the updated information. Such modification would also be needed when changes would occur on socio-political boundary conditions. In fact, the data flow diagrams for two generic URL projects have been revised several times so far due to the increase in the amount of information on geological environments and changes of societal conditions. An advanced technology aimed at in this project is therefore focused on developing flexible approach and tools, which is named as Information Synthesis and Interpretation System (ISIS), to support the stepwise 'optimization' of the site characterization plan. In FY 2007, a basic concept for ISIS has been developed

  3. Cultivating Collaborations: Site Specific Design for Embodied Science Learning.

    Science.gov (United States)

    Gill, Katherine; Glazier, Jocelyn; Towns, Betsy

    2018-05-21

    Immersion in well-designed outdoor environments can foster the habits of mind that enable critical and authentic scientific questions to take root in students' minds. Here we share two design cases in which careful, collaborative, and intentional design of outdoor learning environments for informal inquiry provide people of all ages with embodied opportunities to learn about the natural world, developing the capacity for understanding ecology and the ability to empathize, problem-solve and reflect. Embodied learning, as facilitated by and in well-designed outdoor learning environments, leads students to develop new ways of seeing, new scientific questions, new ways to connect with ideas, with others and new ways of thinking about the natural world. Using examples from our collaborative practices as experiential learning designers, we illustrate how creating the habits of mind critical to creating scientists, science-interested, and science-aware individuals benefits from providing students spaces to engage in embodied learning in nature. We show how public landscapes designed in creative partnerships between educators, scientists, designers and the public have potential to amplify science learning for all.

  4. Report of the Siting Policy Task Force

    International Nuclear Information System (INIS)

    1979-08-01

    In August 1978, the Nuclear Regulatory Commission directed the staff to develop a general policy statement on nuclear power reactor siting. A Task Force was formed for that purpose and has prepared a statement of current NRC policy and practice and has recommended a number of changes to current policy. Recommendations were made to accomplish the following goals: (1) To strengthen siting as a factor in defense in depth by establishing requirements for site approval that are independent of plant design consideration. The present policy of permitting plant design features to compensate for unfavorable site characteristics has resulted in improved designs but has tended to deemphasize site isolation. (2) To take into consideration in siting the risk associated with accidents beyond the design basis (Class 9) by establishing population density and distribution criteria. Plant design improvements have reduced the probability and consequences of design basis accidents, but there remains the residual risk from accidents not considered in the design basis. Although this risk cannot be completely reduced to zero, it can be significantly reduced by selective siting. (3) To require that sites selected will minimize the risk from energy generation. The selected sites should be among the best available in the region where new generating capacity is needed. Siting requirements should be stringent enough to limit the residual risk of reactor operation but not so stringent as to eliminate the nuclear option from large regions of the country. This is because energy generation from any source has its associated risk, with risks from some energy sources being greater than that of the nuclear option

  5. Bioremediation of mixed microbial mats: System development of mixed contaminants for application at the Savannah River Site. Annual technical progress report, October 1, 1995--September 30, 1996

    International Nuclear Information System (INIS)

    Bender, J.; Phillips, P.

    1996-01-01

    The fundamental objective of this project is to develop and field test the mixed microbial mat bioremediation system for decontamination of target sites at SRS. Although microbial mats have performed well in several pilot projects in the past, atypical problems and site characteristics at SRS demand special field designs. In the interest of designing a pilot and locating it at an appropriate site, the project investigators have worked closely with the technical staff at the SREL. We have concluded that the diverse characteristics of contaminations at SRS may dictate testing several pilot designs during the course of this project

  6. Sellafield repository design concept

    International Nuclear Information System (INIS)

    1998-01-01

    Between 1989 and 1997, UK Nirex Ltd carried out a programme of investigations to evaluate the potential of a site adjacent to the BNFL Sellafield works to host a deep repository for the United Kingdom's intermediate-level and certain low-level radioactive waste. The programme of investigations was wound down following the decision in March 1997 to uphold the rejection of the Company's planning application for the Rock Characterisation Facility (RCF), an underground laboratory which would have allowed further investigations to confirm whether or not the site would be suitable. Since that time, the Company's efforts in relation to the Sellafield site have been directed towards documenting and publishing the work carried out. The design concept for a repository at Sellafield was developed in parallel with the site investigations through an iterative process as knowledge of the site and understanding of the repository system performance increased. This report documents the Sellafield repository design concept as it had been developed, from initial design considerations in 1991 up to the point when the RCF planning application was rejected. It shows, from the context of a project at that particular site, how much information and experience has been gained that will be applicable to the development of a deep waste repository at other potential sites

  7. Education Office Application Design and Development

    Science.gov (United States)

    Johnson, Jamie E.

    2013-01-01

    The content of this project focuses on designing and implementing a new prototype website for the Kennedy Intern Tracking System (KITS). The goal of the new website is to allow the user to search for interns based on several different categories and fields. In hence, making it easier to find a count of interns matching a set of criteria. The KSC office of education is the primary users of KITS, their job is to recruit interns year-round. As a secondary goal, each user will be able to generate a report of their searches onto a portable document format (PDF) me. The results of each search will be set to a limited amount per page. This site will be used for Kennedy Space Center internal purposes only. After the implementations are done, a visual walk through using screen shots will be used to guide the users through all of the different scenarios that are likely to occur when the users are navigating through the site. In addition, a demo of the site will be presented to the KSC Office of Education. JavaScript and JQuery are the languages that will focus on the functionality of the implementation. Hyper Text Markup Language will be used to form the foundation for the body structure of the website. Ruby will be the programming language used to elevate the prototype to a dynamic website and enable the programmer to finish with in an efficient time frame. Cascading Style Sheet will be the language used for the design and styling purposes. Rails is the framework that the new website will be built upon. By default, the database will be managed by Sequel Lite (SQLite). All users will need to be granted special privileges in order to use the site.

  8. Modifications to the remedial action plan and site design for stabilization of the inactive Uranium Mill Tailings Site at Green River, Utah

    International Nuclear Information System (INIS)

    1994-09-01

    Modifications to the water resources protection strategy detailed in the remedial action plan for the Green River, Utah, disposal site are presented. The modifications are based on new information, including ground water quality data collected after remedial action was completed and on a revised assessment of disposal cell design features, surface conditions, and site hydrogeology. The modifications will result in compliance with the U.S. EPA proposed ground water standards (52 FR 36000 (1987))

  9. VS30 – A site-characterization parameter for use in building Codes, simplified earthquake resistant design, GMPEs, and ShakeMaps

    Science.gov (United States)

    Borcherdt, Roger D.

    2012-01-01

    VS30, defined as the average seismic shear-wave velocity from the surface to a depth of 30 meters, has found wide-spread use as a parameter to characterize site response for simplified earthquake resistant design as implemented in building codes worldwide. VS30 , as initially introduced by the author for the US 1994 NEHRP Building Code, provides unambiguous definitions of site classes and site coefficients for site-dependent response spectra based on correlations derived from extensive borehole logging and comparative ground-motion measurement programs in California. Subsequent use of VS30 for development of strong ground motion prediction equations (GMPEs) and measurement of extensive sets of VS borehole data have confirmed the previous empirical correlations and established correlations of SVS30 with VSZ at other depths. These correlations provide closed form expressions to predict S30 V at a large number of additional sites and further justify S30 V as a parameter to characterize site response for simplified building codes, GMPEs, ShakeMap, and seismic hazard mapping.

  10. Feedback from performance assessment to site characterisation. The SITE-94 example

    International Nuclear Information System (INIS)

    Dverstorp, B.; Geier, J.

    1999-01-01

    Interaction and information exchange between site characterisation and performance assessment are key features of any successful radioactive waste management programme. Some examples are presented of the types of feedback that can be offered from performance assessment to site characterisation, based on SKI's most recent performance assessment project, SITE-94. SITE-94 in Sweden was an assessment of a hypothetical repository for spent nuclear fuel, based on real data gathered in the surface-based investigation of the Aespoe Hard Rock Laboratory site. Examples of feedback are given concerning quality control of data and site investigation procedures, identification of key parameters for the performance assessment, use of models for planning and evaluation of a site investigation, data sampling strategies, and guidance on future priorities for further development of site investigation methods. Because site characterisation serves multiple purposes, including provision of data for repository design and construction, it must account for and compromise among requirements from several lines of analyses in the performance assessment. (author)

  11. A design study for the isolation of the 281-3H retention basin at the Savannah River Site using the viscous liquid barrier technology

    International Nuclear Information System (INIS)

    Moridis, G.J.; Persoff, P.; Apps, J.; James, A.; Oldenburg, C.; McGrath, A.; Myer, L.; Pellerin, L.; Pruess, K.

    1996-11-01

    This report is a description of the design study for a pilot-scale field demonstration of the Viscous Liquid Barrier (VLB) technology, a new subsurface containment technology for waste isolation using a new generation of barrier liquids. The demonstration site was Retention Basin 281-3H, a shallow catchment basin at the Savannah River Site, which is contaminated mainly by radionuclides ( 137 Cs, 90 Sr, and 238 Pu). The goals of the field demonstration were (a) to demonstrate the ability to create a continuous subsurface barrier in order to isolate the contaminants, and (b) to demonstrate the continuity, performance, and integrity of the barrier. The site was characterized, and preliminary hydraulic conductivity data were obtained from core samples. Based on the site characteristics and the functional requirements, a conceptual model was developed, the barrier specifications were defined, and lance injection was selected as the emplacement method. The injection strategy for the subsurface conditions at the site was determined using numerical simulations. An appropriate variant of Colloidal Silica (CS) was selected as the barrier liquid based on its relative insensitivity to interactions with the site soils, and the formulation for optimum site performance was determined. A barrier verification strategy, including hydraulic, pneumatic, tracer, and geophysical methods, was developed. A lance water injection test was conducted in order to obtain representative estimates of the hydraulic conductivity and its distribution for the design of the barrier emplacement. The water injection test demonstrated the lack of permeable zones for CS injection, and a decision not to proceed with the barrier emplacement was reached

  12. Preliminary design for a maglev development facility

    Energy Technology Data Exchange (ETDEWEB)

    Coffey, H.T.; He, J.L.; Chang, S.L.; Bouillard, J.X.; Chen, S.S.; Cai, Y.; Hoppie, L.O.; Lottes, S.A.; Rote, D.M. (Argonne National Lab., IL (United States)); Zhang, Z.Y. (Polytechnic Univ., Brooklyn, NY (United States)); Myers, G.; Cvercko, A. (Sterling Engineering, Westchester, IL (United States)); Williams, J.R. (Alfred Benesch and Co., Chicago, IL (United States))

    1992-04-01

    A preliminary design was made of a national user facility for evaluating magnetic-levitation (maglev) technologies in sizes intermediate between laboratory experiments and full-scale systems. A technical advisory committee was established and a conference was held to obtain advice on the potential requirements of operational systems and how the facility might best be configured to test these requirements. The effort included studies of multiple concepts for levitating, guiding, and propelling maglev vehicles, as well as the controls, communications, and data-acquisition and -reduction equipment that would be required in operating the facility. Preliminary designs for versatile, dual 2-MVA power supplies capable of powering attractive or repulsive systems were developed. Facility site requirements were identified. Test vehicles would be about 7.4 m (25 ft) long, would weigh form 3 to 7 metric tons, and would operate at speeds up to 67 m/s (150 mph) on a 3.3-km (2.05-mi) elevated guideway. The facility would utilize modular vehicles and guideways, permitting the substitution of levitation, propulsion, and guideway components of different designs and materials for evaluation. The vehicle would provide a test cell in which individual suspension or propulsion components or subsystems could be tested under realistic conditions. The system would allow economical evaluation of integrated systems under varying weather conditions and in realistic geometries.

  13. Nuclear island buildings layout collaborative design platform development and application

    International Nuclear Information System (INIS)

    Chen Li; Huang Wenqiang

    2014-01-01

    Based on characteristics of nuclear island layout design, the large number files and complicated interface, for realizing collaborative design and fine management goal, Establish collaborative design platform, which includes the design task module, 3D design module, project management module. These three modules can package design input files, realize synchronous design and real-time track design drawings state, timely feedback between design, procurement, construction site. There is no design task delay due to tracking and has realized fine management of design. (authors)

  14. Designing apps for success developing consistent app design practices

    CERN Document Server

    David, Matthew

    2014-01-01

    In 2007, Apple released the iPhone. With this release came tools as revolutionary as the internet was to businesses and individuals back in the mid- and late-nineties: Apps. Much like websites drove (and still drive) business, so too do apps drive sales, efficiencies and communication between people. But also like web design and development, in its early years and iterations, guidelines and best practices for apps are few and far between.Designing Apps for Success provides web/app designers and developers with consistent app design practices that result in timely, appropriate, and efficiently

  15. A developing chronology for prehistoric 'moated sites' in northeast Thailand

    International Nuclear Information System (INIS)

    McGrath, R.J.; Boyd, W.E.

    1999-01-01

    Full text: Many mounded Iron Age occupation sites in the Mun River Valley,N.E. Thailand are characterised by distinctive encircling earthworks, these are commonly known as 'moated sites'. The first excavations of any significance within the moats themselves at six sites -Noen U-Loke, Non Muang Khao, Ban Non Khrua Chut, Ban Non Ngiu, Ban Makham Thae and Ban Non Wat - in the form of long trenches have been carried out to enable detailed examination of their structure. Significantly, the surficial morphology of the moats, and the notable regularity of shape and patterning of the moats in plan, usually does not accurately reflect the buried sectional morphology of incised channel features, which are in no way expressed on the surface. Buried channels beneath the edge of the mounds as well as the surrounding moat banks have also been revealed. Stratigraphic and geomorphic relationships of the buried features imply critical chronological relationships which need to be tested to allow full development of a model for the evolution of the archaeological sites. Extremely small quantities of charcoal and shells obtained from the buried features has necessitated the need for AMS dating to develop the chronology for the development, use and decline of the moated features and channels. The dating is an ongoing process, however, results thus far obtained supports the development of older channels towards the archaeological mounds, and yet older buried channels under the sites

  16. Design and development of computerized local and overall country's environmental data analysis network system

    International Nuclear Information System (INIS)

    Kim, Chang Gyu; Kang, Jong Gyu; Han, H.; Han, J. S.; Lee, Y. D.; Lee, S. R.; Kang, D. J.; Cho, Y. G.; Yun, S. H.

    2001-03-01

    In this development, we designed a integrated database for efficient data processing of radiation-environment data and developed the CLEAN (Computerized Local and overall country's Environmental data Analysis Network) system. The CLEAN system consists of local radiation-environment network, data analysis system, data open system. We developed the CLEAN system focused on building an integrated database, a data mart, and a CLEAN web site. It is expected that the developed system, which organizes the information related to environmental radiation data systematically, can be utilize for the accurate interpretation, analysis and evaluation

  17. Geochemical investigation of UMTRAP designated site at Durango, Colorado

    International Nuclear Information System (INIS)

    Markos, G.; Bush, K.J.

    1983-09-01

    This report is the result of a geochemical investigation of the former uranium mill and tailings site at Durango, Colorado. This is one in a series of site specific geochemical investigations performed on the inactive uranium mill tailings included in the UMTRA Project. The objectives of the investigation are to characterize the geochemistry, to determine the contaminant distribution resulting from the former milling activities and tailings, and to infer chemical pathways and transport mechanisms from the contaminant distribution. The results will be used to model contaminant migration and to develop criteria for long-term containment media such as a cover system which is impermeable to contaminant migration. This report assumes a familiarity with the hydrologic conditions of the site and the geochemical concepts underlying the investigation. The results reported are based on a one-time sampling of waters and solid material from the background, the area adjacent to the site, and the site. The solid samples are water extracted remove easily soluble salts and acids extracted to remove cabonates and hydroxides. The water extracts and solid samples were analyzed for the major and trace elements. A limited number of samples were analyzed for radiological components. The report includes the methods of sampling, sample processing, analysis, and data interpretation. Three major conclusions are: (1) carbonate salts and low TDS characterize the tailings; (2) the adjacent area and raffinate ponds contain contaminants deposited by a single event of fluid permeation of the soils; and (3) the Animas River adjacent to the site has elevated gross alpha activity attributed to 226 Ra in the sediments derived from the tailings or milling activities

  18. CIRP Design 2012 Sustainable Product Development

    CERN Document Server

    2013-01-01

    During its life cycle, a product produces waste that is over 20 times its weight. As such it is critical to develop products that are sustainable. Currently product development processes lack high quality methods and tools that are empirically validated to support development of sustainable products. This book is a compilation of over forty cutting edge international research papers from the 22nd CIRP International Design Conference, written by eminent researchers from 15 countries, on engineering design process, methods and tools, broadly for supporting sustainable product development.   A variety of new insights into the product development process, as well as a host of methods and tools that are at the cutting edge of design research are discussed and explained covering a range of diverse topics. The areas covered include: ·Sustainable design and manufacturing, ·Design synthesis and creativity, ·Global product development and product life cycle management, ·Design for X (safety, reliability, manufactu...

  19. Implications of next generation attenuation ground motion prediction equations for site coefficients used in earthquake resistant design

    Science.gov (United States)

    Borcherdt, Roger D.

    2014-01-01

    Proposals are developed to update Tables 11.4-1 and 11.4-2 of Minimum Design Loads for Buildings and Other Structures published as American Society of Civil Engineers Structural Engineering Institute standard 7-10 (ASCE/SEI 7–10). The updates are mean next generation attenuation (NGA) site coefficients inferred directly from the four NGA ground motion prediction equations used to derive the maximum considered earthquake response maps adopted in ASCE/SEI 7–10. Proposals include the recommendation to use straight-line interpolation to infer site coefficients at intermediate values of (average shear velocity to 30-m depth). The NGA coefficients are shown to agree well with adopted site coefficients at low levels of input motion (0.1 g) and those observed from the Loma Prieta earthquake. For higher levels of input motion, the majority of the adopted values are within the 95% epistemic-uncertainty limits implied by the NGA estimates with the exceptions being the mid-period site coefficient, Fv, for site class D and the short-period coefficient, Fa, for site class C, both of which are slightly less than the corresponding 95% limit. The NGA data base shows that the median value  of 913 m/s for site class B is more typical than 760 m/s as a value to characterize firm to hard rock sites as the uniform ground condition for future maximum considered earthquake response ground motion estimates. Future updates of NGA ground motion prediction equations can be incorporated easily into future adjustments of adopted site coefficients using procedures presented herein. 

  20. Site scientific mission plan for the Southern Great Plains CART site: July--December 1997

    Energy Technology Data Exchange (ETDEWEB)

    Peppler, R.A.; Lamb, P.J. [Univ. of Oklahoma, Norman, OK (United States). Cooperative Inst. for Mesoscale Meteorological Studies; Sisterson, D.L. [Argonne National Lab., IL (United States). Environmental Research Div.

    1997-07-01

    The Southern Great Plains (SGP) Cloud and Radiation Testbed (CART) site is designed to help satisfy the data needs of the Atmospheric Radiation Measurement (ARM) Program Science Team. This document defines the scientific priorities for site activities during the six months beginning on July 1, 1997, and looks forward in lesser detail to subsequent six-month periods. The primary purpose of this Site Scientific Mission Plan is to provide guidance for the development of plans for site operations. It also provides information on current plans to the ARM functional teams and serves to disseminate the plans more generally within the ARM Program and among the members of the Science Team. This document includes a description of the operational status of the site and the primary site activities envisioned, together with information concerning approved and proposed intensive observation periods (IOPs). This plan is a living document that is updated and reissued every six months as the observational facilities are developed, tested, and augmented and as priorities are adjusted in response to developments in scientific planning and understanding.

  1. Innovation by design lessons from post box design & development

    CERN Document Server

    Chakravarthy, Battula Kalyana

    2013-01-01

    The book provides an in-depth knowledge on how a product is designed and developed by Product Designers. This has been achieved through a case study of one product – the Post Box. This product was chosen for the study primarily due to its simple and non-technical nature as that would make it easy for the readers to comprehend the design process. At the same time the Post Box posed all the challenges a designer would face while creating a new product. Through a step by step process the book gradually takes the reader through the design and development journey – right from understanding the product, identifying the user need through market research, comprehending client’s brief, generating product ideas and concepts to development of prototype, manufacturing and final performance of the product. The book illustrates the stages in the design process that lead to innovation which is applicable to all types of products. To make the book more stimulating, interesting facts, figures and pictures on related iss...

  2. On methods of sustainable architectural design of bio-positive buildings in the low-rise residential development structure

    Directory of Open Access Journals (Sweden)

    Zhogoleva Anna

    2017-01-01

    Full Text Available The purpose of the author’s research is to determine the actual content of sustainable architectural design for suburban residential development. In accordance with the methodology of area sustainable development the traditional architectural design according to the rules and regulations is completed with additional approaches and methods. As a result, methods of bio-positive design of buildings have been studied and defined, including: the principle of planning transformations, the use of environmentally friendly, local building materials and design concepts, energy-efficient architectural design, the use of alternative energy in building operation, the design of the energy intake and accumulationsystems, the architectural and landscape design that ensures stable functioning of autonomous, sustainable biosystems on the site, non-waste functioning of architectural objects, introduction of waste disposal systems in the project.

  3. Review of a site developer's geo-scientific data and site-characterisation information to support repository certification

    International Nuclear Information System (INIS)

    Peake, R.T.; Byrum, C.; Ghose, S.

    2007-01-01

    The Waste Isolation Pilot Plant (WIPP) in New Mexico is a first-of-a-kind deep geologic facility for the disposal of transuranic (TRU) radioactive waste from weapons production in the United States. In 1993, Congress authorised the Environmental Protection Agency (EPA) to develop and implement WIPP-site-specific compliance criteria based on the general safety and environmental standards in EPA's high-level and transuranic radioactive waste regulations [1]. EPA published its site-specific regulations [2] in 1996 and certified WIPP to open in 1998. This regulatory framework set the stage for balancing diverse input data, provided a structure for document development, provided a mechanism for interaction between EPA and the Department of Energy (DOE), and provided a guide to support our review of WIPP's safety assessment. EPA's involvement continues during WIPP's operational phase. Confidence in repository site geo-scientific data enhances the regulator's ability to make a credible and defensible certification (licensing) decision and to communicate the basis for the decision to the public. Lack of confidence in the data can lead to lack of credibility about site suitability. Clear regulations and specific quality standards can enhance the quality of site-characterisation documentation and assist the regulator in its approval process of the site. In EPA's regulations, documentation is required on numerous issues, and EPA supplemented this with guidance. High-quality documentation is essential, especially for EPA. In the certification process for WIPP, the documentation in the record and our written interpretation of the record was what was used in legal proceedings that followed EPA's certification of WIPP. EPA and DOE had frequent and generally open communication. During formal regulatory proceedings, all communication had to be documented. Some decisions were made at the staff level, but major decisions were typically addressed and resolved through correspondence

  4. Truncated Dual-Cap Nucleation Site Development

    Science.gov (United States)

    Matson, Douglas M.; Sander, Paul J.

    2012-01-01

    During heterogeneous nucleation within a metastable mushy-zone, several geometries for nucleation site development must be considered. Traditional spherical dual cap and crevice models are compared to a truncated dual cap to determine the activation energy and critical cluster growth kinetics in ternary Fe-Cr-Ni steel alloys. Results of activation energy results indicate that nucleation is more probable at grain boundaries within the solid than at the solid-liquid interface.

  5. Supercollider: Design changes

    International Nuclear Information System (INIS)

    Anon.

    1990-01-01

    A major task faced by the new US Superconducting Supercollider (SSC) Laboratory as it began life early last year was to prepare a baseline design, cost and schedule for the site in Ellis County, Texas. The conceptual design developed by the SSC Central Design Group at Berkeley in 1986 was for a generic site, and served as the basis of the cost estimate submitted to Congress for fiscal year 1990. Under the terms of the contract between Universities Research Association (URA - the SSC parent organization) and the US Department of Energy to establish the SSC Laboratory, signed in January 1989, a report on the SiteSpecific Conceptual Design Report was complete by December

  6. Supercollider: Design changes

    Energy Technology Data Exchange (ETDEWEB)

    Anon.

    1990-04-15

    A major task faced by the new US Superconducting Supercollider (SSC) Laboratory as it began life early last year was to prepare a baseline design, cost and schedule for the site in Ellis County, Texas. The conceptual design developed by the SSC Central Design Group at Berkeley in 1986 was for a generic site, and served as the basis of the cost estimate submitted to Congress for fiscal year 1990. Under the terms of the contract between Universities Research Association (URA - the SSC parent organization) and the US Department of Energy to establish the SSC Laboratory, signed in January 1989, a report on the SiteSpecific Conceptual Design Report was complete by December.

  7. That Was Then, This Is Now: Replacing the Mobile-Optimized Site with Responsive Design

    Directory of Open Access Journals (Sweden)

    Laurie M. Bridges

    2013-12-01

    Full Text Available As mobile technologies continue to evolve, libraries seek sustainable ways to keep up with these changes and to best serve our users.  Previous library mobile usability research has examined tasks users predict they might be likely to perform, but little is known about what users actually do on a mobile-optimized library site.  This research used a combination of survey methodology and web analytics to examine what tasks users actually carry out on a library mobile site.  The results indicate that users perform an array of passive and active tasks and do not want content choices to be limited on mobile devices.  Responsive design is described as a long-term solution for addressing both designers and users’ needs.

  8. Development of environmentally advanced hydropower turbine system design concepts

    Energy Technology Data Exchange (ETDEWEB)

    Franke, G.F.; Webb, D.R.; Fisher, R.K. Jr. [Voith Hydro, Inc. (United States)] [and others

    1997-08-01

    A team worked together on the development of environmentally advanced hydro turbine design concepts to reduce hydropower`s impact on the environment, and to improve the understanding of the technical and environmental issues involved, in particular, with fish survival as a result of their passage through hydro power sites. This approach brought together a turbine design and manufacturing company, biologists, a utility, a consulting engineering firm and a university research facility, in order to benefit from the synergy of diverse disciplines. Through a combination of advanced technology and engineering analyses, innovative design concepts adaptable to both new and existing hydro facilities were developed and are presented. The project was divided into 4 tasks. Task 1 investigated a broad range of environmental issues and how the issues differed throughout the country. Task 2 addressed fish physiology and turbine physics. Task 3 investigated individual design elements needed for the refinement of the three concept families defined in Task 1. Advanced numerical tools for flow simulation in turbines are used to quantify characteristics of flow and pressure fields within turbine water passageways. The issues associated with dissolved oxygen enhancement using turbine aeration are presented. The state of the art and recent advancements of this technology are reviewed. Key elements for applying turbine aeration to improve aquatic habitat are discussed and a review of the procedures for testing of aerating turbines is presented. In Task 4, the results of the Tasks were assembled into three families of design concepts to address the most significant issues defined in Task 1. The results of the work conclude that significant improvements in fish passage survival are achievable.

  9. Development of environmentally advanced hydropower turbine system design concepts

    International Nuclear Information System (INIS)

    Franke, G.F.; Webb, D.R.; Fisher, R.K. Jr.

    1997-08-01

    A team worked together on the development of environmentally advanced hydro turbine design concepts to reduce hydropower''s impact on the environment, and to improve the understanding of the technical and environmental issues involved, in particular, with fish survival as a result of their passage through hydro power sites. This approach brought together a turbine design and manufacturing company, biologists, a utility, a consulting engineering firm and a university research facility, in order to benefit from the synergy of diverse disciplines. Through a combination of advanced technology and engineering analyses, innovative design concepts adaptable to both new and existing hydro facilities were developed and are presented. The project was divided into 4 tasks. Task 1 investigated a broad range of environmental issues and how the issues differed throughout the country. Task 2 addressed fish physiology and turbine physics. Task 3 investigated individual design elements needed for the refinement of the three concept families defined in Task 1. Advanced numerical tools for flow simulation in turbines are used to quantify characteristics of flow and pressure fields within turbine water passageways. The issues associated with dissolved oxygen enhancement using turbine aeration are presented. The state of the art and recent advancements of this technology are reviewed. Key elements for applying turbine aeration to improve aquatic habitat are discussed and a review of the procedures for testing of aerating turbines is presented. In Task 4, the results of the Tasks were assembled into three families of design concepts to address the most significant issues defined in Task 1. The results of the work conclude that significant improvements in fish passage survival are achievable

  10. Site scientific mission plan for the southern Great Plains CART site, January--June 1998

    Energy Technology Data Exchange (ETDEWEB)

    Peppler, R.A.; Lamb, P.J. [Univ. of Oklahoma, Norman, OK (United States). Cooperative Inst. for Mesoscale Meteorological Studies; Sisterson, D.L. [Argonne National Lab., IL (United States). Environmental Research Div.

    1998-01-01

    The Southern Great Plains (SGP) Cloud and Radiation Testbed (CART) site is designed to help satisfy the data needs of the Atmospheric Radiation Measurement (ARM) Program Science Team. The primary purpose of this site scientific mission plan is to provide guidance for the development of plans for site operations. It also provides information on current plans to the ARM functional teams (Management Team, Data and Science Integration Team, Operations Team, and Instrument Team) and serves to disseminate the plans more generally within the ARM Program and among the members of the Science Team. This document includes a description of the operational status of the site and the primary site activities envisioned, together with information concerning approved and proposed intensive observation periods (IOPs). The primary users of this document are the Site operator, the Site Scientist Team (SST), the Science Team through the ARM Program science director, the ARM Program Experiment Center, and the aforementioned ARM Program functional teams. This plan is a living document that is updated and reissued every six months as the observational facilities are developed, tested, and augmented and as priorities are adjusted in response to developments in scientific planning and understanding.

  11. Development of a customised design flood estimation tool to ...

    African Journals Online (AJOL)

    The estimation of design flood events, i.e., floods characterised by a specific magnitude-frequency relationship, at a particular site in a specific region is necessary for the planning, design and operation of hydraulic structures. Both the occurrence and frequency of flood events, along with the uncertainty involved in the ...

  12. Development of a software for the design of custom-made hip prostheses using an open-source rapid application development environment.

    Science.gov (United States)

    Viceconti, M; Testi, D; Gori, R; Zannoni, C

    2000-01-01

    The present work describes a technology transfer project called HIPCOM devoted to the re-engineering of the process used by a medical devices manufacturer to design custom-made hip prostheses. Although it started with insufficient support from the end-user management, a very tight scheduling and a moderate budget, the project developed into what is considered by all partners a success story. In particular, the development of the design software, called HIPCOM Interactive Design Environment (HIDE) was completed in a time shorter than any optimistic expectation. The software was quite stable since its first beta version, and once introduced at the user site it fully replaced the original procedure in less than two months. One year after the early adoption, more than 80 custom-made prostheses had been designed with HIDE and the user had reported only two bugs, both cosmetics. The scope of the present work was to report the development experience and to investigate the reasons for these positive results, with particular reference to the development procedure and the software architecture. The choice of TCL/TK as development language and the adoption of well-defined software architecture were found to be the success key factors. Other important determinants were found to be the adoption of an incremental software engineering strategy, well suited for small to medium projects and the presence in the development staff of a technology transfer expert.

  13. Siting, design and construction of underground repositories for radioactive wastes

    International Nuclear Information System (INIS)

    1986-01-01

    The objectives of the Symposium were to provide a forum for exchange of information internationally on the various scientific, technological, engineering and safety bases for the siting, design and construction of underground repositories, and to highlight current important issues and identify possible approaches. Forty-nine papers were presented, covering general approaches and regulatory aspects, disposal in shallow ground and rock cavities, disposal in deep geological formations and safety assessments related to the subject of the Symposium. Separate abstracts were prepared for each of these papers

  14. Biosphere reserves – learning sites of sustainable development?

    Czech Academy of Sciences Publication Activity Database

    Kušová, Drahomíra; Těšitel, Jan; Bartoš, Michael

    2008-01-01

    Roč. 14, č. 3 (2008), s. 221-234 ISSN 1211-7420 Institutional research plan: CEZ:AV0Z60870520 Keywords : nature protection * learning sites * biosphere reserves * sustainable development Subject RIV: DO - Wilderness Conservation

  15. Information Architecture for Bilingual Web Sites.

    Science.gov (United States)

    Cunliffe, Daniel; Jones, Helen; Jarvis, Melanie; Egan, Kevin; Huws, Rhian; Munro, Sian

    2002-01-01

    Discusses creating an information architecture for a bilingual Web site and reports work in progress on the development of a content-based bilingual Web site to facilitate shared resources between speech and language therapists. Considers a structural analysis of existing bilingual Web designs and explains a card-sorting activity conducted with…

  16. Remedial Action Plan and Site Design for Stabilization of the Inactive Uranium Mill Tailings Site, Maybell, Colorado. Remedial action selection report: Attachment 2, Geology report, Final

    Energy Technology Data Exchange (ETDEWEB)

    1994-06-01

    The Maybell uranium mill tailings site is 25 miles (mi) (40 kilometers [km]) west of the town of Craig, Colorado, in Moffat County, in the northwestern part of the state. The unincorporated town of Maybell is 5 road mi (8 km) southwest of the site. The designated site covers approximately 110 acres (ac) (45 hectares [ha]) and consists of a concave-shaped tailings pile and rubble from the demolition of the mill buildings buried in the former mill area. Contaminated materials at the Maybell processing site include the tailings pile, which has an average depth of 20 feet (ft) (6 meters [m]) and contains 2.8 million cubic yards (yd{sup 3}) (2.1 million cubic meters [m{sup 3}]) of tailings. The former mill processing area is on the north side of the site and contains 20,000 yd{sup 3} (15,000 m{sup 3}) of contaminated demolition debris. Off-pile contamination is present and includes areas adjacent to the tailings pile, as well as contamination dispersed by wind and surface water flow. The volume of off-pile contamination to be placed in the disposal cell is 550,000 yd{sup 3} (420,000 m{sup 3}). The total volume of contaminated materials to be disposed of as part of the remedial action is estimated to be 3.37 million yd{sup 3} (2.58 million m{sup 3}). Information presented in this Final Remedial Action Plan (RAP) and referenced in supporting documents represents the current disposal cell design features and ground water compliance strategy proposed by the US Department of Energy (DOE) for the Maybell, Colorado, tailings site. Both the disposal cell design and the ground water compliance strategy have changed from those proposed prior to the preliminary final RAP document as a result of prudent site-specific technical evaluations.

  17. Remedial Action Plan and Site Design for Stabilization of the Inactive Uranium Mill Tailings Site, Maybell, Colorado. Remedial action selection report: Attachment 2, Geology report, Final

    International Nuclear Information System (INIS)

    1994-06-01

    The Maybell uranium mill tailings site is 25 miles (mi) (40 kilometers [km]) west of the town of Craig, Colorado, in Moffat County, in the northwestern part of the state. The unincorporated town of Maybell is 5 road mi (8 km) southwest of the site. The designated site covers approximately 110 acres (ac) (45 hectares [ha]) and consists of a concave-shaped tailings pile and rubble from the demolition of the mill buildings buried in the former mill area. Contaminated materials at the Maybell processing site include the tailings pile, which has an average depth of 20 feet (ft) (6 meters [m]) and contains 2.8 million cubic yards (yd 3 ) (2.1 million cubic meters [m 3 ]) of tailings. The former mill processing area is on the north side of the site and contains 20,000 yd 3 (15,000 m 3 ) of contaminated demolition debris. Off-pile contamination is present and includes areas adjacent to the tailings pile, as well as contamination dispersed by wind and surface water flow. The volume of off-pile contamination to be placed in the disposal cell is 550,000 yd 3 (420,000 m 3 ). The total volume of contaminated materials to be disposed of as part of the remedial action is estimated to be 3.37 million yd 3 (2.58 million m 3 ). Information presented in this Final Remedial Action Plan (RAP) and referenced in supporting documents represents the current disposal cell design features and ground water compliance strategy proposed by the US Department of Energy (DOE) for the Maybell, Colorado, tailings site. Both the disposal cell design and the ground water compliance strategy have changed from those proposed prior to the preliminary final RAP document as a result of prudent site-specific technical evaluations

  18. SITE-2, Power Plant Siting, Cost, Environment, Seismic and Meteorological Effects

    International Nuclear Information System (INIS)

    Frigerio, N.A.; Habegger, L.J.; King, R.F.; Hoover, L.J.; Clark, N.A.; Cobian, J.M.

    1977-01-01

    1 - Description of problem or function: SITE2 is designed to (1) screen candidate energy facility sites or areas within an electric utility region, based on the region's physical and socioeconomic attributes, the planned facility's characteristics, and impact assessments, and (2) evaluate the cumulative regional impacts associated with alternate energy supply options and inter-regional energy import/export practices, specifically, comparison of different energy technologies and their regional distribution in clustered or dispersed patterns. 2 - Method of solution: The SITE2 methodology is based on the quantification of three major site-related vectors. A cost vector is determined which identifies site-specific costs, such as transmission costs, cooling costs as related to water availability, and costs of specific controls needed to protect the surrounding environment. An impact vector is also computed for each potential site, using models of health and environmental impacts incurred in areas adjacent to the site. Finally, a site attribute vector is developed which reflects such characteristics as population, seismic conditions, meteorology, land use, and local ecological systems. This vector can be used to eliminate certain sites because of their inability to satisfy specific constraints. These three vectors can be displayed as density maps and combined in a simple overlay approach, similar to that developed by I. L. McHarg in reference 2, to identify candidate sites. Alternatively, the vector elements can be computationally combined into a weighted sum to obtain quantitative indicators of site suitability

  19. SITE-2, Power Plant Siting, Cost, Environment, Seismic and Meteorological Effects

    Energy Technology Data Exchange (ETDEWEB)

    Frigerio, N A [Environmental Impact Studies, Argonne National Laboratory 9700 South Cass Avenue, Argonne, Illinois 60439 (United States); Habegger, L J; King, R F; Hoover, L J [Energy and Environmental Systems Division, Argonne National Laboratory 9700 South Cass Avenue, Argonne, Illinois 60439 (United States); Clark, N A [Applied Mathematics Division, Argonne National Laboratory, 9700 South Cass Avenue, Argonne, Illinois 60439 (United States); Cobian, J M [Northwestern University, Evanston, Illinois 60201 (United States)

    1977-08-01

    1 - Description of problem or function: SITE2 is designed to (1) screen candidate energy facility sites or areas within an electric utility region, based on the region's physical and socioeconomic attributes, the planned facility's characteristics, and impact assessments, and (2) evaluate the cumulative regional impacts associated with alternate energy supply options and inter-regional energy import/export practices, specifically, comparison of different energy technologies and their regional distribution in clustered or dispersed patterns. 2 - Method of solution: The SITE2 methodology is based on the quantification of three major site-related vectors. A cost vector is determined which identifies site-specific costs, such as transmission costs, cooling costs as related to water availability, and costs of specific controls needed to protect the surrounding environment. An impact vector is also computed for each potential site, using models of health and environmental impacts incurred in areas adjacent to the site. Finally, a site attribute vector is developed which reflects such characteristics as population, seismic conditions, meteorology, land use, and local ecological systems. This vector can be used to eliminate certain sites because of their inability to satisfy specific constraints. These three vectors can be displayed as density maps and combined in a simple overlay approach, similar to that developed by I. L. McHarg in reference 2, to identify candidate sites. Alternatively, the vector elements can be computationally combined into a weighted sum to obtain quantitative indicators of site suitability.

  20. Development of site remediation technologies in European countries

    International Nuclear Information System (INIS)

    Nunno, T.J.; Hyman, J.A.; Pheiffer, T.

    1988-01-01

    Site remediation is a pressing issue in European countries due to limited availability of land. Therefore, much progress is being made in the development of effective technologies for remediating contaminated sites. The purpose of this program was to investigate the most successful and innovative technologies for potential application into US markets. This EPA-sponsored project was based on a 9-month research effort which identified 95 innovative technologies in use or being researched in foreign countries. The most promising technologies were studied in-depth through personal interviews with the engineers who research and apply these technologies, and tours of laboratory models and full-scale installations. The most successful full-scale technologies investigated were developed in Holland, West Germany and Belgium. These technologies include vacuum extraction of hydrocarbons from soil, in situ washing of cadmium-polluted soil, rotating biocontractors for treating pesticides in ground water, high-temperature slagging incineration of low-level radioactive wastes, in situ steam stripping, and a number of landfarming and soil washing operations. The paper provides description of 13 site remediation techniques that have shown such promise in laboratory studies or in practice to warrant consideration of their use in the US

  1. Transitioning from Marketing-Oriented Design to User-Oriented Design: A Case Study

    Science.gov (United States)

    Laster, Shari; Stitz, Tammy; Bove, Frank J.; Wise, Casey

    2011-01-01

    The transition to a new architecture and design for an academic library Web site does not always proceed smoothly. In this case study, a library at a large research university hired an outside Web development contractor to create a new architecture and design for the university's Web site using dotCMS, an open-source content management system. The…

  2. The Role of Virtual Reference in Library Web Site Design: A Qualitative Source for Usage Data

    Science.gov (United States)

    Powers, Amanda Clay; Shedd, Julie; Hill, Clay

    2011-01-01

    Gathering qualitative information about usage behavior of library Web sites is a time-consuming process requiring the active participation of patron communities. Libraries that collect virtual reference transcripts, however, hold valuable data regarding how the library Web site is used that could benefit Web designers. An analysis of virtual…

  3. SITE-94. Discrete-feature modelling of the Aespoe site: 2. Development of the integrated site-scale model

    International Nuclear Information System (INIS)

    Geier, J.E.

    1996-12-01

    A 3-dimensional, discrete-feature hydrological model is developed. The model integrates structural and hydrologic data for the Aespoe site, on scales ranging from semi regional fracture zones to individual fractures in the vicinity of the nuclear waste canisters. Hydrologic properties of the large-scale structures are initially estimated from cross-hole hydrologic test data, and automatically calibrated by numerical simulation of network flow, and comparison with undisturbed heads and observed drawdown in selected cross-hole tests. The calibrated model is combined with a separately derived fracture network model, to yield the integrated model. This model is partly validated by simulation of transient responses to a long-term pumping test and a convergent tracer test, based on the LPT2 experiment at Aespoe. The integrated model predicts that discharge from the SITE-94 repository is predominantly via fracture zones along the eastern shore of Aespoe. Similar discharge loci are produced by numerous model variants that explore uncertainty with regard to effective semi regional boundary conditions, hydrologic properties of the site-scale structures, and alternative structural/hydrological interpretations. 32 refs

  4. SITE-94. Discrete-feature modelling of the Aespoe site: 2. Development of the integrated site-scale model

    Energy Technology Data Exchange (ETDEWEB)

    Geier, J.E. [Golder Associates AB, Uppsala (Sweden)

    1996-12-01

    A 3-dimensional, discrete-feature hydrological model is developed. The model integrates structural and hydrologic data for the Aespoe site, on scales ranging from semi regional fracture zones to individual fractures in the vicinity of the nuclear waste canisters. Hydrologic properties of the large-scale structures are initially estimated from cross-hole hydrologic test data, and automatically calibrated by numerical simulation of network flow, and comparison with undisturbed heads and observed drawdown in selected cross-hole tests. The calibrated model is combined with a separately derived fracture network model, to yield the integrated model. This model is partly validated by simulation of transient responses to a long-term pumping test and a convergent tracer test, based on the LPT2 experiment at Aespoe. The integrated model predicts that discharge from the SITE-94 repository is predominantly via fracture zones along the eastern shore of Aespoe. Similar discharge loci are produced by numerous model variants that explore uncertainty with regard to effective semi regional boundary conditions, hydrologic properties of the site-scale structures, and alternative structural/hydrological interpretations. 32 refs.

  5. Compressed air energy storage: preliminary design and site development program in an aquifer. Final draft, Task 2: Volume 2 of 3. Characterize and explore potential sites and prepare research and development plan

    Energy Technology Data Exchange (ETDEWEB)

    None

    1980-12-01

    The characteristics of sites in Indiana and Illinois which are being investigated as potential sites for compressed air energy storage power plants are documented. These characteristics include geological considerations, economic factors, and environmental considerations. Extensive data are presented for 14 specific sites and a relative rating on the desirability of each site is derived. (LCL)

  6. International developments in uranium mining and mill site remediation

    International Nuclear Information System (INIS)

    Quarch, H.; Kuhlmann, J.; Daroussin, J.L.; Poyser, R.W.

    1993-01-01

    At the end of production, mine sites, mill sites, tailings ponds, heap leaching residues in uranium mining districts world-wide have to be remediated in a responsible and sustainable manner in order to minimize long term environmental impacts. Current practice, regulatory environments and rehabilitation objectives in some of the most important uranium producing countries are briefly characterized as well as applicable radioprotection and geotechnical criteria. Important local and regional variables are outlined which determine optimal site specific solutions. Examples from Europe and North America are shown. Monitoring and control requirements as well as areas of current and necessary research and development are identified

  7. Cost estimate of the Yucca Mountain repository based on the site characterization plan conceptual design: Nevada Nuclear Waste Storage Investigations Project

    International Nuclear Information System (INIS)

    Gruer, E.R.; Fowler, M.E.; Rocha, G.A.

    1987-06-01

    This report of the life-cycle costs of a mined repository in tuff is based on the site characterization conceptual design and contains estimates of two methods of waste emplacement - vertical and horizontal. The life cycle of the repository progresses from design and construction to emplacement operations that last 25 years. When emplacement has ended, a caretaker period begins and continues until 50 years from emplacement of the first waste. The life of the repository concludes with closure and decommissioning, which includes backfilling and sealing the repository, decontaminating and razing the surface facilities, restoring the land to as near its original condition as possible, and marking the site. The estimates, developed for each phase of the life cycle of the repository, are based on January 1986 constant (unescalated) dollars and include an allowance for contingency. This report mainly comprises explanations of design and operating assumptions, estimating methods, exclusions, definition of cost accounts, calculating procedures, data sources, staffing and other qualifying remarks. Cost estimates are approximations of value and should not be construed as exact. The cost and staffing detail provided in this estimate is commensurate with the detail in the conceptual design

  8. Japanese site for ITER: Rokkasho

    International Nuclear Information System (INIS)

    Kishimoto, Hiroshi

    2003-01-01

    This paper describes the status of Japanese efforts for hosting ITER in Japan. In May 2002, Japanese Government decided to propose an ITER site, Rokkasho in Aomori Prefecture, a Northern part of the main island, based on the comprehensive/intensive assessments by the Site Selection Committee established by Japanese Government. ITER is designed basically with a potential flexibility beyond the detailed technical objectives to have more clear scope for developing technical key elements in a future power plant. Various flexibilities in the construction, operation and decommissioning of ITER are totally assessed. Consequently the Japanese site has been chosen and it satisfies sufficiently not only the Site Requirements and the Site Design Assumptions but also the further extension and flexibilities. In particular the potential for more flexible construction schedule and operations is technically described as well as the fulfillment of the site requirements and its assumptions as the minimum requirements in this paper. The socio-cultural environment is also described briefly because of a key aspect for the scientists and engineers who will participate in the project

  9. Early Site Permit Demonstration Program: Plant parameters envelope report

    International Nuclear Information System (INIS)

    1993-03-01

    The Early Site Permit (ESP) Demonstration Program is the nuclear industry's initiative for piloting the early resolution of siting-related issues before the detailed design proceedings of the combined operating license review. The ESP Demonstration Program consists of three phases. The plant parameters envelopes task is part of Phase 1, which addresses the generic review of applicable federal regulations and develops criteria for safety and environmental assessment of potential sites. The plant parameters envelopes identify parameters that characterize the interface between an ALWR design and a potential site, and quantify the interface through values selected from the Utility Requirements Documents, vendor design information, or engineering assessments. When augmented with site-specific information, the plant parameters envelopes provide sufficient information to allow ESPs to be granted based on individual ALWR design information or enveloping design information for the evolutionary, passive, or generic ALWR plants. This document is expected to become a living document when used by future applicants

  10. Even Faster Web Sites Performance Best Practices for Web Developers

    CERN Document Server

    Souders, Steve

    2009-01-01

    Performance is critical to the success of any web site, and yet today's web applications push browsers to their limits with increasing amounts of rich content and heavy use of Ajax. In this book, Steve Souders, web performance evangelist at Google and former Chief Performance Yahoo!, provides valuable techniques to help you optimize your site's performance. Souders' previous book, the bestselling High Performance Web Sites, shocked the web development world by revealing that 80% of the time it takes for a web page to load is on the client side. In Even Faster Web Sites, Souders and eight exp

  11. Development and maintenance of the Hanford Site Radiological Control Manual

    International Nuclear Information System (INIS)

    Munson, L.H.; Selby, J.M.; Vargo, G.J.; Clark, D.L.

    1993-04-01

    In June 1992 the US Department of Energy (DOE) issued DOE N5480.6, Radiological Control, which set forth DOE's Radiological Control Program and established the framework for its implementation at sites nationwide. Accompanying the Order was the DOE Radiological Control Manual (DOE RCM), which provided the detailed requirements for the program. The Order also mandated Field Office issuance of site-specific radiological control manuals by December 1, 1992. This paper presents the approach taken to develop, review, approve, implement, and subsequently maintain the site-specific manual for the DOE Richland Field Office (RL) at Hanford Site

  12. Attitude development in designers' education

    NARCIS (Netherlands)

    Van Doorn, E.; Moes, N.; Fain, N.

    Modern academic design and engineering education adopted the issues and goals of holistic development of design competence. Holistic design competence is a combination of generic capacities: capability, knowledge, skill, experience and attitude. All capacities should be addressed in academic

  13. Site study plan for EDBH [Engineering Design Boreholes] No. 1 and 2: Revision 1

    International Nuclear Information System (INIS)

    1987-12-01

    This site study plan describes the Engineering Design Boreholes 1 and 2 field activities to be conducted during early stages of Site Characterization at the Deaf Smith County site, Texas. The field program has been designed to provide data useful in addressing information/data needs resulting from federal/state/local regulations and repository program requirements. A borehole will be drilled at the centerline of each of the planned exploratory shaft locations. The subsurface rock and fluids will be sampled as the boreholes are advanced to total depth of about 2600 ft. Continuous rock core will be taken below the base of the Dockum Group. Hydrologic testing will occur in units thought to be water bearing and in units of particular interest for shaft seals. Field methods/tests are chosen that provide the best or only means of obtaining the required data. The Salt Repository Project (SRP) Networks specify the schedule under which the program will operate. Drilling will not begin until after site ground-water baseline conditions have been established. The Technical Field Services Contractor is responsible for conducting the field program of drilling and testing. Samples and data will be handled and reported in accordance with established SRP procedures. A quality assurance program will be utilized to assure that activities affecting quality are performed correctly and that the appropriate documentation is maintained. 28 refs., 10 figs., 4 tabs

  14. Site scientific mission plan for the Southern Great Plains CART Site, January--June 1999

    Energy Technology Data Exchange (ETDEWEB)

    Peppler, R.A.; Sisterson, D.L.; Lamb, P.

    1999-03-10

    The Southern Great Plains (SGP) Cloud and Radiation Testbed (CART) site was designed to help satisfy the data needs of the Atmospheric Radiation Measurement (ARM) Program Science Team. This Site Scientific Mission Plan defines the scientific priorities for site activities during the six months beginning on January 1, 1999, and looks forward in lesser detail to subsequent six-month periods. The primary purpose of this document is to provide scientific guidance for the development of plans for site operations. It also provides information on current plans to the ARM functional teams (Management Team, Data and Science Integration Team [DSIT], Operations Team, and Instrument Team [IT]) and serves to disseminate the plans more generally within the ARM Program and among the members of the Science Team. This document includes a description of the operational status of the site and the primary site activities envisioned, together with information concerning approved and proposed intensive observation periods (IOPs). The primary users of this document are the site operator, the site program manager, the Site Scientist Team (SST), the Science Team through the ARM Program science director, the ARM Program Experiment Center, and the aforementioned ARM Program functional teams. This plan is a living document that is updated and reissued every six months as the observational facilities are developed, tested, and augmented and as priorities are adjusted in response to developments in scientific planning and understanding.

  15. Site scientific mission plan for the Southern Great Plains CART site: July--December 1998

    Energy Technology Data Exchange (ETDEWEB)

    Peppler, R.A.; Lamb, P. [Univ. of Oklahoma, Norman, OK (United States). Cooperative Inst. for Mesoscale Meteorological Studies; Sisterson, D.L. [Argonne National Lab., IL (United States). Environmental Research Div.

    1998-07-01

    The Southern Great Plains (SGP) Cloud and Radiation Testbed (CART) site was designed to help satisfy the data needs of the Atmospheric Radiation Measurement (ARM) Program Science Team. This Site Scientific Mission Plan defines the scientific priorities for site activities during the six months beginning on July 1, 1998, and looks forward in lesser detail to subsequent six-month periods. The primary purpose of this document is to provide scientific guidance for the development of plans for site operations. It also provides information on current plans to the ARM functional teams (Management Team, Data and Science Integration Team [DSIT], Operations Team, and Instrument Team [IT]) and serves to disseminate the plans more generally within the ARM Program and among the members of the Science Team. This document includes a description of the operational status of the site and the primary site activities envisioned, together with information concerning approved and proposed intensive observation periods (IOPs). The primary users of this document are the site operator, the site program manager, the Site Scientist Team (SST), the Science Team through the ARM Program science director, the ARM program Experiment Center, and the aforementioned ARM Program functional teams. This plan is a living document that is updated and reissued every six months as the observational facilities are developed, tested, and augmented and as priorities are adjusted in response to developments in scientific planning and understanding.

  16. Report of the Department of Energy (DOE) Office of Energy Research Review Committee on the site-specific conceptual design of the Superconducting Super Collider

    International Nuclear Information System (INIS)

    1990-09-01

    After it was established in early 1989, the Superconducting Super Collider Laboratory (SSCL) began to prepare a detailed site-specific SSC conceptual design, including cost and schedule estimates. As detailed in the SSC Site-Specific Conceptual Design Report (SCDR), this design builds upon the design in the March 1986 SSC Conceptual Design Report (CDR) and takes into account characteristics of the SSC site, results of continuing magnet R ampersand D, and advances in accelerator design

  17. Design and development of GTHTR300

    International Nuclear Information System (INIS)

    Yan, X.; Kunitomi, K.; Nakata, T.; Shiozawa, S.

    2002-01-01

    Development and recent successful operations of the HTTR in JAERI are coordinated with programs to study applied systems of the promising reactor technology. One such program being carried out from 2001 to 2008 is design and development of the Gas Turbine High Temperature Reactor, GTHTR300, with objective to allow for demonstration of the plant in 2010s in Japan. GTHTR300 features an original design of fuel cycle based on improved HTTR fuel element and of simplified plant system in pursuit of targeted economics with minimum development requirements. The fuel cycle characterizes on high burnup, low power peaking factor and extended refueling interval. The plant system applies such simplified design features as conventional steel RPV, non-intercooled cycle, horizontal single-shaft gas turbine generator and distributed modular maintenance of the overall plant. Research and development essential to validating the design includes component development and control testing. This paper describes the reference plant design and associated continuing R and D activities in JAERI. (author)

  18. Conceptual design tool development for a Pb-Bi cooled reactor

    International Nuclear Information System (INIS)

    Lee, K. G.; Chang, S. H.; No, H. C.; Chunm, M. H.

    2000-01-01

    Conceptual design is generally ill-structured and mysterious problem solving. This leads the experienced experts to be still responsible for the most of synthesis and analysis task, which are not amenable to logical formulations in design problems. Especially because a novel reactor such as a Pb-Bi cooled reactor is going on a conceptual design stage, it will be very meaningful to develop the conceptual design tool. This tool consists of system design module with artificial intelligence, scaling module, and validation module. System design decides the optimal structure and the layout of a Pb-Bi cooled reactor, using design synthesis part and design analysis part. The designed system is scaled to be optimal with desired power level, and then the design basis accidents (Dbase) are analyzed in validation module. Design synthesis part contains the specific data for reactor components and the general data for a Pb-Bi cooled reactor. Design analysis part contains several design constraints for formulation and solution of a design problem. In addition, designer's intention may be externalized through emphasis on design requirements. For the purpose of demonstration, the conceptual design tool is applied to a Pb-Bi cooled reactor with 125 M Wth of power level. The Pb-Bi cooled reactor is a novel reactor concept in which the fission-generated heat is transferred from the primary coolant to the secondary coolant through a reactor vessel wall of a novel design. The Pb-Bi cooled reactor is to deliver 125 M Wth per module for 15 effective full power years without any on-site fuel handling. The conceptual design tool investigated the feasibility of a Pb-Bi cooled reactor. Application of the conceptual design tool will be, in detail, presented in the full paper. (author)

  19. Site-specific analysis of radiological and physical parameters for cobbly soils at the Gunnison, Colorado, processing site

    International Nuclear Information System (INIS)

    1994-01-01

    The remedial action at the Gunnison, Colorado, processing site is being performed under the Uranium Mill Tailings Radiation Control Act (UMTRCA) of 1978. Under UMTRCA, the US Environmental Protection Agency (EPA) is charged with the responsibility of developing appropriate and applicable standards for the cleanup of radiologically contaminated land and buildings at 24 designated sites, including the Gunnison, Colorado, inactive processing site. Section 108 of Public Law 95-604 states that the US Department of Energy (DOE) shall ''select and perform remedial actions at the designated processing sites and disposal sites in accordance with the general standards'' prescribed by the EPA. Regulations governing the required remedial action at inactive uranium processing sites were promulgated by the EPA in 1983 and are contained in 40 CFR Part 192 (1993), Health and Environmental Protection Standards for Uranium and Thorium Mill Tailings. This document describes the radiological and physical parameters for the remedial action of the soil

  20. Design and Development of Fire Gridding Platform Based on Internet of Things

    Directory of Open Access Journals (Sweden)

    Wei San-Xi

    2016-01-01

    Full Text Available This article describes the construction background about fire gridding platform, reviews the research and progress in fire Internet of Things and fire gridding. The platform includes perception / execution layer, field control layer, network layer, center platform layer and application layer, which provide a good bonding about site control and remote monitoring. This article supplies a detail design for the main functions of application and task flow of fire hazard investigation. At the same time, a digital management platform was developed.

  1. Cap stabilization for reclaimed uranium sites

    International Nuclear Information System (INIS)

    Abt, S.R.; Nelson, J.D.; Johnson, T.L.; Hawkins, E.F.

    1989-01-01

    The reclamation and stabilization of uranium-mill tailings sites requires engineering designs to protect against the disruption of tailings and the potential release of radioactive materials. The reclamation design is to be effective for 200-1000 years. This paper presents recently developed or refined techniques and methodologies used to evaluate uranium-tailings-reclamation plans designed to provide long-term stability against failure modes. Specific cap-design aspects presented include design flood selection, influence of fluvial geomorphology on site stabilization, stable slope prediction, slope stabilization using riprap, and riprap selection relative to rock quality and durability. Design relationships are presented for estimating flow through riprap, sizing riprap, and estimating riprap flow resistance for overtopping conditions. Guidelines for riprap-layer thickness and gradation are presented. A riprap-rating procedure for estimating rock quality and durability is also presented

  2. Methods for assessing mine site rehabilitation design for erosion impact

    International Nuclear Information System (INIS)

    Evans, K. G.

    2000-01-01

    Erosion of rehabilitated mines may result in landform instability, which in turn may result in exposure of encapsulated contaminants, elevated sediment delivery at catchment outlets, and subsequent degradation of downstream water quality. Rehabilitation design can be assessed using erosion and hydrology models calibrated to mine site conditions. Incision rates in containment structures can be quantified using 3-dimensional landform evolution simulation techniques. Sediment delivery at catchment outlets for various landform amelioration techniques can be predicted using process-based and empirical erosion-prediction models and sediment delivery ratios. The predicted sediment delivery can be used to estimate an average annual stream sediment load that can, in turn, be used to assess water quality impacts. Application of these techniques is demonstrated through a case study applied to a proposed rehabilitation design option for the Energy Resources of Australia Ltd (ERA) Ranger Mine in the Northern Territory of Australia. Copyright (2000) CSIRO Australia

  3. Preparatory research to develop an operational method to calibrate airborne sensor data using a network of ground calibration sites

    International Nuclear Information System (INIS)

    Milton, E.J.; Smith, G.M.; Lawless, K.P.

    1996-01-01

    The objective of the research is to develop an operational method to convert airborne spectral radiance data to reflectance using a number of well-characterized ground calibration sites located around the UK. The study is in three phases. First, a pilot study has been conducted at a disused airfield in southern England to test the feasibility of the open-quote empirical line close-quote method of sensor calibration. The second phase is developing methods to predict temporal changes in the bidirectional reflectance of ground calibration sites. The final phase of the project will look at methods to extend such calibrations spatially. This paper presents some results from the first phase of this study. The viability of the empirical line method of correction is shown to depend upon the use of ground targets whose in-band reflectance encompasses that of the targets of interest in the spectral band(s) concerned. The experimental design for the second phase of the study, in which methods to predict temporal trends in the bidirectional reflectance of these sites will be developed, is discussed. Finally, it is planned to develop an automated method of searching through Landsat TM data for the UK to identify a number of candidate ground calibration sites for which the model can be tested. 11 refs., 5 figs., 5 tabs

  4. Development of a site-specific water quality criterion for hexavalent chromium

    International Nuclear Information System (INIS)

    McIntyre, D.O.; Sticko, J.P.; Reash, R.J.

    1995-01-01

    The effluent of treated fly ash from a coal-fired power plant located on the Ohio River periodically exceeds its NPDES acute permit limit for hexavalent chromium of 15 microg/L. The increased levels of hexavalent chromium in the effluent are a recent occurrence which are likely due to changes in coal blends burned in the generating units. Ohio EPA determined the use designation of the receiving stream (Limited Resource Water) was being attained and a one-year biomonitoring program of the effluent detected no acute toxicity to Ceriodaphnia dubia or Daphnia magna. The water-effect ratio (WER) procedure was selected to develop a site-specific criterion maximum concentration for hexavalent chromium for the effluent's receiving stream. WER procedures followed those described in EPA's ''Interim Guidance on Determination and Use of Water-Effect Ratios for Metals'' (1994). Site water used in the WER determinations was undiluted effluent since the receiving stream originates at the discharge point of the outfall. 48-hour acute D. magna and 96-hour acute fathead minnow toxicity tests were selected as the primary and secondary tests, respectively for use in three seasonal WER determinations. The results of the three WER determinations and the status of the regulatory process will be presented

  5. Mobile hot cell transition design phase study for radioactive waste treatment on the Hanford reservation site

    International Nuclear Information System (INIS)

    Pons, Y.

    2010-01-01

    Full text of publication follows: At the US Department of Energy's Hanford Reservation site, 4 caissons in under ground storage contain approximately 23 cubic meters of Transuranic (TRU) waste, in over 5,000 small packages. The retrieval of these wastes presents a number of very difficult issues, including the configuration of the vaults, approximately 50,000 curies of activity, high dose rates, and damaged/degraded waste packages. The waste will require remote retrieval and processing sufficient to produce certifiable RH-TRU waste packages. This RH-TRU will be packaged for staging on site until certification by CCP is completed to authorize shipment to the Waste Isolation Pilot Plant (WIPP). The project has introduced AREVA' s innovative Hot Mobile Cell (HMC) technology to perform size reduction, sorting, characterization, and packaging of the RH waste stream at the point of generation, the retrieval site in the field. This approach minimizes dose and hazard exposure to workers that is usually associated with this operation. The HMC can also be used to provide employee protection, weather protection, and capacity improvements similar to those realized in general burial ground. AREVA TA and his partner AFS will provide this technology based on the existing HMCs developed and operated in France: - ERFB (Bituminized Waste Drum Retrieval Facility): ERFB was built specifically for retrieving the bituminized waste drums (approximately 6,000 stored in trenches in the North zone on the Marcoule site (in operation since 2001). - ERCF (Waste Drum Recovery and Packaging Facility): The ERCF was built specifically to retrieve bituminized waste drums stored in 35 pits located in the south area on Marcoule site (in operation) - FOSSEA (Legacy Waste Removal and Trench Cleanup): The FOSSEA project consists of the retrieval of waste stored on the Basic Nuclear Facility. Waste from the 56 trenches will be inspected, characterised, and if necessary processed or repackaged, and

  6. Response spectra by blind faults for design purpose of stiff structures on rock site

    International Nuclear Information System (INIS)

    Hiroyuki Mizutani; Kenichi Kato; Masayuki Takemura; Kazuhiko Yashiro; Kazuo Dan

    2005-01-01

    The goal of this paper is to propose the response spectra by blind faults for seismic design of nuclear power facilities. It is impossible to evaluate earthquake ground motions from blind faults, because the size and the location of blind fault cannot be identified even if the detailed geological surveys are conducted. From the viewpoint of seismic design, it is crucial to investigate the upper level of earthquake ground motions due to blind faults. In this paper, 41 earthquakes that occurred in the upper crust in Japan and California are selected and classified into the active and the blind fault types. On the basis of near-source strong motion records observed on rock sites, upper level of response spectra by blind faults is examined. The estimated upper level is as follows: the peak ground acceleration is 450 cm/s 2 , the flat level of the acceleration response spectra is 1200 cm/s 2 , and the flat level of the velocity response spectra is 100 cm/s on rock sites with shear wave velocity Vs of about 700 m/s. The upper level can envelop the observed response spectra in near-source region on rock sites. (authors)

  7. Nevada National Security Site: Site-Directed Research and Development (SDRD) Fiscal Year 2015 Annual Report

    Energy Technology Data Exchange (ETDEWEB)

    Bender, Howard A. [National Security Technologies, LLC. (NSTec), Mercury, NV (United States). Site-Directed Research and Development Program

    2016-04-01

    This report presents results of multiple research projects, new and ongoing, funded under the Site-Directed Research and Development Program for the Nevada National Security Site during federal fiscal year 2015. The Site's legacy capabilities in remote sensing combined with new paradigms for emergency response and consequence management help drive the need to develop advanced aerial sensor platforms. Likewise, dynamic materials science is a critical area of scientific research for which basic physics issues are still unresolved. New methods of characterizing materials in extreme states are vitally needed, and these efforts are paving the way with new knowledge. Projects selected in FY 2015 for the Exploratory Research portfolio exhibit a strong balance of NNSS mission relevance. Geoscience, seismology, and techniques for detecting underground nuclear events are still essential focus areas. Many of the project reports in the second major section of this annual report are ongoing continuations in multi-year lifecycles. Diagnostic techniques for stockpile and nuclear security science figured prominently as well, with a few key efforts coming to fruition, such as phase transition detection. In other areas, modeling efforts toward better understanding plasma focus physics has also started to pay dividends for major program needs.

  8. Development of a decision support system for off-site emergency management in the early phase of a nuclear accident

    International Nuclear Information System (INIS)

    Datta, D.; Sharma, R.M.

    2002-01-01

    Full text: Experience gained after the Chernobyl accident clearly demonstrated the importance of improving administrative, organizational and technical emergency management arrangements in India. The more important areas where technical improvements were needed were early warning monitoring, communication networks for the rapid and reliable exchange of radiological and other information and decision support systems for off-site emergency management. A PC based artificial intelligent software has been developed to have a decision support system that can easily implement to manage off-site nuclear emergency and subsequently analyze the off-site consequences of the nuclear accident. A decision support tool, STEPS (source term estimate based on plant status), that provides desired input to the present software was developed. The tool STEPS facilitates meta knowledge of the system. The paper describes the details of the design of the software, functions of various modules, tuning of respective knowledge base and overall its scope in real sense in nuclear emergency preparedness and response

  9. Bifunctional chelating agent for the design and development of site specific radiopharmaceuticals and biomolecule conjugation strategy

    Science.gov (United States)

    Katti, Kattesh V.; Prabhu, Kandikere R.; Gali, Hariprasad; Pillarsetty, Nagavara Kishore; Volkert, Wynn A.

    2003-10-21

    There is provided a method of labeling a biomolecule with a transition metal or radiometal in a site specific manner to produce a diagnostic or therapeutic pharmaceutical compound by synthesizing a P.sub.2 N.sub.2 -bifunctional chelating agent intermediate, complexing the intermediate with a radio metal or a transition metal, and covalently linking the resulting metal-complexed bifunctional chelating agent with a biomolecule in a site specific manner. Also provided is a method of synthesizing the --PR.sub.2 containing biomolecules by synthesizing a P.sub.2 N.sub.2 -bifunctional chelating agent intermediate, complexing the intermediate with a radiometal or a transition metal, and covalently linking the resulting radio metal-complexed bifunctional chelating agent with a biomolecule in a site specific manner. There is provided a therapeutic or diagnostic agent comprising a --PR.sub.2 containing biomolecule.

  10. Learning Design Development for Blended Learning

    DEFF Research Database (Denmark)

    Hansen, Janne Saltoft

    Learning design development for blended learning We started implementing Blackboard at Aarhus University in 2013. At the Health Faculty Blackboard replaced AULA which was a LMS with functionality for file distribution and only a vague focus on learning tools. Most teachers therefore had...... no experiences with blended leaning and technology supported out-of-class activities. At the pedagogical unit at the Health faculty we wanted to follow the Blackboard implementation with pedagogical tools for learning design to evolve the pedagogical use of the system. We needed to make development of blended...... learning courses easier for the teachers and also ensure quality in the courses. This poster describes the process from development of the learning design to implementation of the learning design at the faculty: 1. How to place demands on a learning design-model and how to develop and use such a model. 2...

  11. The design, development, and test of balloonborne and groundbased lidar systems. Volume 3: Groundbased lidar systems

    Science.gov (United States)

    Shepherd, O.; Aurilio, G.; Bucknam, R. D.; Hurd, A. G.; Robertie, N. F.

    1991-06-01

    This is Volume 3 of a three volume final report on the design, development and test of balloonborne and groundbased lidar systems. Volume 1 describes the design and fabrication of a balloonborne CO2 coherent payload to measure the 10.6 micrometers backscatter from atmospheric aerosols as a function of altitude. Volume 2 describes the August 1987 flight test of Atmospheric Balloonborne Lidar Experiment, ABLE 2. In this volume we describe groundbased lidar development and measurements. A design was developed for installation of the ABLE lidar in the GL rooftop dome. A transportable shed was designed to house the ABLE lidar at the various remote measurement sites. Refurbishment and modification of the ABLE lidar were completed to permit groundbased lidar measurements of clouds and aerosols. Lidar field measurements were made at Ascension Island during SABLE 89. Lidar field measurements were made at Terciera, Azores during GABLE 90. These tasks have been successfully completed, and recommendations for further lidar measurements and data analysis have been made.

  12. Primer on the implementation of a pharmacy intranet site to improve department communication.

    Science.gov (United States)

    Hale, Holly J

    2013-07-01

    The purpose of the article is to describe the experience of selecting, developing, and implementing a pharmacy department intranet site with commentary regarding application to other institutions. Clinical practitioners and supporting staff need an effective, efficient, organized, and user-friendly communication tool to utilize and relay information required to optimize patient care. To create a functional and user-friendly department intranet site, department leadership and staff should be involved in the process from selection of product through implementation. A product that supports both document storage management and communication delivery and has the capability to be customized to provide varied levels of site access is desirable. The designation of an intranet site owner/developer within the department will facilitate purposeful site design and site maintenance execution. A well-designed and up-to-date site along with formal end-user training are essential for staff adoption and continued utilization. Development of a department intranet site requires a considerable time investment by several members of the department. The implementation of an intranet site can be an important step toward achieving improved communications. Staff utilization of this resource is key to its success.

  13. Development of core design technology for LMR

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Young Jin; Kim Young In; Kim, Young Il; Kim, Y. G.; Kim, S. J.; Song, H.; Kim, T. K.; Kim, W. S.; Hwang, W.; Lee, B. O.; Park, C. K.; Joo, H. K.; Yoo, J. W.; Kang, H. Y.; Park, W. S

    2000-05-01

    For the development of KALIMER (150 MWe) core conceptual design, design evolution and optimization for improved economics and safety enhancement was performed in the uranium metallic fueled equilibrium core design which uses U-Zr binary fuel not in excess of 20 percent enrichment. Utilizing results of the uranium ,metallic fueled core design, the breeder equilibrium core design with breeding ratio being over 1.1 was developed. In addition, utilizing LMR's excellent neutron economy, various core concepts for minor actinide burnup, inherent safety, economics and non-proliferation were realized and its optimization studies were performed. A code system for the LMR core conceptual design has been established through the implementation of needed functions into the existing codes and development of codes. To improve the accuracy of the core design, a multi-dimensional nodal transport code SOLTRAN, a three-dimensional transient code analysis code STEP, MATRA-LMR and ASSY-P for T/H analysis are under development. Through the automation of design calculations for efficient core design, an input generator and several interface codes have been developed. (author)

  14. Site Recommendation Subsurface Layout

    International Nuclear Information System (INIS)

    C.L. Linden

    2000-01-01

    The purpose of this analysis is to develop a Subsurface Facility layout that is capable of accommodating the statutory capacity of 70,000 metric tons of uranium (MTU), as well as an option to expand the inventory capacity, if authorized, to 97,000 MTU. The layout configuration also requires a degree of flexibility to accommodate potential changes in site conditions or program requirements. The objective of this analysis is to provide a conceptual design of the Subsurface Facility sufficient to support the development of the Subsurface Facility System Description Document (CRWMS M andO 2000e) and the ''Emplacement Drift System Description Document'' (CRWMS M andO 2000i). As well, this analysis provides input to the Site Recommendation Consideration Report. The scope of this analysis includes: (1) Evaluation of the existing facilities and their integration into the Subsurface Facility design. (2) Identification and incorporation of factors influencing Subsurface Facility design, such as geological constraints, thermal loading, constructibility, subsurface ventilation, drainage control, radiological considerations, and the Test and Evaluation Facilities. (3) Development of a layout showing an available area in the primary area sufficient to support both the waste inventories and individual layouts showing the emplacement area required for 70,000 MTU and, if authorized, 97,000 MTU

  15. Development of core design technology for LMR

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Young Jin; In, Kim Young; Kim, Young Il; Kim, Y G; Kim, S J; Song, H; Kim, T K; Kim, W S; Hwang, W; Lee, B O; Park, C K; Joo, H K; Yoo, J W; Kang, H Y; Park, W S

    2000-05-01

    For the development of KALIMER (150 MWe) core conceptual design, design evolution and optimization for improved economics and safety enhancement was performed in the uranium metallic fueled equilibrium core design which uses U-Zr binary fuel not in excess of 20 percent enrichment. Utilizing results of the uranium ,metallic fueled core design, the breeder equilibrium core design with breeding ratio being over 1.1 was developed. In addition, utilizing LMR's excellent neutron economy, various core concepts for minor actinide burnup, inherent safety, economics and non-proliferation were realized and its optimization studies were performed. A code system for the LMR core conceptual design has been established through the implementation of needed functions into the existing codes and development of codes. To improve the accuracy of the core design, a multi-dimensional nodal transport code SOLTRAN, a three-dimensional transient code analysis code STEP, MATRA-LMR and ASSY-P for T/H analysis are under development. Through the automation of design calculations for efficient core design, an input generator and several interface codes have been developed. (author)

  16. Site scientific mission plan for the southern Great Plain CART site July-December 1997.

    Energy Technology Data Exchange (ETDEWEB)

    Lamb, P.J.; Peppler, R.A.; Sisterson, D.L.

    1997-08-28

    The Southern Great Plains (SGP) Cloud and Radiation Testbed (CART) site is designed to help satisfy the data needs of the Atmospheric Radiation Measurement (ARM) Program Science Team. This document defines the scientific priorities for site activities during the six months beginning on July 1, 1997, and looks forward in lesser detail to subsequent six-month periods. The primary purpose of this Site Scientific Mission Plan is to provide guidance for the development of plans for site operations. It also provides information on current plans to the ARM functional teams (Management Team, Data and Science Integration Team [DSIT], Operations Team, Instrument Team [IT], and Campaign Team) and serves to disseminate the plans more generally within the ARM Program and among the members of the Science Team. This document includes a description of the operational status of the site and the primary site activities envisioned, together with information concerning approved and proposed intensive observation periods (IOPs). The primary users of this document are the site operator, the Site Scientist Team (SST), the Science Team through the ARM Program science director, the ARM Program Experiment Center, and the aforementioned ARM Program functional teams. This plan is a living document that is updated and reissued every six months as the observational facilities are developed, tested, and augmented and as priorities are adjusted in response to developments in scientific planning and understanding.

  17. A Website Design with the Mobile-first Approach

    OpenAIRE

    Satyal, Umesh

    2016-01-01

    This thesis aims to explain the mobile first design approach in web design and development and its advantages over other prevalent approaches. In the study, the mobile web, its trends and different approaches for design and developing a mobile first web application are described and a comparison between mobile sites and mobile first sites is made. The concept of responsive web design and different grid systems are discussed as they are essential factors for responsive web design. Duri...

  18. Low-level waste disposal site selection demonstration

    International Nuclear Information System (INIS)

    Rogers, V.C.

    1984-01-01

    This paper discusses the results of recent studies undertaken at EPRI related to low-level waste disposal technology. The initial work provided an overview of the state of the art including an assessment of its influence upon transportation costs and waste form requirements. The paper discusses work done on the overall system design aspects and computer modeling of disposal site performance characteristics. The results of this analysis are presented and provide a relative ranking of the importance of disposal parameters. This allows trade-off evaluations to be made of factors important in the design of a shallow land burial facility. To help minimize the impact of a shortage of low-level radioactive waste disposal sites, EPRI is closely observing the development of bellweather projects for developing new sites. The purpose of this activity is to provide information about lessons learned in those projects in order to expedite the development of additional disposal facilities. This paper describes most of the major stems in selecting a low-level radioactive waste disposal site in Texas. It shows how the Texas Low-Level Radioactive Waste Disposal Authority started with a wide range of potential siting areas in Texas and narrowed its attention down to a few preferred sites. The parameters used to discriminate between large areas of Texas and, eventually, 50 candidate disposal sites are described, along with the steps in the process. The Texas process is compared to those described in DOE and EPRI handbooks on site selection and to pertinent NRC requirements. The paper also describes how an inventory of low-level waste specific to Texas was developed and applied in preliminary performance assessments of two candidate sites. Finally, generic closure requirements and closure operations for low-level waste facilities in arid regions are given

  19. The Role of Adolescent Development in Social Networking Site Use: Theory and Evidence

    Directory of Open Access Journals (Sweden)

    Drew P. Cingel

    2014-03-01

    Full Text Available Using survey data collected from 260 children, adolescents, and young adults between the ages of 9 and 26, this paper offers evidence for a relationship between social networking site use and Imaginary Audience, a developmental variable in which adolescents believe others are thinking about them at all times. Specifically, after controlling for a number of variables, results indicate a significant, positive relationship between social networking site use and Imaginary Audience ideation. Additionally, results indicate a positive relationship between Imaginary Audience ideation and Facebook customization practices. Together, these findings provide evidence, based on Vygotskian developmental theory, for a general consideration of the role that currently available tools, in this case social networking sites, can have on development. Thus, findings implicate both the role of development on social networking site use, as well as the role of social networking site use on development. Overall, these findings have important implications for the study of media and human development, which are discussed in detail.

  20. Spectral Shapes for accelerograms recorded at rock sites

    International Nuclear Information System (INIS)

    Ghosh, A.K.; Muralidharan, N.; Sharma, R.D.

    1986-01-01

    Earthquake accelerograms recorded on rock sites have been analysed to develop site-specific response spectra for use in aseismic design. Normalized pseudo absolute acceleration spectra for various values of damping, pertinent to nuclear power plant design in particular are presented. Various ground motion parameters, viz. peak displacement, velocity acceleration (including v/a, ad/v 2 and the ratios of the three orthogonal components) for fifty four accelerograms are examined through motion time histories to be used in structural response analysis. The analysis presented in this paper aims at specifying site specific response spectra for earthquake resistant design of structures and generation of spectrum compatible accelerograms. The salient features of the data set have been discussed. (author)

  1. Hydrogeochemical site descriptive model - a strategy for the model development during site investigations

    International Nuclear Information System (INIS)

    Smellie, John; Laaksoharju, Marcus; Tullborg, Eva-Lena

    2002-12-01

    In 2002, SKB commenced site characterisation investigations using deep boreholes at different sites. As an integral part of the planning work SKB has prepared a strategy to develop a Hydrogeochemical Site Descriptive Model; similar strategies have been developed for the other major geoscience disciplines. The main objectives of the Hydrogeochemical Site Descriptive Model are to describe the chemistry and distribution of the groundwater in the bedrock and overburden and the hydrogeochemical processes involved in its origin and evolution. This description is based primarily on measurements of the groundwater composition but incorporates the use of available geological and hydrogeological site descriptive models. The SKB hydrogeochemistry programme is planned to fulfil two basic requirements: 1) to provide representative and quality assured data for use as input parameter values in calculating long-term repository safety, and 2) to understand the present undisturbed hydrogeochemical conditions and how these conditions will change in the future. Parameter values for safety analysis include pH, Eh, S, SO 4 , HCO 3 , HPO 4 and TDS (mainly cations), together with colloids, fulvic and humic acids, other organics, bacteria and nitrogen. These values will be used to characterise the groundwater environment at, above and below repository depths. In the hydrogeochemical site investigation programme the number and location of the sampling points will be constrained by: a) geology (e.g. topography, overburden types, bedrock structures etc), b) hydrogeology (e.g. groundwater recharge/discharge areas, residence times), c) reliability (e.g. undisturbed vs disturbed groundwater chemical conditions), and d) resources (e.g. number and type of samples, and also available personnel, may be restricted by budgetary and schedule concerns). Naturally a balance is required between these constraints and the scientific aims of the programme. The constraints should never detrimentally affect

  2. Title I conceptual design for Pit 6 landfill closure at Lawrence Livermore National Laboratory Site 300

    International Nuclear Information System (INIS)

    MacDonnell, B.A.; Obenauf, K.S.

    1996-08-01

    The objective of this design project is to evaluate and prepare design and construction documents for a closure cover cap for the Pit 6 Landfill located at Lawrence Livermore National Laboratory Site 300. This submittal constitutes the Title I Design (Conceptual Design) for the closure cover of the Pit 6 Landfill. A Title I Design is generally 30 percent of the design effort. Title H Design takes the design to 100 percent complete. Comments and edits to this Title I Design will be addressed in the Title II design submittal. Contents of this report are as follows: project background; design issues and engineering approach; design drawings; calculation packages; construction specifications outline; and construction quality assurance plan outline

  3. Hydrogeochemical site descriptive model - a strategy for the model development during site investigations

    Energy Technology Data Exchange (ETDEWEB)

    Smellie, John [Conterra AB, Uppsala (Sweden); Laaksoharju, Marcus [GeoPoint AB, Sollentuna (Sweden); Tullborg, Eva-Lena [Terralogica AB, Graabo (Sweden)

    2002-12-01

    In 2002, SKB commenced site characterisation investigations using deep boreholes at different sites. As an integral part of the planning work SKB has prepared a strategy to develop a Hydrogeochemical Site Descriptive Model; similar strategies have been developed for the other major geoscience disciplines. The main objectives of the Hydrogeochemical Site Descriptive Model are to describe the chemistry and distribution of the groundwater in the bedrock and overburden and the hydrogeochemical processes involved in its origin and evolution. This description is based primarily on measurements of the groundwater composition but incorporates the use of available geological and hydrogeological site descriptive models. The SKB hydrogeochemistry programme is planned to fulfil two basic requirements: 1) to provide representative and quality assured data for use as input parameter values in calculating long-term repository safety, and 2) to understand the present undisturbed hydrogeochemical conditions and how these conditions will change in the future. Parameter values for safety analysis include pH, Eh, S, SO{sub 4}, HCO{sub 3}, HPO{sub 4} and TDS (mainly cations), together with colloids, fulvic and humic acids, other organics, bacteria and nitrogen. These values will be used to characterise the groundwater environment at, above and below repository depths. In the hydrogeochemical site investigation programme the number and location of the sampling points will be constrained by: a) geology (e.g. topography, overburden types, bedrock structures etc), b) hydrogeology (e.g. groundwater recharge/discharge areas, residence times), c) reliability (e.g. undisturbed vs disturbed groundwater chemical conditions), and d) resources (e.g. number and type of samples, and also available personnel, may be restricted by budgetary and schedule concerns). Naturally a balance is required between these constraints and the scientific aims of the programme. The constraints should never

  4. Developing Educational Materials about Risks on Social Network Sites: A Design Based Research Approach

    Science.gov (United States)

    Vanderhoven, Ellen; Schellens, Tammy; Vanderlinde, Ruben; Valcke, Martin

    2016-01-01

    Nearly all of today's Western teenagers have a profile on a social network site (SNS). As many risks have been reported, researchers and governments have emphasized the role of school education to teach teenagers how to deal safely with SNSs. However, little is known about the specific characteristics which would make interventions effective.…

  5. The JINR Tier1 Site Simulation for Research and Development Purposes

    Directory of Open Access Journals (Sweden)

    Korenkov V.

    2016-01-01

    A system for grid and cloud services simulation is developed at LIT (JINR, Dubna. This simulation system is focused on improving the effciency of the grid/cloud structures development by using the work quality indicators of some real system. The development of such kind of software is very important for making a new grid/cloud infrastructure for such big scientific experiments like the JINR Tier1 site for WLCG. The simulation of some processes of the Tier1 site is considered as an example of our application approach.

  6. Radioactive Waste Evaporation: Current Methodologies Employed for the Development, Design, and Operation of Waste Evaporators at the Savannah River Site and Hanford Waste Treatment Plant

    International Nuclear Information System (INIS)

    Calloway, T.B.

    2003-01-01

    Evaporation of High level and Low Activity (HLW and LAW) radioactive wastes for the purposes of radionuclide separation and volume reduction has been conducted at the Savannah River and Hanford Sites for more than forty years. Additionally, the Savannah River Site (SRS) has used evaporators in preparing HLW for immobilization into a borosilicate glass matrix. This paper will discuss the methodologies, results, and achievements of the SRTC evaporator development program that was conducted in support of the SRS and Hanford WTP evaporator processes. The cross pollination and application of waste treatment technologies and methods between the Savannah River and Hanford Sites will be highlighted. The cross pollination of technologies and methods is expected to benefit the Department of Energy's Mission Acceleration efforts by reducing the overall cost and time for the development of the baseline waste treatment processes

  7. Site Scientific Mission Plan for the Southern Great Plains CART site: January--June 1994

    Energy Technology Data Exchange (ETDEWEB)

    Schneider, J.M.; Lamb, P.J. [Univ. of Oklahoma, Norman, OK (United States). Cooperative Inst. for Mesoscale Meteorological Studies; Sisterson, D.L. [Argonne National Lab., IL (United States). Environmental Research Div.

    1993-12-01

    The Southern Great Plains (SGP) Cloud and Radiation Testbed (CART) site is designed to help satisfy the data needs of the Atmospheric Radiation Measurement (ARM) Program Science Team. This document defines the scientific priorities for site activities during the six months beginning on January 1, 1994, and also looks forward in lesser detail to subsequent six-month periods. The primary purpose of this Site Scientific Mission Plan is to provide guidance for the development of plans for site operations. It also provides information on current plans to the ARM Functional Teams (Management Team, Experiment Support Team, Operations Team, Data Management Team, Instrument Team, and Campaign Team), and it serves to disseminate the plans more generally within the ARM Program and among the Science Team. This document includes a description of the site`s operational status and the primary envisaged site activities, together with information concerning approved and proposed Intensive Observation Periods. Amendments will be prepared and distributed whenever the content changes by more than 30% within a six-month period. The primary users of this document are the site operator, the site scientist, the Science Team through the ARM Program Science Director, the ARM Program Experiment Center, and the aforementioned ARM Program Functional Teams. This plan is a living document that will be updated and reissued every six months as the observational facilities are developed, tested, and augmented and as priorities are adjusted in response to developments in scientific planning and understanding.

  8. Remedial Action Plan and site conceptual design for stabilization of the inactive uranium mill tailings site at Spook, Wyoming

    Energy Technology Data Exchange (ETDEWEB)

    Matthews, M L [USDOE Albuquerque Operations Office, NM (United States). Uranium Mill Tailings Remedial Action Project Office; Sullivan, M [Wyoming State Government, Cheyenne, WY (United States)

    1990-04-01

    This Remedial Action Plan (RAP) has been developed to serve a threefold purpose. It presents the series of activities which are proposed by the US Department of Energy (DOE) to accomplish long-term stabilization and control of radioactive materials at an inactive uranium processing site northeast of Casper, Wyoming, and referred to as the Spook site. It provides a characterization of the present conditions at the site and also serves to document the concurrence of the State of Wyoming and the US Nuclear Regulatory Commission (NRC) in the remedial action. This agreement, upon execution by the DOE and the State of Wyoming, and concurrence by the NRC, becomes Appendix B of the Cooperative Agreement.

  9. Remedial Action Plan and site conceptual design for stabilization of the inactive uranium mill tailings site at Spook, Wyoming

    International Nuclear Information System (INIS)

    Matthews, M.L.

    1990-04-01

    This Remedial Action Plan (RAP) has been developed to serve a threefold purpose. It presents the series of activities which are proposed by the US Department of Energy (DOE) to accomplish long-term stabilization and control of radioactive materials at an inactive uranium processing site northeast of Casper, Wyoming, and referred to as the Spook site. It provides a characterization of the present conditions at the site and also serves to document the concurrence of the State of Wyoming and the US Nuclear Regulatory Commission (NRC) in the remedial action. This agreement, upon execution by the DOE and the State of Wyoming, and concurrence by the NRC, becomes Appendix B of the Cooperative Agreement

  10. Developing and promoting an intranet site for a drug information service.

    Science.gov (United States)

    Costerison, Emily C; Graham, Angie S

    2008-04-01

    The development and promotion of a drug information service (DIS) intranet site are described. Stanford Hospital and Clinics (SHC) is an acute and tertiary care facility with 613 licensed inpatient beds and 48 outpatient clinics. A DIS intranet site was developed to allow better accessibility to pharmacy forms and products (e.g., drug shortage list, reference guides) and to reduce repetitive requests to the DIS. The goal was to continue to provide information to SHC health care providers but allow the drug information specialist to focus on answering clinical questions. The intranet site was completed over a four-month period. The intranet site was divided into seven webpages: DIS overview, pharmacy and therapeutics, frequently asked questions, quick drug reference guide, ask the pharmacist, drug information resources, and referral center. The preparation for and implementation of the promotional phase took approximately two months. Promotional strategies included the creation and dissemination of brochures and stickers. The intranet site went live on January 1, 2007, and the advertising campaign began one month later. The utility of the site was measured for five months by tracking the number of visits to the site, the number of visits to each webpage, and the number of downloaded files. Request volume, caller affiliation, and question types received by the DIS call center were also recorded. Establishing a DIS intranet site required a considerable time investment and a willingness to work with existing infrastructures, such as the marketing and communications department and Web marketing staff.

  11. Savannah River Site reactor hardware design modification study

    International Nuclear Information System (INIS)

    Fisher, J.E.

    1990-01-01

    A study was undertaken to assess the merits of proposed design modifications to the Savannah River Site (SRS) reactors. The evaluation was based on the responses calculated by the RELAP5 systems code to double-ended guillotine break loss-of-coolant-accidents (DEGB LOCAs). The three concepts evaluated were (a) elevated plenum inlet piping with a guard vessel and clamshell enclosures, (b) closure of both rotovalves in the affected loop, and (c) closure of the pump suction valve in the affected loop. Each concept included a fast reactor shutdown (to 65% power in 100 ms) and a 2-s ac pump trip. System recovery potential was evaluated for break locations at the pump suction, the pump discharge, and the plenum inlet. The code version used was RELAP5/MOD2.5 version 3d3, a preliminary version of RELAP5/MOD3. The model was a three-dimensional representation of the K-Reactor water plenum and moderator tank. It included explicit representations of all six loops, which were based on the configuration of L-Reactor. A combination of features is recommended to ensure liquid inventory recovery for all break locations. Valve closure design performance for a break location in the short section of piping between the reactor concrete shield and the pump suction valve would benefit from the clamshell enclosing that section of piping. 7 refs., 10 figs., 2 tabs

  12. Geothermal energy in Idaho: site data base and development status

    Energy Technology Data Exchange (ETDEWEB)

    McClain, D.W.

    1979-07-01

    Detailed site specific data regarding the commercialization potential of the proven, potential, and inferred geothermal resource areas in Idaho are presented. To assess the potential for geothermal resource development in Idaho, several kinds of data were obtained. These include information regarding institutional procedures for geothermal development, logistical procedures for utilization, energy needs and forecasted demands, and resource data. Area reports, data sheets, and scenarios were prepared that described possible geothermal development at individual sites. In preparing development projections, the objective was to base them on actual market potential, forecasted growth, and known or inferred resource conditions. To the extent possible, power-on-line dates and energy utilization estimates are realistic projections of the first events. Commercialization projections were based on the assumption that an aggressive development program will prove sufficient known and inferred resources to accomplish the projected event. This report is an estimate of probable energy developable under an aggressive exploration program and is considered extremely conservative. (MHR)

  13. Computer code development plant for SMART design

    International Nuclear Information System (INIS)

    Bae, Kyoo Hwan; Choi, S.; Cho, B.H.; Kim, K.K.; Lee, J.C.; Kim, J.P.; Kim, J.H.; Chung, M.; Kang, D.J.; Chang, M.H.

    1999-03-01

    In accordance with the localization plan for the nuclear reactor design driven since the middle of 1980s, various computer codes have been transferred into the korea nuclear industry through the technical transfer program from the worldwide major pressurized water reactor supplier or through the international code development program. These computer codes have been successfully utilized in reactor and reload core design works. As the results, design- related technologies have been satisfactorily accumulated. However, the activities for the native code development activities to substitute the some important computer codes of which usages are limited by the original technique owners have been carried out rather poorly. Thus, it is most preferentially required to secure the native techniques on the computer code package and analysis methodology in order to establish the capability required for the independent design of our own model of reactor. Moreover, differently from the large capacity loop-type commercial reactors, SMART (SYSTEM-integrated Modular Advanced ReacTor) design adopts a single reactor pressure vessel containing the major primary components and has peculiar design characteristics such as self-controlled gas pressurizer, helical steam generator, passive residual heat removal system, etc. Considering those peculiar design characteristics for SMART, part of design can be performed with the computer codes used for the loop-type commercial reactor design. However, most of those computer codes are not directly applicable to the design of an integral reactor such as SMART. Thus, they should be modified to deal with the peculiar design characteristics of SMART. In addition to the modification efforts, various codes should be developed in several design area. Furthermore, modified or newly developed codes should be verified their reliability through the benchmarking or the test for the object design. Thus, it is necessary to proceed the design according to the

  14. Computer code development plant for SMART design

    Energy Technology Data Exchange (ETDEWEB)

    Bae, Kyoo Hwan; Choi, S.; Cho, B.H.; Kim, K.K.; Lee, J.C.; Kim, J.P.; Kim, J.H.; Chung, M.; Kang, D.J.; Chang, M.H

    1999-03-01

    In accordance with the localization plan for the nuclear reactor design driven since the middle of 1980s, various computer codes have been transferred into the korea nuclear industry through the technical transfer program from the worldwide major pressurized water reactor supplier or through the international code development program. These computer codes have been successfully utilized in reactor and reload core design works. As the results, design- related technologies have been satisfactorily accumulated. However, the activities for the native code development activities to substitute the some important computer codes of which usages are limited by the original technique owners have been carried out rather poorly. Thus, it is most preferentially required to secure the native techniques on the computer code package and analysis methodology in order to establish the capability required for the independent design of our own model of reactor. Moreover, differently from the large capacity loop-type commercial reactors, SMART (SYSTEM-integrated Modular Advanced ReacTor) design adopts a single reactor pressure vessel containing the major primary components and has peculiar design characteristics such as self-controlled gas pressurizer, helical steam generator, passive residual heat removal system, etc. Considering those peculiar design characteristics for SMART, part of design can be performed with the computer codes used for the loop-type commercial reactor design. However, most of those computer codes are not directly applicable to the design of an integral reactor such as SMART. Thus, they should be modified to deal with the peculiar design characteristics of SMART. In addition to the modification efforts, various codes should be developed in several design area. Furthermore, modified or newly developed codes should be verified their reliability through the benchmarking or the test for the object design. Thus, it is necessary to proceed the design according to the

  15. In situ gamma spectrometry development for site mapping

    International Nuclear Information System (INIS)

    Panza, F.

    2012-01-01

    The high-resolution gamma spectrometry currently provides a powerful analytical tool for performing environmental measurements. In the context of radiological characterization of a site (natural or artificial radioactivity) and for the dismantling of nuclear installations, mapping of radionuclides is an important asset. The idea is to move a HPGe spectrometer to study the site and from nuclear and position data, to identify, to locate and to quantify the radionuclides present in the soil. The development of this tool follows an intercomparison (ISIS 2007) where an intervention/crisis exercise showed the limits of current tools. The main part of this research project has focused on mapping of nuclear data. Knowledge of the parameters of an in situ spectrum helped to create a simulator, modeling the response of a spectrometer moving over contaminated soil. The simulator itself helped to develop algorithms for mapping and to test them in extreme situations and not realizable. A large part of this research leads to the creation of a viable prototype providing real-time information concerning the identity and locality as possible radionuclides. The work performed on the deconvolution of data can make in post processing a map of the activity of radionuclide soil but also an indication of the depth distribution of the source. The prototype named OSCAR was tested on contaminated sites (Switzerland and Japan) and the results are in agreement with reference measurements. (author)

  16. Development of a site analysis tool for distributed wind projects

    Energy Technology Data Exchange (ETDEWEB)

    Shaw, Shawn [The Cadmus Group, Inc., Waltham MA (United States)

    2012-02-28

    The Cadmus Group, Inc., in collaboration with the National Renewable Energy Laboratory (NREL) and Encraft, was awarded a grant from the Department of Energy (DOE) to develop a site analysis tool for distributed wind technologies. As the principal investigator for this project, Mr. Shawn Shaw was responsible for overall project management, direction, and technical approach. The product resulting from this project is the Distributed Wind Site Analysis Tool (DSAT), a software tool for analyzing proposed sites for distributed wind technology (DWT) systems. This user-friendly tool supports the long-term growth and stability of the DWT market by providing reliable, realistic estimates of site and system energy output and feasibility. DSAT-which is accessible online and requires no purchase or download of software-is available in two account types; Standard: This free account allows the user to analyze a limited number of sites and to produce a system performance report for each; and Professional: For a small annual fee users can analyze an unlimited number of sites, produce system performance reports, and generate other customizable reports containing key information such as visual influence and wind resources. The tool’s interactive maps allow users to create site models that incorporate the obstructions and terrain types present. Users can generate site reports immediately after entering the requisite site information. Ideally, this tool also educates users regarding good site selection and effective evaluation practices.

  17. Berm design to reduce risks of catastrophic slope failures at solid waste disposal sites.

    Science.gov (United States)

    De Stefano, Matteo; Gharabaghi, Bahram; Clemmer, Ryan; Jahanfar, M Ali

    2016-11-01

    Existing waste disposal sites are being strained by exceeding their volumetric capacities because of exponentially increasing rates of municipal solid waste generation worldwide, especially in densely populated metropolises. Over the past 40 years, six well-documented and analyzed disposal sites experienced catastrophic failure. This research presents a novel analysis and design method for implementation of a series of in-situ earth berms to slow down the movement of waste material flow following a catastrophic failure. This is the first study of its kind that employs a dynamic landslide analysis model, DAN-W, and the Voellmy rheological model to approximate solid waste avalanche flow. A variety of single and multiple berm configuration scenarios were developed and tested to find an optimum configuration of the various earth berm geometries and number of berms to achieve desired energy dissipation and reduction in total waste material runout length. The case study application of the novel mitigation measure shows that by constructing a series of six relatively inexpensive 3 m high earth berms at an optimum distance of 250 m from the slope toe, the total runout length of 1000 m and associated fatalities of the Leuwigajah dumpsite catastrophic failure in Bandung, Indonesia, could have been reduced by half. © The Author(s) 2016.

  18. Informational ergonomics and design: signage design for Monte Sião Camp.

    Science.gov (United States)

    Marques, Luiz Guilherme Oliveira; Cardoso, Vânia Maria Batalha

    2012-01-01

    This paper refers to the development of a signage system, driven by the vector of Signage Design and Informational Ergonomics associated with Regulatory Standards. The methodology of the Ergonomic Intervention of Moraes and Mont'Alvão (2003), in its early stages, and the Method of the Signage Pyramid of Calori (2007) were used to develop the research, data collection and analysis and to guide the design by a signaling system. The system contemplated by this job is called Mount Zion, a site of 19 hectares, which has signs of disturbance. As a result, we obtained a signaling system, with graphic features that refer to formal-site, capable of meeting the needs of orientation and displacement inherent to the site.

  19. Site layout and balance of plant design for an accelerator-driven materials processing complex

    Energy Technology Data Exchange (ETDEWEB)

    Cunliffe, J.; Taussig, R.; Ghose, S. [Bechtel Corporation, San Francisco, CA (United States)] [and others

    1995-10-01

    High energy proton beam accelerators are under consideration for use in radioisotope production, surplus weapons material destruction, radioactive waste transmutation, and thorium-based energy conversion cycles. While there are unique aspects to each of these applications that must be accommodated in the design of the associated facility, all share a set of fundamental characteristics that in large measure dictate the site layout features and many balance-of-plant (BOP) design requirements found to be common to all. This paper defines these key design determinants and goes on to discuss the manner in which they have been accommodated in the pre-conceptual design for a particular materials production application. An estimate of the costs associated with this BOP design is also presented with the aim of guiding future evaluations where the basic plant designs are similar to that of this specific case.

  20. Trends in Supersonic Separator design development

    Directory of Open Access Journals (Sweden)

    Altam Rami Ali

    2017-01-01

    Full Text Available Supersonic separator is a new technology with applications in hydrocarbon dew pointing and gas dehydration which can be used to condensate and separate water and heavy hydrocarbons from natural gas. Many researchers have studied the design, performance and efficiency, economic viability, and industrial applications of these separators. The purpose of this paper is to succinctly review recent progress in the design and application of supersonic separators and their limitations. This review has found that while several aspects of this study are well studied, considerable gaps within the published literature still exists in the areas such as turndown flexibility which is a critical requirement to cater for variation of mass flow and since almost all the available designs have a fixed geometry and therefore cannot be considered suitable for variable mass flow rate, which is a common situation in actual site. Hence, the focus needs to be more on designing a flexible geometry that can maintain a high separation efficiency regardless of inlet conditions and mass flow variations. This review is focusing only on the design and application of the supersonic separators without going through the experimental facilities, industrial platform, pilot plants as well as theoretical, analytical, and numerical modelling.

  1. Developing design premises for a KBS-3V repository based on results from the safety assessment - 16027

    International Nuclear Information System (INIS)

    Andersson, Johan; Hedin, Allan

    2009-01-01

    As a part of the planned license application for a final repository for spent nuclear fuel the Swedish Nuclear Fuel and Waste Management Co. (SKB), has developed design premises from a long term safety aspect of a KBS-3V repository for spent nuclear fuel. The purpose is to provide requirements from a long term safety aspect, to form the basis for the development of the reference design of the repository and to justify that design. Design premises typically concern specification on what mechanical loads the barriers must withstand, restrictions on the composition of barrier materials or acceptance criteria for the various underground excavations. These design constraints, if all fulfilled by the actual design, should form a good basis for demonstrating repository safety. The justification for these design premises is derived from SKB's most recent safety assessment SR-Can complemented by a few additional analyses. Some of the design premises may be modified in future stages of SKB's program, as a result of analyses based on more detailed site data and a more developed understanding of processes of importance for long-term safety. (authors)

  2. Geothermal resources in Oregon: site data base and development status

    Energy Technology Data Exchange (ETDEWEB)

    Justus, D.L.

    1979-04-01

    An inventory of resources based on available information is presented. Potential for utilization and the legal and institutional environment in which development is likely to occur were also considered. Sites selected for this investigation include the 13 identified KGRA's, one PGRA which was chosen because of substantial local interest expressed in favor of development, and one major geologic fault zone which shows indications of high potential. Each chapter represents a planning region and is introduced by a regional overview of the physical setting followed by a narrative summary statement of the specific resource location and characteristics, existing utilization and potential end-uses for future development. Detailed site information in the form of data sheets follows each narrative. (MHR)

  3. Design and development of computerized local and overall country's environmental data analysis network system

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Chang Gyu; Kang, Jong Gyu; Han, H.; Han, J. S.; Lee, Y. D.; Lee, S. R.; Kang, D. J.; Cho, Y. G.; Yun, S. H. [Daedeok College, Taejon (Korea, Republic of)

    2001-03-15

    In this development, we designed a integrated database for efficient data processing of radiation-environment data and developed the CLEAN (Computerized Local and overall country's Environmental data Analysis Network) system. The CLEAN system consists of local radiation-environment network, data analysis system, data open system. We developed the CLEAN system focused on building an integrated database, a data mart, and a CLEAN web site. It is expected that the developed system, which organizes the information related to environmental radiation data systematically, can be utilize for the accurate interpretation, analysis and evaluation.

  4. Design innovations of the next-step spherical torus experiment and spherical torus development path

    International Nuclear Information System (INIS)

    Ono, M.; Kessel, C.; Peng, M.

    2003-01-01

    The spherical torus (ST) fusion energy development path is complementary to the tokamak burning plasma experiment such as ITER as it focuses toward the compact Component Test Facility (CTF) and higher toroidal beta regimes to improve the design of DEMO and a Power Plant. To support the ST development path, one option of a Next Step Spherical Torus (NSST) device is examined. NSST is a 'performance extension' (PE) stage ST with a plasma current of 5 - 10 MA, R = 1.5, B T ≤ 2.7 T with flexible physics capability to 1) Provide a sufficient physics basis for the design of the CTF, 2) Explore advanced operating scenarios with high bootstrap current fraction/high performance regimes, which can then be utilized by CTF, DEMO, and Power Plants, 3) Contribute to the general plasma/fusion science of high β toroidal plasmas. The NSST facility is designed to utilize the TFTR site to minimize the cost and time required for the construction. (author)

  5. Library Web Sites in Pakistan: An Analysis of Content

    Science.gov (United States)

    Qutab, Saima; Mahmood, Khalid

    2009-01-01

    Purpose: The purpose of this paper is to investigate library web sites in Pakistan, to analyse their content and navigational strengths and weaknesses and to give recommendations for developing better web sites and quality assessment studies. Design/methodology/approach: Survey of web sites of 52 academic, special, public and national libraries in…

  6. Natural phenomena hazards, Hanford Site, south central Washington

    International Nuclear Information System (INIS)

    Tallman, A.M.

    1996-01-01

    This document presents the natural phenomena hazard (NPH) loads for use in implementing DOE Order 5480.28, Natural Phenomena Hazards Mitigation, at the Hanford Site in south-central Washington State. The purpose of this document is twofold: (1) summarize the NPH that are important to the design and evaluation of structures, systems, and components at the Hanford Site; (2) develop the appropriate natural phenomena loads for use in the implementation of DOE Order 5480.28. The supporting standards, DOE-STD-1020-94, Natural Phenomena Hazards Design and Evaluation Criteria for Department of Energy Facilities (DOE 1994a); DOE-STD-1022-94, Natural Phenomena Hazards Site Characteristics Criteria (DOE 1994b); and DOE-STD-1023-95, Natural Phenomena Hazards Assessment Criteria (DOE 1995) are the basis for developing the NPH loads

  7. On-site and off-site activities

    International Nuclear Information System (INIS)

    Martin, H.D.

    1986-01-01

    Design principles for NPP training programs. Effects of NPP contracts. Effects of domestic industrial activities. The role of international bodies. Requirements for on-site training. Training abroad, technical, financial and social aspects. Training center on-site, an evaluation. (orig.)

  8. Site scientific mission plan for the Southern Great Plains CART site: January 1997--June 1997

    Energy Technology Data Exchange (ETDEWEB)

    Peppler, R.A.; Lamb, P.J. [Univ. of Oklahoma, Norman, OK (United States). Cooperative Institute for Mesoscale Meteorological Studies; Sisterson, D.L. [Argonne National Lab., IL (United States)

    1997-01-01

    The Southern Great Plains (SGP) Cloud and Radiation Testbed (CART) site is designed to help satisfy the data needs of the Atmospheric Radiation Measurement (ARM) Program Science Team. This document defines the scientific priorities for site activities during the six months beginning on January 1, 1997, and looks forward in lesser detail to subsequent six-month periods. The primary purpose of this Site Scientific Mission Plan is to provide guidance for the development of plans for site operations. It also provides information on current plans to the ARM functional teams (Management Team, Data and Science Integration Team [DSIT], Operations Team, Instrument Team [IT], and Campaign Team) and serves to disseminate the plans more generally within the ARM Program and among the members of the Science Team. This document includes a description of the operational status of the site and the primary site activities envisioned, together with information concerning approved and proposed intensive observation periods (IOPs). The primary users of this document are the site operator, the Site Scientist Team (SST), the Science Team through the ARM Program science director, the ARM Program Experiment Center, and the aforementioned ARM Program functional teams. This plan is a living document that is updated and reissued every six months as the observational facilities are developed, tested, and augmented and as priorities are adjusted in response to developments in scientific planning and understanding.

  9. Development of mechanical structure design technology for LMR

    Energy Technology Data Exchange (ETDEWEB)

    Yoo, Bong; Lee, Jae Han; Joo, Young Sang [and others

    2000-05-01

    In this project, fundamentals for conceptual design of mechanical structure system for LMR are independently established. The research contents are as follow; at first, conceptual design for SSC, design integration of interfaces, design consistency to keep functions and interfaces by developing arrangement of reactor system and 3 dimensional concept drawings, development and revision of preliminary design requirements and structural design basis, and evaluation of structural integrity for SSC following structural design criteria to check the conceptual design to be proper, at second, development of high temperature structure design and analysis technology and establishment of high temperature structural analysis codes and scheme, development of seismic isolation design concept to reduce seismic design loads to SCC and establishment of seismic analysis codes and scheme.

  10. Development of mechanical structure design technology for LMR

    International Nuclear Information System (INIS)

    Yoo, Bong; Lee, Jae Han; Joo, Young Sang

    2000-05-01

    In this project, fundamentals for conceptual design of mechanical structure system for LMR are independently established. The research contents are as follow; at first, conceptual design for SSC, design integration of interfaces, design consistency to keep functions and interfaces by developing arrangement of reactor system and 3 dimensional concept drawings, development and revision of preliminary design requirements and structural design basis, and evaluation of structural integrity for SSC following structural design criteria to check the conceptual design to be proper, at second, development of high temperature structure design and analysis technology and establishment of high temperature structural analysis codes and scheme, development of seismic isolation design concept to reduce seismic design loads to SCC and establishment of seismic analysis codes and scheme

  11. Evaluation of the impact of a committed site on fusion reactor development

    International Nuclear Information System (INIS)

    Reid, R.L.; Nagy, A.

    1979-01-01

    The technical and economic merits of a committed fusion site for development of tokamak, mirror, and EBT reactor from ignition through demo phases were evaluated. Schedule compression resulting from evolving several reactor concepts and/or phases on a committed site as opposed to sequential use of independent sites was estimated. Land, water, and electrical power requirements for a committed fusion site were determined. A conceptual plot plan for siting three fusion reactors on a committed site was configured. Reactor support equipment common to the various concepts was identified as candidates for sharing. Licensing issues for fusion plants were briefly addressed

  12. Remotely operated excavator needs assessment/site visit summary

    Energy Technology Data Exchange (ETDEWEB)

    Straub, J.; Haller, S.; Worsley, R. [Westinghouse Environmental Management Co. of Ohio, Cincinnati, OH (United States); King, M. [THETA Technology Inc. (United States)

    1992-12-02

    The Uranium in Soils Integrated Demonstration requested an assessment of soil excavation needs relative to soil remediation. The following list identifies the DOE sites assessed: Mound Laboratory, Paducah Gaseous Diffusion Plant, Portsmouth Gaseous Diffusion Plant, Nevada Test Site, Lawrence Livermore National Laboratory, Rocky Flats Plant, Los Alamos National Laboratory, Sandia National Laboratory, Idaho National Engineering Laboratory, Hanford Site, and Fernald Site. The reviewed sites fall into one or more of the following three categories: production, EPA National Priorities List, or CERCLA (superfund) designation. Only three of the sites appear to have the need for a remotely operated excavator rope. Hanford and Idaho Falls have areas of high-level radioactive contamination either buried or in/under buildings. The Fernald site has a need for remote operated equipment of different types. It is their feeling that remote equipment can be used to remove the health dangers to humans by removing them from the area. Most interviewees stated that characterization technologies needs are more immediate concern over excavation. In addition, the sites do not have similar geographic conditions which would aid in the development of a generic precision excavator. The sites visited were not ready to utilize or provide the required design information necessary to draft a performance specification. This creates a strong case against the development of one type of ROPE for use at these sites. Assuming soil characterization technology/methodology is improved sufficiently to allow accurate and real time field characterization then development of a precision excavator might be pursued based on FEMP needs, since the FEMP`s sole scope of work is remediation. The excavator could then be used/tested and then later modified for other sites as warranted.

  13. Liquid metal reactor development. Development of LMR design technology

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Young Cheol; Kim, Y I; Kim, Y G; Kim, E K; Song, H; Chung, H T; Sim, Y S; Min, B T; Kim, Y S; Wi, M H; Yoo, B; Lee, J H; Lee, H Y; Kim, J B; Koo, G H; Hahn, D H; Na, B C; Hwang, W; Nam, C; Ryu, W S; Lim, G S; Kim, D H; Kim, J D; Gil, C S

    1997-07-01

    This project was performed in five parts, the scope and contents of which are as follows: The nuclear data processing system was established and the KFS group constant library was improved and verified. Basic computation system was constructed by either developing or adding its function. Input/output (I/O) interface processing was developed to establish an integrated calculation system for LMR core nuclear rand thermal-hydraulic design and analysis. An experimental data analysis was performed to validate the constructed core neutronic calculation system. Using the established core calculation system and design technology, preliminary core design and performance analysis on the domestic LMR core design concept were carried out. To develop the basic technology of the LMR system analysis, LMR system behavior characteristics evaluation, thermal -fluid system analysis in the reactor pool, preliminary overall plant analysis and computer codes development have been performed. A porous model and simple one-dimensional model have been evaluated for the reactor pool analysis. The evaluation of the residual heat removal system on different design concepts has been also conducted. For the development of high temperature structural analysis, the heat transfer and thermal stress analyses were performed using finite element program with user subroutine that has been developed with an implementation of the Chaboche constitutive model for inelastic analysis capability, and the evaluation of creep-fatigue and ratcheting behavior of high temperature structure was carried out using this program. for development of the seismic isolation system and to predict the shear behavior for the laminated rubber bearing were established. And the behavior tests of isolation bearing and rubber specimens were carried out, and the seismic response tests for the isolation model structure were performed using the 30 ton shaking table. (author). 369 refs., 119 tabs., 320 figs.

  14. Liquid metal reactor development. Development of LMR design technology

    International Nuclear Information System (INIS)

    Kim, Young Cheol; Kim, Y. I.; Kim, Y. G.; Kim, E. K.; Song, H.; Chung, H. T.; Sim, Y. S.; Min, B. T.; Kim, Y. S.; Wi, M. H.; Yoo, B.; Lee, J. H.; Lee, H. Y.; Kim, J. B.; Koo, G. H.; Hahn, D. H.; Na, B. C.; Hwang, W.; Nam, C.; Ryu, W. S.; Lim, G. S.; Kim, D. H.; Kim, J. D.; Gil, C. S.

    1997-07-01

    This project was performed in five parts, the scope and contents of which are as follows: The nuclear data processing system was established and the KFS group constant library was improved and verified. Basic computation system was constructed by either developing or adding its function. Input/output (I/O) interface processing was developed to establish an integrated calculation system for LMR core nuclear rand thermal-hydraulic design and analysis. An experimental data analysis was performed to validate the constructed core neutronic calculation system. Using the established core calculation system and design technology, preliminary core design and performance analysis on the domestic LMR core design concept were carried out. To develop the basic technology of the LMR system analysis, LMR system behavior characteristics evaluation, thermal -fluid system analysis in the reactor pool, preliminary overall plant analysis and computer codes development have been performed. A porous model and simple one-dimensional model have been evaluated for the reactor pool analysis. The evaluation of the residual heat removal system on different design concepts has been also conducted. For the development of high temperature structural analysis, the heat transfer and thermal stress analyses were performed using finite element program with user subroutine that has been developed with an implementation of the Chaboche constitutive model for inelastic analysis capability, and the evaluation of creep-fatigue and ratcheting behavior of high temperature structure was carried out using this program. for development of the seismic isolation system and to predict the shear behavior for the laminated rubber bearing were established. And the behavior tests of isolation bearing and rubber specimens were carried out, and the seismic response tests for the isolation model structure were performed using the 30 ton shaking table. (author). 369 refs., 119 tabs., 320 figs

  15. Evaluation of the Potential for Agricultural Development at the Hanford Site

    Energy Technology Data Exchange (ETDEWEB)

    Evans, Robert G.; Hattendorf, Mary J.; Kincaid, Charles T.

    2000-02-25

    By 2050, when cleanup of the Hanford Site is expected to be completed, large worldwide demands to increase the global production of animal and fish protein, food, and fiber are anticipated, despite advancements in crop breeding, genetic engineering, and other technologies. The most likely large areas for expanded irrigation in the Pacific Northwest are the undeveloped East High areas of the Columbia Basin Project and non-restricted areas within the Hanford Site in south-central Washington State. The area known as the Hanford Site has all the components that favor successful irrigated farming. Constraints to agricultural development of the Hanford Site are political and social, not economic or technical. Obtaining adequate water rights for any irrigated development will be a major issue. Numerous anticipated future advances in irrigation and resource conservation techniques such as precision agriculture techniques, improved irrigation systems, and irrigation system controls will greatly minimize the negative environmental impacts of agricultural activities.

  16. Finding New Water: Development of On-Site Non-Potable Water Reuse Systems

    Science.gov (United States)

    By designing our buildings to collect and treat water generated on-site, can be and reused for flushing our toilets and irrigating our landscaping. Several water sources are generated with-in a building including: rainwater, stormwater, graywater, blackwater and foundation drain...

  17. World Heritage Site Designation Impacts on a Historic Village: A Case Study on Residents’ Perceptions of Hahoe Village (Korea

    Directory of Open Access Journals (Sweden)

    Soonki Kim

    2016-03-01

    Full Text Available This study examines the relationship between World Heritage Site (WHS designation and the community sustainability of a historic village, focusing on Hahoe Village, Korea, which was inscribed in 2010. It examines residents’ perceptions of increasing tourism at Hahoe Village by adopting a questionnaire and using an interview as research methods. This study examined both the positive and negative impacts that Hahoe Village’s WHS designation has had on its sustainability. Of all of the impacts examined in this research, the three most noteworthy issues are identified: (1 the acceleration of the change of the village’s industrial base and the influx of strangers; (2 the degradation of quality of life (in the physical aspects caused by increasing tourism; and (3 the collision predicated by the tension between conserving the village’s historic environments and developing tourism. In conclusion, the WHS designation impacts on Hahoe Village, which local residents perceived, have both positive and negative aspects. WHS designation needs to be accompanied by a management plan that is more concerned about the impact from tourism after the designation. In this context, Hahoe Village must not only have a comprehensive preservation plan that balances with the demand for tourism development, but also secure the village’s community sustainability as a living place other than a tourist destination.

  18. Bird Pollinator Visitation is Equivalent in Island and Plantation Planting Designs in Tropical Forest Restoration Sites

    Directory of Open Access Journals (Sweden)

    Ginger M. Thurston

    2013-03-01

    Full Text Available Active restoration is one strategy to reverse tropical forest loss. Given the dynamic nature of climates, human populations, and other ecosystem components, the past practice of using historical reference sites as restoration targets is unlikely to result in self-sustaining ecosystems. Restoring sustainable ecological processes like pollination is a more feasible goal. We investigated how flower cover, planting design, and landscape forest cover influenced bird pollinator visits to Inga edulis trees in young restoration sites in Costa Rica. I. edulis trees were located in island plantings, where seedlings had been planted in patches, or in plantation plantings, where seedlings were planted to cover the restoration area. Sites were located in landscapes with scant (10–21% or moderate (35–76% forest cover. Trees with greater flower cover received more visits from pollinating birds; neither planting design nor landscape forest cover influenced the number of pollinator visits. Resident hummingbirds and a migratory bird species were the most frequent bird pollinators. Pollination in the early years following planting may not be as affected by details of restoration design as other ecological processes like seed dispersal. Future work to assess the quality of various pollinator species will be important in assessing this idea.

  19. Prototype Hanford Surface Barrier: Design basis document

    International Nuclear Information System (INIS)

    Myers, D.R.; Duranceau, D.A.

    1994-11-01

    The Hanford Site Surface Barrier Development Program (BDP) was organized in 1985 to develop the technology needed to provide a long-term surface barrier capability for the Hanford Site and other arid sites. This document provides the basis of the prototype barrier. Engineers and scientists have momentarily frozen evolving barrier designs and incorporated the latest findings from BDP tasks. The design and construction of the prototype barrier has required that all of the various components of the barrier be brought together into an integrated system. This integration is particularly important because some of the components of the protective barreir have been developed independently of other barreir components. This document serves as the baseline by which future modifications or other barrier designs can be compared. Also, this document contains the minutes of meeting convened during the definitive design process in which critical decisions affecting the prototype barrier's design were made and the construction drawings

  20. A Continuing Education Short Course and Engineering Curriculum to Accelerate Workforce Development in Wind Power Plant Design, Construction, and Operations

    Energy Technology Data Exchange (ETDEWEB)

    Tinjum, James [Univ. of Wisconsin, Madison, WI (United States)

    2012-11-29

    Significant advances in wind turbine technology and wind turbine power plant capabilities are appearing in the U.S. Sites that only 10 years ago might have been overlooked are being considered for build out. However, the development of a skilled workforce in the engineering fields and construction trades lags the potential market, especially if the industry is expected to site, design, construct, and operate sufficient wind power plant sites to meet the potential for 20% wind energy by 2030. A select few firms have penetrated the engineer-procure-construction (EPC) market of wind power plant construction. Competition and know-how in this market is vital to achieve cost-effective, design-construct solutions. The industry must produce or retrain engineers, contractors, and technicians to meet ambitious goals. Currently, few universities offer undergraduate or graduate classes that teach the basics in designing, building, and maintaining wind power plants that are safe, efficient, and productive.

  1. Ternate Historical Site as an Object Based Education for Sustainable Development

    Directory of Open Access Journals (Sweden)

    Suswandari Suswandari

    2019-10-01

    Full Text Available This study aims to classify the historical sites of Ternate based on the timeliness of its existence. This study uses a critical qualitative historical approach and is conducted in several locations related to the history of Ternate. Data relating to the physical facts of Ternate history sites, then the location of research in the Ternate region of North Maluku. Data were collected from several findings and poured in filed notes. Then do the sorting and grouping to found description. Data were analyzed using critical historical analysis techniques. The Ternate history sites identified in this research consist of Ternate Museum of Ternate, Ternate Great Mosque, Kastela Fortress, Toluko Fortress, Kalamata Fortress, Oranje Bull, and Nala Fortress. Seven sites are conditions vary and still require government intervention to be used as an object of tourism which can then become an economic power for the people of Ternate. With the Education For Sustainable Development (EDS approach, historical site development takes care of the needs and involves the community directly with full results for the benefit of the people of Ternate and the wider Indonesian community.

  2. Site-specific issues related to structural/seismic design of an underground independent spent fuel storage installation (ISFSI)

    International Nuclear Information System (INIS)

    Tripathi, B.P.

    2005-01-01

    Utilities owning and operating commercial nuclear power plants (NPP) in USA may choose to build an underground Independent Spent Fuel Storage Installation (ISFSI) to store the spent nuclear fuels. The regulatory requirements and other guidance are based on 10 CFR Part 72, Regulatory Guide RG 3.73, Standard Review Plans NUREG-1536 and NUREG-1567, and Interim staff Guidance (ISG) documents as applicable. Structures, Systems, and Components (SSCs) classified as important to safety are designed to withstand the effects of site-specific environmental conditions and natural phenomena such as earthquake, tornado, flood, etc. An underground ISFSI for storage of spent nuclear fuel, presents some unique analysis and design challenges. This paper will briefly address some of these challenges and discuss site-specific loads, including seismic for the ISFSI design. (authors)

  3. Raptor nest-site use in relation to the proximity of coalbed methane development

    Science.gov (United States)

    Carlile, J.D.; Sanders, Lindsey E.; Chalfoun, Anna D.; Gerow, K.G.

    2018-01-01

    Raptor nest–site use in relation to the proximity of coalbed–methane development. Energy development such as coalbed–methane (CBM) extraction is a major land use with largely unknown consequences for many animal species. Some raptor species may be especially vulnerable to habitat changes due to energy development given their ecological requirements and population trajectories. Using 12,977 observations of 3,074 nests of 12 raptor species across nine years (2003–2011) in the Powder River Basin, Wyoming, USA, we evaluated relationships between raptor nest–site use and CBM development. Our objectives were to determine temporal trends in nest–use rates, and whether nest–site use was related to the proximity of CBM development. Across the study area, nest–use rates varied across species and years in a non–linear fashion. We developed a novel randomization test to assess differences in use between nests at developed and undeveloped sites, while controlling for annual variation in nest–site use. Red–tailed hawks (Buteo jamaicensis), burrowing owls (Athene cunicularia), and long–eared owls (Asio otus) used nests in undeveloped areas more than nests in developed areas (i.e. nests near CBM development). Differences between development groups were equivocal for the remaining nine species; however, we caution that we likely had lower statistical power to detect differences for rarer species. Our findings suggest potential avoidance of nesting in areas near CBM development by some species and reveal that CBM effects may be fairly consistent across distances between 400–2,415 m from wells. Future work should consider habitat preferences and fitness outcomes, and control for other key factors such as local prey availability, raptor densities, and weather.

  4. Seismic design criteria for the system 80+ advanced light water reactor

    International Nuclear Information System (INIS)

    Manrique, M.A.; Dermitzakis, S.N.; Gerdes, L.D.; Kennedy, R.P.; Idriss, I.M.; Cassidy, J.R.

    1991-01-01

    This paper presents the development of seismic design criteria in support of design certification by the Nuclear Regulatory Commission (NRC) of the ABB-Combustion Engineering's System 80+ Standard Design. The design certification effort is sponsored by the US Department of Energy (DOE). The development of the design criteria included: (a) development of the seismic control motion, (b) development of generic soil profiles for anticipated sites, (c) generation of in-structure response spectra and design loads for structures and equipment through soil-structure interaction (SSI) analyses, and (d) acceptance criteria for future construction sites

  5. Smashing UX design foundations for designing online user experiences

    CERN Document Server

    Allen, Jesmond

    2012-01-01

    The ultimate guide to UX from the world's most popular resource for web designers and developers Smashing Magazine is the world's most popular resource for web designers and developers and with this book, the authors provide the pinnacle resource to becoming savvy with User Experience Design (UX). The authors first provide an overview of UX and chart its rise to becoming a valuable and necessary practice for narrowing the gap between Web sites, applications, and users in order to make a user's experience a happy, easy, and successful one.Examines the essential aspects of User Experience Design

  6. Development of uniform hazard response spectra for rock sites considering line and point sources of earthquakes

    International Nuclear Information System (INIS)

    Ghosh, A.K.; Kushwaha, H.S.

    2001-12-01

    Traditionally, the seismic design basis ground motion has been specified by normalised response spectral shapes and peak ground acceleration (PGA). The mean recurrence interval (MRI) used to computed for PGA only. It is shown that the MRI associated with such response spectra are not the same at all frequencies. The present work develops uniform hazard response spectra i.e. spectra having the same MRI at all frequencies for line and point sources of earthquakes by using a large number of strong motion accelerograms recorded on rock sites. Sensitivity of the number of the results to the changes in various parameters has also been presented. This work is an extension of an earlier work for aerial sources of earthquakes. These results will help to determine the seismic hazard at a given site and the associated uncertainities. (author)

  7. Selecting Suitable Sites for Wind Energy Development in Ghana ...

    African Journals Online (AJOL)

    Selecting Suitable Sites for Wind Energy Development in Ghana. ... In the event of shortages in petroleum products, these power plants will have ... Layers of these criteria setting were combined using the overlay function in a GIS environment.

  8. Hydroelectric generating site signage

    Energy Technology Data Exchange (ETDEWEB)

    Bentley, K [British Columbia Hydro, Vancouver, BC (Canada)

    1997-04-01

    Recreational sites have been developed at several BC Hydro reservoirs. These sites are visited by approximately 800,000 people annually and therefore, require consistent control measures to ensure public safety and to restrict public access to hazardous areas. BC Hydro is in the process of establishing a province-wide standard in which layout, colour, description of hazards, BC Hydro identity and sign placement would follow an established set of criteria. Proposed signs would consist of a pictograph and a printed warning below. Preliminary designs for 16 of the signs were presented. 16 figs.

  9. Automatic web site authoring with SiteGuide

    NARCIS (Netherlands)

    de Boer, V.; Hollink, V.; van Someren, M.W.; Kłopotek, M.A.; Przepiórkowski, A.; Wierzchoń, S.T.; Trojanowski, K.

    2009-01-01

    An important step in the design process for a web site is to determine which information is to be included and how the information should be organized on the web site’s pages. In this paper we describe ’SiteGuide’, a tool that automatically produces an information architecture for a web site that a

  10. Early Site Permit Demonstration Program: Plant parameters envelope report. Volume 1

    Energy Technology Data Exchange (ETDEWEB)

    1993-03-01

    The Early Site Permit (ESP) Demonstration Program is the nuclear industry`s initiative for piloting the early resolution of siting-related issues before the detailed design proceedings of the combined operating license review. The ESP Demonstration Program consists of three phases. The plant parameters envelopes task is part of Phase 1, which addresses the generic review of applicable federal regulations and develops criteria for safety and environmental assessment of potential sites. The plant parameters envelopes identify parameters that characterize the interface between an ALWR design and a potential site, and quantify the interface through values selected from the Utility Requirements Documents, vendor design information, or engineering assessments. When augmented with site-specific information, the plant parameters envelopes provide sufficient information to allow ESPs to be granted based on individual ALWR design information or enveloping design information for the evolutionary, passive, or generic ALWR plants. This document is expected to become a living document when used by future applicants.

  11. Site Characterization and Preliminary Performance Assessment Calculation Applied To JAEA-Horonobe URL Site of Japan

    International Nuclear Information System (INIS)

    Lim, Doo Hyun; Hatanaka, Koichiro; Ishii, Eiichi

    2010-01-01

    JAEA-Horonobe Underground Research Laboratory (URL) is designed for research and development on high-level radioactive waste (HLW) repository in sedimentary rock. For a potential HLW repository, understanding and implementing fracturing and faulting system, with data from the site characterization, into the performance assessment is essential because fracture and fault will be the major conductors or barriers for the groundwater flow and radionuclide release. The objectives are i) quantitative derivation of characteristics and correlation of fracturing/faulting system with geologic and geophysics data obtained from the site characterization, and ii) preliminary performance assessment calculation with characterized site information

  12. Site Characterization and Preliminary Performance Assessment Calculation Applied To JAEA-Horonobe URL Site of Japan

    Energy Technology Data Exchange (ETDEWEB)

    Lim, Doo Hyun [NE Union Hill Road, Suite 200, WA 98052 (United States); Hatanaka, Koichiro; Ishii, Eiichi [Japan Atomic Energy Agency, Hokkaido (Japan)

    2010-10-15

    JAEA-Horonobe Underground Research Laboratory (URL) is designed for research and development on high-level radioactive waste (HLW) repository in sedimentary rock. For a potential HLW repository, understanding and implementing fracturing and faulting system, with data from the site characterization, into the performance assessment is essential because fracture and fault will be the major conductors or barriers for the groundwater flow and radionuclide release. The objectives are i) quantitative derivation of characteristics and correlation of fracturing/faulting system with geologic and geophysics data obtained from the site characterization, and ii) preliminary performance assessment calculation with characterized site information

  13. Salt site performance assessment activities

    International Nuclear Information System (INIS)

    Kircher, J.F.; Gupta, S.K.

    1983-01-01

    During this year the first selection of the tools (codes) for performance assessments of potential salt sites have been tentatively selected and documented; the emphasis has shifted from code development to applications. During this period prior to detailed characterization of a salt site, the focus is on bounding calculations, sensitivity and with the data available. The development and application of improved methods for sensitivity and uncertainty analysis is a focus for the coming years activities and the subject of a following paper in these proceedings. Although the assessments to date are preliminary and based on admittedly scant data, the results indicate that suitable salt sites can be identified and repository subsystems designed which will meet the established criteria for protecting the health and safety of the public. 36 references, 5 figures, 2 tables

  14. Site locality identification study: Hanford Site. Volume I. Methodology, guidelines, and screening

    International Nuclear Information System (INIS)

    1980-07-01

    Presented in this report are the results of the site locality identification study for the Hanford Site using a screening process. To enable evaluation of the entire Hanford Site, the screening process was applied to a somewhat larger area; i.e., the Pasco Basin. The study consisted of a series of screening steps that progressively focused on smaller areas which are within the Hanford Site and which had a higher potential for containing suitable repository sites for nuclear waste than the areas not included for further study. Five site localities, designated H-1, H-2, H-3, H-4, H-5 (Figure A), varying in size from approximately 10 to 50 square miles, were identified on the Hanford Site. It is anticipated that each site locality may contain one or more candidate sites suitable for a nuclear waste repository. The site locality identification study began with definition of objectives and the development of guidelines for screening. Three objectives were defined: (1) maximize public health and safety; (2) minimize adverse environmental and socioeconomic impacts; and (3) minimize system costs. The screening guidelines have numerical values that provided the basis for the successive reduction of the area under study and to focus on smaller areas that had a higher likelihood of containing suitable sites

  15. Development of corrective measures and site stabilization technologies for shallow land burial facilities at semiarid sites: summary paper

    International Nuclear Information System (INIS)

    Nyhan, J.W.; Abeele, W.V.

    1987-01-01

    The overall purpose of the corrective measures task performed for the national Low-Level Waste Management Program (NLLWMP) has been to develop and test methods that can be used to correct any actual or anticipated problems with new and existing shallow land burial (SLB) sites in a semiarid environment. These field tests have not only evaluated remedial actions, but have also investigated phenomena suspected of being a possible problem at semiarid SLB sites. The approach the authors have taken in developing remedial action and site closure technologies for low-level waste sites is to recognize the physical and biological processes affecting site integrity are interdependent, and therefore, cannot be treated as separate problems. More specifically the field experiments performed for this task were to identify, evaluate, and model erosion control technologies, field test second generation biointrusion barriers, determine by field experiments the extent of upward radionuclide migration due to moisture cycling, and measure the effects of subsidence on remedial action of other system components. In the following sections of this final task summary report, the authors describe the progress made in establishing the facility in which many of these field experiments were performed, the Los Alamos Experimental Engineered Test Facility (EETF), as well as a brief description of the four research areas encompassed by this task. 45 references, 4 figures

  16. Design, Development and Analysis of Centrifugal Blower

    Science.gov (United States)

    Baloni, Beena Devendra; Channiwala, Salim Abbasbhai; Harsha, Sugnanam Naga Ramannath

    2018-06-01

    Centrifugal blowers are widely used turbomachines equipment in all kinds of modern and domestic life. Manufacturing of blowers seldom follow an optimum design solution for individual blower. Although centrifugal blowers are developed as highly efficient machines, design is still based on various empirical and semi empirical rules proposed by fan designers. There are different methodologies used to design the impeller and other components of blowers. The objective of present study is to study explicit design methodologies and tracing unified design to get better design point performance. This unified design methodology is based more on fundamental concepts and minimum assumptions. Parametric study is also carried out for the effect of design parameters on pressure ratio and their interdependency in the design. The code is developed based on a unified design using C programming. Numerical analysis is carried out to check the flow parameters inside the blower. Two blowers, one based on the present design and other on industrial design, are developed with a standard OEM blower manufacturing unit. A comparison of both designs is done based on experimental performance analysis as per IS standard. The results suggest better efficiency and more flow rate for the same pressure head in case of the present design compared with industrial one.

  17. Site Study Plan for salt, Deaf Smith County site, Texas: Environmental Field Program: Preliminary draft

    International Nuclear Information System (INIS)

    1987-06-01

    The Salt Site Study Plan (SSP) describes a program for characterizing the existing salt environment in the site vicinity. A step-by-step approach is described which proceeds from published data and planned theoretical studies, to planned laboratory studies, and finally to planned field studies, to provide the necessary data to meet program requirements contained in the Salt Repository Project - Requirements Document (SRP-RD). The plan also draws on the results of other SSP's for certain data; for example, soil salinity data are to be provided under the Soils SSP. The salt studies consist of evaluation of control and mitigation measures, salt monitoring studies, emission factors development, air models development and validation, and risk assessment. For each study, its design and design rationale; analysis, management, and use of data; schedule of activities; organization of personnel and sample management; and quality assurance requirements are described. 90 refs., 9 figs., 7 tabs

  18. Technical Site Information: Planning group of the Directorate and Conventional Construction Division

    International Nuclear Information System (INIS)

    1993-11-01

    This document presents the technical site information for the Superconducting Super Collider project. The Ellis County, Texas site was selected by the Department of Energy in 1989. After assembling the initial staff at temporary facilities in Dallas, the SSC Laboratory began site-specific design work. The resulting design for the SSC accelerators, experimental areas, and laboratory facilities were described in the Site-Specific Conceptual Design Report of July 1990. Since then, design specifications for the technical components and conventional facilities have been formulated. In fact, a very significant amount of surface and underground construction has been initiated and many buildings have been completed. Testing of prototypes for most technical components is advanced. The construction phase of the SSC project is approximately 20% complete. At this time, it is appropriate to capture the conventional design work which has taken place since 1990. This documents records regional and physical information used in site studies, summarizes the site studies for conventional facilities, and presents site layouts for buildings and utilities as they would have been at the end of the construction project. As such, this documents summarizes and complements the work of many groups in the SSC laboratory, the Texas National Research Laboratory Commission (TNRLC), and several subcontractors to the SSC project. The document contains extensive references to their work contained in other drafts and final reports. In particular, it borrows heavily from the Site Development Plan (released in draft form in January, 1992) which has, to date, guided aspects of site development

  19. Technical Site Information: Planning group of the Directorate and Conventional Construction Division

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1993-11-01

    This document presents the technical site information for the Superconducting Super Collider project. The Ellis County, Texas site was selected by the Department of Energy in 1989. After assembling the initial staff at temporary facilities in Dallas, the SSC Laboratory began site-specific design work. The resulting design for the SSC accelerators, experimental areas, and laboratory facilities were described in the Site-Specific Conceptual Design Report of July 1990. Since then, design specifications for the technical components and conventional facilities have been formulated. In fact, a very significant amount of surface and underground construction has been initiated and many buildings have been completed. Testing of prototypes for most technical components is advanced. The construction phase of the SSC project is approximately 20% complete. At this time, it is appropriate to capture the conventional design work which has taken place since 1990. This documents records regional and physical information used in site studies, summarizes the site studies for conventional facilities, and presents site layouts for buildings and utilities as they would have been at the end of the construction project. As such, this documents summarizes and complements the work of many groups in the SSC laboratory, the Texas National Research Laboratory Commission (TNRLC), and several subcontractors to the SSC project. The document contains extensive references to their work contained in other drafts and final reports. In particular, it borrows heavily from the Site Development Plan (released in draft form in January, 1992) which has, to date, guided aspects of site development.

  20. A study for the safety evaluation of geological disposal of TRU waste and influence on disposal site design by change of amount of TRU waste (Joint research)

    International Nuclear Information System (INIS)

    Hasegawa, Makoto; Kondo, Hitoshi; Takahashi, Kuniaki; Funabashi, Hideaki; Kawatsuma, Shinji; Kamei, Gento; Hirano, Fumio; Mihara, Morihiro; Ueda, Hiroyoshi; Ohi, Takao; Hyodo, Hideaki

    2011-02-01

    In the safety evaluation of the geological disposal of the TRU waste, it is extremely important to share the information with the Research and development organization (JAEA: that is also the waste generator) by the waste disposal entrepreneur (NUMO). In 2009, NUMO and JAEA set up a technical commission to investigate the reasonable TRU waste disposal following a cooperation agreement between these two organizations. In this report, the calculation result of radionuclide transport for a TRU waste geological disposal system was described, by using the Tiger code and the GoldSim code at identical terms. Tiger code is developed to calculate a more realistic performance assessment by JAEA. On the other hand, GoldSim code is the general simulation software that is used for the computation modeling of NUMO TRU disposal site. Comparing the calculation result, a big difference was not seen. Therefore, the reliability of both codes was able to be confirmed. Moreover, the influence on the disposal site design (Capacity: 19,000m 3 ) was examined when 10% of the amount of TRU waste increased. As a result, it was confirmed that the influence of the site design was very little based on the concept of the Second Progress Report on Research and Development for TRU Waste Disposal in Japan. (author)

  1. ONWI [Office of Nuclear Waste Isolation] 30% design review findings report for Exploratory Shaft Facility, Deaf Smith site

    International Nuclear Information System (INIS)

    1987-01-01

    This document describes a review of the standards for the design of the high-level radioactive waste facility at the Deaf Smith, Texas site. It includes public comments and the official responses to the designs produced to date

  2. A sensitivity analysis of hazardous waste disposal site climatic and soil design parameters using HELP3

    International Nuclear Information System (INIS)

    Adelman, D.D.; Stansbury, J.

    1997-01-01

    The Resource Conservation and Recovery Act (RCRA) Subtitle C, Comprehensive Environmental Response, Compensation, And Liability Act (CERCLA), and subsequent amendments have formed a comprehensive framework to deal with hazardous wastes on the national level. Key to this waste management is guidance on design (e.g., cover and bottom leachate control systems) of hazardous waste landfills. The objective of this research was to investigate the sensitivity of leachate volume at hazardous waste disposal sites to climatic, soil cover, and vegetative cover (Leaf Area Index) conditions. The computer model HELP3 which has the capability to simulate double bottom liner systems as called for in hazardous waste disposal sites was used in the analysis. HELP3 was used to model 54 combinations of climatic conditions, disposal site soil surface curve numbers, and leaf area index values to investigate how sensitive disposal site leachate volume was to these three variables. Results showed that leachate volume from the bottom double liner system was not sensitive to these parameters. However, the cover liner system leachate volume was quite sensitive to climatic conditions and less sensitive to Leaf Area Index and curve number values. Since humid locations had considerably more cover liner system leachate volume than and locations, different design standards may be appropriate for humid conditions than for and conditions

  3. Site scientific mission plan for the southern great plains CART site January-June 2000.; TOPICAL

    International Nuclear Information System (INIS)

    Peppler, R. A.; Sisterson, D. L.; Lamb, P.

    2001-01-01

    The Southern Great Plains (SGP) Cloud and Radiation Testbed (CART) site was designed to help satisfy the data needs of the Atmospheric Radiation Measurement (ARM) Program Science Team. This Site Scientific Mission Plan defines the scientific priorities for site activities during the six months beginning on January 1, 2000, and looks forward in less detail to subsequent six-month periods. The primary purpose of this document is to provide scientific guidance for the development of plans for site operations. It also provides information on current plans to the ARM functional teams (Management Team, Data and Science Integration Team[DSIT], Operations Team, and Instrument Team[IT]) and serves to disseminate the plans more generally within the ARM Program and among the members of the Science Team. This document includes a description of the operational status of the site and the primary site activities envisioned, together with information concerning approved and proposed intensive observation periods (IOPs). The primary users of this document are the site operator, the site program manager, the Site Scientist Team (SST), the Science Team through the ARM Program science director, the ARM Program Experiment Center, and the aforementioned ARM Program functional teams. This plan is a living document that is updated and reissued every six months as the observational facilities are developed, tested, and augmented and as priorities are adjusted in response to developments in scientific planning and understanding. With this issue, many aspects of earlier Site Scientific Mission Plan reports have been moved to ARM sites on the World Wide Web. This report and all previous reports are available on the SGP CART web site

  4. Practical applications approach to design, development and implementation of an integrated management system

    International Nuclear Information System (INIS)

    Holdsworth, Rodger

    2003-01-01

    The introduction of quality, risk, safety, health and environmental management philosophies has significantly changed industry's view of company organization and controlling processes. Quality, risk, safety, health and environmental programs and systems, such as ISO 9000, ISO 14000, process safety, and risk management are impacting the way industry will meet the challenges of safety and environmental risks and the needs of the customer in the future. A wealth of knowledge has been extracted from practical application case studies, which would otherwise be unobtainable without years of experience related to management systems design, development, implementation and control. This paper discusses a practical applications approach to design, develop and implement an integrated management system encompassing quality (ISO 9000), process safety management (CFR 29 1910.119), risk management programs (CFR 40 part 68), environmental management (ISO 14000), and safety and health. This paper includes a discussion of management systems integration and an overview of management systems standards that apply to the petrochemical and chemical manufacturers industries. The paper also provides an overview on integrating management systems, including issues related to the following topics: - Establishing a management system team and objectives. - Assessing and knowing your organization. - Designing the management system to meet site objectives. - Developing system documentation. - Implementing effective management systems. - Measuring program performance. - Continuous improvement

  5. PhosphoSiteAnalyzer

    DEFF Research Database (Denmark)

    Bennetzen, Martin V; Cox, Jürgen; Mann, Matthias

    2012-01-01

    an algorithm to retrieve kinase predictions from the public NetworKIN webpage in a semiautomated way and applies hereafter advanced statistics to facilitate a user-tailored in-depth analysis of the phosphoproteomic data sets. The interface of the software provides a high degree of analytical flexibility......Phosphoproteomic experiments are routinely conducted in laboratories worldwide, and because of the fast development of mass spectrometric techniques and efficient phosphopeptide enrichment methods, researchers frequently end up having lists with tens of thousands of phosphorylation sites...... and is designed to be intuitive for most users. PhosphoSiteAnalyzer is a freeware program available at http://phosphosite.sourceforge.net ....

  6. Discussion about design basis flood of site of research reactors by river

    International Nuclear Information System (INIS)

    Rong Feng; Zhao Jianjun; Du Qiaomin; Zhang Lingyan

    2006-01-01

    This paper presents the well-defined standard in relation to design the basis flood of the sites of research reactors by river. It is based on the concept of some relational standards, analysis of hydrological calculation technology and methods, and analysis of accident dangerous degrees of research reactor, as well as in combination with the engineering practices. The flood preventing standard for research reactors with higher power should be the same with that of the nuclear power plants. (authors)

  7. Multiagency radiation survey and site investigation manual (MARSSIM): Survey design

    International Nuclear Information System (INIS)

    Abelquist, E.W.; Berger, J.D.

    1996-01-01

    This paper describes the MultiAgency Radiation Survey and Site Investigation Manual (MARSSIM) strategy for designing a final status survey. The purpose of the final status survey is to demonstrate that release criteria established by the regulatory agency have been met. Survey design begins with identification of the contaminants and determination of whether the radionuclides of concern exist in background. The decommissioned site is segregated into Class 1, Class 2, and Class 3 areas, based on contamination potential, and each area is further divided into survey units. Appropriate reference areas for indoor and outdoor background measurements are selected. Survey instrumentation and techniques are selected in order to assure that the instrumentation is capable of detecting the contamination at the derived concentration guideline level (DCGL). Survey reference systems are established and the number of survey data points is determined-with the required number of data points distributed on a triangular grid Pattern. Two suitistical tests are used to evaluate data from final status surveys. For contaminants that are b, present in background, the Wilcoxon Rank Sum test is used; for contaminants that are not present in background, the Wilcoxon Signed Rank (or Sign) test is used. The number of data points needed to satisfy these nonparametric tests is based on the contaminant DCGL value, the expected Standard deviation of the contaminant in background and in the survey unit, and the acceptable probability of making Type I and Type II decision errors. The MARSSIM also requires a reasonable level of assurance that any small areas of elevated residual radioactivity that could be significant relative to regulatory limits are not missed during the final status survey. Measurements and sampling on a specified grid size are used to obtain an adequate assurance level that small locations of elevated radioactivity will Still satisfy DCGLs-applicable to small areas

  8. Evaluation and design of drained low-level radioactive disposal sites. Final report

    International Nuclear Information System (INIS)

    Eichholz, G.G.

    1984-12-01

    Low-level disposal in shallow trenches has been the subject of much critical assessment in recent years. Historically most trenches have been located in fairly permeable settings and any liquid waste stored has migrated at rates limited mainly by hydraulic effects and the ion exchange capacity of underlying soil minerals. Attempts to minimize such seepage by choosing sites in very impermeable settings lead to overflow and surface runoff, whenever the trench cap is breached by subsidence or erosion. The work described in this report was directed to an optimum compromise situation where less reliance is placed on cap permanence, any ground seepage is directed and controlled, and the amount of waste leaching that would occur is minimized by keeping the soil surrounding the waste at only residual moisture levels at all times. Measurements have been conducted to determine these residual levels for some representative soils, to estimate the impact on waste migration of mainly unsaturated flow conditions, and to generate a conceptual design of a disposal facility which would provide adequate drainage to keep the waste from being exposed to continuous leaching by standing water. An attempt has also been made to quantify the reduced source terms under such periodic, unsaturated flow conditions, but those tests have not been conclusive to date. For low-permeability soils the waste should be placed about 1 ft. above the saturated layer formed by suction forces immediately above the gravel layer. Since most disposal sites, even in humid regions of the United States, are exposed only to intermittent rainfall and as most trench designs incorporate some gravel base for drainage, the results of this project have broader applications in assessing actual migration conditions in shallow trench disposal sites. Similar considerations may also apply to disposal of hazardous wastes

  9. Heritage planning and rethinking the meaning and values of designating heritage sites in a post-disaster context: The case of Aceh, Indonesia

    Science.gov (United States)

    Meutia, Z. D.; Akbar, R.; Zulkaidi, D.

    2018-05-01

    Heritage has become a driver of development as stated in the New Urban Agenda 2016 report. A starting premise of most recent studies of the concept of heritage suggests that its nature is not as a static inheritance with fixed and enduring values. Rather, the identification of sites as heritage requires a process of identification, or heritage creation. Heritage is a fluid phenomenon rather than a static set of objects or sites with fixed meanings. This paper uses theory from Smith [1] who argued that there is no such thing as a heritage; heritage is essentially a cultural custom and social process. Today, site-based heritage planning only considers the values of old towns and lacks clarity in terms of values that create criteria for the designation of cultural heritage sites in another context. Yet, this approach is needed as a way to maintain urban assets that significantly contribute to the establishment of values and quality parts of the city. Heritage planning is also the act of communicating and remembering the past for the present and the future in the public domain. This paper aims to formulate a conceptual heritage planning of designating heritage sites that challenges the traditional notion of heritage which considers age as a key element in heritage, the privileges monumentality and grand scale, with scientific/aesthetic expert judgment as a requirement of heritage designations. The limited idea of heritage based on exclusive values as something ancient, grand-scale, historical, and with other exclusive values has excluded many places as heritage in communities emerging from disasters. Debates within the critical heritage studies movement argue that heritage is a cultural product linked to activities of remembering and is an act of communication. The dominant hypothesis is that heritage values cannot remain to exist if the physical or material aspects of sites are destroyed and this hypothesis feels flawed. This paper asks us to acknowledge the

  10. Development of corrective measures technology for shallow land burial facilities at arid sites

    International Nuclear Information System (INIS)

    Nyhan, J.W.; Abeele, W.V.; Perkins, B.A.; Lane, L.J.

    1984-01-01

    The field research program involving corrective measure technologies for arid shallow land burial (SLB) sites is described. Soil erosion and infiltration of water into a simulated trench cap with various surface treatments was measured and compared with similar data from agricultural systems across the United States. Field testing of biointrustion barriers at closed-out waste disposal sites at Los Alamos and in the experimental clusters are reported. The final results of an experiment designed to measure the extent of contaminant transport to the surface of a SLB facility, and the influence of plants on this relationship, are presented. An experiment designed to determine the effects of subsidence on the performance of a cobble-gravel biobarrier system is described and current field data are presented. 11 references, 11 figures, 5 tables

  11. Public participation and regional development at a nuclear waste disposal site

    International Nuclear Information System (INIS)

    Ipsen, D.

    2005-01-01

    The propositions brought forward in this article try to implement sociological aspects into the search for nuclear waste disposal sites based on two theses: Firstly without the willingness of public participation in the search and inspection processes the success of the process is severly put into question in a democratic state. Secondly the potential disposal site must not block the further economic development of the region. These two theses lead to socio-economic criteria for consideration or debarment, to a concept of active and intensive participation, and to considerations about long-term regional development. (orig.)

  12. Repository site characterization

    International Nuclear Information System (INIS)

    Voss, J.W.; Pentz, D.L.

    1987-01-01

    The characterization of candidate repository sites has a number of programmatic objectives. Principal among these is the acquisition of data: a) to determine the suitability of a site relative to the DOE repository siting guidelines, b) to support model development and calculations to determine the suitability of a site relative to the post closure criteria of the NRC and EPA, c) to support the design of a disposal system, including the waste package and the engineered barrier system, as well as the shafts and underground openings of the repository. In meeting the gaols of site characterization, the authors have an obligation to conduct their investigations within an appropriate budget and schedule. This mandates that a well-constructed and systematic plan for field investigations be developed. Such a plan must fully account for the mechanisms which will control the radiologic performance in the repository. The plan must also flexibly and dynamically respond to the results of each step of field investigation, responding to the spatial variability of earth as well as to enhanced understandings of the performance of the disposal system. Such a plan must ensure that sufficient data are available to support the necessary probabilistic calculations of performance. This paper explores the planning for field data acquisition with specific reference to requirements for demonstrations of the acceptable performance for disposal systems

  13. Nevada Test Site-Directed Research and Development FY 2010 Annual Report

    Energy Technology Data Exchange (ETDEWEB)

    Howard Bender, comp.

    2011-04-04

    This annual report of the Site-Directed Research and Development (SDRD) program represents the highly significant R&D accomplishments conducted during fiscal year 2010. This year was noteworthy historically, as the Nevada Test Site was renamed to the Nevada National Security Site (NNSS). This change not only recognizes how the site's mission has evolved, but also heralds a future of new challenges and opportunities for the NNSS. In many ways, since its inception in 2002, the SDRD program has helped shape that evolving mission. As we approach 2012, SDRD will also mark a milestone, having completed its first full decade of innovative R&D in support of the site and national security. The program continues to fund advanced science and technology development across traditional Department of Energy (DOE) nuclear security areas such as stockpile stewardship and non-proliferation while also supporting Department of Homeland Security (DHS) needs, and specialized work for government agencies like the Department of Defense (DoD) and others. The NNSS will also contribute technologies in the areas of treaty verification and monitoring, two areas of increasing importance to national security. Keyed to the NNSS's broadened scope, the SDRD program will continue to anticipate and advance R&D projects that will help the NNSS meet forthcoming challenges.

  14. Development of MMIS design technology for integral reactor

    Energy Technology Data Exchange (ETDEWEB)

    Koo, In Soo; Park, H. Y.; Lee, C. K. and others

    1999-03-01

    The objective of this study is to establish the concept design of the SMART MMIS through the setup of a structure and design concept of MMIS, the development of design methodology, and essential technologies for MMIS considering computer based digital technologies and human factors. Main activities of this study divided into three categories such as the development of conceptual design and requirement of the SMART I and C, the development of conceptual design and requirement of the SMART MMI, and essential technology for the MMIS. The results of main activities that have been performed during the study are as follows; 1) The review of licensing requirements and operating experience of existing plants. 2) The establishment of a system design concept about development strategy, basic functions and requirements, and applicable technology through the adoption of digital technology and human factorsengineering. 3) The accomplishment of function, structure, and design requirement of each MMIS through the performance of conceptual design on system structure and actuation logic using function analysis. It is necessary to develop and apply new technologies for the MMIS design compatible with the design basis of SMART. Considered essential technologies for the MMIS in this study are 1) the development of a signal validation algorithm and sensor diagnosis technique 2) the development of a soft controller for operator's action 3) the establishment of a data communication structure for MMIS architecture 4) the development of an information optimization basis and automatic start-up algorithm 5) the development of sensor reduction requirements 6) the development of a qualification method of digital equipment for applied digital technology and commercial grade items. (author)

  15. Development of MMIS design technology for integral reactor

    International Nuclear Information System (INIS)

    Koo, In Soo; Park, H. Y.; Lee, C. K. and others

    1999-03-01

    The objective of this study is to establish the concept design of the SMART MMIS through the setup of a structure and design concept of MMIS, the development of design methodology, and essential technologies for MMIS considering computer based digital technologies and human factors. Main activities of this study divided into three categories such as the development of conceptual design and requirement of the SMART I and C, the development of conceptual design and requirement of the SMART MMI, and essential technology for the MMIS. The results of main activities that have been performed during the study are as follows; 1) The review of licensing requirements and operating experience of existing plants. 2) The establishment of a system design concept about development strategy, basic functions and requirements, and applicable technology through the adoption of digital technology and human factors engineering. 3) The accomplishment of function, structure, and design requirement of each MMIS through the performance of conceptual design on system structure and actuation logic using function analysis. It is necessary to develop and apply new technologies for the MMIS design compatible with the design basis of SMART. Considered essential technologies for the MMIS in this study are 1) the development of a signal validation algorithm and sensor diagnosis technique 2) the development of a soft controller for operator's action 3) the establishment of a data communication structure for MMIS architecture 4) the development of an information optimization basis and automatic start-up algorithm 5) the development of sensor reduction requirements 6) the development of a qualification method of digital equipment for applied digital technology and commercial grade items. (author)

  16. Northeast Oregon Hatchery Project, Final Siting Report.

    Energy Technology Data Exchange (ETDEWEB)

    Watson, Montgomery

    1995-03-01

    This report presents the results of site analysis for the Bonneville Power Administration Northeast Oregon Hatchery Project. The purpose of this project is to provide engineering services for the siting and conceptual design of hatchery facilities for the Bonneville Power Administration. The hatchery project consists of artificial production facilities for salmon and steelhead to enhance production in three adjacent tributaries to the Columbia River in northeast Oregon: the Grande Ronde, Walla Walla, and Imnaha River drainage basins. Facilities identified in the master plan include adult capture and holding facilities; spawning incubation, and early rearing facilities; full-term rearing facilities; and direct release or acclimation facilities. The evaluation includes consideration of a main production facility for one or more of the basins or several smaller satellite production facilities to be located within major subbasins. The historic and current distribution of spring and fall chinook salmon and steelhead was summarized for the Columbia River tributaries. Current and future production and release objectives were reviewed. Among the three tributaries, forty seven sites were evaluated and compared to facility requirements for water and space. Site screening was conducted to identify the sites with the most potential for facility development. Alternative sites were selected for conceptual design of each facility type. A proposed program for adult holding facilities, final rearing/acclimation, and direct release facilities was developed.

  17. The morphological development of newly inundated intertidal areas: the mechanisms driving the early evolution of an estuarine environment designed and constructed by humans

    Science.gov (United States)

    Dale, Jonathan; Burgess, Heidi; Cundy, Andrew

    2017-04-01

    Intertidal saltmarsh and mudflat habitats are of global importance due to the ecosystem, economic and cultural services they provide. These services include wildlife habitat provision and species diversity, immobilisation of pollutants and protection from coastal flooding. Saltmarsh and mudflat environments are, however, being lost and degraded due to erosion caused by rising sea levels and increased storminess. These losses are exacerbated by anthropogenic influences including land reclamation, increased coastal development and the construction of coastal flood defences which prevent the landwards migration of saltmarsh and mudflat environments, resulting in coastal squeeze. To compensate for saltmarsh and mudflat losses areas of the coastal hinterland are being inundated by breaching defences and constructing new defences inland, thus extending or constructing new estuarine environments; a processes known as de-embankment or managed realignment. Morphological engineering and landscaping within managed realignment sites prior to site inundation varies depending on the aims of the scheme. However, there is a shortage of data on the morphological evolution within these sites post site inundation impeding the ability of coastal engineers to effectively design and construct future sites. To date there has been a focus on the colonisation of marine macro fauna and flora within newly inundated managed realignment sites, which can be relatively rapid and easily quantified. Little is known of the morphological evolution in response to altered sedimentary processes, its driving mechanisms and therefore the success and ecological sustainability of these sites. This study evaluates the post-inundation morphological development of the largest open coast managed realignment site in Europe, at Medmerry on the south coast of the United Kingdom. Inundated in September 2013, the Medmerry Managed Realignment Site consists of a mosaic of former agricultural land and areas of lower

  18. The principles of design of a shallow disposal site for low and intermediate level radioactive wastes

    International Nuclear Information System (INIS)

    Holmes, R.E.

    1985-01-01

    This paper addresses the principles of design of a shallow disposal site for low and intermediate level radioactive wastes. The objective of the author is to review the need for shallow land disposal facilities in the UK and to propose design principles which will protect the public and operatives from excessive risk. It is not the intent of the author to present a detailed design of facility which will meet the design standards proposed although such a design is feasible and within the scope of currently available technology. The principles and standards proposed in this paper are not necessarily those of PPC Consultant Services Ltd. or NEI Waste Technologies Ltd. (author)

  19. Usefulness of Social Network Sites for Adolescents' Development of Online Career Skills

    NARCIS (Netherlands)

    Rutten, Mariëlle; Ros, Anje; Kuijpers, Marinka; Kreijns, Karel

    2018-01-01

    Schools have an important role in teaching students how to use Social Network Site (SNS) for career purposes. This involves the opportunity for students to practice online career skills. Different types of digital environments are available for schools. There are SNS designed to enable users to

  20. Design-Basis Flood Estimation for Site Characterization at Nuclear Power Plants in the United States of America

    International Nuclear Information System (INIS)

    Prasad, Rajiv; Hibler, Lyle F.; Coleman, Andre M.; Ward, Duane L.

    2011-01-01

    The purpose of this document is to describe approaches and methods for estimation of the design-basis flood at nuclear power plant sites. Chapter 1 defines the design-basis flood and lists the U.S. Nuclear Regulatory Commission's (NRC) regulations that require estimation of the design-basis flood. For comparison, the design-basis flood estimation methods used by other Federal agencies are also described. A brief discussion of the recommendations of the International Atomic Energy Agency for estimation of the design-basis floods in its member States is also included.