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Sample records for site designation draft

  1. Pipe drafting and design

    CERN Document Server

    Parisher, Roy A; Parisher

    2000-01-01

    Pipe designers and drafters provide thousands of piping drawings used in the layout of industrial and other facilities. The layouts must comply with safety codes, government standards, client specifications, budget, and start-up date. Pipe Drafting and Design, Second Edition provides step-by-step instructions to walk pipe designers and drafters and students in Engineering Design Graphics and Engineering Technology through the creation of piping arrangement and isometric drawings using symbols for fittings, flanges, valves, and mechanical equipment. The book is appropriate primarily for pipe

  2. Drafting method of electricity and electron design

    International Nuclear Information System (INIS)

    Gungbon, Junchun

    1989-11-01

    This book concentrates on drafting of electricity and electron design. It deals with The meaning of electricity and electron drafting JIS standard regulation the types of drafting and line and letter, basics drafting with projection drafting method, plan projection and development elevation, Drafting method of shop drawing, practical method of design and drafting, Design and drafting of technic and illustration, Connection diagram, Drafting of wiring diagram for light and illumination, Drafting of development connection diagram for sequence control, Drafting of logic circuit sign of flow chart and manual, drafting for a electron circuit diagram and Drawing of PC board.

  3. Pipe drafting and design

    CERN Document Server

    Parisher, Roy A

    2011-01-01

    Pipe Drafting and Design, Third Edition provides step-by-step instructions to walk pipe designers, drafters, and students through the creation of piping arrangement and isometric drawings. It includes instructions for the proper drawing of symbols for fittings, flanges, valves, and mechanical equipment. More than 350 illustrations and photographs provide examples and visual instructions. A unique feature is the systematic arrangement of drawings that begins with the layout of the structural foundations of a facility and continues through to the development of a 3-D model. Advanced chapters

  4. Socioeconomic Site Study Plan: Draft

    International Nuclear Information System (INIS)

    1987-07-01

    Social and economic issues and concerns of the Deak Smith County site area will be evaluated during site characterization. Effects that the area could experience from a repository project include demographic, economic, community service, fiscal, and social impacts. The Socioeconomic Site Study Plan is designed to provide a strategy to assess the potential for those impacts. The Socioeconomic Site Study Plan is structured to provide an overview of the socioeconomic program requirements, objectives, and activities to be conducted during site characterization. This report will describe the study design and its rationale; data collection, management, and reporting; program schedules and milestones; site study organization and management; and quality assurance issues. 43 refs

  5. Site study plan for Exploratory shaft facilities design foundation boreholes (shaft surface facility foundation borings), Deaf Smith County Site, Texas: Surface-based geotechnical field program: Preliminary draft

    International Nuclear Information System (INIS)

    1987-12-01

    This site study plan describes the Exploratory Shaft Facilities (ESF) Design Foundation Boreholes field activities to be conducted during early stages of Site Characterization at the Deaf Smith County, Texas, site. 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. Approximately 50 foundation boreholes will be drilled within the ESP location to provide data necessary for design of the ESF and to satisfy applicable shaft permitting requirements. Soils and subsurface rock will be sampled as the foundation boreholes are advanced. Soil samples or rock core will be taken through the Blackwater Draw and Ogallala Formations and the Dockum Group. Hydrologic testing will be performed in boreholes that penetrates the water table. In-situ elastic properties will be determined from both the soil strata and rock units along the length of the boreholes. 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. 25 refs., 10 figs., 6 tabs

  6. Environmental Regulatory Compliance Plan for site: Draft characterization of the Yucca Mountain site:Draft

    International Nuclear Information System (INIS)

    1988-01-01

    The objective of the EMMP is to document compliance with the NWPA. To do so, a summary description of site characterization activites is provided, based on the consultation draft of the SCP. Subsequent chpaters identify those technical areas having the potential to be impacted by site characterization activities and the monitoring plans proposed to identify whether those impacts acutally occur. Should monitoring confirm the potential for significant adverse impact, mitigative measures will be developed. In the context of site characterization, mitigation is defined as those changes in site characterization activities that serve to avoid or minimize, to the maximum extent practicle, any significant adverse environmental impacts. Although site characterization activies involve both surface and subsurface activities, it is the surface-based aspect of site characterization that is addressed in detailed by the EMMP. The schedule and duration of these activities is given in the consultation draft of the SCP. A breif summary of all proposed activities is given in the EMMP. 10 refs., 8 figs

  7. Drafting & Design Technology. Technical Committee Report.

    Science.gov (United States)

    Idaho State Dept. of Education, Boise. Div. of Vocational Education.

    This Technical Committee Report prepared by industry representatives in Idaho lists the skills currently necessary for an employee in that state to obtain a job in drafting and design technology, retain a job once hired, and advance in that occupational field. (Task lists are grouped according to duty areas generally used in industry settings, and…

  8. CFD based draft tube hydraulic design optimization

    International Nuclear Information System (INIS)

    McNabb, J; Murry, N; Mullins, B F; Devals, C; Kyriacou, S A

    2014-01-01

    The draft tube design of a hydraulic turbine, particularly in low to medium head applications, plays an important role in determining the efficiency and power characteristics of the overall machine, since an important proportion of the available energy, being in kinetic form leaving the runner, needs to be recovered by the draft tube into static head. For large units, these efficiency and power characteristics can equate to large sums of money when considering the anticipated selling price of the energy produced over the machine's life-cycle. This same draft tube design is also a key factor in determining the overall civil costs of the powerhouse, primarily in excavation and concreting, which can amount to similar orders of magnitude as the price of the energy produced. Therefore, there is a need to find the optimum compromise between these two conflicting requirements. In this paper, an elaborate approach is described for dealing with this optimization problem. First, the draft tube's detailed geometry is defined as a function of a comprehensive set of design parameters (about 20 of which a subset is allowed to vary during the optimization process) and are then used in a non-uniform rational B-spline based geometric modeller to fully define the wetted surfaces geometry. Since the performance of the draft tube is largely governed by 3D viscous effects, such as boundary layer separation from the walls and swirling flow characteristics, which in turn governs the portion of the available kinetic energy which will be converted into pressure, a full 3D meshing and Navier-Stokes analysis is performed for each design. What makes this even more challenging is the fact that the inlet velocity distribution to the draft tube is governed by the runner at each of the various operating conditions that are of interest for the exploitation of the powerhouse. In order to determine these inlet conditions, a combined steady-state runner and an initial draft tube analysis

  9. CFD based draft tube hydraulic design optimization

    Science.gov (United States)

    McNabb, J.; Devals, C.; Kyriacou, S. A.; Murry, N.; Mullins, B. F.

    2014-03-01

    The draft tube design of a hydraulic turbine, particularly in low to medium head applications, plays an important role in determining the efficiency and power characteristics of the overall machine, since an important proportion of the available energy, being in kinetic form leaving the runner, needs to be recovered by the draft tube into static head. For large units, these efficiency and power characteristics can equate to large sums of money when considering the anticipated selling price of the energy produced over the machine's life-cycle. This same draft tube design is also a key factor in determining the overall civil costs of the powerhouse, primarily in excavation and concreting, which can amount to similar orders of magnitude as the price of the energy produced. Therefore, there is a need to find the optimum compromise between these two conflicting requirements. In this paper, an elaborate approach is described for dealing with this optimization problem. First, the draft tube's detailed geometry is defined as a function of a comprehensive set of design parameters (about 20 of which a subset is allowed to vary during the optimization process) and are then used in a non-uniform rational B-spline based geometric modeller to fully define the wetted surfaces geometry. Since the performance of the draft tube is largely governed by 3D viscous effects, such as boundary layer separation from the walls and swirling flow characteristics, which in turn governs the portion of the available kinetic energy which will be converted into pressure, a full 3D meshing and Navier-Stokes analysis is performed for each design. What makes this even more challenging is the fact that the inlet velocity distribution to the draft tube is governed by the runner at each of the various operating conditions that are of interest for the exploitation of the powerhouse. In order to determine these inlet conditions, a combined steady-state runner and an initial draft tube analysis, using a

  10. Review of site recommendation process in Draft Environmental Assessments

    International Nuclear Information System (INIS)

    Joy, H.; Longo, T.; Burton, E.S.

    1985-01-01

    In December 1984, the US Department of Energy (DOE) published Draft Environmental Assessments (EAs) on nine potentially acceptable nuclear waste repository sites. Five sites in the states of Mississippi, Nevada, Texas, Utah, and Washington were proposed in the Draft EAs for nomination under the Nuclear Waste Policy Act as suitable for further detailed study (site characterization). The Nevada, Texas, and Washington sites were further proposed for recommendation to the President as preferred for site characterization. This paper reviews the process that DOE used in selecting the three sites proposed for site characterization. The process is consistent with DOE's implementation guidelines for selecting repository sites, and proceeds in three steps. First, the sites are ranked in order of preference for each of twenty technical guidelines based on information in the Draft EAs. The second step combines the individual guideline rankings into postclosure and preclosure guideline group rankings, and, finally, into an overall ranking. In the third step, the sensitivity of the choice of the three preferred sites is examined for a range of guideline weightings

  11. Draft reclamation program plan for site characterization

    International Nuclear Information System (INIS)

    1989-08-01

    As part of its obligations under the Nuclear Waste Policy Act, as amended, the US Department of Energy (DOE) has developed an environmental program that is to be implemented during site characterization at the Yucca Mountain site. This site is proposed for the location of the nation's first high-level radioactive waste repository. A program for the reclamation of areas disturbed by site characterization is part of the overall environmental program for that site. This Reclamation Program Plan (RPP) describes the reclamation policy of the DOE for the Yucca Mountain site and presents an overview of the reclamation program. The RPP also provides an overview of the reclamation needs relative to site characterization; a review of legislation and requirements pertinent to reclamation; and a review of previous commitments made by the DOE to certain types of reclamation activities. The objective of the DOE reclamation program at Yucca Mountain is to return land disturbed by site-characterization activities to a stable ecological state with a form and productivity similar to the predisturbance state. The DOE will take all reasonable and necessary steps to achieve this objective. 19 refs., 2 tabs

  12. Mississippi Curriculum Framework for Drafting and Design Technology (Program CIP: 48.0102--Architectural Drafting Technology) (Program CIP: 48.0101--General Drafting). Postsecondary Programs.

    Science.gov (United States)

    Mississippi Research and Curriculum Unit for Vocational and Technical Education, State College.

    This document, which is intended for use by community and junior colleges throughout Mississippi, contains curriculum frameworks for the two course sequences of the state's postsecondary-level drafting and design technology program: architectural drafting technology and drafting and design technology. Presented first are a program description and…

  13. Draft Site Treatment Plan (DSTP), Volumes I and II

    International Nuclear Information System (INIS)

    D'Amelio, J.

    1994-01-01

    Site Treatment Plans (STP) are required for facilities at which the DOE generates or stores mixed waste. This Draft Site Treatment Plan (DSTP) the second step in a three-phase process, identifies the currently preferred options for treating mixed waste at the Savannah River Site (SRS) or for developing treatment technologies where technologies do not exist or need modification. The DSTP reflects site-specific preferred options, developed with the state's input and based on existing available information. To the extent possible, the DSTP identifies specific treatment facilities for treating the mixed waste and proposes schedules. Where the selection of specific treatment facilities is not possible, schedules for alternative activities such as waste characterization and technology assessment are provided. All schedule and cost information presented is preliminary and is subject to change. The DSTP is comprised of two volumes: this Compliance Plan Volume and the Background Volume. This Compliance Plan Volume proposes overall schedules with target dates for achieving compliance with the land disposal restrictions (LDR) of RCRA and procedures for converting the target dates into milestones to be enforced under the Order. The more detailed discussion of the options contained in the Background Volume is provided for informational purposes only

  14. Draft Site Management and Monitoring Plan for Corpus Christi Maintenance and New Work Ocean Dredged Material Disposal Site

    Science.gov (United States)

    USEPA Region 6 and the US Army Corps of Engineers submit for public comment the Draft Site Management and Monitoring Plan for Corpus Christi Maintenance and New Work Ocean Dredged Material Disposal Site

  15. 77 FR 66483 - Public Comment on the Draft Federal Urban Design Element and the Draft Update to the Federal...

    Science.gov (United States)

    2012-11-05

    ... NCPC review required by law. The new Federal Urban Design Element provides policies that will guide the... public comment a draft new Federal Urban Design Element and draft revisions to the Preservation and... Features Element articulates policies that guide federal actions preserving Washington's historic character...

  16. Site characterization plan overview: Yucca Mountain Site, Nevada Research and Development Area, Nevada: Consultation Draft

    International Nuclear Information System (INIS)

    1988-01-01

    The consultation draft of the site characterization plan is a lengthy document that describes in considerable detail the program that will be conducted to characterize the geologic, hydrologic, and other conditions relevant to the suitability of the site for a repository. The overview presented here consists of brief summaries of important topics covered in the consultation draft of the site-characterization plan; it is not a substitute for the site-characterization plan. The arrangement of the overview is similar to that of the plan itself, with brief descriptions of the disposal system -- the site, the repository, and the waste package -- preceding the discussion of the characterization program to be carried out at the Yucca Mountain site. It is intended primarily for the management staff of organizations involved in the DOE's repository program -- staff who might wish to understand the general scope of the site-characterization program, the activities to be conducted, and the facilities to be constructed rather than the technical details of site characterization. 22 figs., 1 tab

  17. Federal Facilities Compliance Act, Draft Site Treatment Plan: Background Volume, Part 2, Volume 1

    International Nuclear Information System (INIS)

    1994-01-01

    This Draft Site Treatment Plan was prepared by Ames Laboratory to meet the requirements of the Federal Facilities Compliance Act. Topics discussed include: purpose and scope of the plan; site history and mission; draft plant organization; waste minimization; waste characterization; preferred option selection process; technology for treating low-level radioactive wastes and TRU wastes; future generation of mixed waste streams; funding; and process for evaluating disposal issues in support of the site treatment plan

  18. 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)

  19. Optimization design of solar enhanced natural draft dry cooling tower

    International Nuclear Information System (INIS)

    Zou, Zheng; Guan, Zhiqiang; Gurgenci, Hal

    2013-01-01

    Highlights: • We proposed a cost model for solar enhanced natural draft dry cooling tower. • We proposed an optimization scheme for this new cooling system. • We optimally designed one for a 50 MW EGS geothermal plant as a demonstration. • Results proved its economic advantages for EGS geothermal application. - Abstract: This paper proposed an optimization scheme for solar enhanced natural draft dry cooling tower design, in which a detailed cost model was proposed including capital, labour, maintenance and operation costs of each component. Based on the developed cost model, the optimal design option can be identified in terms of the relatively lower annual cost and the relatively higher total extra income over the Solar Enhanced Natural Draft Dry Cooling Tower (SENDDCT) lifetime. As a case study, a SENDDCT was optimally designed to meet the cooling demand for a 50 MW geothermal power plant with Engineered Geothermal System (EGS) technology. The results showed that the optimized SENDDCT not only has better cooling performance during the daytime but also is a cost effective option for EGS geothermal power plants

  20. Remedial action standards for inactive uranium processing sites (40 cfr 192). Draft environmental impact statement

    International Nuclear Information System (INIS)

    1980-12-01

    The Environmental Protection Agency is proposing standards for disposing of uranium mill tailings from inactive processing sites and for cleaning up contaminated open land and buildings. These standards were developed pursuant to the Uranium Mill Tailings Radiation Control Act of 1978 (Public Law 95-604). This Act requires EPA to promulgate standards to protect the environment and public health and safety from radioactive and nonradioactive hazards posed by uranium mill tailings at designated inactive processing sites. The Draft Environmental Impact Statement examines health, technical, cost, and other factors relevant to determining standards. The proposed standards for disposal of the tailings piles cover radon emissions from the tailings to the air, protection of surface and ground water from radioactive and nonradioactive contaminants, and the length of time the disposal system should provide a reasonable expectation of meeting these standards. The proposed cleanup standards limit indoor radon decay product concentrations and gamma radiation levels and the residual radium concentration of contaminated land after cleanup

  1. 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

  2. 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.

  3. 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.

  4. Human-factors engineering-control-room design review: Shoreham Nuclear Power Station. Draft audit report

    International Nuclear Information System (INIS)

    Peterson, L.R.; Preston-Smith, J.; Savage, J.W.; Rousseau, W.F.

    1981-01-01

    A human factors engineering preliminary design review of the Shoreham control room was performed at the site on March 30 through April 3, 1981. This design review was carried out by a team from the Human Factors Engineering Branch, Division of Human Factors Safety. This report was prepared on the basis of the HFEB's review of the applicant's Preliminary Design Assessment and the human factors engineering design review/audit performed at the site. The presented sections are numbered to conform to the guidelines of the draft version of NUREG-0700. They summarize the teams's observations of the control room design and layout, and of the control room operators' interface with the control room environment

  5. Mechanical Design Technology--Modified. (Computer Assisted Drafting, Computer Aided Design). Curriculum Grant 84/85.

    Science.gov (United States)

    Schoolcraft Coll., Livonia, MI.

    This document is a curriculum guide for a program in mechanical design technology (computer-assisted drafting and design developed at Schoolcraft College, Livonia, Michigan). The program helps students to acquire the skills of drafters and to interact with electronic equipment, with the option of becoming efficient in the computer-aided…

  6. Draft environmental assessment: Cypress Creek Dome site, Mississippi. Nuclear Waste Policy Act (Section 112)

    International Nuclear Information System (INIS)

    1984-12-01

    In February 1983, the US Department of Energy (DOE) identified the Cypress Creek dome site in Mississippi as one of nine potentially acceptable sites for a mined geologic repository for spent nuclear fuel and high-level radioactive waste. To determine their suitability, the Cypress Creek dome site and the eight other potentially acceptable sites have been evaluated in accordance with the DOE's General Guidelines for the Recommendation of Sites for Nuclear Waste Repositories. These evaluations are reported in this draft environmental assessment (EA), which is being issued for public review and comment. The DOE findings and determinations that are based on these evaluations are preliminary and subject to public review and comment. A final EA will be prepared after considering the comments received. On the basis of the evaluations contained in this draft EA, the DOE has found that the Cypress Creek dome site is not disqualified under the guidelines. The site is contained in the Gulf Interior Region of the Gulf Coastal Plain, which is one of five distinct geohydrologic settings considered for the first repository. This setting contains two other potentially acceptable sites - the Richton dome site and the Vacherie dome site. Although the Cypress Creek dome site appears to be suitable for site characterization, the DOE has concluded that the Richton dome site is the preferred site in the Gulf Interior Region and is proposing to nominate the Richton dome site rather than the Cypress Creek dome site as one of the three sites suitable for characterization

  7. Draft environmental assessment: Vacherie Dome site, Louisiana. Nuclear Waste Policy Act (Section 112)

    International Nuclear Information System (INIS)

    1984-12-01

    In February 1983, the US Department of Energy (DOE) identified the Vacherie dome in Louisiana as one of nine potentially acceptable sites for a mined geologic repository for spent nuclear fuel and high-level radioactive waste. To determine their suitability, the Vacherie dome site and the eight other potentially acceptable sites have been evaluated in accordance with the DOE's General Guidelines for the Recommendation of Sites for Nuclear Waste Repositories. These evaluations are reported in this draft environmental assessment (EA), which is being issued for public review and comment. The DOE findings and determinations that are based on these evaluations are preliminary and subject to public review and comment. A final EA will be prepared after considering the comments received. On the basis of the evaluations contained in this draft EA, the DOE has found that the Vacherie dome site is not disqualified under the guidelines. The site is contained in the Gulf Interior Region of the Gulf Coastal Plain, which is one of five distinct geohydrologic settings considered for the first repository. This setting contains two other potentially acceptable sites - the Cypress Creek dome site and the Richton dome site. Although the Vacherie dome site appears to be suitable for site characterization, the DOE has concluded that the Richton dome site is the preferred site in the Gulf Interior Region. On the basis of these findings, the DOE is proposing to nominate the Richton dome site rather than the Vacherie dome site as one of the five sites suitable for characterization

  8. Draft environmental assessment: Swisher County site, Texas. Nuclear Waste Policy Act (Section 112)

    International Nuclear Information System (INIS)

    1984-12-01

    In February 1983, the US Department of Energy (DOE) identified a location in Swisher County, Texas, as one of nine potentially acceptable sites for a mined geologic repository for spent nuclear fuel and high-level radioactive waste. The potentially acceptable site was subsequently narrowed to an area of 9 square miles. To determine their suitability, the Swisher site and the eight other potentially acceptable sites have been evaluated in accordance with the DOE's General Guidelines for the Recommendation of Sites for Nuclear Waste Repositories. These evaluations are reported in this draft environmental assessment (EA), which is being issued for public review and comment. The DOE findings and determinations that are based on these evaluations are preliminary and subject to public review and comment. A final EA will be prepared after considering the comments received. On the basis of the evaluations contained in this draft EA, the DOE has found that the Swisher site is not disqualified under the guidelines. The site is contained in the Permian Basin, which is one of five distinct geohydrologic settings considered for the first repository. This setting contains one other potentially acceptable site - the Deaf Smith site. Although the Swisher site appears to be suitable for site characterization, the DOE has concluded that the Deaf Smith site is the preferred site in the Permian Basin and is proposing to nominate the Deaf Smith site rather than the Swisher site as one of the five sites suitable for characterization

  9. Draft environmental assessment: Lavender Canyon site, Utah. Nuclear Waste Policy Act (Section 112)

    International Nuclear Information System (INIS)

    1984-12-01

    In February 1983, the US Department of Energy (DOE) identified the Lavender Canyon site in Utah, as one of nine potentially acceptable sites for a mined geologic repository for spent nuclear fuel and high-level radioactive waste. To determine their suitability, the Lavender Canyon site and the eight other potentially acceptable sites have been evaluated in accordance with the DOE's General Guidelines for the Recommendation of Sites for Nuclear Waste Repositories. These evaluations are reported in this draft environmental assessment (EA), which is being issued for public review and comment. The DOE findings and determinations that are based on these evaluations are preliminary and subject to public review and comment. A final EA will be prepared after considering the comments received. On the basis of the evaluations contained in this draft EA, the DOE has found that the Lavender Canyon site is not disqualified under the guidelines. The site is contained in the Paradox Basin, which is one of five distinct geohydrologic settings considered for the first repository. This setting contains one other potentially acceptable site - the Davis Canyon site. Although the Lavender Canyon site appears to be suitable for site characterization, the DOE has concluded that the Davis Canyon site is the preferred site in the Paradox Basin. On the basis of these findings, the DOE is proposing to nominate the Davis Canyon site rather than the Lavender Canyon site as one of the five sites suitable for characterization

  10. Draft environmental assessment: Richton Dome site, Mississippi. Nuclear Waste Policy Act (Section 112)

    International Nuclear Information System (INIS)

    1984-12-01

    In February 1983, the US Department of Energy identified the Richton dome site as one of the nine potentially acceptable sites for a mined geologic repository for spent nuclear fuel and high-level radioactive waste. To determine their suitability, the Richton dome site and the eight other potentially acceptable sites have been evaluated in accordance with the DOE's General Guidelines for the Recommendation of Sites for Nuclear Waste Repositories. These evaluations are reported in this draft (EA), which is being issued for public review and comment. The DOE findings and determinations that are based on these evaluations are preliminary and subject to public review and comment. A final EA will be prepared after considering the comments received. On the basis of the evaluations reported in this draft EA, the DOE has found that the Richton dome site is not disqualified under the guidelines. The site is in the Gulf Interior Region of the Gulf Coastal Plain. This setting contains two other potentially acceptable sites - the Cypress Creek dome site and the Vacherie dome site. Although these other two sites appear to be suitable for site characterization, the DOE has concluded that the Richton dome site is the preferred site in the Gulf Interior Region. Furthermore, the DOE finds that the site is suitable for site characterization because the evidence does not support a conclusion that the site will not be able to meet each of the qualifying conditions specified in the guidelines. On the basis of these findings, the DOE is proposing to nominate the Richton dome site as one of five sites suitable for characterization. Having compared the Richton dome site with the other four sites proposed for nomination, the DOE has determined that the Richton dome site is not one of the three preferred sites for recommendation to the President as candidates for characterization

  11. Draft environmental assessment: Davis Canyon site, Utah. Nuclear Waste Policy Act (Section 112)

    International Nuclear Information System (INIS)

    1984-12-01

    In February 1983, the US Department of Energy (DOE) identified the Davis Canyon site in Utah, as one of nine potentially acceptable sites for a mined geologic repository for spent nuclear fuel and high-level radioactive waste. To determine their suitability, the Davis Canyon site and the eight other potentially acceptable sites have been evaluated in accordance with the DOE's General Guidelines for the Recommendation of Sites for Nuclear Waste Repositories. These evaluations are reported in this draft environmental assessment (EA), which is being issued for public review and comment. The DOE findings and determinations that are based on these evaluations are preliminary and subject to public review and comment. A final EA will be prepared after considering the comments received. On the basis of the evaluations reported in this draft EA, the DOE has found that the Davis Canyon site is not disqualified under the guidelines. The site is in the Paradox Basin, which is one of five distinct geohydrologic settings considered for the first repository. This setting contains one other potentially acceptable site - the Lavender Canyon site. Although the Lavender Canyon site appears to be suitable for site characterization, the DOE has concluded that the Davis Canyon site is the preferred site in the Paradox Basin. Furthermore, the DOE finds that the site is suitable for site characterization because the evidence does not support a conclusion that the site will not be able to meet each of the qualifying conditions specified in the guidelines. On the basis of these findings, the DOE is proposing to nominate the Davis Canyon site as one of five sites suitable for characterization. Having compared the Davis Canyon site with the other four sites proposed for nomination, the DOE has determined that the Davis Canyon site is not one of the three preferred sites for recommendation to the President as candidates for characterization

  12. Draft environmental assessment: Deaf Smith County site, Texas. Nuclear Waste Policy Act (Section 112)

    International Nuclear Information System (INIS)

    1984-12-01

    In February 1983, the US Department of Energy identified a location in Deaf Smith County, Texas, as one of nine potentially acceptable sites for a mined geologic repository for spent nuclear fuel and high-level radioactive waste. The potentially acceptable site was subsequently narrowed to an area of 9 square miles. To determine their suitability, the Deaf Smith site and the eight other potentially acceptable sites have been evaluated in accordance with the DOE's General Guidelines for the Recommendation of Sites for Nuclear Waste Repositories. These evaluations are reported in this draft environmental assessment, which is being issued for public review and comment. The DOE findings and determinations that are based on these evaluations are preliminary and subject to public review and comment. A final EA will be prepared after considering the comments received. On the basis of the evaluations reported in this draft EA, the DOE has found that the Deaf Smith site is not disqualified under the guidelines. The site is in the Permian Basin, which is one of five distinct geohydrologic settings considered for the first repository. This setting contains one other potentially acceptable site - the Swisher site. Although the Swisher site appears to be suitable for site characterization, DOE has concluded that the Deaf Smith site is the preferred site. The DOE finds that the site is suitable for site characterization because the evidence does not support a conclusion that the site will not be able to meet each of the qualifying conditions specified in the guidelines. On the basis of these findings, the DOE is proposing to nominate the Deaf Smith site as one of five sites suitable for characterization. Having compared the Deaf Smith site with the other four sites proposed for nomination, the DOE has determined that the Deaf Smith site is one of the three preferred sites for recommendation to the President as candidates for characterization

  13. Consultation draft: Site characterization plan overview, Deaf Smith County Site, Texas: Nuclear Waste Policy Act (Section 113)

    International Nuclear Information System (INIS)

    1988-01-01

    The Department of Energy (DOE) is preparing a site characterization plan for the candidate site in Deaf Smith County, Texas. The DOE has provided, for information and review, a consultation draft of the plan to the State of Texas and the US Nuclear Regulatory Commission. The site characterization plan is a lengthy document that describes in considerable detail the program that will be conducted to characterize the geologic, hydrologic, and other conditions relevant to the suitability of the site for a repository. The overview presented here consists of brief summaries of important topics covered in the consultation draft of the site characterization plan; it is not a substitute for the site characterization plan. The arrangement of the overview is similar to that of the plan itself, with brief descriptions of the repository system - the site, the repository, and the waste package - preceding the discussion of the characterization program to be carried out at the Deaf Smith County site. It is intended primarily for the management staff of organizations involved in the DOE's repository program or other persons who might wish to understand the general scope of the site-characterization program, the activities to be conducted, and the facilities to be constructed rather than the technical details of site characterization. 15 figs., 1 tab

  14. Site study plan for cultural resources, Deaf Smith County site, Texas: Environmental Field Program: Preliminary draft

    International Nuclear Information System (INIS)

    1987-06-01

    The Cultural Resources Site Study Plan describes a field program to identify and evaluate the archaeological, historical, and Native American Indian resources of the site on local and regional perspectives; monitor and manage discovered cultural resources; and establish a worker education program. The archaeological field program consists of three pedestrian surveys: Survey 1 includes two EDBH seismic survey lines and the area within the exploratory shaft facility (ESF); Survey 2 includes the remainder of the site plus a 1/4 to 3/4-mi border area; and Survey 3 includes an assortment of offsite areas. The historical studies will identify and evaluate known and discovered historical sites and structures and the Native American Indian will identify and evaluate cultural and religious concerns expressed by Indian tribal groups. Prehistoric and historic sites will be evaluated to determine if they meet eligibility criteria for listing on the National Register of Historic Places. This site study plan describes the need for each study; its design and design rationale; analysis, management, and use of data; schedule of field activities; organization of field personnel and sample management; and quality assurance requirements. The cultural resource studies will provide data for satisfying the Programmatic Agreement, engineering design needs, and SRP requirements for permits and approvals, and for minimizing effects to any cultural properties discovered during site characterization. 75 refs., 10 figs., 2 tabs

  15. Draft environmental assessment: reference repository location, Hanford Site, Washington. Nuclear Waste Policy Act (Section 112)

    International Nuclear Information System (INIS)

    1984-12-01

    In February 1983, the US Department of Energy (DOE) identified a reference repository location at the Hanford Site in Washington as one of nine potentially acceptable sites for a mined geologic repository for spent nuclear fuel and high-level radioactive waste. To determine their suitability, the reference repository location at the Hanford Site and the eight other potentially acceptable sites have been evaluated in accordance with the DOE's General Guidelines for the Recommendation of Sites for Nuclear Waste Repositories. These evaluations are reported in this draft environmental assessment (EA), which is being issued for public review and comment. The DOE findings and determinations that are based on these evaluations are preliminary and subject to public review and comment. A final EA will be prepared after considering the comments received on the draft EA. The reference repository location at Hanford is located in the Columbia Plateau, one of five distinct geohydrologic settings that are being considered for the first repository. On the basis of the evaluations reported in this draft EA, the DOE has found that the reference repository location at Hanford is not disqualified under the guidelines. The DOE has also found that it is suitable for site characterization because the evidence does not support a conclusion that the site will not be able to meet each of the qualifying conditions specified in the guidelines. On the basis of these findings, the DOE is proposing to nominate the reference repository location at Hanford as one of five sites suitable for characterization. Furthermore, having performed a comparative evaluation of the five sites proposed for nomination, the DOE has determined that the reference repository location at Hanford is one of three sites preferred for site characterization

  16. 75 FR 984 - Draft Recommended Interim Preliminary Remediation Goals for Dioxin in Soil at CERCLA and RCRA Sites

    Science.gov (United States)

    2010-01-07

    ...The Environmental Protection Agency (EPA or the Agency) is announcing a 50-day public comment period for draft recommended interim preliminary remediation goals (PRGs) developed in the Draft Recommended Interim Preliminary Remediation Goals for Dioxin in Soil at Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) and Resource Conservation and Recovery Act (RCRA) Sites. EPA's Office of Solid Waste and Emergency and Emergency Response (OSWER) has developed the draft recommended interim PRGs for dioxin in soil. These draft recommended interim PRGs were calculated using existing, peer- reviewed toxicity values and current EPA equations and default exposure assumptions. This Federal Register notice is intended to provide an opportunity for public comment on the draft recommended interim PRGs. EPA will consider any public comments submitted in accordance with this notice and may revise the draft recommended interim PRGs thereafter.

  17. Site characterization plan overview: reference repository location, Hanford Site, Washington: Consultation draft: Nuclear Waste Policy Act (Section 113)

    International Nuclear Information System (INIS)

    1988-01-01

    As part of the process for siting the nation's first geologic repository for radioactive waste, the Department of Energy (DOE) is preparing a site characterization plan for the Hanford site in Benton County, Washington. As a step in the preparation of that plan, the DOE has provided, for information and review, a consultation draft of the plan to the State of Washington, the affected Indian Tribes - the Confederated Tribes of the Umatilla Indian Reservation, the Nez Perce Indian Tribe, and the Yakima Indian Nation - and the US Nuclear Regulatory Commission. The Hanford site is one of three sites that the DOE currently plans to characterize;the other sites are the Deaf Smith County site in Texas and the Yucca Mountain site in Nevada. After site characterization has been completed and its results evaluated, the DOE will identify from among the three characterized sites the site that is preferred for the repository. The overview presented here consists of brief summaries of important topics covered in the consulation draft of the site characterization plan;it is not a substitute for the site characterization plan. The arrangement of the overview is similar to that of the plan itself, with breif descriptions of the dispoal system - the site, the repository, and the waste package - preceding the discussion of the characterization program to be carried out at the Hanford site. It is intended primarily for the management staff of organizations involved in the DOE's repository program or other persons who might wish to understand the general scope of the site-characterization program, the activities to be conducted, and the facilities to be constructed rather than the technical details of site characterization

  18. Yucca Mountain Project Site Atlas: Volume 1: Draft

    International Nuclear Information System (INIS)

    1988-10-01

    The Nevada Nuclear Waste Storage Investigations (NNWSI) Project Site Atlas is a reference document of field activities which have been, or are being, conducted by the US Department of Energy (DOE) to support investigations of Yucca Mountain as a potential site for an underground repository for high-level radioactive waste. These investigations, as well as future investigations, will yield geologic, geophysical, geochemical, geomechanical, hydrologic, volcanic, seismic, and environmental data necessary to characterize Yucca Mountain and its regional setting. This chapter summarizes the background of the NNWSI Project and the objective, scope, structure, and preparation of the Site Atlas. Chapter 2 describes in more detail the bibliography and map portfolio portions of the Atlas, which are presented in Chapter 4 and Volume 2, respectively. Chapter 3 describes how to use the Atlas. The objective of the Site Atlas is to create a management tool for the DOE Waste Management Project Office (WMPO) that will allow the WMPO to compile and disseminate information regarding the location of NNWSI Project field investigations, and document the permits acquired and the environmental, archaeological, and socioeconomic surveys conducted to support those investigations. The information contained in the Atlas will serve as a historical reference of site investigation field activities. A companion document to the Atlas is the NNWSI Project Surface Based Investigations Plan (SBIP)

  19. Design of Eco Friendly Shallow Draft Fishing Vessel

    Directory of Open Access Journals (Sweden)

    Sunardi Sunardi

    2016-04-01

    Full Text Available One of the main problem of inland waterways fisheries is the transportation of fish from ponds to fish market during low tide trough inland waterways with 0.6m water depth.The boat is experiences grounding due to water depth of the river is not sufficient for the fishing boat to carry fish at it’s maximum2 tones capacity or experience dead freight . This condition forces fisherman to wait until the high tide from the sea, this delay causes the quality of the fish is decreasing.Besides the problem dead freight  problem the existing vessel is causes environmental problem such as erosion of the river bank due to wake wash. The other important issue is the increases of fuel price and it’s scarcity.  This paper presents the results of comparison of existing monohull fishing boat and two other alternativecatamaran designs. The catamaran design alternatives are is ordinary catamaran and flat side catamaran.  Both of the catamaran fishing boat design shows that the catamaran boat with 0.5m draft is able to carry more than 2 tonnes payload during low tide water depth.  The CFD simulation results shows that flat side catamaran resistance is more than 17.7% lower compared to ordinary catamaran and 44% lower compared to monohull. It means that the consumption of flat side catamaran is lowest compared to two other type of hull design. The flat side catamaran also produces lowest wake wash compared to o two other design. The low wake wash means more friendly to environment.

  20. Site study plan for Transportation, Deaf Smith County Site, Texas: Preliminary draft

    International Nuclear Information System (INIS)

    1987-06-01

    This site study plan describes transportation field studies to be conducted during the characterization of the Deaf Smith County, Texas, site for the US Department of Energy's Salt Repository Project. The studies are needed to identify and assess potential project impacts to transportation infrastructure and systems in the project vicinity and along potential transportation routes to the site across the State of Texas. The studies are also needed to locate and design project transportation facilities, and to evaluate and design impact mitigation. After identifying the transportation information requirements needed to comply with Federal, State, and local regulations and repository program requirements, the site study plan describes the study design and rationale, the field data collection procedures and equipment, the data analysis methods and application of results, the data management strategy, the schedule of field activities, the management of the study, and the study's quality assurance program. The field data collection activities are organized into programs for the characterization of site vicinity rail corridors and highway corridors, characterization of alternative statewide transportation routes, monitoring of site characterization effects on transportation, characterization of aircraft overflight patterns and hazardous material transportation patterns, and assessment of emergency response preparedness along alternative statewide transportation routes. 34 refs., 10 figs., 2 tabs

  1. Utilities availability report for seven candidate salt sites: Final draft

    International Nuclear Information System (INIS)

    1984-12-01

    Stearns Catalytic Corporation (SC) conducted a study of availability and accessibility of electric power and natural gas supplies for each of the seven candidate sites in salt for a nuclear waste repository. The objective of this study is to indicate the existing or potential availability of adequate electric power and natural gas supplies, together with representative routing of reasonable access corridors for utility lines, for the candidate sites at Richton and Cypress Creek Domes in Mississippi, Vacherie Dome in Louisiana, Swisher and Deaf Smith Counties in Texas, and Davis and Lavender Canyons in Utah. The report describes the major characteristics of each supply and the representative routes by which each supply could be connected to the assumed respective repository site. Included are a brief narrative, maps showing representative utilities access routes, and a summary tabulation of relevant data. The supply routes used in this study are not necessarily the recommended, preferred, or selected routes. No decision affecting the final location of the preferred route has been made, therefore the routes used in this study are not to be construed as an implied decision. The routes and supply sources used in this study are for comparative purposes only, as no final selections will be made prior to site characterization

  2. Design optimization of hydraulic turbine draft tube based on CFD and DOE method

    Science.gov (United States)

    Nam, Mun chol; Dechun, Ba; Xiangji, Yue; Mingri, Jin

    2018-03-01

    In order to improve performance of the hydraulic turbine draft tube in its design process, the optimization for draft tube is performed based on multi-disciplinary collaborative design optimization platform by combining the computation fluid dynamic (CFD) and the design of experiment (DOE) in this paper. The geometrical design variables are considered as the median section in the draft tube and the cross section in its exit diffuser and objective function is to maximize the pressure recovery factor (Cp). Sample matrixes required for the shape optimization of the draft tube are generated by optimal Latin hypercube (OLH) method of the DOE technique and their performances are evaluated through computational fluid dynamic (CFD) numerical simulation. Subsequently the main effect analysis and the sensitivity analysis of the geometrical parameters of the draft tube are accomplished. Then, the design optimization of the geometrical design variables is determined using the response surface method. The optimization result of the draft tube shows a marked performance improvement over the original.

  3. 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...

  4. Site Study Plan for Aesthetics, Deaf Smith County Site, Texas: Environmental Field Program: Preliminary draft

    International Nuclear Information System (INIS)

    1987-06-01

    The Aesthetic Site Study Plan describes a field program consisting of identification of the visually affected area; determination of scenic quality, visual sensitivity, and visual management classes of the site and vicinity; and analysis of the level of visual contrast that would be created by the project. Field ratings of scenic quality, visual sensitivity, and visual contrast will be supplemented by a public perception survey designed to incorporate the views of the public. This plan describes the need for the study, the study design, data management and use, schedule for proposed activities, and quality assurance program. This study will provide data needed to satisfy requirements contained in, or derived from, SRPO Requirement Document (SRP-RD). 35 refs., 6 figs., 2 tabs

  5. 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

  6. Site Study Plan for Acoustics, Deaf Smith County Site, Texas: Environmental Field Program: Preliminary draft

    International Nuclear Information System (INIS)

    1987-06-01

    The Acoustics site study plan describes a field program which characterizes existing sound levels, determines the area's sound propagation characteristics, and monitors the project-related sound emissions. The plan describes for each study: the need for the study, study design, data management and use, schedule, and quality assurance requirements. These studies will provide data needed to satisfy requirements contained in, or derived from, the Salt Repository Requirements Document. 37 refs., 9 figs., 3 tabs

  7. Site Study Plan for land use, Deaf Smith County site, Texas: Environmental Field Program: Preliminary draft

    International Nuclear Information System (INIS)

    1987-06-01

    The Land Use Site Study Plan describes a field program consisting of characterization of the site; seismic survey rights-of-way and transportation and utility corridors, the vicinity, the region, future land use, and monitoring land-use change. Aerial photography will be used to characterize the site, seismic rows and transportation and utility corridors, and the vicinity. The resulting land-use maps and overlays will then be verified in the field. Interviews with farm managers and local experts will provide additional information. A Geographic Information System (GIS) and satellite imagery will be used to characterize the region, monitor land-use change, and provide information to assist with the future land use study. The site study plan describes the study design and rationale, the filed data collection procedures and equipment, the data analysis methods and application of results, the data management strategy, the schedule of field activities, the personnel requirements and management of the study, and the study's quality assurance program. The directives and requirements that drive these studies are derived from the Salt Repository Project Requirements Document. 51 refs; 6 figs; 3 tabs

  8. Site study plan for ecology, Deaf Smith County Site, Texas: Environmental Field Program: Preliminary Draft

    International Nuclear Information System (INIS)

    1987-06-01

    The Ecology Site Study Plan describes a field program consisting of studies which include surveys for endangered, threatened, and candidate species; vegetation characterization, including mapping and cover typing, plant succession, wetlands description, and preexisting stresses; and wildlife community characterization, including availability and quality of habitats and descriptions of mammal, bird, reptile, amphibian, and invertebrate populations. The plan for each study describes the need for the study, study design, data management and use, schedule and personnel requirements, and quality assurance. These studies will provide data needed to satisfy requirements contained in, or derived from, the Salt Repository Project Requirements Document (SRP-RD). 83 refs., 3 tabs

  9. BIM approach for automated drafting and design for modular construction manufacturing

    NARCIS (Netherlands)

    Alwisy, A.; Al-Hussein, M.; Al-Jibouri, Saad H.S.; Issa, R.R.; Flood, I.

    2012-01-01

    Industrialization creates new requirements for design. Designers need to consider not only building performance, but also production plan needs. This requires a well-structured Building Information Model (BIM) to support the manufacturing needs for design and drafting. BIM, in combination with CAD

  10. Site study plan for exploratory shaft monitoring wells, Deaf Smith County Site, Texas: Preliminary Draft

    International Nuclear Information System (INIS)

    1988-01-01

    As part of site characterization studies, two exploratory shafts will be constructed at the Deaf Smith County site, Texas. Twelve wells at five locations have been proposed to monitor potential impacts of shaft construction on water-bearing zones in the Ogallala Formation and the Dockum Group. In addition, tests have been proposed to determine the hydraulic properties of the water-bearing zones for use in design and construction of the shafts. Samples of the Blackwater Draw Formation, Ogallala Formation, and Dockum Group will be obtained during construction of these wells. Visual indentification, laboratory testing, and in situ testing will yield data necessary for Exploratory Shaft Facility design and construction. This activity provides the earliest data on the Blackwater Drew Formation, Ogallala Formation, and Dockum Group near the exploratory shaft locations. Drilling and hydrologic testing are scheduled prior to other subsurface activity at the Exploratory Shaft Facility to establish ground-water baseline conditions. 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 Salt Repository Project procedures. A quality assurance program will be utilized to assure that activities affecting quality are performed correctly and that the appropriate documentation is maintained. 45 refs., 11 figs., 4 tabs

  11. Site Study Plan for soils, Deaf Smith County site, Texas: Environmental Field Program: Preliminary draft

    International Nuclear Information System (INIS)

    1987-06-01

    The Soils Site Study Plan describes a field program consisting of a soil characterization survey, impact monitoring of soils, predisturbance soil salinity survey, and a reclamation suitability study. This information will be used to plan for soil stripping, stockpiling, and replacement; reclamation of soils; determining predisturbance chemical and physical characteristics of the soils; including salinity levels; and monitoring for changes in chemical and physical characteristics of the soil. The SSP describes for each study the need for the study, the study design, data management and use, schedule of proposed activities, and the quality assurance program. These studies will provide data needed to satisfy requirements contained in, or derived from, the Salt Repository Project Requirements Document. 75 refs., 10 figs., 5 tabs

  12. A Survey of Former Drafting & Engineering Design Technology Students. Summary Findings of Respondents District-Wide.

    Science.gov (United States)

    Glyer-Culver, Betty

    In fall 2001 staff of the Los Rios Community College District Office of Institutional Research collaborated with occupational deans, academic deans, and faculty to develop and administer a survey of former Drafting and Engineering Design Technology students. The survey was designed to determine how well courses had met the needs of former drafting…

  13. 77 FR 74195 - Draft Guidance for Industry and Food and Drug Administration Staff; Design Considerations for...

    Science.gov (United States)

    2012-12-13

    ... DEPARTMENT OF HEALTH AND HUMAN SERVICES Food and Drug Administration [Docket No. FDA-2012-D-1161] Draft Guidance for Industry and Food and Drug Administration Staff; Design Considerations for Devices Intended for Home Use; Availability AGENCY: Food and Drug Administration, HHS. ACTION: Notice. SUMMARY: The...

  14. Draft environmental assessment: Yucca Mountain site, Nevada research and development area, Nevada. Nuclear Waste Policy Act (Section 112)

    International Nuclear Information System (INIS)

    1984-12-01

    In February 1983, the US Department of Energy (DOE) identified the Yucca Mountain site in Nevada as one of nine potentially acceptable sites for a mined geologic repository for spent nuclear fuel and high-level radioactive waste. To determine their suitability, the Yucca Mountain site and the eight other potentially acceptable sites have been evaluated in accordance with the DOE's General Guidelines for the Recommendation of Sites for Nuclear Waste Repositories. These evaluations are reported in this draft environmental assessment (EA), which is being issued for public review and comment. The DOE findings and determinations that are based on these evaluations are preliminary and subject to public review and comment. A final EA will be prepared after considering the comments received on the draft EA. The Yucca Mountain site is located in the Great Basin, one of five distinct geohydrologic settings that are being considered for the first repository. On the basis of the evaluations reported in this draft EA, the DOE has found that the Yucca Mountain site is not disqualified under the guidelines. The DOE has also found that it is suitable for site characterization because the evidence does not support a conclusion that the site will not be able to meet each of the qualifying conditions specified in the guidelines. On the basis of these findings, the DOE is proposing to nominate the Yucca Mountain site as one of five sites suitable for characterization. Furthermore, having performed a comparative evaluation of the five sites proposed for nomination, the DOE has determined that the Yucca Mountain site is one of three sites preferred for site characterization

  15. Site study plan for regional hydrologic sampling and monitoring: Preliminary draft

    International Nuclear Information System (INIS)

    Dutton, A.R.

    1987-01-01

    The purpose of the Regional Hydrologic Studies Plan is to describe those field activities required for completion of the objectives of hydrologic activities. Many of these activities are regional in scope and are designed to provide a framework for understanding the hydrologic setting of the site and the hydrologic processes that influence site characteristics. Site Study Plans (SSPs) define activates at and in the immediate vicinity of the site. The activities specified in the Regional Hydrologic Studies Plan are performed beyond the confines of the site because the hydrologic systems extend beyond the site boundaries, because pertinent data that bear on site suitability are available outside of the site, and because natural analogues exist outside of the site that allow analysis of processes that are expected to operate within the site. 15 refs., 5 figs., 1 tab

  16. Outline of the seismic design guideline of an FBR - a tentative draft

    International Nuclear Information System (INIS)

    Akiyama, Hiroshi; Ohtsubo, Hideomi; Nakamura, Hideharu; Matsuura, Shinichi; Hagiwara, Yutaka; Yuhara, Tetsuo; Hirayama, Hiroshi; Kokubo, Kunio; Ooka, Yuji.

    1993-01-01

    Central Research Institute of Electric Power Industry (Japan) is carrying out the Demonstration Test and Research Program of Buckling of FBR (FY 1987-FY 1993). The first half of the research program was finished after establishing a seismic buckling design guideline (a tentative draft). The purpose of this paper is to describe the dynamic buckling characteristics of FBR main vessels and the outline of the rationalized buckling design guideline for seismic loadings. (orig.)

  17. 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.

  18. 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

  19. Site study plan for Deep Hydronest Test Wells, Deaf Smith County Site, Texas: Preliminary draft

    International Nuclear Information System (INIS)

    1987-05-01

    Wells called Deep Hydronest Wells will be installed at six locations at the Deaf Smith County Site to characterize hydraulic parameters in the geologic column between the top of the San Andres Formation and the base of Pennsylvanian System. Three hydronests will be drilled during early stages of site characterization to provide data for performance assessment modeling. Four wells are proposed for each of these 3 nests. Results of drilling, testing, and preliminary modeling will direct drilling and testing activities at the last 3 nests. Two wells are proposed at each of the last 3 nests for a total of 18 wells. The Salt Repository Project (SRP) Networks specify the schedule under which this program will operate. Drilling and hydrologic testing of the first Deep Hydronest will begin early in the Surface Investigation Program. Drilling and testing of the first three Deep Hydronests will require about 18 months. After 12 months of evaluating and analyzing data from the first three hydronests, the remaining three hydronests will be drilled during a 12-month period. The Technical Field Services Contractor is responsible for conducting the field program. Samples and data will be handled and reported in accordance with established SRP procedures. A quality assurance program will be used to assure that activities affecting quality are performed correctly and that the appropriate documentation is maintained. 36 refs., 20 figs., 6 tabs

  20. 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

  1. 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

  2. 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.

  3. 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.

  4. 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.

  5. 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.

  6. 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.

  7. 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

  8. Revised Draft Hanford Site Solid (Radioactive and Hazardous) Waste Program Environmental Impact Statement, Richland, Washington

    International Nuclear Information System (INIS)

    2003-01-01

    This ''Revised Draft Hanford Site Solid (Radioactive and Hazardous) Waste Program Environmental Impact Statement'' (HSW EIS) covers three primary aspects of waste management at Hanford--waste treatment, storage, and disposal. It also addresses four kinds of solid waste--low-level waste (LLW), mixed (radioactive and chemically hazardous) low-level waste (MLLW), transuranic (TRU) waste, and immobilized low-activity waste (ILAW). It fundamentally asks the question: how should we manage the waste we have now and will have in the future? This EIS analyzes the impacts of the LLW, MLLW, TRU waste, and ILAW we currently have in storage, will generate, or expect to receive at Hanford. The HSW EIS is intended to help us determine what specific facilities we will continue to use, modify, or construct to treat, store, and dispose of these wastes (Figure S.1). Because radioactive and chemically hazardous waste management is a complex, technical, and difficult subject, we have made every effort to minimize the use of acronyms (making an exception for our four waste types listed above), use more commonly understood words, and provide the ''big picture'' in this summary. An acronym list, glossary of terms, and conversions for units of measure are provided in a readers guide in Volume 1 of this EIS

  9. 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

  10. 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.

  11. Design of a Kaplan turbine for a wide range of operating head -Curved draft tube design and model test verification-

    Science.gov (United States)

    KO, Pohan; MATSUMOTO, Kiyoshi; OHTAKE, Norio; DING, Hua

    2016-11-01

    As for turbomachine off-design performance improvement is challenging but critical for maximising the performing area. In this paper, a curved draft tube for a medium head Kaplan type hydro turbine is introduced and discussed for its significant effect on expanding operating head range. Without adding any extra structure and working fluid for swirl destruction and damping, a carefully designed outline shape of draft tube with the selected placement of center-piers successfully supresses the growth of turbulence eddy and the transport of the swirl to the outlet. Also, more kinetic energy is recovered and the head lost is improved. Finally, the model test results are also presented. The obvious performance improvement was found in the lower net head area, where the maximum efficiency improvement was measured up to 20% without compromising the best efficiency point. Additionally, this design results in a new draft tube more compact in size and so leads to better construction and manufacturing cost performance for prototype. The draft tube geometry parameter designing process was concerning the best efficiency point together with the off-design points covering various water net heads and discharges. The hydraulic performance and flow behavior was numerically previewed and visualized by solving Reynolds-Averaged Navier-Stokes equations with Shear Stress Transport turbulence model. The simulation was under the assumption of steady-state incompressible turbulence flow inside the flow passage, and the inlet boundary condition was the carefully simulated flow pattern from the runner outlet. For confirmation, the corresponding turbine efficiency performance of the entire operating area was verified by model test.

  12. Technical procedures for the implementation of cultural resource site studies, Deaf Smith County, Texas: Preliminary draft

    International Nuclear Information System (INIS)

    1987-01-01

    Cultural resources at the Deaf Smith County site will be identified, evaluated and managed through the implementation of studies detailed in the Site Study Plan for Cultural Resources. This technical procedure outlines the conduct of pedestrian survey and the documentation of identified cultural resources. The purpose of the field surveys is to identify and document cultural resources in the areas that will be affected by site characterization activities and to record the environmental setting of identified cultural resources. Three pedestrian surveys will cover 100 percent of the on-site and off-site project areas. Survey 1 will provide coverage of the Repository Surface Facility (RSF) area, which includes the Exploratory Shaft Facility (ESF) and two linear engineering design borehole (EDBH) seismic survey corridors. Survey 2 will provide coverage of a 39 km 2 (15 mi 2 ) area that includes the 23 km 2 (9 mi 2 ) Deaf Smith County site plus a 0.4 to 0.8 kM (1/4 to 1/2 mi) border area but excludes the area covered by Survey 1. Survey 3 will cover offsite geotechnical test areas, such as the locations of playa boreholes, deep playa wells, hydrologic tests, site foundation borings, and their access routes. The purpose of site documentation or recording is to address the project information needs for land use permits and approvals, engineering design support, and cultural resource evaluation for National Register of Historic Places eligibility. Site documentation will consist of gathering sufficient data on identified resources to complete Texas Natural Resource Information System (TNRIS). 7 refs., 3 figs

  13. CADDS [Computer-aided Drafting and Design System] brings quality and precision to the Canadian Maple [research reactor

    International Nuclear Information System (INIS)

    Goland, D.

    1989-01-01

    Atomic Energy of Canada Ltd (AECL) has found that using the ''intelligent'' Computer-Aided Drafting and Design System (CADDS) helped address design problems at an early stage and led to productivity gains of around 50 per cent. Other bonuses were the quality and precision of the designs and documents produced. Its application to the MAPLE research reactor project is described. (author)

  14. Site Study Plan for meteorology/air quality, Deaf Smith County site, Texas: Environmental Field Program: Preliminary draft

    International Nuclear Information System (INIS)

    1987-06-01

    The Meteorological/Air Quality Site Study Plan describes a field program consisting of continuous measurements of surface (10-meter) wind speed and direction, temperature, humidity, dew point, pressure, and sensible heat flux (vertical). Air quality measurements will be limited to suspended particulate matter. After the first year of measurements, a 60-meter tower will be added to incorporate measurements needed for later modeling and dose calculations; these will include upper level winds, vertical temperature structure, and vertical wind speed. All of these measurements will be made at a site located within the 9-mi 2 site area but remote from the ESF. A second site, located near and downwind from the ESF, will monitor only particulate matter. The SSP describes the need for each study; its design and design rationale; analysis, management, and use of data, schedule of field activities, organization of field personnel and sample management, and quality assurance requirements. These studies will provide data needed to satisfy requirements contained in, or derived from the Salt Repository Project Requirements Document. 38 refs., 8 figs., 3 tabs

  15. Draft environmental assessment for characterization of the Hanford Site pursuant to the Nuclear Waste Policy Act of 1982 (Public Law 97-425), Hanford Site, Richland, Benton County, Washington

    International Nuclear Information System (INIS)

    1983-02-01

    The Hanford Site is evaluated in this draft environmental assessment. The results of this evaluation are the basis for nominating the Hanford Site for site characterization leading to selection of the first repository site. The major conclusions are presented. 120 refs., 26 figs., 8 tabs

  16. 75 FR 8968 - Draft Guidance for Industry on Adaptive Design Clinical Trials for Drugs and Biologics; Availability

    Science.gov (United States)

    2010-02-26

    ... DEPARTMENT OF HEALTH AND HUMAN SERVICES Food and Drug Administration [Docket No. FDA-2010-D-0090] Draft Guidance for Industry on Adaptive Design Clinical Trials for Drugs and Biologics; Availability... familiar and less familiar approaches. As more experience is obtained with the less familiar designs...

  17. Site study plan for utilities and solid waste, Deaf Smith County Site, Texas: Environmental Field Program: Preliminary draft

    International Nuclear Information System (INIS)

    1987-06-01

    This site plan describes utilities and solid waste studies to be conducted during the characterization of the Deaf Smith County, Texas, site for the US Department of Energy's Salt Repository Project. After utilities and solid waste information needs derived from Federal, State, and local statutes and regulations and the project specifications are briefly described, the site study plan describes the study design and rationale, the field data collection procedures and equipment, and data analysis methods and application of results, the data management strategy, the schedule of field activities, the management of the study, and the study's quality assurance program. The field data collection activities are organized into programs to characterize electrical power, natural gas, communication, water, wastewater sludge, nonradiological solid waste, nonradiological hazardous waste, and low-level radiological waste. These programs include details for the collection of project needs, identification of utilities and solid waste disposal contractor capabilities, and verification of the obtained data. Utilities and solid waste field activities will begin approximately at the time of site access. Utilities and solid waste characterization will be completed within the first year of activity. 29 refs., 6 figs., 2 tabs

  18. Impact of computer-aided design and drafting on operator perceptions and performance intentions

    Energy Technology Data Exchange (ETDEWEB)

    Mandeville, D.E.

    1987-01-01

    The goal of the introduction of computer-aided design and drafting (CADD) technology is to improve engineering quantity and quality outcomes. What is not so obvious is that the manner in which the operator views the CADD job may affect these outcomes. The study found that: (1) the subjects hold job characteristic beliefs about their jobs that are similar to those held by individuals in related professional and technical positions in other organizations; (2) subjects in routine jobs who had little experience with CADD believe that the characteristics of the job with CADD will be less desirable than there present job utilizing manual drafting; however, experienced users believe that there is little difference; (3) the subjects performing technologically routine jobs indicate that quantity and quality of their jobs decreases with CADD, while holders of technologically nonroutine jobs indicate the opposite; (4) significant but weak relationships existed between job characteristic beliefs, attitudes, and job intentions; however, the model relationships and strengths varied when subgroups were analyzed; and (5) the correlation of social referent group beliefs with subject beliefs are significant but weak.

  19. Draft Underground Test Plan for site characterization and testing in an exploratory shaft facility in salt

    International Nuclear Information System (INIS)

    1987-05-01

    An exploratory shaft facility (ESF) at the Deaf Smith County, Texas is a potential candidate repository site in salt. This program of underground testing constitutes part of the effort to determine site suitability, provide data for repository design and performance assessment, and prepare licensing documentation. This program was developed by defining the information needs, as derived from the governing regulatory requirements and associated performance issues; evaluating the efficacy of available tests in satisfying the information needs; and selecting the suite of underground tests that are most cost-effective and timely, considering the other surface-based, surface borehole, and laboratory test programs. Tests are described conceptually, categorized in terms of geology, geomechanics, thermomechanics, geohydrology, or geochemistry, and range in scope from site characterization to site/engineered system interactions. The testing involves construction testing, conducted in the shafts during construction, and in situ testing at depth, conducted in the shafts and in the at-depth test facility at the repository horizon after shaft connection. 41 refs., 67 figs., 16 tabs

  20. Site Study Plan for background environmental radioactivity, Deaf Smith County site, Texas: Environmental Field Program: Preliminary draft

    International Nuclear Information System (INIS)

    1987-06-01

    The Background Environmental Radioactivity Site Study Plan describes a field program consisting of an initial radiological survey and a radiological sampling program. The field program includes measurement of direct radiation and collection and analysis of background radioactivity samples of air, precipitation, soil, water, milk, pasture grass, food crops, meat, poultry, game, and eggs. The plan describes for each study: the need for the study, the study design, data management and use, schedule of proposed activities, and quality assurance requirements. These studies will provide data needed to satisfy requirements contained in, or derived from, the Salt Repository Project (SRP) Requirements Document. 50 refs., 11 figs., 7 tabs

  1. Design and drafting document control procedures for CPRF/ZTH experiment

    International Nuclear Information System (INIS)

    Pollat, L.L.; Kewish, R.W.

    1989-01-01

    This paper will present, in general, the control procedures for design approval, review, changes, and release of engineering documents. It will also discuss interface control for tasks so that possible design interference does not occur. A document control procedure to insure that design criteria are met and technical specifications translate into workable drawings was instituted to support the Confinement Physics Research Facility (CPRF/ZTH) construction program. Our goal, to eliminate any conflicts that might arise between various tasks as the final designs are developed, required tight control and up-to-date design information. Detailed procedure for reviews were instituted, since circumventing the process of design and drafting anywhere might have proven disastrous to the CPRF/ZTH program. Design is a process of translating technical requirements, according to established standards, into drawings that are usable for fabrication and assembly. Both the designer and engineer are responsible for adhering to standards that have been established by the Mechanical Engineering Section for the CPRF/ZTH program. 6 refs., 5 figs

  2. A State Articulated Instructional Objectives Guide for Occupational Education Programs. State Pilot Model for Drafting (Graphic Communications). Part I--Basic. Part II--Specialty Programs. Section A (Mechanical Drafting and Design). Section B (Architectural Drafting and Design).

    Science.gov (United States)

    North Carolina State Dept. of Community Colleges, Raleigh.

    A two-part articulation instructional objective guide for drafting (graphic communications) is provided. Part I contains summary information on seven blocks (courses) of instruction. They are as follow: introduction; basic technical drafting; problem solving in graphics; reproduction processes; freehand drawing and sketching; graphics composition;…

  3. A practical technique for benefit-cost analysis of computer-aided design and drafting systems

    International Nuclear Information System (INIS)

    Shah, R.R.; Yan, G.

    1979-03-01

    Analysis of benefits and costs associated with the operation of Computer-Aided Design and Drafting Systems (CADDS) are needed to derive economic justification for acquiring new systems, as well as to evaluate the performance of existing installations. In practice, however, such analyses are difficult to perform since most technical and economic advantages of CADDS are ΣirreduciblesΣ, i.e. cannot be readily translated into monetary terms. In this paper, a practical technique for economic analysis of CADDS in a drawing office environment is presented. A Σworst caseΣ approach is taken since increase in productivity of existing manpower is the only benefit considered, while all foreseen costs are taken into account. Methods of estimating benefits and costs are described. The procedure for performing the analysis is illustrated by a case study based on the drawing office activities at Atomic Energy of Canada Limited. (auth)

  4. 78 FR 69690 - Draft Guidance for Industry: Considerations for the Design of Early-Phase Clinical Trials of...

    Science.gov (United States)

    2013-11-20

    ... (referred to collectively as CGT products) with recommendations to assist in designing early-phase clinical... Fishers Lane, Rm. 1061, Rockville, MD 20852. Submit written requests for single copies of the draft... 20852-1448. Send one self-addressed adhesive label to assist the office in processing your request. The...

  5. 78 FR 39736 - Draft Guidance for Industry: Considerations for the Design of Early-Phase Clinical Trials of...

    Science.gov (United States)

    2013-07-02

    ... collectively as CGT products) with recommendations to assist in designing early-phase clinical trials of CGT...-addressed adhesive label to assist the office in processing your requests. The draft guidance may also be...-305), Food and Drug Administration, 5630 Fishers Lane, rm. 1061, Rockville, MD 20852. FOR FURTHER...

  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. Radioactive waste isolation in salt: Peer review of the Office of Nuclear Waste Isolation's draft report on an issues hierarchy and data needs for site characterization

    International Nuclear Information System (INIS)

    Harrison, W.; Fenster, D.F.; Ditmars, J.D.; Paddock, R.A.; Rote, D.M.; Hambley, D.F.; Seitz, M.G.; Hull, A.B.

    1986-12-01

    At the request of the Salt Repository Project (SRPO), Argonne National Laboratory conducted an independent peer review of a report by the Battelle Office of Nuclear Waste Isolation entitled ''Salt Repository Project Issues Hierarchy and Data Needs for Site Characterization (Draft).'' This report provided a logical structure for evaluating the outstanding questions (issues) related to selection and licensing of a site as a high-level waste repository. It also provided a first estimate of the information and data necessary to answer or resolve those questions. As such, this report is the first step in developing a strategy for site characterization. Microfiche copies of ''Draft Issues Hierarchy, Resolution Strategy, and Information Needs for Site Characterization and Environmental/Socioeconomic Evaluation - July, 1986'' and ''Issues Hierarchy and Data Needs for Site Characterization - February, 1985'' are included in the back pocket of this report

  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. Safe interim storage of Hanford tank wastes, draft environmental impact statement, Hanford Site, Richland, Washington

    International Nuclear Information System (INIS)

    1994-07-01

    This Draft EIS is prepared pursuant to the National Environmental Policy Act (NEPA) and the Washington State Environmental Policy Act (SEPA). DOE and Ecology have identified the need to resolve near-term tank safety issues associated with Watchlist tanks as identified pursuant to Public Law (P.L.) 101-510, Section 3137, ''Safety Measures for Waste Tanks at Hanford Nuclear Reservation,'' of the National Defense Authorization Act for Fiscal Year 1991, while continuing to provide safe storage for other Hanford wastes. This would be an interim action pending other actions that could be taken to convert waste to a more stable form based on decisions resulting from the Tank Waste Remediation System (TWRS) EIS. The purpose for this action is to resolve safety issues concerning the generation of unacceptable levels of hydrogen in two Watchlist tanks, 101-SY and 103-SY. Retrieving waste in dilute form from Tanks 101-SY and 103-SY, hydrogen-generating Watchlist double shell tanks (DSTs) in the 200 West Area, and storage in new tanks is the preferred alternative for resolution of the hydrogen safety issues

  10. Safe interim storage of Hanford tank wastes, draft environmental impact statement, Hanford Site, Richland, Washington

    Energy Technology Data Exchange (ETDEWEB)

    1994-07-01

    This Draft EIS is prepared pursuant to the National Environmental Policy Act (NEPA) and the Washington State Environmental Policy Act (SEPA). DOE and Ecology have identified the need to resolve near-term tank safety issues associated with Watchlist tanks as identified pursuant to Public Law (P.L.) 101-510, Section 3137, ``Safety Measures for Waste Tanks at Hanford Nuclear Reservation,`` of the National Defense Authorization Act for Fiscal Year 1991, while continuing to provide safe storage for other Hanford wastes. This would be an interim action pending other actions that could be taken to convert waste to a more stable form based on decisions resulting from the Tank Waste Remediation System (TWRS) EIS. The purpose for this action is to resolve safety issues concerning the generation of unacceptable levels of hydrogen in two Watchlist tanks, 101-SY and 103-SY. Retrieving waste in dilute form from Tanks 101-SY and 103-SY, hydrogen-generating Watchlist double shell tanks (DSTs) in the 200 West Area, and storage in new tanks is the preferred alternative for resolution of the hydrogen safety issues.

  11. 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)

  12. 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)

  13. The SocioEconomic analysis of repository siting (SEARS): Guide to data base preparation: Final draft

    International Nuclear Information System (INIS)

    Hamm, R.R.; Murdock, S.H.; Leistritz, F.L.; Kiel, B.; Parpia, B.

    1984-11-01

    This guide describes the data bases in the SocioEconomic Analysis of Repository Siting (SEARS) modeling system. This model is a user-interactive, computerized model for projecting the economic, demographic, public service, and fiscal impacts of repository siting. This guide provides a description of the data bases, sources of data, data formats, and preprocessing programs for adapting and implementing the SEARS system and is seen as an essential reference for technical users of the model. It should be used in conjunction with reports describing the model's features and characteristics. 95 refs., 3 tabs

  14. Early site reviews for nuclear power facilities: procedures and possible technical review options. Draft

    International Nuclear Information System (INIS)

    1978-02-01

    The document provides guidance for utility companies, State and other governmental agencies, and others who may request or may wish to participate in an early review of site suitability issues related to a site proposed for a nuclear power or test reactor. Although the emphasis of this document is on a nuclear electric generating station, the guidance provided can be used for a test reactor or other kinds of reactors. The procedures to be followed by applicants for construction permits and by others are described and the possible significant areas of technical review are delineated

  15. Technical procedures for land use, Deaf Smith County site, Texas: Environmental Field Program: Final draft

    International Nuclear Information System (INIS)

    1987-09-01

    This volume contains Technical Procedures pursuant to the Land Use Site Study Plan including land use data acquisition, land use/land cover map compilation, verification of land use/land cover map accuracy, and land use/land cover data analysis. 22 refs., 5 figs

  16. Technical procedures for implementation of acoustics site studies, Deaf Smith County site, Texas: Environmental Field Program: Preliminary draft

    International Nuclear Information System (INIS)

    1987-09-01

    The purpose and scope of the technical procedure for processing data from the tethered meteorological system are covered. Definitions, interfaces, and concurrent data needs are also addressed. This technical procedure describes how to control, organize, verify, and archive tethered meteorological system data. These data will be received at the processing location from the field measurement location and are part of the characterization of the Deaf Smith County Site, Texas for the salt repository program. These measurements will be made in support of the sound propagation study and are a result of environmental data requirements for acoustics. 6 refs., 15 figs., 5 tabs

  17. Federal Facilities Compliance Act, Draft Site Treatment Plan: Compliance Plan Volume. Part 2, Volume 2

    International Nuclear Information System (INIS)

    1994-01-01

    This document presents the details of the implementation of the Site Treatment Plan developed by Ames Laboratory in compliance with the Federal Facilities Compliance Act. Topics discussed in this document include: implementation of the plan; milestones; annual updates to the plan; inclusion of new waste streams; modifications of the plan; funding considerations; low-level mixed waste treatment plan and schedules; and TRU mixed waste streams

  18. Technical procedures for ecology: Environmental field program, Deaf Smith County Site, Texas: Final draft

    International Nuclear Information System (INIS)

    1987-08-01

    This volume contains Technical Procedures pursuant to the Land Use Site Study Plan including walkover surveys for threatened, endangered, or candidate species; vegetation classification and mapping; reclamation planning; wetland and floodplain determination and characterization of playas; wildlife habitat mapping methods; mammal sampling; bird survey methods; reptile and amphibian survey methods; preexisting environmental; stress and disturbance studies methods; voucher specimens for plants; and voucher specimens to wildlife. 9 refs., 5 figs., 1 tab

  19. Evaluation of the need, feasibility, and siting of the MRS in Tennessee. Draft final report

    Energy Technology Data Exchange (ETDEWEB)

    Colglazier, E.W. Jr. [Tennessee Univ., Knoxville, TN (United States)

    1985-12-16

    This summary report outlines the results of an independent assessment of the need, feasibility, and siting of the proposed Monitored Retrievable Storage (MRS) facility. The detailed reports of this assessment are included as appendices to the summary report. The Department of Energy (DOE) has concluded that the MRS is not absolutely necessary, but preferred, in order to manage and move spent fuel from reactors to a repository. The team has attemped to assess ``need`` by comparing to advantages and disadvantages of various systems, with and without the MRS. ``Feasibility has been assessed by comparing the technical and economic advantages and disadvantages. The team was not asked to recommend a preferred system. That choice will depend on the importance that are used to compare alternatives. The five key criteria selected by the team for comparing alternate systems were: economic cost, radiological risk, non-radiological transportation impacts, the likelihood of successful implementation and operation of the system, and the likelihood of meeting the schedule in the Nuclear Waste Policy Act. The team compared twelve different systems and modeled the transportation impacts and risks with three repository sites and two MRS sites.

  20. Conceptual model for regional radionuclide transport from a basalt repository site. Final draft, technical memorandum

    Energy Technology Data Exchange (ETDEWEB)

    Walton, W.C.; Voorhees, M.L.; Prickett, T.A.

    1980-05-23

    This technical memorandum was prepared to: (1) describe a typical basalt radionuclide repository site, (2) describe geologic and hydrologic processes associated with regional radionuclide transport in basalts, (3) define the parameters required to model regional radionuclide transport from a basalt repository site, and (4) develop a ''conceptual model'' of radionuclide transport from a basalt repository site. In a general hydrological sense, basalts may be described as layered sequences of aquifers and aquitards. The Columbia River Basalt, centered near the semi-arid Pasco Basin, is considered by many to be typical basalt repository host rock. Detailed description of the flow system including flow velocities with high-low hydraulic conductivity sequences are not possible with existing data. However, according to theory, waste-transport routes are ultimately towards the Columbia River and the lengths of flow paths from the repository to the biosphere may be relatively short. There are many physical, chemical, thermal, and nuclear processes with associated parameters that together determine the possible pattern of radionuclide migration in basalts and surrounding formations. Brief process descriptions and associated parameter lists are provided. Emphasis has been placed on the use of the distribution coefficient in simulating ion exchange. The use of the distribution coefficient approach is limited because it takes into account only relatively fast mass transfer processes. In general, knowledge of hydrogeochemical processes is primitive.

  1. Conceptual model for regional radionuclide transport from a basalt repository site. Final draft, technical memorandum

    International Nuclear Information System (INIS)

    Walton, W.C.; Voorhees, M.L.; Prickett, T.A.

    1980-01-01

    This technical memorandum was prepared to: (1) describe a typical basalt radionuclide repository site, (2) describe geologic and hydrologic processes associated with regional radionuclide transport in basalts, (3) define the parameters required to model regional radionuclide transport from a basalt repository site, and (4) develop a ''conceptual model'' of radionuclide transport from a basalt repository site. In a general hydrological sense, basalts may be described as layered sequences of aquifers and aquitards. The Columbia River Basalt, centered near the semi-arid Pasco Basin, is considered by many to be typical basalt repository host rock. Detailed description of the flow system including flow velocities with high-low hydraulic conductivity sequences are not possible with existing data. However, according to theory, waste-transport routes are ultimately towards the Columbia River and the lengths of flow paths from the repository to the biosphere may be relatively short. There are many physical, chemical, thermal, and nuclear processes with associated parameters that together determine the possible pattern of radionuclide migration in basalts and surrounding formations. Brief process descriptions and associated parameter lists are provided. Emphasis has been placed on the use of the distribution coefficient in simulating ion exchange. The use of the distribution coefficient approach is limited because it takes into account only relatively fast mass transfer processes. In general, knowledge of hydrogeochemical processes is primitive

  2. Surface-based test plan, Deaf Smith County, Texas Site: Draft

    International Nuclear Information System (INIS)

    1985-01-01

    The Surface-Based Test Plan (SBTP) is the plan which accounts for all surface-based site field work to be conducted at the Permian salt site selected for characterization. The SBTP relates data needs from program requirement documents and presents plans to satisfy the data needs. The SBTP excludes plans for construction of the Exploratory Shaft Facility (ESF) and plans for the in situ testing. The SBTP is a hierarchical plan stemming from the Technical Program Plan. The SBTP describes in detail the process by which surface-based study plans are defined, developed, and controlled. The plans hierarchy extends downward thru subordinate Site Study Plans (SSPs), which describe in detail elements of field work to be done, to detailed Procedures which document the exact methodologies to be employed in the conduct of field work. The plan is a QA level S document, although some of its elements are at lower QA levels. The plan is a controlled document, and any proposed amendments to the plan or subordinate documents can only be implemented through the specified change control procedure

  3. Environmental regulatory compliance plan, Deaf County site, Texas: Draft revision 1

    International Nuclear Information System (INIS)

    1987-01-01

    The DOE is committed to conduct its operation in an environmentally safe and sound manner and comply with the letter and spirit of applicable environmental statues and regulations. These objectives are codified in DOE order N 5400.2, ''Environmental Policy Statement.'' This document, the Deaf Smith County site (Texas) Environmental Regulatory Compliance Plam (ERCP), is one means of implementing that policy. The ERCP describes the environmental regulatory requirements applicable to the Deaf Smith County site (Texas), and presented the framework within which the Salt Repository Project Office (SRPO) will comply with the requirements. The plan also discusses how DOE will address State and local environmental requirements. To achieve this purpose the ERCP will be developed in phases. This version of the ERCP is the first phase in the delopment of the ERCP. It represents the Salt Repository Project Office's understanding of environmental requirements for the site characterization phase of repository development. After consultation with the appropriate federal and state agencies and affected Indian tribes, the ERCP will be updated to reflect the results of consultation with these agencies and affected Indian tribes. 6 refs., 38 figs

  4. 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

  5. Shutdown of the River Water System at the Savannah River Site: Draft environmental impact statement

    International Nuclear Information System (INIS)

    1996-11-01

    This environmental impact statement (EIS) evaluates alternative approaches to and environmental impacts of shutting down the River Water System at the Savannah River Site (SRS). Five production reactors were operated at the site.to support these facilities, the River Water System was constructed to provide cooling water to pass through heat exchangers to absorb heat from the reactor core in each of the five reactor areas (C, K, L, P, and R). The DOE Savannah River Strategic Plan directs the SRS to find ways to reduce operating costs and to determine what site infrastructure it must maintain and what infrastructure is surplus. The River Water System has been identified as a potential surplus facility. Three alternatives to reduce the River Water System operating costs are evaluated in this EIS. In addition to the No-Action Alternative, which consists of continuing to operate the River Water System, this EIS examines one alternative (the Preferred Alternative) to shut down and maintain the River Water System in a standby condition until DOE determines that a standby condition is no longer necessary, and one alternative to shut down and deactivate the River Water System. The document provides background information and introduces the River Water System at the SRS; sets forth the purpose and need for DOE action; describes the alternatives DOE is considering; describes the environment at the SRS and in the surrounding area potentially affected by the alternatives addressed and provides a detailed assessment of the potential environmental impacts of the alternatives; and identifies regulatory requirements and evaluates their applicability to the alternatives considered

  6. The SocioEconomic Analysis of Repository Siting (SEARS): Technical description: Final draft

    International Nuclear Information System (INIS)

    1984-11-01

    Socioeconomic impacts must be assessed both for the near term and for the future. One means of addressing the need for the assessment of such impacts has been through the development of the computerized socioeconomic assessment model called the SocioEconomic Analysis of Repository Siting (SEARS) model. The SEARS model was developed for the Battelle Project Management Division. It was refined and adapted from state-of-the-art computerized projection models and thoroughly validated and is now available for use in projecting the likely socioeconomic impacts of a repository facility. This Technical Description is one of six major products that describe the SEARS modeling system. 61 refs., 11 figs., 9 tabs

  7. General basin modeling for site suitability. Draft report 1. Baseline data

    International Nuclear Information System (INIS)

    1979-04-01

    This report summarizes work completed by Golder Associates under Task 2 - Site Suitability specifically for modeling of fluid flow and mass transport in sedimentary basins containing thick shale or salt. It also describes ongoing and future work on the above topic. The purpose of the study is to develop a general model for a nuclear waste repository situated in a deep sedimentary basin environment. The model will be used in conjunction with Golder's fluid flow and mass transport codes to study specific aspects of nuclide transport by groundwater flow

  8. Development of Draft Regulatory Guide on Accident Analysis for Nuclear Power Plants with New Safety Design Features

    Energy Technology Data Exchange (ETDEWEB)

    Bang, Young Seok; Woo, Sweng Woong; Hwang, Tae Suk [KINS, Daejeon (Korea, Republic of); Sim, Suk K; Hwang, Min Jeong [Environment and Energy Technology, Daejeon (Korea, Republic of)

    2016-05-15

    The present paper discusses the development process of the draft version of regulatory guide (DRG) on accident analysis of the NPP having the NSFD and its result. Based on the consideration on the lesson learned from the previous licensing review, a draft regulatory guide (DRG) on accident analysis for NPP with new safety design features (NSDF) was developed. New safety design features (NSDF) have been introduced to the new constructing nuclear power plants (NPP) since the early 2000 and the issuance of construction permit of SKN Units 3 and 4. Typical examples of the new safety features includes Fluidic Device (FD) within Safety Injection Tanks (SIT), Passive Auxiliary Feedwater System (PAFS), ECCS Core Barrel Duct (ECBD) which were adopted in APR1400 design and/or APR+ design to improve the safety margin of the plants for the postulated accidents of interest. Also several studies of new concept of the safety system such as Hybrid ECCS design have been reported. General and/or specific guideline of accident analysis considering the NSDF has been requested. Realistic evaluation of the impact of NSDF on accident with uncertainty and separated accident analysis accounting the NSDF impact were specified in the DRG. Per the developmental process, identification of key issues, demonstration of the DRG with specific accident with specific NSDF, and improvement of DGR for the key issues and their resolution will be conducted.

  9. Draft environmental impact statement. High-level waste repository site suitability criteria

    International Nuclear Information System (INIS)

    1978-01-01

    The purpose of HLWRSSC is to present guidelines which will help in the development of safe waste management schemes. Current regulations require solidification of all high-level waste within 5 years of their generation and transfer to a Federal waste repository within 10 years. Development of the proposed HLWRSSC is part of the overall NRC program to close the ''back end'' of the commercial LWR fuel cycle. In this document, the need for the HLWRSSC is reviewed, and the national energy policy, the need for electrical energy, and the nuclear fuel cycle are discussed. Considerations for HLWRSSC are presented, including the nature of the repository, important site-related factors, and radiological risk assessment methodology. Radiological and nonradiological environment impacts associated with the HLWRSSC are defined. Alternatives to the criteria are presented, and the cost-benefit-risk evaluation is reviewed

  10. 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.

  11. Draft environmental impact statement. Los Alamos Scientific Laboratory Site, Los Alamos, New Mexico

    International Nuclear Information System (INIS)

    1978-05-01

    This statement assesses the potential cumulative environmental impacts associated with current and continuing activities at the LASL site. This includes the adverse impacts from postulated accidents associated with the activities. Various effluents including radioactive ones are released to the environment. However, a continuing, comprehensive, monitoring program is carried out to assist in the control of hazardous effluents. Alternatives to current operation of LASL include: cessation or relocation of programs; continue activities as presently constituted; further limitation of adverse impacts by institutional or other improvements in various operations; and expansion of current activities. Liquid, gaseous, and solid wastes are generated as by-products of the laboratory operation. Liquid wastes include radioactively contaminated solutions, chemically contaminated wastes, sanitary sewage, cooling water discharges, and storm drainage. The ordinary sanitary liquid wastes are processed by conventional sewage treatment plants, lagoons, and septic tanks. Industrial liquid wastes are processed by special treatment plants to remove radioactive components and to detoxify or neutralize other chemical agents. The results of analyses of treated effluents released in 1976 are summarized. The treated effluents contain radioactive pollutants at levels of only a few percent of guidelines applicable to exposure to the public from ingestion of water and food

  12. Rocky Flats Plant Site, Golden, Colorado. Volume I. Draft environmental impact statement

    International Nuclear Information System (INIS)

    1977-09-01

    Two previous environmental statements have been issued for the Rocky Flats Plant site. One concerned a new plutonium recovery facility (WASH-1517, USAEC, January 1972); the second concerned land acquisition (WASH-1518, USAEC, April 1972). This document responds to those who indicated concerns and also ERDA's anticipated concerns about activities associated with the Rocky Flats Plant. Most concerns focus on two points including the Plant's involvement in the production of nuclear weapons and the Plant's handling of hazardous materials, particularly the radioactive element plutonium. The production of nuclear weapons, in which the Rocky Flats Plant maintains a vital role, will probably continue for as long as the world situation suggests that this country must have a strong defense. Operations at the Rocky Flats Plant have resulted in some plutonium being released to the environment, but evidence does not indicate that the amounts involved have presented any measurable hazard to human health. Ongoing improvements to the Plant's facilities and operational procedures are intended to preclude any recurrence of past releases. Despite these improvements, some public concern has resulted from past releases and the potential adverse effects from any possible future releases. This DEIS addresses that concern. It comments on past mishaps along with their causes and effects. It discusses current operations plus related costs and benefits to the region. Various alternatives to continuing present operations are explored, and the costs and benefits of the different options are compared

  13. Savannah River Site, spent nuclear fuel management, draft environmental impact statement

    International Nuclear Information System (INIS)

    1998-12-01

    The management of spent nuclear fuel (SNF) has been an integral part of the mission of the Savannah River Site (SRS) for more than 40 years. Until the early 1990s, SNF management consisted primarily of short-term onsite storage and reprocessing in the SRS chemical separation facilities to produce strategic nuclear materials. With the end of the Cold War, the US Department of Energy (DOE) decided to phase out reprocessing of SNF for the production of nuclear weapons materials. Therefore, the management strategy for this fuel has shifted from short-term storage and reprocessing for the recovery of highly-enriched uranium and transuranic isotopes to stabilization, when necessary, and interim storage pending final disposition that includes preparing aluminum-based SNF for placement in a geologic repository. In addition to the fuel already onsite, the SRS will receive SNF from foreign research reactors until 2009 and from domestic research reactors until, potentially, 2035. As a result, the safe and efficient management of SNF will continue to be an important SRS mission. This EIS evaluates the potential environmental impacts of DOE's proposed plans for management SNF assigned to SRS

  14. Design of hoisting device used in nuclear power plants. KTA safety engineering code. Draft amendment, as of 6/98

    International Nuclear Information System (INIS)

    1998-06-01

    The draft amendment specifies, according to the hazards involved, (a) the general provisions, (b) additional provisions supplementing the general provisions, (c) more stringent provisions relating to aggravated risks, applicable to lifting gear, and (d) additional requirements for elevators in reactor containments and refuelling equipment, to be taken into account in the design of hoisting device used in nuclear power plants. The term hoisting device in this context covers elevators, cranes, winches, trolleys, load carrying equipment, and LWR refuelling machines as are used in nuclear power plants. (orig./CB) [de

  15. 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.

  16. 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

  17. Developing a Ballistic Software Kit to Estimate Vehicle Characteristics at the Draft Design Stage

    Directory of Open Access Journals (Sweden)

    V. I. Maiorova

    2015-01-01

    Full Text Available The article describes a ballistic software kit to calculate a moving vehicle trajectory in atmosphere and space. Such software gives an opportunity to accelerate the acquisition of flying vehicle’s ballistic parameters at the stage of draft design. It contributes to improving collaboration efficiency between adjacent departments involved in the project. The developed software kit includes three different programs: Trajectory-LAND© (motion in atmosphere with possible correction of a trajectory, Trajectory-SPACE© (motion in the non-central gravity field with possible simulation of maneuvers, Trajectory-LAUNCH© (launch-vehicle’s insertion into the orbit with possible defining the impact points of separated stages. Each of the software concedes the addition of computational modules to use the solution results of the basic task. Implemented mathematical models permit to take into account the influence of main perturbations on the flying vehicle during the flight. For illustration purposes, the article gives some examples of using each of the programs and their block-diagrams.The developed software implements some algorithms, which allow attaining the convergence of numerical simulation of differential equations of motion. This problem arises, for example, while determining an attitude in case the stages have already separated from the launch vehicle. The mathematical conversion from Rodriguez-Hamilton parameters into Euler’s angles disables us to obtain reliable values of attitude angles due to the limitations for existing area of inverse trigonometric functions being used. Incorrect values of pitch lead to raw and roll channels divergences. Moreover, the mistakes in attitude determination lead to mistakes in obtained values of attack angle, which is included into the forms for aerodynamic forces and torques. As a result, the solution of system of differential equations is a failure when a flying vehicle enters the height of 30-35 km. The

  18. Draft site characterization analysis of the site characterization report for the Basalt Waste Isolation Project, Hanford, Washington Site. Main report and Appendices A through D

    International Nuclear Information System (INIS)

    1983-03-01

    On November 12, 1982, the US Department of Energy submitted to the US Nuclear Regulatory Commission the Site Characterization Report for the Basalt Waste Isolation Project (DOE/RL 82-3). The Basalt Waste Isolation Project is located on DOE's Hanford Reservation in the State of Washington. NUREG-0960 contains the detailed analysis, by the NRC staff, of the site characterization report. Supporting technical material is contained in Appendices A through W

  19. 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.

  20. Draft site characterization analysis of the site characterization report for the Basalt Waste Isolation Project, Hanford, Washington site. Appendices E through W

    International Nuclear Information System (INIS)

    1983-03-01

    Volume 2 contains Appendices E through W: potential for large-scale pump tests in the Grande Ronde; review of hydrochemical characterization related to flow system interpretation in Hanford basalts; limitations of packer-testing for head evaluation in Hanford basalts; hydrogeologic data integration for conceptual groundwater flow models; drilling mud effects on hydrogeologic testing; site issue analyses related to the nature at the present groundwater system at the Hanford site, Washington; structural and stratigraphic characteristics related to groundwater flow at the Hanford site, Washington; seismic hazard and some examples of hazard studies at Hanford; earthquake swarms in the Columbia Plateau; seismic ground motion at depth; failure modes for the metallic waste package component; degradation mechanisms of borosilicate glass; transport and retardation of radionuclides in the waste package; determination and interpretation of redox conditions and changes in underground high-level repositories; determination and interpretation of sorption data applied to radionuclide migration in underground repositories; solubility of radionuclide compounds presented in the BWIP site characterization report; and release rate from engineered system

  1. 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...

  2. 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...

  3. Proposed plan for interim remedial measures at the 100-HR-1 Operable Unit, Hanford Site, Richland, Washington. Draft A

    International Nuclear Information System (INIS)

    1994-09-01

    This proposed plan introduces the interim remedial measures for addressing contaminated soil at the 100-HR-1 Operable Unit, located at the Hanford Site. In addition, this plan includes a summary of other alternatives analyzed and considered for the 100-HR-1 Operable Unit. The EPA, DOE, and Washington State Dept. of Ecology believe that a combination of removal, treatment, and disposal technologies, where appropriate, would significantly reduce the potential threats to human health and the environment at the 100-HR-1 Operable Unit high-priority waste sites. The remedial actions described in this proposed plan are designed to minimize human health and ecological risks and ensure that additional contaminants originating from these waste sites are not transported to the groundwater. The 100-HR-1 Operable Unit contains the retention basin for the H reactor cooling system, process effluent trenches, the Pluto crib which received an estimated 260 gallons of radioactive liquid waste, process effluent pipelines, and solid waste sites used for the burial of decontaminated and decommissioned equipment from other facilities. Potential health threats would be from the isotopes of cesium, cobalt, europium, plutonium, and strontium, and from chromium, arsenic, lead, and chysene

  4. The use of 3D CADD (Computer Aided Design and Drafting) models in operation and maintenance cost reduction

    International Nuclear Information System (INIS)

    Didsbury, R.; Bains, N.; Cho, U.Y.

    1998-01-01

    The use of three dimensional(3D) computer-aided design and drafting(CADD) models, and the associated information technology and databases, in the engineering and construction phases of large projects is well established and yielding significant improvements in project cost, schedule and quality. The information contained in these models can also be extremely valuable to operating plants, particularly when the visual and spatial information contained in the 3D models is interfaced to other plant information databases. Indeed many plant owners and operators in the process and power industries are already using this technology to assist with such activities as plant configuration management, staff training, work planning and radiation protection. This paper will explore the application of 3D models and the associated databases in an operating plant environment and describe the resulting operational benefits and cost reduction benefits. Several industrial experience case studies will be presented along with suggestions for further future applications. (author). 4 refs., 1 tab., 8 figs

  5. Cluster: Drafting. Course: Introduction to Technical Drafting.

    Science.gov (United States)

    Sanford - Lee County Schools, NC.

    The set of 10 units is designed for use with an instructor as an introduction to technical drafting, and is also keyed to other texts. Each unit contains several task packages specifying prerequisites, rationale for learning, objectives, learning activities to be supervised by the instructor, and learning practice. The units cover: drafting…

  6. Present activities for the preparation of a Japanese draft of structural design guidelines for the experimental fusion reactor

    International Nuclear Information System (INIS)

    Miya, K.; Muto, Y.; Takatsu, H.; Hada, K.; Koizumi, K.; Jitsukawa, S.; Arai, T.; Ohkawa, Y.; Shimakawa, T.; Aoto, K.; Shiraishi, H.; Takagi, T.; Miki, N.; Takahashi, S.; Sato, K.; Takemasa, F.; Kasaba, M.; Kudough, F.; Fujita, J.; Kajiura, S.; Kinoshita, S.

    1996-01-01

    Since November 1990, systematic research has been carried out in preparation for a Japanese draft of structural design guidelines for the experimental fusion reactor. This report summarizes the major results of the work and the status of these efforts. A classification of components and definition of operating conditions are proposed on the basis of the ITER-CDA design, in the light of the safety characteristics of the fusion reactor and relevant conventions for the existing fission reactor design code. Specific issues regarding the structural design of the experimental fusion reactor are discussed based on the experimental and analytical work. The validity of the existing structural design method is confirmed for the use of irradiated 316 SS, irrespective of the significant reduction in uniform elongation capability caused by heavy neutron irradiation. Further important phenomena are treated such as magnetic damping, magnetic stiffness and fracture due to electromagnetic forces. Finally, the issues concerned with welding and non-destructive examinations are discussed with relevance to component classification. (orig.)

  7. 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)

  8. Design Considerations for Multilingual Web Sites

    Directory of Open Access Journals (Sweden)

    Joan Starr

    2005-09-01

    Full Text Available The most powerful marketing, service, and information-distribution tool a library has today is its Web site, but providing Web content in many languages is complex. Before allocating scarce technical and financial resources, it is valuable to learn about writing systems, types of writing, how computers render and represent writing systems, and to study potential problem areas and their possible solutions. The accepted Web standard for presenting languages is Unicode and a full understanding of its history and the coding tools it provides is essential to making appropriate decisions for specific multilingual and internationalization projects. Actual coding examples, as well as a sampling of existing multilingual library services, also serve to illuminate the path of implementation.

  9. Draft Environmental Impact Statement for Construction and Operation of a Depleted Uranium Hexafluoride Conversion Facility at the Paducah, Kentucky, Site

    International Nuclear Information System (INIS)

    2003-01-01

    This document is a site-specific environmental impact statement (EIS) for construction and operation of a proposed depleted uranium hexafluoride (DUF 6 ) conversion facility at the U.S. Department of Energy (DOE) Paducah site in northwestern Kentucky (Figure S-1). The proposed facility would convert the DUF 6 stored at Paducah to a more stable chemical form suitable for use or disposal. In a Notice of Intent (NOI) published in the ''Federal Register'' (FR) on September 18, 2001 (''Federal Register'', Volume 66, page 48123 [66 FR 48123]), DOE announced its intention to prepare a single EIS for a proposal to construct, operate, maintain, and decontaminate and decommission two DUF 6 conversion facilities at Portsmouth, Ohio, and Paducah, Kentucky, in accordance with the National Environmental Policy Act of 1969 (NEPA) (''United States Code'', Title 42, Section 4321 et seq. [42 USC 4321 et seq.]) and DOE's NEPA implementing procedures (''Code of Federal Regulations'', Title 10, Part 1021 [10 CFR Part 1021]). Subsequent to award of a contract to Uranium Disposition Services, LLC (hereafter referred to as UDS), Oak Ridge, Tennessee, on August 29, 2002, for design, construction, and operation of DUF 6 conversion facilities at Portsmouth and Paducah, DOE reevaluated its approach to the NEPA process and decided to prepare separate site-specific EISs. This change was announced in a ''Federal Register'' Notice of Change in NEPA Compliance Approach published on April 28, 2003 (68 FR 22368); the Notice is included as Attachment B to Appendix C of this EIS. This EIS addresses the potential environmental impacts from the construction, operation, maintenance, and decontamination and decommissioning (DandD) of the proposed conversion facility at three alternative locations within the Paducah site; from the transportation of depleted uranium conversion products to a disposal facility; and from the transportation, sale, use, or disposal of the fluoride-containing conversion products

  10. Competency Reference for Computer Assisted Drafting.

    Science.gov (United States)

    Oregon State Dept. of Education, Salem. Div. of Vocational Technical Education.

    This guide, developed in Oregon, lists competencies essential for students in computer-assisted drafting (CAD). Competencies are organized in eight categories: computer hardware, file usage and manipulation, basic drafting techniques, mechanical drafting, specialty disciplines, three dimensional drawing/design, plotting/printing, and advanced CAD.…

  11. Draft audit report, human factors engineering control room design review: Saint Lucie Nuclear Power Plant, Unit No. 2

    International Nuclear Information System (INIS)

    Peterson, L.R.; Lappa, D.A.; Moore, J.W.

    1981-01-01

    A human factors engineering preliminary design review of the Saint Lucie Unit 2 control room was performed at the site on August 3 through August 7, 1981. This design review was carried out by a team from the Human Factors Engineering Branch, Division of Human Factors Safety. This report was prepared on the basis of the HFEB's review of the applicant's Preliminary Design Assessment and the human factors engineering design review/audit performed at the site. The review team included human factors consultants from BioTechnology, Inc., Falls Church, Virginia, and from Lawrence Livermore National Laboratory (University of California), Livermore, California

  12. Security credentials management system (SCMS) design and analysis for the connected vehicle system : draft.

    Science.gov (United States)

    2013-12-27

    This report presents an analysis by Booz Allen Hamilton (Booz Allen) of the technical design for the Security Credentials Management System (SCMS) intended to support communications security for the connected vehicle system. The SCMS technical design...

  13. 78 FR 37759 - Ocean Dumping; Atchafalaya-West Ocean Dredged Material Disposal Site Designation

    Science.gov (United States)

    2013-06-24

    ....regulations.gov or email. The www.regulations.gov Web site is an ``anonymous access'' system, which means EPA... docket and made available on the Internet. If you submit an electronic comment, EPA recommends that you....gov . SUPPLEMENTARY INFORMATION: The proposed rule and draft EIS may both be obtained via the Internet...

  14. 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.

  15. 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,

  16. 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.

  17. 77 FR 9694 - Notice of Availability of the Draft Environmental Impact Statement for the Restoration Design...

    Science.gov (United States)

    2012-02-17

    ... SEZs for utility-scale production of solar energy and to establish national program guidance... lands across Arizona that may be suitable for developing renewable solar and wind energy, and to... the project Web site: http://www.blm.gov/az/st/en/prog/energy/arra_solar.htm . FOR FURTHER INFORMATION...

  18. State of Nevada comments on the US Department of Energy consultation draft site characterization plan, Yucca Mountain site, Nevada research and development area, Nevada

    International Nuclear Information System (INIS)

    1988-09-01

    The SCPCD has identified a number of key issues that need to be addressed for characterization of the Yucca Mountain site. A variety of complex experiments have been proposed in an attempt to address these issues. Although a lot of time, money and effort has been spent on characterizing the Yucca Mountain area to date, there are still many unresolved technical issues. Since many of the experiments proposed in the SCPCD have never been done in an unsaturated fractured media, it is impossible to tell if they will be successful. Results of these experiments may indicate that new test designs or data collection procedures are needed to address the issues. Our approach to reviewing the SCPCD has been to first identify key technical issues which have not been resolved and to make specific comments associated with the hydrologic experiments proposed

  19. 77 FR 74196 - Draft Guidance for Industry on Safety Considerations for Product Design To Minimize Medication...

    Science.gov (United States)

    2012-12-13

    ... error-prone label and packaging designs. Among these measures, FDA agreed that by the end of FY 2010... minimizing risks with the design of drug product container labels, carton labeling, and packaging... DEPARTMENT OF HEALTH AND HUMAN SERVICES Food and Drug Administration [Docket No. FDA-2012-D-1005...

  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. 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.

  2. 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

  3. 77 FR 14716 - Notice of Availability: Draft Documents Related to the Development of Emissions Estimating...

    Science.gov (United States)

    2012-03-13

    ..., Tyson Foods, Inc. collected data from two broiler sites, which are also included in the NAEMS dataset... ), and volatile organic compounds (VOCs). For lagoons and basins, the study was designed to collect NH 3... draft documents describe the sites monitored, the statistical methodology used to analyze the data, and...

  4. Baseline risk assessment for groundwater contamination at the uranium mill tailings site near Monument Valley, Arizona. Draft

    Energy Technology Data Exchange (ETDEWEB)

    1993-09-01

    This baseline risk assessment evaluates potential impact to public health or the environment resulting from groundwater contamination at the former uranium mill processing site near Monument Valley, Arizona. The tailings and other contaminated material at this site are being relocated and stabilized in a disposal cell at Mexican Hat, Utah, through the US Department of Energy (DOE) Uranium Mill Tailings Remedial Action (UMTRA) Project. The tailings removal is planned for completion by spring 1994. After the tailings are removed, groundwater contamination at the site will continue to be evaluated. This risk assessment is the first document specific to this site for the Groundwater Project. It will be used to assist in determining what remedial action is needed for contaminated groundwater at the site.

  5. Multiobjective optimal design of runner blade using efficiency and draft tube pulsation criteria

    International Nuclear Information System (INIS)

    Pilev, I M; Sotnikov, A A; Rigin, V E; Semenova, A V; Cherny, S G; Chirkov, D V; Bannikov, D V; Skorospelov, V A

    2012-01-01

    In the present work new criteria of optimal design method for turbine runner [1] are proposed. Firstly, based on the efficient method which couples direct simulation of 3D turbulent flow and engineering semi empirical formulas, the combined method is built for hydraulic energy losses estimation in the whole turbine water passage and the efficiency criterion is formulated. Secondly, the criterion of dynamic loads minimization is developed for those caused by vortex rope precession downstream of the runner. This criterion is based on the finding that the monotonic increase of meridional velocity component in the direction to runner hub, downstream of its blades, provides for decreasing the intensity of vortex rope and thereafter, minimization of pressure pulsation amplitude. The developed algorithm was applied to optimal design of 640 MW Francis turbine runner. It can ensure high efficiency at best efficiency operating point as well as diminished pressure pulsations at full load regime.

  6. Methodology for assessing the impacts of alternative rate designs on industrial energy use. Draft report

    Energy Technology Data Exchange (ETDEWEB)

    None

    1980-01-11

    A task was undertaken to develop a method for analyzing industrial user responses to alternative rate designs. The method described considers the fuel switching and conservation responses of industrial users and the impact to a hypothetical utility regarding revenue stability, annual gas demand, and seasonal fluctuations. Twenty-seven hypothetical industrial plant types have been specified. For each combustor in the plant, the fuel consumption by season, initial fuel type, fuel switching costs, conservation costs, and amount of fuel conservable is provided. The decision making takes place at the plant level and is aggregated to determine the impact to the utility. Section 2 discusses the factors affecting an industrial user's response to alternative rate designs. Section 3 describes the methodology, includes an overview of the model and an example industrial user's response to a set of fuel prices. The data describing the 27 hypothetical firms is in an appendix.

  7. 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

  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. Advanced software development workstation. Engineering scripting language graphical editor: DRAFT design document

    Science.gov (United States)

    1991-01-01

    The Engineering Scripting Language (ESL) is a language designed to allow nonprogramming users to write Higher Order Language (HOL) programs by drawing directed graphs to represent the program and having the system generate the corresponding program in HOL. The ESL system supports user generation of HOL programs through the manipulation of directed graphs. The components of this graphs (nodes, ports, and connectors) are objects each of which has its own properties and property values. The purpose of the ESL graphical editor is to allow the user to create or edit graph objects which represent programs.

  10. Components of the LWR primary circuit. Pt. 2. Design, construction and calculation. Draft

    International Nuclear Information System (INIS)

    1995-01-01

    This standard is to be applied to components made of metallic materials, operated at design temperatures of up to 673 K (400 deg C). The primary circuit as the pressure containment of the reactor coolant comprises: Reactor pressure vessel (without internals), steam generator (primary loop), pressurizer, reactor coolant pump housing, interconnecting pipings between the components mentioned above and appropriate various valve and instrument casings, pipings branding from the above components and interconnecting pipings, including the appropriate instrument casings, up to and including the first isolating valve, pressure shielding of control rod drives. (orig.) [de

  11. (Review Draft) Radiation Site Cleanup Regulations: Technical Support Document For The Development Of Radionuclide Cleanup Levels For Soil

    Science.gov (United States)

    This document describes parts of the technical analysis being undertaken in support of standards that ensure certain sites are cleaned up to a level that is protective of human health and the environment before they are released for public use.

  12. Environmental assessment of remedial action at the Slick Rock uranium mill tailings sites Slick Rock, Colorado. Draft

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1993-06-01

    The Uranium Mill Tailings Radiation Control Act of 1978 (UMTRCA) authorized the US Department of Energy (DOE) to clean up two uranium mill tailings processing sites near Slick Rock, Colorado, in San Miguel County. The purpose of the cleanup is to reduce the potential health effects associated with the radioactive materials remaining on the sites and on vicinity properties (VP) associated with the sites. The US Environmental Protection Agency (EPA) promulgated standards for the UMTRCA that contained measures to control the contaminated materials and to protect the groundwater from further degradation. Remedial actions at the Slick Rock sites must be performed in accordance with these standards and with the concurrence of the US Nuclear Regulatory Commission (NRC).

  13. Planning for a program design for energy environmental analysis. Final report, draft

    Energy Technology Data Exchange (ETDEWEB)

    Denton, J; Saaty, T; Blair, P; Ma, F; Buneman, P

    1976-04-01

    The objective of the work reported here is to assist BER/ERDA in program planning with respect to a regional assessment study program for energy environmental analysis. The focus of the work was to examine the use of operational gaming fof regional assessment studies. Specific concerns were gaming applications (1) in regional assessment or management and direction of regional assessments; (2) for achieving a higher level of public understanding of environmental, health, and safety problems of energy; (3) with respect to the supply of adequately trained manpower for energy; (4) with respect to computational requirements; and (5) with respect to current state-of-the-art in computer simulation. In order to investigate these concerns and examine the feasibility of using operational gaming in a regional assessment study program, a Regional Energy Environment Game (REEG) was designed and implemented on an IBM 370/168 digital computer employing APL (A Programming Language). The applicability of interactive operational gaming has been demonstrated by the REEG as applied to a region consisting of Delaware, Maryland, New Jersey, Pennsylvania, and the District of Columbia.

  14. Socioeconomic monitoring and mitigation plan for the Salt Repository Project Site, Deaf Smith County, Texas: Revision 5: Draft

    International Nuclear Information System (INIS)

    1988-03-01

    The purpose of the Socioeconomic Monitoring and Mitigation Plan (SMMP) is to identify, in consultation with the affected States and Indian Tribes, potentially significant adverse socioeconomic impacts that could result from site characterization activities, to describe approaches that will be used to monitor any such identified impacts, and to describe procedures for mitigating them. Chapter 3 of the SMMP provides a description of site characterization phase activities planned to assess the geologic condition of the site and construction the exploratory shafts and surface support facilities. The rationale for developing socioeconomic monitoring studies is presented in Chapter 4. Chapter 5 contains descriptions of the socioeconomic monitoring and mitigation procedures whenever they are applicable. Additionally, in Chapter 6, the SMMP includes a procedure for modifying the monitoring and mitigation program and an approach for reporting monitoring results to interested parties. 8 refs., 20 figs., 4 tabs

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

    International Nuclear Information System (INIS)

    1987-08-01

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

  16. Draft environmental impact statement siting, construction, and operation of New Production Reactor capacity. Volume 4, Appendices D-R

    Energy Technology Data Exchange (ETDEWEB)

    None

    1991-04-01

    This Environmental Impact Statement (EIS) assesses the potential environmental impacts, both on a broad programmatic level and on a project-specific level, concerning a proposed action to provide new tritium production capacity to meet the nation`s nuclear defense requirements well into the 21st century. A capacity equivalent to that of about a 3,000-megawatt (thermal) heavy-water reactor was assumed as a reference basis for analysis in this EIS; this is the approximate capacity of the existing production reactors at DOE`s Savannah River Site near Aiken, South Carolina. The EIS programmatic alternatives address Departmental decisions to be made on whether to build new production facilities, whether to build one or more complexes, what size production capacity to provide, and when to provide this capacity. Project-specific impacts for siting, constructing, and operating new production reactor capacity are assessed for three alternative sites: the Hanford Site near Richland, Washington; the Idaho National Engineering Laboratory near Idaho Falls, Idaho; and the Savannah River Site. For each site, the impacts of three reactor technologies (and supporting facilities) are assessed: a heavy-water reactor, a light-water reactor, and a modular high-temperature gas-cooled reactor. Impacts of the no-action alternative also are assessed. The EIS evaluates impacts related to air quality; noise levels; surface water, groundwater, and wetlands; land use; recreation; visual environment; biotic resources; historical, archaeological, and cultural resources; socioeconomics; transportation; waste management; and human health and safety. The EIS describes in detail the potential radioactive releases from new production reactors and support facilities and assesses the potential doses to workers and the general public. This volume contains 15 appendices.

  17. Technical procedures for water resources: Volume 4, Deaf Smith County site, Texas: Environmental Field Program: Final draft

    International Nuclear Information System (INIS)

    1987-08-01

    This volume contains Technical Procedures pursuant to the water Resources Site Study Plan: including Collection, Preservation, and Shipment of Ground-Water Samples; Inventory Current Water Use and Estimating Projected Water Use; Estimation of Precipitation Depth, Duration, Frequence; Estimation of Probable Maximum Precipitation; Calculation of Floodplains

  18. Technical procedures for water resources, Deaf Smith County site, Texas: Volume 1: Environmental Field Program: Final draft

    International Nuclear Information System (INIS)

    1987-08-01

    This volume contains Technical Procedures pursuant to the Water Resources Site Study Plan including, determination of basin topographic characteristics, determination of channel and playa lake characteristics, operation of a stream gaging station, operation of a playa lake stage gaging system, and processing of data from a playa lake stage gaging system

  19. 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

  20. 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.)

  1. Baseline risk assessment of groundwater contamination at the uranium mill tailings site near Shiprock, New Mexico. Draft

    Energy Technology Data Exchange (ETDEWEB)

    1993-09-01

    This report evaluates potential impact to public health or the environment resulting from groundwater contamination at the former uranium mill processing site. The tailings and other contaminated material at this site were placed in a disposal cell on the site in 1986 by the US Department of Energy`s (DOE) Uranium Mill Tailings Remedial Action (UMTRA) Project. Currently, the UMTRA Project is evaluating groundwater contamination. This risk assessment is the first document specific to this site for the Groundwater Project. This risk assessment follows the approach outlined by the US Environmental Protection Agency (EPA). The first step is to evaluate groundwater data collected from monitor wells at the site. Evaluation of these data showed that the main contaminants in the floodplain groundwater are arsenic, magnesium, manganese, nitrate, sodium, sulfate, and uranium. The complete list of contaminants associated with the terrace groundwater could not be determined due to the lack of the background groundwater quality data. However, uranium, nitrate, and sulfate are evaluated since these chemicals are clearly associated with uranium processing and are highly elevated compared to regional waters. It also could not be determined if the groundwater occurring in the terrace is a usable water resource, since it appears to have originated largely from past milling operations. The next step in the risk assessment is to estimate how much of these contaminants people would be exposed to if a drinking well were installed in the contaminated groundwater or if there were exposure to surface expressions of contaminated water. Potential exposures to surface water include incidental contact with contaminated water or sediments by children playing on the floodplain and consumption of meat and milk from domestic animals grazed and watered on the floodplain.

  2. Draft Reformulation. Phase I. General Design Memorandum and Draft Environmental Impact Statement: Geneva-on-the-Lake, Ohio Small Boat Harbor. Revision.

    Science.gov (United States)

    1981-04-01

    Wisconsin qiaLrier openecd up a new envirox.,zint after 12,000 L.C. These Paleo- Irndian-s folloo-x3 ndigrating herasD intO Ir’niarla, Ohio aYA contin-ue-d...the f irst dirczt contact. This second stage is usually represente Lt qreaoLr ratios of Euroiu an goods at Ir~dian sites and is docuner:ted i, diaries

  3. Technical procedures for utilities and solid waste: Environmental Field Program, Deaf Smith County site, Texas: Final draft

    International Nuclear Information System (INIS)

    1987-08-01

    The evaluation of environmental issues and concerns and the addressing of statutory requirements are fundamental parts in the characterization of the site in Deaf Smith County, Texas for the US Department of Energy's Salt Repository Project (SRP). To ensure that the environmental field program comprehensively addresses the issues and requirements of the project, a site study plan (SSP) has been prepared for Utilities and Solid Waste considerations. This technical procedure (TP) has been developed to implement the field program described in the Utilities and Solid Waste Site Study Plan. The purpose and scope of the Utilities and Solid Waste Technical Procedure is to develop and implement a data collection procedure to fulfill the data base needs of the Utilities and Solid Waste SSP. The procedure describes a method of obtaining, assessing and verifying the capabilities of the regional service utilities and disposal contractors. This data base can be used to identify a preferred service source for the engineering contractor. The technical procedure was produced under the guidelines established in Technical Administrative Procedure No. 1.0, Preparation, Review and Approval of Technical Procedures

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

    International Nuclear Information System (INIS)

    1987-08-01

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

  5. 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

  6. 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...

  7. 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

  8. Site study plan for Upper Aquifer Hydrology Clusters, Deaf Smith County Site, Texas: Surface-based geotechnical field program: Preliminary draft

    International Nuclear Information System (INIS)

    1988-01-01

    As part of site characterization studies, at the Deaf Smith County site, Texas, 15 wells at 5 locations will be completed in the Ogallala Formation and Dockum Group. The purposes of the wells, which are called Upper Aquifer (2) establish background hydrologic and water quality conditions, (3) provide analysis, (4) monitor responses of the shallow hydrologic system to site activities and nearby pumpage for irrigation, (5) collect water samples from both saturated and unsaturated materials to help define recharge rates and ground-water flow patterns, (6) monitor variations on water quality, and (7) define ground-water resources near the site. The test wells will be installed during a 14-month period starting about 1-1/2 years after site characterization activities begin. 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 Salt Repository Project procedures. A quality assurance program will assure that activities affecting quality are performed correctly and that the appropriate documentation is maintained. 44 refs., 19 figs., 5 tabs

  9. Federal environmental standards of potential importance to operations and activities at US Department of Energy sites. Draft

    Energy Technology Data Exchange (ETDEWEB)

    Fowler, K.M.; Bilyard, G.R.; Davidson, S.A.; Jonas, R.J.; Joseph, J.

    1993-06-01

    The US Department of Energy (DOE) is now engaged in a program of environmental restoration nationwide across its 45 sites. It is also bringing its facilities into compliance with environmental regulations, decontaminating and decommissioning unwanted facilities, and constructing new waste management facilities. One of the most difficult questions that DOE must face in successfully remediating its inactive waste sites, decontaminating and decommissioning its inactive facilities, and operating its waste management facilities is: ``What criteria and standards should be met?`` Acceptable standards or procedures for determining standards will assist DOE in its conduct of ongoing waste management and pending cleanup activities by helping to ensure that those activities are conducted in compliance with applicable laws and regulations and are accepted by the regulatory community and the public. This document reports on the second of three baseline activities that are being conducted as prerequisites to either the development of quantitative standards that could be used by DOE, or consistent procedures for developing such standards. The first and third baseline activities are also briefly discussed in conjunction with the second of the three activities.

  10. 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

  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. 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

  13. 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

  14. 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

  15. 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

  16. 75 FR 6697 - Endangered and Threatened Wildlife and Plants; Draft Yuma Clapper Rail (Rallus longirostris...

    Science.gov (United States)

    2010-02-10

    ... 236; by e-mail at [email protected] ; or on our Web site at www.fws.gov/southwest/es/arizona... designated. The primary threats to the Yuma clapper rail are habitat loss and degradation due to changes in... included in the draft revised recovery plan and include population and habitat monitoring and evaluation...

  17. PART I: Bioventing Pilot Test Work Plan for Fire Protection Training Area Site FY-03, Charleston AFB, South Carolina. PART II: Draft Interim Pilot Test Results Report for Fire Protection Training Area Site FT-03, Charleston AFB, South Carolina

    National Research Council Canada - National Science Library

    1993-01-01

    This site-specific work plan presents the scope of a bioventing pilot test for in situ treatment of fuel contaminated soils at the Fire Protection Training Area designated as Site FT-O3, Charleston Air Force Base (AFB), South Carolina...

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

    International Nuclear Information System (INIS)

    1996-01-01

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

  19. 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

  20. 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

  1. 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.

  2. Remedial action plan for the inactive Uranium Processing Site at Naturita, Colorado. Remedial action plan: Attachment 2, Geology report, Attachment 3, Ground water hydrology report: Working draft

    International Nuclear Information System (INIS)

    1994-09-01

    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). This RAP 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 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

  3. 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

  4. Draft Environmental Impact Statement for the Nevada Test Site and off-site locations in the State of Nevada. Volume 1, Part B

    International Nuclear Information System (INIS)

    1996-01-01

    This EIS identifies the impacts of past, current, and potential programs of the DOE/NV. Potential programs are included in one or more of the four alternatives and fall into three basic levels: (1) current activities, (2) planned projects, and (3) proposed projects. Current activities are those that are presently part of the normal operations of the NTS, the Tonopah test Range, portions of the NAFR Complex, and other areas considered in this EIS, such as the Area 5 Radioactive Waste management Site. Planned projects are those that are within the 5-year planning cycle and are likely to be implemented, such as the Solar Enterprise Zone. Proposed projects are outside the 5-year planning window, but have undergone sufficient conceptual development to allow a reasonable assessment. The most reliable data are clearly derived from ongoing activities. Planned projects would present somewhat less reliable data. Data for proposed projects would be the least reliable, but were determined to be essential to a full and open evaluation and disclosure of the potential effects of the alternatives. To provide an adequate analysis, conservative assumptions and parameter values were used to evaluate potential impacts of the less-defined activities. Implementation of any of the alternatives could result in a permanent commitment of resources such as groundwater, soil, biota, minerals, surface area, and subsurface geology and would represent an irreversible and irretrievable commitment of such resources. In addition to the National Environmental Policy Act requirement to identify the irreversible and irretrievable commitments of resources, it is also the intent of the DOE to identify these same resources within the meaning of the Comprehensive Environmental Response, Compensation, and Liability Act

  5. 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

  6. 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.

  7. State of Nevada comments on the US Department of Energy draft environmental assessment for the proposed high-level nuclear waste site at Yucca Mountain

    International Nuclear Information System (INIS)

    1985-03-01

    In order to assure development of a comprehensive and coordinated State response to the Nevada draft EA, the State Nuclear Waste Project Office (NWPO) performed an extensive review of the draft document and its supporting references. Comments were also solicited from other State agencies and from local governments in southern Nevada. The results of this overall State effort are contained in subsequent sections of this document. Because the draft EA and the decision process of which it is a part are of major importance to the state as a whole as well as to individual local communities (especially those in southern Nevada), we have attempted to organize the State response in such a way as to clearly reflect areas of commonality without abridging the need for a clear delineation of issues of specific concern to local governments and individual State agencies. Part I of our response document focuses on those issues and topics that are considered to be of major concern. These comments are relatively general in nature and are organized according to subject area--not according to chapter or location in the draft EA. As such, this section represents something of an overview of our response to the document

  8. 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

  9. Lawrence Livermore National Laboratory Decontamination and Waste Treatment Facility: Documentation of impact analysis for design alternatives presented in the Draft Environmental Impact Statement

    International Nuclear Information System (INIS)

    1988-05-01

    Lawrence Livermore National Laboratory (LLNL) is proposing to construct and operate a new Decontamination and Waste Treatment Facility (DWTF). The proposed DWTF would replace the existing Hazardous Waste Management (HWM) facilities at LLNL. The US Department of Energy (DOE) is preparing a Draft Environmental Impact Statement (DEIS) to assess the environmental consequences of the proposed DWTF and its alternatives. This report presents the assumptions, methodologies, and analyses used to estimate the waste flows, air emissions, ambient air quality impacts, and public health risks that are presented in the DEIS. Two DWTF design alternatives (Level I and Level II) have been designated as reasonable design alternatives considering available technologies, environmental regulations, and current and future LLNL waste generation. Both design alternatives would include new, separate radioactive and nonradioactive liquid waste treatment systems, a solidification unit, a new decontamination facility, storage and treatment facilities for reactive materials, a radioactive waste storage area, receiving and classification areas, and a uranium burn pan. The Level I design alternative would include a controlled-air incinerator system, while the Level II design alternative would include a rotary kiln incinerator system. 43 refs., 4 figs., 24 tabs

  10. 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

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

    Science.gov (United States)

    Sanford - Lee County Schools, NC.

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

  12. 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

  13. 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

  14. 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.

  15. Design basis flood for nuclear power plants on river sites

    International Nuclear Information System (INIS)

    1983-01-01

    The Guide presents techniques for determining the design basis flood (DBF) to be used for siting nuclear power plants at or near non-tidal reaches of rivers and for protecting nuclear power plants against floods. Since flooding of a nuclear power plant can have repercussions on safety, the DBF is always chosen to have a very low probability of exceedance per annum. The DBF may result from one or more of the following causes: (1) Precipitation, snowmelt; (2) Failure of water control structures, either from seismic or hydrological causes or from faulty operation of these structures; (3) Channel obstruction such as landslide, ice effects, log or debris jams, and effects of vulcanism. Normally the DBF is not less than any recorded or historical flood occurrence. For flood evaluation two types of methods are discussed in this Guide: probabilistic and deterministic. Simple probabilistic methods to determine floods of such low exceedance probability have a great degree of uncertainty and are presented for use only during the site survey. However, the more sophisticated probabilistic methods, the so-called stochastic methods, may give an acceptable result, as outlined in this Guide. The preferred method of evaluating the component of the DBF due to precipitation, as described in this Guide, is the deterministic one, based on the concept of a limit to the probable maximum precipitation (PMP) and on the unit hydrograph technique. Dam failures may generate a flood substantially more severe than that due to precipitation. The methodology for evaluating these types of floods is therefore presented in this Guide. Making allowance for the possible simultaneous occurrence of two or more important flood-producing events is also discussed here. The Guide does not deal with floods caused by sabotage

  16. Basic Drafting. Revised.

    Science.gov (United States)

    Schertz, Karen

    This introductory module on drafting includes the technical content and tasks necessary for a student to be employed in an entry-level drafting occupation. The module contains 18 instructional units that cover the following topics: introduction to drafting; tools and equipment; supplies and materials; sketching; scales; drawing format; lettering;…

  17. General Drafting. Technical Manual.

    Science.gov (United States)

    Department of the Army, Washington, DC.

    The manual provides instructional guidance and reference material in the principles and procedures of general drafting and constitutes the primary study text for personnel in drafting as a military occupational specialty. Included is information on drafting equipment and its use; line weights, conventions and formats; lettering; engineering charts…

  18. 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

  19. Comparison of Conventional and Computer-aided Drafting Methods from the View of Time and Drafting Quality

    OpenAIRE

    OZKAN, Aysen; YILDIRIM, Kemal

    2016-01-01

    Problem Statement: Drafting course is essential for students in the design disciplines for becoming more organized and for complying with standards in the educational system. Drafting knowledge is crucial, both for comprehension of the issues and for the implementation phase. In any design project, drafting performance and success are as important as the design process, especially in the educational environments aimed at professional life. However, there have been relatively any studies under...

  20. 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

  1. 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...

  2. Long-term management of the existing radioactive wastes and residues at the Niagara Falls Storage Site. Draft Environmental Impact Statement

    International Nuclear Information System (INIS)

    1984-08-01

    The statement assesses and compares several alternatives for long-term management of the existing radioactive wastes and residues at the Niagara Falls Storage Site (NFSS), Lewiston, New York. The alternatives include: (1) no action (continued interim storage at NFSS within a diked and capped containment area), (2) long-term management at NFSS (improved containment, with or without modified form of the residues), (3) long-term management at other DOE sites (Hanford, Washington, or Oak Ridge, Tennessee), and (4) offsite management of the residues at Hanford or Oak Ridge and either leaving the wastes at NFSS or removing them for disposal in the ocean. In addition to alternatives analyzed in depth, several options are also considered, including: other modifications of residue form, modification of the basic conceptual designs, other containment design options, transportation routes, and transportation modes. The radiological health effects (primarily increased risk of cancer) associated with long-term management of the wastes and residues are expected to be smaller than the nonradiological risks of occupational and transportation-related injuries and deaths. During the action period, the risk is highest for workers if all wastes and residues are moved to Hanford. The risk is highest for the general public if the residues are moved to Hanford and the wastes are moved to the ocean. Dispersal of the slightly contaminated wastes in the ocean is not expected to result in any significant impacts on the ocean environment or pose any significant radiological risk to humans. For all alternatives, if controls ceased, there would be eventual dispersion of the radioactive materials to the environment. If it is assumed that all controls cease, predicted time for loss of covers over the buried materials ranges from several hundred years to more than two million years, depending on the use of the land surface

  3. 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

  4. Functional Complexity and Web Site Design : Evaluating the Online Presence of UNESCO World Heritage Sites

    NARCIS (Netherlands)

    De Jong, Menno D.T.; Wu, Yuguang

    2018-01-01

    Functional complexity is a widespread and underresearched phenomenon in Web sites. This article explores a specific case of functional complexity by analyzing the content of UNESCO World Heritage Web sites, which have to meet demands from both World Heritage and tourism perspectives. Based on a

  5. 77 FR 9946 - Draft Guidance for Industry on Drug Interaction Studies-Study Design, Data Analysis, Implications...

    Science.gov (United States)

    2012-02-21

    ... industry entitled ``Drug Interaction Studies--Study Design, Data Analysis, Implications for Dosing, and... data analysis in the context of identifying potential drug interactions. The guidance also addresses... Studies--Study Design, Data Analysis, and Implications for Dosing and Labeling.'' Comments were received...

  6. 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

  7. 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)

  8. Methodology for the elaboration of Natura 2000 sites designation acts in the Walloon Region (Belgium: calcareous grasslands in the Lesse-and-Lomme area

    Directory of Open Access Journals (Sweden)

    Mahy G.

    2005-01-01

    Full Text Available In the Walloon Region (Belgium, 239 sites have been selected to be included in the Natura 2000 network. The next step is to write designation acts in order to legally protect these 221,000 ha. In this pilot study, a designation act was elaborated for a Natura 2000 site of 2,569 ha and located in the Lesse-and-Lomme area within the Calestienne region. Although the site includes 40 ha of calcareous grasslands, characterised by an exceptional flora and fauna, this habitat is very threatened by abandonment and fragmentation.The methodology used to elaborate the designation act is presented with respect to calcareous grassland. Firstly, in spring and summer 2003, an accurate map of natural habitats was produced, with every single patch of calcareous grassland being mapped. Information was also collected in order to evaluate conservation status. Based on this information, conservation status was then assessed with respect to three different criteria: (1 integrity of the cortege species, (2 habitat structure and (3 degradations. Thirdly, the site was divided into objective zones according to the different habitats and species of Community interest found in the site. Hence, an objective zone was delineated for calcareous grasslands. This objective zone was then divided in several management units. Finally, at these different spatial levels (site, objective zone, management unit, management measures were suggested. As a result, in the draft designation act, the target is to maintain or restore 230 ha of calcareous grassland, instead of the existing 40 ha. This ambitious target requires large-scale restoration and an efficient grazing scheme. These will need important resources for their successful implementation

  9. 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

  10. Site-specific design of the super collider in Texas

    International Nuclear Information System (INIS)

    Laughton, C.; Nelson, P.P.; Lundin, T.K.

    1990-01-01

    This paper outlines the scope of the Superconducting Super Collider (SSC) in Texas, underground works and present the current accelerator layout. After a brief overview of the site geotechnical characteristics, emphasis will be placed upon the possibilities for the incorporation of mechanical excavation technology into the construction of the various underground structures

  11. Geochemical investigation of UMTRAP designated site at Canonsburg, Pennsylvania

    International Nuclear Information System (INIS)

    Markos, G.; Bush, K.J.; Freeman, T.

    1981-05-01

    UMTRAP is an acronym for Uranium Mill Tailings Remedial Action Project. The Canonsburg, Pennsylvania site was utilized from 1911 to 1922 and from 1930 to 1942, first to remove radium from sedimentary uranium ore, and later to remove uranium from ore as well as process various materials, ceasing operations in 1957. Of the three areas, Area A is the former mill site and is occupied in part by present industrial activities. Area B is comprised of mill residues mixed with sediment dredged from Chartiers Creek, a disturbed terrace along Chartiers Creek, and a ditch on the north side. The ditch contains water with the highest concentrations of contaminants measured in the Canonsburg site. It is believed that unprocessed ore is deposited here and effluent from leaks in a sewer line across the north edge of Areas A and B carry contaminants from heavily contaminated drains in the buildings of Area A. Area C contains the former liquid disposal lagoon, and the central part of the area is highly contaminated to a depth of about 3 meters. Area C contains the most concentrated waste material with maximum levels (except for the ditch on the north side of Area B) of all the contaminants distributed throughout the area. Contamination outside the site is limited. The presence of contaminants in the ditches, in the soils on the river bank, and below the tailings pile is not attributed to migration processes, but rather to the presence of ore materials and concentrated wastes mechanically dispersed throughout the area

  12. Basic repository environmental assessment design basis: Deaf Smith County site

    International Nuclear Information System (INIS)

    1988-03-01

    This study examines the engineering factors and costs associated with the construction, operation, and decommissioning of a high-level nuclear waste repository in salt in the Palo Duro Basin in Deaf Smith County, Texas. The study assumes a repository capacity of 36,000 metric tons of heavy metal (MTHM) of unreprocessed spent fuel and 36,000 MTHM of commercial high-level reprocessing waste, along with 7,020 canisters of defense high-level reprocessing waste and associated quantities or remote- and contact-handled transuranic waste (TRU). With the exception of TRU, all the waste forms are placed in 300- to 1000-year-life carbon-steel waste packages in a collocated waste handling and packaging facility (WHPF), which is also described. The construction, operation, and decommissioning of the proposed repository is estimated to cost approximately $4.64 billion. Costs include those for the collocate WHPF, engineering, and contingency, but exclude waste form assembly and shipment to the site and waste package fabrication and shipment to the site. These costs reflect the relative average wage rates of the region, the relatively easy access to the site, and the relatively weak nature of the salt at this site. Construction would require an estimated 7 to 7.5 years. Engineering factors and costs are not strongly influenced by environmental considerations. 62 refs., 24 figs., 20 tabs

  13. Site-specific design of the super collider in Texas

    International Nuclear Information System (INIS)

    Laughton, C.; Nelson, P.P.; Lundin, T.K.

    1990-06-01

    This paper will outline the scope of the Superconducting Super Collider (SSC), underground works and present the current accelerator layout. After a brief overview of the site geotechnical characteristics, emphasis will be placed upon the possibilities for the incorporation of mechanical excavation technology into the construction of the various underground structures. 5 figs

  14. 77 FR 46986 - Revisions to Electric Quarterly Report Filing Process; Availability of Draft XML Schema

    Science.gov (United States)

    2012-08-07

    ... Supplementary Information Section below for details. DATES: The draft XML Schema is now available at the links...] Revisions to Electric Quarterly Report Filing Process; Availability of Draft XML Schema AGENCY: Federal... Regulatory Commission is making available on its Web site ( http://www.ferc.gov ) a draft of the XML schema...

  15. 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.

  16. 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

  17. Geochemical investigation of UMTRAP designated site at Grand Junction, 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 Grand Junction, Colorado. 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 should 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 sampling of waters in two seasons and solid material from the background, the area adjacent to the site, and the site. The solid samples were water extracted to remove easily soluble salts and acid extracted to remove carbonates 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. Four major conclusions are: (1) trace element concentrations in shallow subsurface waters adjacent to the tailings temporally vary up to an order of magnitude; (2) the riverbank soils and borehole waters are contaminated with uranium, radium, and trace elements from discharge of tailings solids and solutions during the active time of the mill; however, the movement of contaminants toward the Colorado River does not appear to be significant; (3) the Colorado River adjacent to the tailings is not contaminated; and (4) trace metals have accumulated at both the tailings/cover and tailings/soil interface because of precipitation reactions caused by chemical differences between the two materials

  18. Monitoring well design and sampling techniques at NAPL sites

    International Nuclear Information System (INIS)

    Collins, M.; Rohrman, W.R.; Drake, K.D.

    1992-01-01

    The existence of Non-Aqueous Phase Liquids (NAPLs) at many Superfund and RCRA hazardous waste sites has become a recognized problem in recent years. The large number of sites exhibiting this problem results from the fact that many of the most frequently used industrial solvents and petroleum products can exist as NAPLs. Hazardous waste constituents occurring as NAPLs possess a common characteristic that causes great concern during groundwater contamination evaluation: while solubility in water is generally very low, it is sufficient to cause groundwater to exceed Maximum Contamination Levels (MCLs). Thus, even a small quantity of NAPL within a groundwater regime can act as a point source with the ability to contaminate vast quantities of groundwater over time. This property makes it imperative that groundwater investigations focus heavily on characterizing the nature, extent, and migration pathways of NAPLs at sites where it exists. Two types of NAPLs may exist in a groundwater system. Water-immiscible liquid constituents having a specific gravity greater than one are termed Dense Non-Aqueous Phase Liquids, while those with a specific gravity less than one are considered Light Non-Aqueous Phase Liquids. For a groundwater investigation to properly characterize the two types of NAPLs, careful consideration must be given to the placement and sampling of groundwater monitoring wells. Unfortunately, technical reviewers at EPA Region VII and the Corps of Engineers find that many groundwater investigations fall short in characterizing NAPLs because several basic considerations were overlooked. Included among these are monitoring well location and screen placement with respect to the water table and significant confining units, and the ability of the well sampling method to obtain samples of NAPL. Depending on the specific gravity of the NAPL that occurs at a site, various considerations can substantially enhance adequate characterization of NAPL contaminants

  19. Basic repository environment assessment design basis, Cypress Creek Dome Site

    International Nuclear Information System (INIS)

    1988-03-01

    This study examines the engineering factors and costs associated with the construction, operation, and decommissioning of a high-level nuclear waste repository in salt in the Gulf Interior Region at Cypress Creek Cone, Mississippi. The study assumes a repository capacity of 36,000 metric tons of heavy metal (MTHM) of unreprocessed spent fuel and 36,000 MTHM of commercial high-level reprocessing waste, along with 7020 canisters of defense high-level reprocessing waste and associated quantities of remote- and contact-handled transuranic waste (TRU). With the exception of TRU, all the waste forms are placed in 300- to 1000-year-life carbon-steel waste packages in a collocated waste handling and packaging facility (WHPF), which is also described. The construction, operation, and decommissioning of the proposed repository is estimated to cost approximately $4.66 billion. Costs include those for the collocated WHPF, engineering, and contingency, but exclude waste from assembly and shipment to the site and waste package fabrication and shipment to the site. These costs reflect the relatively easy access to the site. Construction would require an estimated 7 years. Engineering factors and costs are not strongly influenced by environmental considerations. 53 refs., 24 figs., 10 tabs

  20. Basic repository environmental assessment design basis, Richton Dome site

    International Nuclear Information System (INIS)

    1988-01-01

    This study examines the engineering factors and costs associated with the construction, operation, and decommissioning of a high-level nuclear waste repository in salt in the Gulf Interior Region at Richton Dome in Perry County, Mississippi. The study assumes a repository capacity of 36,000 metric tons of heavy metal (MTHM) of unreprocessed spent fuel and 36,000 MTHM of commercial high-level reprocessing waste, along with 7,020 canisters of defense high-level reprocessing waste and associated quantities of remote-and contact-handled transuranic waste (TRU). With the exception of TRU, all the waste forms are placed in 300- to 1,000-year-life carbon-steel waste packages in a collocated waste handling and packaging facility (WHPF), which is also described. The construction, operation, and decommissioning of the proposed repository is estimated to cost approximately $4.49 billion. Costs include those for the WHPF, engineering, and contingency, but exclude waste form assembly and shipment to the site and waste package fabrication and shipment to the site. These costs reflect the relative average wage rates of the region and the relatively easy access to the site. Construction would require an estimated 6.25 years. Engineering factors and costs are not strongly influenced by environmental considerations. 52 refs., 24 figs., 20 tabs

  1. Basic repository environmental assessment design basis, Davis Canyon site

    International Nuclear Information System (INIS)

    1984-01-01

    This study examines the engineering factors and costs associated with the construction, operation, and decommissioning of a high-level nuclear waste repository in salt in the Paradox Basin in Davis Canyon, Utah. The study assumes a repository capacity of 36,000 metric tons of heavy metal (MTHM) of unreprocessed spent fuel and 36,000 MTHM of commercial high-level reprocessing waste, along with 7,020 canisters of defense high-level reprocessing waste and associated quantities of remote- and contact-handled transuranic waste (TRU). With the exception of TRU, all the waste forms are placed in 300- to 1,000-year-life carbon-steel waste packages in a collected waste handling and packaging facility (WHPF), which is also described. The construction, operation, and decommissioning of the proposed repository is estimated to cost approximately $5.49 billion. Costs include those for the collocated WHPF, engineering, and contingency, but exclude waste form assembly and shipment to the site and waste package fabrication and shipment to the site. These costs reflect the relative average wage rates of the region and the relatively sound nature of the salt at this site. Construction would require an estimated 7.75 years. Engineering factors and costs are not strongly influenced by environmental considerations. 50 refs., 24 figs., 20 tabs

  2. Basic repository environmental assessment design basis, Lavender Canyon site

    International Nuclear Information System (INIS)

    1988-01-01

    This study examines the engineering factors and costs associated with the construction, operation, and decommissioning of a high-level nuclear waste repository in salt in the Paradox Basin in Lavender Canyon, Utah. The study assumes a repository capacity of 36,000 metric tons of heavy metal (MTHM) of unreprocessed spent fuel and 36,000 MTHM of commercial high-level reprocessing waste, along with 7020 canisters of defense high-level reprocessing waste and associated quantities of remote- and contact-handled transuranic waste (TRU). With the exception of TRU, all the waste forms are placed in 300- to 1000-year-life carbon-steel waste packages in a collocated waste handling and packaging facility (WHPF), which is also described. The construction, operation, and decommissioning of the proposed repository is estimated to cost approximately $5.51 billion. Costs include those for the collocated WHPP, engineering, and contingency, but exclude waste form assembly and shipment to the site and waste package fabrication and shipment to the site. These costs reflect the relative average wage rates of the region and the relatively sound nature of the salt at this site. Construction would require an estimated 7.75 years. Engineering factors and costs are not strongly influenced by environmental considerations. 51 refs., 24 figs., 20 tabs

  3. Roadmap for Integrating Sustainable Design into Site-Level Operations

    Energy Technology Data Exchange (ETDEWEB)

    Peterson, Keith L.; Dorsey, Judy A.

    2000-04-19

    Sustainable Design recognizes that products and processes are interdependent with the environmental, economic, and social systems surrounding them and implements measures to prevent an unsustainable compromise to these systems.

  4. Savannah River Site reactor hardware design modification study

    International Nuclear Information System (INIS)

    Fisher, J.E.

    1990-03-01

    A study was undertaken to assess the merits of proposed design modifications to the 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. For the elevated piping design, system recovery was predicted for breaks in the plenum inlet or pump suction piping; response to the pump discharge break location did not show improvement compared to the present system configuration. The rotovalve closure design improved system response to plenum inlet or pump discharge breaks; recovery was not predicted for pump suction breaks. The pump suction valve closure design demonstrated system recovery for all break locations downstream of the valve. A combination of features is recommended to ensure liquid inventory recovery for all break locations. The elevated piping design performance during pump discharge breaks would be improved with addition of a dc pump trip in the affected loop. 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. 12 refs., 10 figs., 2 tabs

  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. Draft Environmental Impact Statement for the Nevada Test Site and off-site locations in the State of Nevada. Volume 1, Appendix G: American Indian comments for the Nevada Test Site Environmental Impact Statement

    International Nuclear Information System (INIS)

    1996-01-01

    The purpose of this report is to provide a record of activities of the American Indian Writers Subgroup (AIWS) so they can communicate better with the tribes and Indian organizations they represent. This is a living document, which may be modified as long as the AIWS is working on the Nevada Test Site Environmental Impact Statement (NTS EIS). This document has been submitted to the Consolidated Group of Tribes and Organizations for review and comment. The Consolidated Group of Tribes and Organizations comments will be incorporated into the final version which will be sent to all Indian tribes and organizations represented by the Consolidated Group of Tribes and Organizations. This document is composed of the following sections: Section G.1 -- AIWS and Meeting Summaries; Section G.2 -- Writing Tasks; Section G.3 -- American Indian Comments for the NTS EIS; and Section G.4 -- References

  7. 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)

  8. 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.)

  9. 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...

  10. 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] ...

  11. 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.

  12. 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

  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. Review: Design parameters of rating scales for Web sites

    NARCIS (Netherlands)

    van den Broek, Egon

    2007-01-01

    With the increasing popularity of the Internet, more and more online questionnaires are being conducted. However, little research is being done on their construction, in particular on their design. The authors of this paper have conducted such a study, within the scope of rating scales for Web

  15. 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.)

  16. 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.

  17. Design basis flood for nuclear power plants on coastal sites

    International Nuclear Information System (INIS)

    1983-01-01

    This Guide discusses the phenomena causing coastal floods (storm surge, seiche, tsunami and wind-wave) and gives a general description of the methods used and the critical factors involved in the evaluation of such floods and of their associated effects. In addition, some treatment is presented of the possible combinations of two or more of these phenomena to produce a DBF. Methods are also provided for evaluating the reference water levels, taking into account the effect of tides, sea level anomalies and changes in lake level and river flow. Sites vulnerable to coastal flooding are located on open coastal regions, semi-enclosed bodies of water and enclosed bodies of water. Open coastal regions are those portions of land directly exposed to and having a shore on a major body of water. Semi-enclosed bodies of water are lagoons, river estuaries, gulfs, fjords and rias. Enclosed bodies of water are lakes and reservoirs. The phenomena of the lowering of the water level at coastal sites caused by offshore winds, low tides, wave effects or of drawdown caused by tsunamis are discussed. The static and dynamic effects of floods resulting from the various combinations (independent and interdependent) of surface waves of varying frequency are also discussed. Consideration is also given to shoreline instabilities and to the effects of erosion. Estimated flood levels and related effects on the nuclear power plant, which will vary according to the method of analysis and the type of flooding considered, shall be compared with available historical data where this is relevant, to check the conservativeness of the evaluated results

  18. 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

  19. Comparative simulation of wind park design and siting in Algeria

    International Nuclear Information System (INIS)

    Youcef Ettoumi, Fatiha; Adane, Abd El Hamid; Benzaoui, Mohamed Lassaad; Bouzergui, Nabila

    2008-01-01

    In this paper, five typical regions of Algeria where wind is strong enough are selected. These regions usually intended for traditional agriculture are, centred around the towns of Guelma, El Oued, Tindouf, Touggourt and Tamanrasset. To make wind energy conversion available as an alternative energy source for the populations living in such countries, nine types of small and medium wind turbines constructed by American and European manufacturers are studied for their suitability. To account for the wind variations with height, four possible heights of the pylon holding the turbines are considered: 10, 20, 40 and 60 m. In each of the five locations and at each pylon height, wind energy converted by the turbines, is cumulated over the year and computed. Depending on the site and their size, most of these turbines are found to produce about 1000-10,000 MWh of electricity per year at 60 m of altitude and can easily satisfy the electricity need in irrigation and its household applications in rustic and arid regions. A quick glance of the results of the above computation shows that the choice of pylons of 20 m height yields a trade-off between the production of electrical energy and the requirements of economy. Owing to the sporadic wind variations, wind energy conversion systems can only be used as an auxiliary source. In particular, these systems can advantageously be coupled to stand-alone photovoltaic conversion systems in remote locations or connected to the electric mains in urban zones. (author)

  20. Remedial actions at the former Climax Uranium Company Uranium Mill Site, Grand Junction, Mesa County, Colorado. Volume 1. Text. Draft environmental impact statement

    International Nuclear Information System (INIS)

    1986-03-01

    This statement evaluates and compares the environmental impacts associated with the remedial actions of the residual radioactive materials remaining at the inactive uranium processing site and associated vicinity properties at Grand Junction, Mesa County, Colorado. The site is a 114-acre tract of private and state owned land which contains approximately 3.1 million cubic yards of tailings and associated contaminated soils. The vicinity properties are homes, businesses, public buildings, and vacant lots which may have been contaminated during construction by the use of tailings as building material. An estimated 3465 vicinity properties would be cleaned up during remedial action of the tailings pile. This statement evaluates six alternatives for stabilization and disposal of the tailings and other contaminated materials: no action; stabilization at the Grand Junction site; disposal at the Cheney Reservoir site with truck transport; disposal at the Cheney Reservoir site with train and truck transport; disposal at the Two Road site with truck transport; disposal at the Two Road site with train and truck transport. All of the alternatives except include remedial action at an estimated 3465 vicinity properties. Alternative 3 is DOE's preferred alternative. 29 figs., 25 tabs

  1. Human-factors control-room-design review draft audit report: Detroit Edison Company, Enrico Fermi Atomic Power Plant--Unit 2

    International Nuclear Information System (INIS)

    Savage, J.W.

    1981-01-01

    A human factors audit of the Fermi-2 control room was conducted April 27 through May 1, 1981. This report contains the audit team findings, organized according to the draft NUREG-0700 guidelines sections. The discrepancies identified during the audit are categorized according to their severity and the required schedule for their resolution

  2. 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

  3. Business plan: Supplemental draft environmental impact statement. Volume 2. Appendices

    International Nuclear Information System (INIS)

    1995-02-01

    This document contains the appendices for the Bonneville Power Administration (BPA) Business Plan: Supplemental Draft Environmental Impact Statement. Included are: BPA products and services; Rate design; Methodology and assumptions for numerical analysis; Retail utility operations; Comments and responses to the draft business plan EIS

  4. Business Plan : Supplemental Draft Environmental Impact Statement, Volume 2, Appendices.

    Energy Technology Data Exchange (ETDEWEB)

    United States. Bonneville Power Administration.

    1995-02-01

    This document contains the appendices for the Bonneville Power Administration (BPA) Business Plan: Supplemental Draft Environmental Impact Statement. Included are: BPA products and services; Rate design; Methodology and assumptions for numerical analysis; Retail utility operations; Comments and responses to the draft business plan EIS.

  5. EPA Region 2 Draft NPL Site Contamination Area Boundaries as of February 2007 GIS Layer [EPA.R2_NPL_CONTAMBND

    Data.gov (United States)

    U.S. Environmental Protection Agency — This layer represents the contamination boundaries of all NPL sites located in EPA Region Region 2 (New York, New Jersey, Puerto Rico and the U.S. Virgin Islands)....

  6. Evaluations for draft reports on geological disposal

    International Nuclear Information System (INIS)

    Maekawa, Keisuke; Igarashi, Hiroshi

    2002-10-01

    This report summarizes the results of the technical evaluations on two reports which are named as 'Overview of the Geological Disposal Facility' and Considerable Factors on Selection of Potential Sites for Geological Disposal' drafted by NUMO (Nuclear Waste Management Organization of Japan). The review of each draft report has been referred to committee (held on 9th September, 2002) and working group (held on 1st October, 2002) which were organized in order to confirm a progress of implementation of geological disposal by government. (author)

  7. 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...

  8. Draft environmental impact statement for the siting, construction, and operation of New Production Reactor capacity. Volume 2, Sections 1-6

    Energy Technology Data Exchange (ETDEWEB)

    1991-04-01

    This (EIS) assesses the potential environmental impacts, both on a broad programmatic level and on a project-specific level, concerning a proposed action to provide new tritium production capacity to meet the nation`s nuclear defense requirements well into the 21st century. A capacity equivalent to that of about a 3,000-megawatt (thermal) heavy-water reactor was assumed as a reference basis for analysis in this EIS; this is the approximate capacity of the existing production reactors at DOE`s Savannah River Site. The EIS programmatic alternatives address Departmental decisions to be made on whether to build new production facilities, whether to build one or more complexes, what size production capacity to provide, and when to provide this capacity. Project-specific impacts for siting, constructing, and operating new production reactor capacity are assessed for three alternative sites: the Hanford Site near Richland, Washington; the Idaho National Engineering Laboratory near Idaho Falls, Idaho; and the Savannah River Site. For each site, the impacts of three reactor technologies (and supporting facilities) are assessed: a heavy-water reactor, a light-water reactor, and a modular high-temperature gas-cooled reactor. Impacts of the no-action alternative also are assessed. The EIS evaluates impacts related to air quality; noise levels; surface water, groundwater, and wetlands; land use; recreation; visual environment; biotic resources; historical, archaeological, and cultural resources; socioeconomics; transportation; waste management; and human health and safety. The EIS describes in detail the potential radioactive releases from new production reactors and support facilities and assesses the potential doses to workers and the general public. This volume contains the analysis of programmatic alternatives, project alternatives, affected environment of alternative sites, environmental consequences, and environmental regulations and permit requirements.

  9. 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.

  10. 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

  11. 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.

  12. 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

  13. 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

  14. Draft environmental impact statement for the siting, construction, and operation of New Production Reactor capacity. Volume 3, Sections 7-12, Appendices A-C

    Energy Technology Data Exchange (ETDEWEB)

    1991-04-01

    This Environmental Impact Statement (EIS) assesses the potential environmental impacts, both on a broad programmatic level and on a project-specific level, concerning a proposed action to provide new tritium production capacity to meet the nation`s nuclear defense requirements well into the 21st century. A capacity equivalent to that of about a 3,000-megawatt (thermal) heavy-water reactor was assumed as a reference basis for analysis in this EIS; this is the approximate capacity of the existing production reactors at DOE`s Savannah River Site near Aiken, South Carolina. The EIS programmatic alternatives address Departmental decisions to be made on whether to build new production facilities, whether to build one or more complexes, what size production capacity to provide, and when to provide this capacity. Project-specific impacts for siting, constructing, and operating new production reactor capacity are assessed for three alternative sites: the Hanford Site near Richland, Washington; the Idaho National Engineering Laboratory near Idaho Falls, Idaho; and the Savannah River Site. For each site, the impacts of three reactor technologies (and supporting facilities) are assessed: a heavy-water reactor, a light-water reactor, and a modular high-temperature gas-cooled reactor. Impacts of the no-action alternative also are assessed. The EIS evaluates impacts related to air quality; noise levels; surface water, groundwater, and wetlands; land use; recreation; visual environment; biotic resources; historical, archaeological, and cultural resources; socioeconomics; transportation; waste management; and human health and safety. The EIS describes in detail the potential radioactive releases from new production reactors and support facilities and assesses the potential doses to workers and the general public. This volume contains references; a list of preparers and recipients; acronyms, abbreviations, and units of measure; a glossary; an index and three appendices.

  15. 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

  16. 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)

  17. 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…

  18. 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...

  19. 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

  20. 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

  1. Energy infrastructure of the United States and projected siting needs: Scoping ideas, identifying issues and options. Draft report of the Department of Energy Working Group on Energy Facility Siting to the Secretary

    Energy Technology Data Exchange (ETDEWEB)

    1993-12-01

    A Department of Energy (DOE) Working Group on Energy Facility Siting, chaired by the Policy Office with membership from the major program and staff offices of the Department, reviewed data regarding energy service needs, infrastructure requirements, and constraints to siting. The Working Group found that the expeditious siting of energy facilities has important economic, energy, and environmental implications for key Administration priorities.

  2. 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.

  3. 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

  4. 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

  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 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. 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

  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. Supplement to the Surplus Plutonium Disposition Draft Environmental Impact Statement

    International Nuclear Information System (INIS)

    1999-01-01

    On May 22, 1997, DOE published a Notice of Intent in the Federal Register (62 Federal Register 28009) announcing its decision to prepare an environmental impact statement (EIS) that would tier from the analysis and decisions reached in connection with the ''Storage and Disposition of Weapons-Usable Fissile Materials Final Programmatic EIS (Storage and Disposition PEIS)''. ''The Surplus Plutonium Disposition Draft Environmental Impact Statement'' (SPD Draft EIS) (DOWEIS-0283-D) was prepared in accordance with NEPA and issued in July 1998. It identified the potential environmental impacts of reasonable alternatives for the proposed siting, construction, and operation of three facilities for plutonium disposition. These three facilities would accomplish pit disassembly and conversion, immobilization, and MOX fuel fabrication. For the alternatives that included MOX fuel fabrication, the draft also described the potential environmental impacts of using from three to eight commercial nuclear reactors to irradiate MOX fuel. The potential impacts were based on a generic reactor analysis that used actual reactor data and a range of potential site conditions. In May 1998, DCE initiated a procurement process to obtain MOX fuel fabrication and reactor irradiation services. The request for proposals defined limited activities that may be performed prior to issuance of the SPD EIS Record of Decision (ROD) including non-site-specific work associated with the development of the initial design for the MOX fuel fabrication facility, and plans (paper studies) for outreach, long lead-time procurements, regulatory management, facility quality assurance, safeguards, security, fuel qualification, and deactivation. No construction on the proposed MOX facility would begin before an SPD EIS ROD is issued. In March 1999, DOE awarded a contract to Duke Engineering and Services; COGEMA, Inc.; and Stone and Webster (known as DCS) to provide the requested services. The procurement process

  10. Supplement to the Surplus Plutonium Disposition Draft Environmental Impact Statement

    Energy Technology Data Exchange (ETDEWEB)

    N/A

    1999-05-14

    On May 22, 1997, DOE published a Notice of Intent in the Federal Register (62 Federal Register 28009) announcing its decision to prepare an environmental impact statement (EIS) that would tier from the analysis and decisions reached in connection with the ''Storage and Disposition of Weapons-Usable Fissile Materials Final Programmatic EIS (Storage and Disposition PEIS)''. ''The Surplus Plutonium Disposition Draft Environmental Impact Statement'' (SPD Draft EIS) (DOWEIS-0283-D) was prepared in accordance with NEPA and issued in July 1998. It identified the potential environmental impacts of reasonable alternatives for the proposed siting, construction, and operation of three facilities for plutonium disposition. These three facilities would accomplish pit disassembly and conversion, immobilization, and MOX fuel fabrication. For the alternatives that included MOX fuel fabrication, the draft also described the potential environmental impacts of using from three to eight commercial nuclear reactors to irradiate MOX fuel. The potential impacts were based on a generic reactor analysis that used actual reactor data and a range of potential site conditions. In May 1998, DCE initiated a procurement process to obtain MOX fuel fabrication and reactor irradiation services. The request for proposals defined limited activities that may be performed prior to issuance of the SPD EIS Record of Decision (ROD) including non-site-specific work associated with the development of the initial design for the MOX fuel fabrication facility, and plans (paper studies) for outreach, long lead-time procurements, regulatory management, facility quality assurance, safeguards, security, fuel qualification, and deactivation. No construction on the proposed MOX facility would begin before an SPD EIS ROD is issued. In March 1999, DOE awarded a contract to Duke Engineering & Services; COGEMA, Inc.; and Stone & Webster (known as DCS) to provide the requested

  11. 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.

  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. 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.

  14. 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

  15. 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)

  16. Automation of Military Civil Engineering and Site Design Functions: Software Evaluation

    Science.gov (United States)

    1989-09-01

    AutoCad , in-house application programs written in AutoCad command language, AutoLISP , and BASIC Would like to obtain: Surveying, earthwork, utilities...Experiment Station (WES) Corps library programs, no one software is being used more than another. For drafting, AutoCAD has been the most commonly...ware packages evaluated. D.C.A. Engineering Software D.C.A. software is used to enhance the AutoCAD drafting package and operates solely within the

  17. Computer Assisted Drafting (CNC) Drawings. Drafting Module 6. Instructor's Guide.

    Science.gov (United States)

    Missouri Univ., Columbia. Instructional Materials Lab.

    This Missouri Vocational Instruction Management System instructor's drafting guide has been keyed to the drafting competency profile developed by state industry and education professionals. This unit contains information on computer-assisted drafting drawings. The guide contains a cross-reference table of instructional materials and 20 worksheets.…

  18. 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

  19. 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.

  20. State of Nevada comments on the US Department of Energy draft environmental assessment for the proposed high-level nuclear waste site at Yucca Mountain

    International Nuclear Information System (INIS)

    1985-03-01

    A page by page review of the geologic and mineral-resources considerations in DOE's Yucca Mountain EA is included. This review does not cover geohydrological or earthquake/faulting considerations in any detail, as they are being reviewed in detail by others. Other, non-geologic errors of fact are also pointed out. It appears that the process of evaluation has been done backwards---possible sites have been selected for nongeologic reasons, then efforts made to make the geologic settings (for example: rock type) appear favorable. Additional, more detailed studies need to be made by organizations other than DOE or the US Geological Survey to cross-check the accuracy, completeness, and conclusions of existing studies

  1. 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)

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

    International Nuclear Information System (INIS)

    1990-02-01

    This radiologic characterization of tho two inactive uranium millsites at Rifle, Colorado, was conducted by Bendix Field Engineering Corporation (Bendix) for the US Department of Energy (DOE), Grand Junction Projects Office, in accord with a Statement of Work prepared by the DOE Uranium Mill Tailings Remedial Action (UMTRA) Project Technical Assistance Contractor, Jacobs Engineering Group, Inc. (Jacobs). The purpose of this project is to define the extent of radioactive contamination at the Rifle sites that exceeds US Environmental Protection Agency, (EPA) standards for UMTRA sites. The data presented in this report are required for characterization of the areas adjacent to the tailings piles and for the subsequent design of cleanup activities. An orientation visit to the study area was conducted on 31 July--1 August 1984, in conjunction with Jacobs, to determine the approximate extent of contaminated area surrounding tho piles. During that visit, survey control points were located and baselines were defined from which survey grids would later be established; drilling requirements were assessed; and radiologic and geochemical data were collected for use in planning the radiologic fieldwork. The information gained from this visit was used by Jacobs, with cooperation by Bendix, to determine the scope of work required for the radiologic characterization of the Rifle sites. Fieldwork at Rifle was conducted from 1 October through 16 November 1984

  3. 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

  4. 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.

  5. 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....

  6. 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.

  7. 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.

  8. Disposal of Hanford defense high-level, transuranic and tank wastes, Hanford Site, Richland, Washington. Draft environmental impact statement. Volume 3. Appendices M-V

    International Nuclear Information System (INIS)

    1986-03-01

    The purpose of this Environmental Impact Statement (EIS) is to provide environmental input into the selection and implementation of final disposal actions for high-level, transuranic and tank wastes located at the Hanford Site, Richland, Washington, and into the construction, operation and decommissioning of waste treatment facilities that may be required in implementing waste disposal alternatives. Specifically evaluated are a Hanford Waste Vitrification Plant, Transportable Grout Facility, and a Waste Receiving and Packaging Facility. Also an evaluation is presented to assist in determining whether any additional action should be taken in terms of long-term environmental protection for waste that was disposed of at Hanford prior to 1970 as low-level waste (before the transuranic waste category was established by the AEC) but which might fall into that category if generated today. The alternatives considered in this EIS are: (1) in-place stabilization and disposal, where waste is left in place but is isolated by protective and natural barriers; (2) geologic disposal, where most of the waste (to the extent practicable) is exhumed, treated, segregated, packaged and disposed of in a deep geologic repository; waste classified as high-level would be disposed of in a commercial repository developed pursuant to the Nuclear Waste Policy Act; transuranic waste would be disposed of in the Waste Isolation Pilot Plant near Carlsbad, New Mexico; (3) reference alternative, where some classes of waste are disposed of in geologic repositories and other classes of waste are disposed of by in-place stabilization and disposal; and (4) a ''no disposal'' action alternative (continued storage)

  9. Disposal of Hanford defense high-level, transuranic and tank wastes, Hanford Site, Richland, Washington. Draft environmental impact statement. Volume 2. Appendices A-L

    International Nuclear Information System (INIS)

    1986-03-01

    The purpose of this Environmental Impact Statement (EIS) is to provide environmental input into the selection and implementation of final disposal actions for high-level, transuranic and tank wastes located at the Hanford Site, Richland, Washington, and into the construction, operation and decommissioning of waste treatment facilities that may be required in implementing waste disposal alternatives. Specifically evaluated are a Hanford Waste Vitrification Plant, Transportable Grout Facility, and a Waste Receiving and Packaging Facility. Also an evaluation is presented to assist in determining whether any additional action should be taken in terms of long-term environmental protection for waste that was disposed of at Hanford prior to 1970 as low-level waste (before the transuranic waste category was established by the AEC) but which might fall into that category if generated today. The alternatives considered in this EIS are: (1) in-place stabilization and disposal, where waste is left in place but is isolated by protective and natural barriers; (2) geologic disposal, where most of the waste (to the extent practicable) is exhumed, treated, segregated, packaged and disposed of in a deep geologic repository; waste classified as high-level would be disposed of in a commercial repository developed pursuant to the Nuclear Waste Policy Act; transuranic waste would be disposed of in the Waste Isolation Pilot Plant near Carlsbad, New Mexico; (3) reference alternative, where some classes of waste are disposed of in geologic repositories and other classes of waste are disposed of by in-place stabilization and disposal; and (4) a ''no disposal'' action alternative (continued storage)

  10. Area Recommendation Report for the Crystalline Repository Project: Volume 1, Draft

    International Nuclear Information System (INIS)

    1986-01-01

    This Draft Area Recommendation Report for the Crystalline Repository Project identifies portions of crystalline rock bodies as proposed potentially acceptable sites for consideration in the second high-level radioactive waste repository program. The US Department of Energy evaluated available geologic and environmental data for 235 crystalline rock bodies in the North Central, Northeastern, and Southeastern regions to identify preliminary candidate areas. Further evaluation of these preliminary candidate areas resulted in the selection of 12 as proposed potentially acceptable sites. The 12 proposed potentially acceptable sites are located in the States of Georgia (1), Maine (2), Minnesota (3), New Hampshire (1), North Carolina (2), Virginia (2), and Wisconsin (1). The data, analyses, and rationale with which the 12 proposed potentially acceptable sites were selected are presented in this draft report. The analyses presented demonstrate that the evidence available for each proposed potentially acceptable site supports (1) a finding that the site is not disqualified in accordance with the application requirements of Appendix III of the siting guidelines and (2) a decision to proceed with the continued investigation of the site on the basis of the favorable and potentially adverse conditions identified to date. Once this report is finalized, potentially acceptable sites in crystalline rock will be formally identified by the Secretary of Energy, in accordance with the DOE siting guidelines. These potentially acceptable sites will be investigated and evaluated in more detail during the area phase of the siting process. An additional eight areas, which meet the requirements for identification as potentially acceptable sites, will retain their designation as candidate areas

  11. 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

  12. 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

  13. 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

  14. 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

  15. Design guidelines for teaching about design guidelines for educational WWW-sites

    NARCIS (Netherlands)

    Collis, Betty; Winnips, Koos; Ottmann, Thomas; Tomek, Ivan

    1998-01-01

    This paper describes how the authors use a mixture of World Wide Web (WWW)-based functionalities and new didactics to teach educational technology students at the University of Twente (Netherlands) about the design of WWW-based learning environments. Topics discussed include: (1) the content of

  16. Drafting Lab Management Guide.

    Science.gov (United States)

    Ohio State Univ., Columbus. Instructional Materials Lab.

    This manual was developed to guide drafting instructors and vocational supervisors in sequencing laboratory instruction and controlling the flow of work for a 2-year machine trades training program. The first part of the guide provides information on program management (program description, safety concerns, academic issues, implementation…

  17. 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 ...

  18. 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.

  19. 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.

  20. 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

  1. 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.

  2. 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

  3. 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)

  4. 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)

  5. 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

  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. 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…

  8. 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.

  9. Remedial action 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 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 (EPA, 1987). According to the Uranium Mill Tailings Radiation Control Act (UMTRCA) of 1978 Public Law (PL) 95-604 (PL 95-604), the US Department of Energy (DOE) is responsible for assessing the inactive uranium processing sites. The DOE has determined that for Slick Rock, this assessment shall include hydrogeologic site characterization for two separate uranium processing sites, the Union Carbide (UC) site and the North Continent (NC) site, and for the proposed Burro Canyon disposal site

  10. 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

  11. 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

  12. An exploratory shaft facility in SALT: Draft shaft study plan

    International Nuclear Information System (INIS)

    1987-03-01

    This draft Shaft Study Plan describes a program of testing and monitoring in the Exploratory Shafts of a candidate high-level nuclear waste repository site in Deaf Smith County, Texas. The purpose of the programs to assist with site characterization in support of a determination of site suitability for development as a repository design and performance assessment evaluations. The program includes a variety of geological, geophysical, geomechanical, thermomechanical, and geohydrological testing and monitoring. The program is presented as a series of separate studies concerned with geological, geomechanical, and geohydrological site characterization, and with evaluating the mechanical and hydrological response of the site to construction of the shafts. The various studies, and associated test or monitoring methods are shown. The procedure used in developing the test program has been to initially identify the information necessary to satisfy (1) federal, state, and local requirements, and (2) repository program requirements. These information requirements have then been assessed to determine which requirements can be addressed wholly or in significant part by monitoring and testing from within the shafts. Test methods have been identified to address specific information requirements. 67 refs., 39 figs., 31 tabs

  13. 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

  14. 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

  15. 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.

  16. 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

  17. 46 CFR 167.55-1 - Draft marks and draft indicating systems.

    Science.gov (United States)

    2010-10-01

    ... 46 Shipping 7 2010-10-01 2010-10-01 false Draft marks and draft indicating systems. 167.55-1... NAUTICAL SCHOOL SHIPS Special Markings Required § 167.55-1 Draft marks and draft indicating systems. (a... aft to the location of the draft marks, due to a raked stem or cut away skeg, the draft must be...

  18. 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)

  19. 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.

  20. 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

  1. 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

  2. Optimum Drafting Conditions Of Polyester And Viscose Blend Yarns

    Directory of Open Access Journals (Sweden)

    Hatamvand Mohammad

    2017-09-01

    Full Text Available In this study, we used an experimental design to investigate the influence of the total draft, break draft, distance between the aprons (Clips and production roller pressure on yarn quality in order to obtain optimum drafting conditions for polyester and viscose (PES/CV blend yarns in ring spinning frame. We used PES fibers (1.4 dtex × 38 mm long and CV fibers (1.6 dtex × 38 mm long to spin a 20 Tex blend yarn of PES (70%/CV (30% blend ratio. When the break draft, adjustment of distance between of aprons and roller pressure is not reasonable, controlling and leading of the fibers is not sufficient for proper orientation of the fibers in the yarn structure to produce a high quality yarn. Experimental results and statistical analysis show that the best yarn quality will be obtained under drafting conditions total draft of 38, 1.2 break draft, 2.8 mm distance between of aprons and maximum pressure of the production top roller (18daN.

  3. 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

  4. 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)

  5. 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

  6. India's draft nuclear doctrine

    International Nuclear Information System (INIS)

    Kapur, A.

    2000-01-01

    India's draft nuclear doctrine and its nuclear and missile testing are a response to recent international, regional and domestic developments. Nehru's policy of nuclear disarmament, non-discriminatory international arrangements and unilateral restraint has been overturned in favour of self-reliant security and negotiated nuclear restraints. The draft nuclear doctrine is aimed at transparency and formalization of existing capacities. It is anchored in the United Nations Charter, based on the legitimacy of self-defence and espouses minimum nuclear deterrence. After the launching of Pokhran II, the debate in India has been settled on weaponization and deployment. The doctrine is not country-specific with respect to threat perceptions, but the author posits that the long-term focus is on China and the short-term on Pakistan. The doctrine emphasizes civilian command and control. India's decision to test incurred diplomatic and other economic costs, but afforded new opportunities for the country to assert itself militarily and politically in Asia and in the world. There were no diplomatic costs in issuing the draft nuclear doctrine, but the author estimates the economic costs of a full-blown (triad) Indian nuclear deterrent. (author)

  7. 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.

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

    International Nuclear Information System (INIS)

    Elder, J.C.; Graf, J.M.; Dewart, J.M.; Buhl, T.E.; Wenzel, W.J.; Walker, L.J.; Stoker, A.K.

    1986-01-01

    This guide was prepared to provide the experienced safety analyst with accident analysis guidance in greater detail than is possible in Department of Energy (DOE) Orders. The guide addresses analysis of postulated serious accidents considered in the siting and selection of major design features of DOE nuclear facilities. Its scope has been limited to radiological accidents at nonreactor nuclear facilities. The analysis steps addressed in the guide lead to evaluation of radiological dose to exposed persons for comparison with siting guideline doses. Other possible consequences considered are environmental contamination, population dose, and public health effects. Choices of models and parameters leading to estimation of source terms, release fractions, reduction and removal factors, dispersion and dose factors are discussed. Although requirements for risk analysis have not been established, risk estimates are finding increased use in siting of major nuclear facilities, and are discussed in the guide. 3 figs., 9 tabs

  9. 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

  10. 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.

  11. 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

  12. 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

  13. 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.)

  14. 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)

  15. Design and operation of a low-level solid-waste disposal site at Los Alamos

    International Nuclear Information System (INIS)

    Balo, K.A.; Wilson, N.E.; Warren, J.L.

    1982-01-01

    Since the mid-1940's, approximately 185000 m 3 of low-level and transuranic radioactive solid waste, generated in operations at the Los Alamos National Laboratory, have been disposed of by on-site shallow land burial. Procedures and facilities have been designed and evaluated in the areas of waste acceptance, treatment and storage, disposal, traffic control, and support systems. The methodologies assuring the proper management and disposal of radioactive solid waste are summarized

  16. 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.

  17. Site Identification by Ligand Competitive Saturation (SILCS) Simulations for Fragment-Based Drug Design

    OpenAIRE

    Faller, Christina E.; Raman, E. Prabhu; MacKerell, Alexander D.; Guvench, Olgun

    2015-01-01

    Fragment-based drug design (FBDD) involves screening low molecular weight molecules (“fragments”) that correspond to functional groups found in larger drug-like molecules to determine their binding to target proteins or nucleic acids. Based on the principle of thermodynamic additivity, two fragments that bind non-overlapping nearby sites on the target can be combined to yield a new molecule whose binding free energy is the sum of those of the fragments. Experimental FBDD approaches, like NMR ...

  18. 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)

  19. 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

  20. 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.

  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. On random pressure pulses in the turbine draft tube

    Science.gov (United States)

    Kuibin, P. A.; Shtork, S. I.; Skripkin, S. G.; Tsoy, M. A.

    2017-04-01

    The flow in the conical part of the hydroturbine draft tube undergoes various instabilities due to deceleration and flow swirling at off-design operation points. In particular, the precessing vortex rope develops at part-load regimes in the draft tube. This rope induces periodical low-frequency pressure oscillations in the draft tube. Interaction of rotational (asynchronous) mode of disturbances with the elbow can bring to strong oscillations in the whole hydrodynamical system. Recent researches on flow structure in the discharge cone in a regime of free runner had revealed that helical-like vortex rope can be unstable itself. Some coils of helix close to each other and reconnection appears with generation of a vortex ring. The vortex ring moves toward the draft tube wall and downstream. The present research is focused on interaction of vortex ring with wall and generation of pressure pulses.

  3. 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

    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 US Department of Energy (DOE) is responsible for assessing the inactive uranium processing sites. The DOE has determined this assessment shall include information on hydrogeologic site characterization. This document contains appendices to Attachment 3, Groundwater Hydrology Report included are calculations

  4. 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

    Attachment 3 Groundwater Hydrology Report describes the hydrogeology, water quality, and water resources at the processing site and Dry Flats disposal site. The Hydrological Services calculations contained in Appendix A of Attachment 3, are presented in a separate report. Attachment 4 Water Resources Protection Strategy describes how the remedial action will be in compliance with the proposed EPA groundwater standards

  5. 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...

  6. Seismic stability evaluation using 2-D FEM analysis for modeling nuclear power plants sited on gravel soil

    International Nuclear Information System (INIS)

    Iba, T.; Konno, T.; Irino, K.; Hama, I.; Oguro, E.; Iizuka, S.; Enami, A.

    1995-01-01

    Throughout Europe and the United States, many nuclear power plants have been built on Quaternary deposit sites. While in Japan, all nuclear power plants have been built at rock sites primarily to maintain a high seismic resistivity. However, as more nuclear power plants are planned for the future, it has become necessary to develop new siting technology from the stand point of expanding the available range of site selection and effective utilization of land. A draft on guidelines of the seismic design for siting on Quaternary deposits is being carried out with a purpose to ensure proper design and construction for such sites. (author). 10 figs., 2 tabs

  7. 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)

  8. EPA scientific integrity policy draft

    Science.gov (United States)

    Showstack, Randy

    2011-08-01

    The U.S. Environmental Protection Agency (EPA) issued its draft scientific integrity policy on 5 August. The draft policy addresses scientific ethical standards, communications with the public, the use of advisory committees and peer review, and professional development. The draft policy was developed by an ad hoc group of EPA senior staff and scientists in response to a December 2010 memorandum on scientific integrity from the White House Office of Science and Technology Policy. The agency is accepting public comments on the draft through 6 September; comments should be sent to osa.staff@epa.gov. For more information, see http://www.epa.gov/stpc/pdfs/draft-scientific-integrity-policy-aug2011.pdf.

  9. 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.

  10. Final report on the radiological surveys of designated DX firing sites at Los Alamos National Laboratory

    International Nuclear Information System (INIS)

    1996-01-01

    CHEMRAD was contracted by Los Alamos National Laboratory to perform USRADS reg-sign (UltraSonic Ranging And Data System) radiation scanning surveys at designated DX Sites at the Los Alamos National Laboratory. The primary purpose of these scanning surveys was to identify the presence of Depleted Uranium (D-38) resulting from activities at the DX Firing Sites. This effort was conducted to update the most recent surveys of these areas. This current effort was initiated with site orientation on August 12, 1996. Surveys were completed in the field on September 4, 1996. This Executive Summary briefly presents the major findings of this work. The detail survey results are presented in the balance of this report and are organized by Technical Area and Site number in section 2. This organization is not in chronological order. USRADS and the related survey methods are described in section 3. Quality Control issues are addressed in section 4. Surveys were conducted with an array of radiation detectors either mounted on a backpack frame for man-carried use (Manual mode) or on a tricycle cart (RadCart mode). The array included radiation detectors for gamma and beta surface near surface contamination as well as dose rate at 1 meter above grade. The radiation detectors were interfaced directly to an USRADS 2100 Data Pack

  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. Influence of site on thermal design of a two floor ZEH in the desert

    KAUST Repository

    Serag-Eldin, M. A.

    2010-12-01

    The paper presents the results of investigating the effect of Latitude angle and environmental temperature on the thermal behavior and performance of a fully equipped, air-conditioned, zero energy house located in a desert residential compound. It makes use of the thermal design and analysis tools presented in other work and extends the investigation to include different site environmental characteristics. Data from eight different meteorological sites in the KSA where considered. It is demonstrated that for the same house and occupancy profile, the PV modules, battery storage, and air-conditioning equipment requirements can differ markedly depending on local environment properties. During Summer and Spring the main heat load is due to cooling, but during winter season the load can vary from full cooling, to mixed cooling and heating, to even full heating; the heating load sometimes dictating the size of the required equipment. © 2010 IEEE.

  13. Influence of site on thermal design of a two floor ZEH in the desert

    KAUST Repository

    Serag-Eldin, M. A.

    2010-01-01

    The paper presents the results of investigating the effect of Latitude angle and environmental temperature on the thermal behavior and performance of a fully equipped, air-conditioned, zero energy house located in a desert residential compound. It makes use of the thermal design and analysis tools presented in other work and extends the investigation to include different site environmental characteristics. Data from eight different meteorological sites in the KSA where considered. It is demonstrated that for the same house and occupancy profile, the PV modules, battery storage, and air-conditioning equipment requirements can differ markedly depending on local environment properties. During Summer and Spring the main heat load is due to cooling, but during winter season the load can vary from full cooling, to mixed cooling and heating, to even full heating; the heating load sometimes dictating the size of the required equipment. © 2010 IEEE.

  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. 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

  16. 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.

  17. 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

  18. 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.

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

    International Nuclear Information System (INIS)

    1990-02-01

    This volume contains appendices D6 through D8 containing laboratory test data: from MK-F investigation, 1987, Old Rifle and New Rifle sites; on bentonite amended radon barrier material; and from MK-F investigation, 1987, riprap tests

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

    International Nuclear Information System (INIS)

    1993-07-01

    This report presents geologic considerations that are pertinent to the Remedial Action Plan for Slick Rock mill tailings. Topics covered include regional geology, site geology, geologic stability, and geologic suitability

  1. A study of swirl flow in draft tubes

    Energy Technology Data Exchange (ETDEWEB)

    Dahlhaug, Ole Gunnar

    1997-12-31

    This thesis presents measurements performed inside conical diffuser and bend, draft tubes of model hydro turbines, and draft tube of a prototype hydro turbine. Experimental results for swirling flow in conical diffuser and bend are presented in three different geometries. The axial velocity decreases at the centre of the tube at high swirl numbers because of an axial pressure gradient set up by the downstream frictional damping of the tangential velocities and the pressure increase downstream of the diffuser. Analytical models of the tangential velocity profiles are found and the radial pressure distribution calculated. Good correlation to the measured pressure distribution was achieved. Diffuser efficiency was calculated based on the equations for velocity and pressure profiles, which gave a qualified estimate of the diffuser hydraulic performance. The calculation shows that the bend reduces the efficiency by more than 30%. For a straight tube followed by a diffuser, numerical calculations were done, using K{epsilon}, RNG and RSM turbulence models for all measured swirl numbers. The K{epsilon} model gave best results for the forced vortex profile at low swirl numbers, while the RSM model gave best results at high swirl number. The turbulent kinetic energy at high swirl numbers gave the largest difference between the calculated and the measured values. Measurements on draft tubes in model turbines show the importance of good draft tube design. Prototype measurements on a Francis turbine show how the outlet draft tube flow should be measured for prototype draft tube evaluation. 54 refs., 118 figs., 2 tabs.

  2. A study of swirl flow in draft tubes

    Energy Technology Data Exchange (ETDEWEB)

    Dahlhaug, Ole Gunnar

    1998-12-31

    This thesis presents measurements performed inside conical diffuser and bend, draft tubes of model hydro turbines, and draft tube of a prototype hydro turbine. Experimental results for swirling flow in conical diffuser and bend are presented in three different geometries. The axial velocity decreases at the centre of the tube at high swirl numbers because of an axial pressure gradient set up by the downstream frictional damping of the tangential velocities and the pressure increase downstream of the diffuser. Analytical models of the tangential velocity profiles are found and the radial pressure distribution calculated. Good correlation to the measured pressure distribution was achieved. Diffuser efficiency was calculated based on the equations for velocity and pressure profiles, which gave a qualified estimate of the diffuser hydraulic performance. The calculation shows that the bend reduces the efficiency by more than 30%. For a straight tube followed by a diffuser, numerical calculations were done, using K{epsilon}, RNG and RSM turbulence models for all measured swirl numbers. The K{epsilon} model gave best results for the forced vortex profile at low swirl numbers, while the RSM model gave best results at high swirl number. The turbulent kinetic energy at high swirl numbers gave the largest difference between the calculated and the measured values. Measurements on draft tubes in model turbines show the importance of good draft tube design. Prototype measurements on a Francis turbine show how the outlet draft tube flow should be measured for prototype draft tube evaluation. 54 refs., 118 figs., 2 tabs.

  3. 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

    shipped to BNF number 164, named CEDRA on Cadarache site (in operation in 2009). AREVA TA (ATA) is pleased to provide AREVA Federal Services (AFS) a phased plan to provide an Adaptation Design Technical Report and Organization. This approach will facilitate the assessment of the Final design Phase (After September 2010) and funding to support the engineering, procurement, and construction planning leading to the fabrication of a Mobile Hot Cell (MHC). (author)

  4. Postclosure performance assessment of the SCP [Site Characterization Plan] conceptual design for horizontal emplacement: Revision 1

    International Nuclear Information System (INIS)

    1987-08-01

    This report is a preliminary postclosure performance assessment of the repository design specified in the Site Characterization Plan Conceptual Design Report (SCP-CDR) for horizontal emplacement of high-level nuclear waste. At the time that these analyses were done, horizontal emplacement was the preferred orientation for the waste packages but vertical emplacement is now the reference design. This assessment consists of (1) a review of the regulatory requirements and strategy to demonstrate compliance with these requirements, (2) an analysis of the performance of the total repository system, (3) an analysis of the thermomechanical behavior of the repository, (4) an analysis of brine mobility in the repository, (5) an analysis of the waste package performance, (6) an analysis of the performance of seals, and (7) comments on the sensitivity of the various performance measures to uncertainties in the data and models. These are preliminary analyses and, in most cases, involve bounding calculations of the repository behavior. They have several purposes including (1) assessing how well this conceptual design ''measures up'' against requirements, (2) gaining experience in implementing the performance assessment strategy and tools and thereby learning where improvements are needed, (3) helping to identify needed data, and (4) helping to indicate required design modifications. 26 refs., 40 figs., 20 tabs

  5. 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))

  6. 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

  7. Management assessment using draft ANSI/ASQC-E4

    International Nuclear Information System (INIS)

    Hampton, E. Jr.

    1992-01-01

    Presented herein is a description of the process, methods, and techniques employed to conduct a comprehensive environmental management assessment of environmental waste management activities conducted by the Waste Management Department of Reynolds Electrical ampersand Engineering Co., Inc. (REECo) at the Nevada Test Site (NTS) using the draft ANSI/ASQC-E4 standard

  8. 75 FR 48382 - Draft Regulatory Guide: Issuance, Availability

    Science.gov (United States)

    2010-08-10

    .... Introduction The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment a draft guide in the... provides text and image files of NRC's public documents. If you do not have access to ADAMS or if there are... analysis may be found in ADAMS under Accession No. ML101740327. Federal Rulemaking Web site: Public...

  9. 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

  10. 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.

  11. Design and performance of the Savannah River Site Billet Active Well Coincidence Counter

    International Nuclear Information System (INIS)

    Griffin, J.C.; Sadowski, E.T.

    1991-01-01

    The Savannah River Site (SRS) has acquired, installed, and tested a custom-built Billet Active Well (neutron) Coincidence Counter (BAWCC). The BAWCC is used to make accountability measurements of the 235 U content of U-Al coextrusion billets in the SRS fuel fabrication facility. The instrument design incorporates a unique center-source configuration, with two moderated americium-lithium (AmLi) neutron sources located in a central spindle that inserts through the center hole of the U-Al billets. This configuration, a result of earlier experimental studies at SRS, yields improved response and precision for billet assay when compared to the standard AWCC source arrangement. Initial tests of the BAWCC at SRS have yielded one-sigma uncertainties of 0.8--1.0% for a fifteen-minute assay. This paper will describe the design, testing program and performance characteristics of the BAWCC

  12. 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)

  13. Remedial action plan and site design for stabilization of the inactive uranium mill tailings site at Lowman, Idaho

    International Nuclear Information System (INIS)

    1991-09-01

    The US Environmental Protection Agency (EPA) has established health and environmental regulations to correct and prevent groundwater contamination resulting from former uranium processing activities at inactive uranium processing sites (40 CFR 192). According to the Uranium Mill Tailings Radiation Control Act of 1978 (UMTRCA), the US Department of Energy (DOE) is responsible for assessing the inactive uranium processing sites. The DOE has decided that each assessment shall include information on hydrogeologic site characterization. The water resources protection strategy that describes how the proposed action will comply with the EPA groundwater protection standards is presented in Attachment 4. Site characterization activities discussed in this section include: Definition of the hydrogeologic characteristics of the environment, including hydrostratigraphy, aquifer parameters, areas of aquifer recharge and discharge, potentiometric surfaces, and groundwater velocities. Definition of background groundwater quality and comparison with the proposed EPA groundwater protection standards. Evaluation of the physical and chemical characteristics of the contaminant source and/or residual radioactive materials. Definition of existing groundwater contamination by comparison with the EPA groundwater protection standards. Description of the geochemical processes that affect the downward migration of the source contaminants at the processing site. Description of water resource utilization, including availability, current and future use and value, and alternate water supplies

  14. 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.

  15. 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

  16. Accelerating Cleanup: Focus on 2006. Discussion draft

    International Nuclear Information System (INIS)

    1997-01-01

    This executive summary addresses the activities associated with the National Transuranic (TRU) Program managed by the Carlsbad Area Office (CAO). The CAO programmatically reports to the Assistant Secretary for Environmental Management and receives administrative support through the Albuquerque Operations Office. The mission of the Carlsbad Area Office (CAO) is to protect human health and the environment by opening and operating the Waste Isolation Pilot Plant for site disposal of TRU waste and by establishing an effective system for management of TRU waste from generation to disposal. It includes personnel assigned to the CAO, the Waste Isolation Pilot Plant (WIPP) site operations, and other activities associated with the National TRU Program. The CAO develops and directs implementation of the program, while the DOE Headquarters establishes policy and guidelines. The CAO assesses compliance with the program guidance, as well as the commonality of activities and assumptions among all the sites. Since the development of the February 28, 1997, database used to develop this Discussion Draft, the opening of the WIPP facility for receipt of Contact Handled waste has been delayed from November 1997 to May 1998. This slippage is significant enough to require a change in the milestones and volumes included in the documents to be reviewed by our stakeholders. Changes have been incorporated into this Discussion Draft and its supporting Project Baseline Summaries (PBSs)

  17. "A Virtual Canvas"—Designing a Blog Site to Research Young Muslims' Friendships & Identities

    Directory of Open Access Journals (Sweden)

    Orla McGarry

    2012-11-01

    Full Text Available This article is based on research among a group of Muslim youth living in the west of Ireland as part of a study on "social belonging" and identity. One part of the research involved designing a youth centered, participatory research method, in the form of a blog site, to investigate what young people say and do when they are asked to talk about themselves and their relationships, with minimal researcher involvement. Participants were presented with a "blank virtual canvas" where they determined what became discussed. Twenty-two teenaged Muslims—comprising close friends as well as fellow students of the same school and living in the same West of Ireland town—contributed to a time limited, closed blog site over a four month period. The blog site offers interesting snippets of Muslim identification, and how they choose to present themselves to others. In the process of contributing to this exercise, we can also observe subtle means through which inclusion and exclusion co-exist online, refracting young people's offline worlds. The blog affords an opportunity to consciously "do" friendship by presenting to each other images, symbols and statements of friendship that invoke both cohesion and closure. The research unravels certain gendered patterns in online performances. In demonstrating this evidence, we argue that the study of online interactions of youth can provide an alternative window in exploring relationships, identification and social positioning. URN: http://nbn-resolving.de/urn:nbn:de:0114-fqs130115

  18. 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

    To achieve compliance with the proposed US Environmental Protection Agency (EPA) groundwater protection standards the US Department of Energy (DOE) proposes to meet background concentrations or the EPA maximum concentration limits (MCLS) for hazardous constituents in groundwater in the uppermost aquifer at the point of compliance (POC) at the Gunnison Uranium Mill Tailings Remedial Action (UMTRA) Project disposal site near Gunnison, Colorado. The proposed remedial action will ensure protection of human health and the environment. A summary of the principal features of the water resources protection strategy for the Gunnison disposal site is included in this report

  19. A Multidisciplinary Research Team Approach to Computer-Aided Drafting (CAD) System Selection. Final Report.

    Science.gov (United States)

    Franken, Ken; And Others

    A multidisciplinary research team was assembled to review existing computer-aided drafting (CAD) systems for the purpose of enabling staff in the Design Drafting Department at Linn Technical College (Missouri) to select the best system out of the many CAD systems in existence. During the initial stage of the evaluation project, researchers…

  20. 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

  1. 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

  2. System for implement draft reduction

    DEFF Research Database (Denmark)

    2008-01-01

    Abstract of WO 2008095503  (A1) There is disclosed a system and method of reducing draft forces when working soil with agricultural soil working implements (206, 211) creating draft forces, the soil working implements (208, 206, 211) beingoperable connectable to a frame (204, 304, 404, 504, 604......, the second part of the width comprising an other part of said width (212) than the first part (222), so as e.g. to reduce draft forces compared to working both first and second parts at the same time....

  3. 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

  4. The shape of natural draft cooling towers

    International Nuclear Information System (INIS)

    Grange, J.L.

    1992-07-01

    The shape of cooling towers is more often designed empirically. There, it is considered from a theoretical point of view. The analysis of dynamic of natural draft and of the air flow in a cooling tower shell is presented. It is shown, that although it is convergent, a tower works like a diffuser for pressure recovery. And it is turbulence that produces a transfer of kinetic energy and allows a good operation of the diffusor. The equations permit to define a shell profile which depends upon the operating conditions of the cooling tower. In the same way, a stability criteria for natural draft depending upon operating conditions is established. A heating model of one meter diameter has been built in a thermal similitude. The turbulence rate has been measured with a hot wire anemometer at the tower exit and visualizations have also been made. Natural draft stability has been studied by these means for four different shell shapes and a wide range of operating conditions. Experimental and theoretical results agree satisfactorily and experiments can be considered as a validation of theory

  5. 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

  6. Evaluation of Landfill Cover Design Options for Waste Disposal Sites in the Coastal Regions of Ghana

    Directory of Open Access Journals (Sweden)

    Kodwo Beedu Keelson

    2015-01-01

    Full Text Available Uncontrolled leachate generation from operational and closed waste disposal sites is a major environmental concern in the coastal regions of Ghana which have abundant surface water and groundwater resources. The Ghana Landfill Guidelines requires the provision of a final cover or capping system as part of a final closure plan for waste disposal sites in the country as a means of minimizing the harmful environmental effects of these emissions. However, this technical manual does not provide explicit guidance on the material types or configuration for landfill covers that would be suitable for the different climatic conditions in the country. Four landfill cover options which are based on the USEPA RCRA-type and evapotranspirative landfill cover design specifications were evaluated with the aid of the HELP computer program to determine their suitability for waste disposal sites located in the Western, Central and Greater Accra regions. The RCRA Subtitle C cover which yielded flux rates of less than 0.001 mm/yr was found to be suitable for the specific climatic conditions. The RCRA Subtitle D cover was determined to be unsuitable due to the production of very large flux rates in excess of 200 mm/yr. The results for the anisotropic barrier and capillary barrier covers were inconclusive. Recommendations for further study include a longer simulation period as well the study of the combined effects of different topsoil vegetative conditions and evaporative zone depths on the landfill water balance. The use of other water balance models such as EPIC, HYDRUS-2D and UNSAT-H for the evaluation of the evapotranspirative landfill cover design options should also be considered.

  7. 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

  8. SR 97 - Waste, repository design and sites. Background report to SR 97 SKB

    International Nuclear Information System (INIS)

    1999-10-01

    SR 97 is a comprehensive analysis of long-term safety of a deep repository for spent nuclear fuel. The repository is assumed to be designed according to the KBS-3 method. Assessments are performed in SR 97 for three fictitious sites: Aberg, Beberg and Ceberg. One premise is that data used for assessment of the fictitious sites are to be taken from sites that have previously been investigated. The spent nuclear fuel is enclosed in copper canisters with an insert of cast iron. The canisters are emplaced in bored holes in the floor of the deposition tunnels. Around each canister, bentonite blocks are stacked which, after absorbing water and swelling, will isolate the canister from groundwater, hold the canister in place and retard transport of radionuclides from the canister to the surrounding rock. The spent nuclear fuel will emit heat for a long time, due to the decay heat. The maximum permissible temperature on the canister surface has been chosen at 100 deg C. The spacing between the deposition holes and between the deposition tunnels is adjusted site-specifically to meet this requirement. The thermal properties of the rock and the buffer material are of importance for how closely the deposition holes and tunnels can be spaced. After deposition, the deposition tunnels are backfilled with a mixture of bentonite and crushed rock. SR 97 examines above all the consequences of various scenarios and the handling of various types of uncertainties. The different repository sites illustrate normal properties for Swedish bedrock which are of importance for safety. To facilitate the work, the repositories on the three sites are configured as similarly as possible, which means for example that they are located at roughly the same depth and are fitted into the bedrock in a relatively similar fashion. Apart from the siting of a repository for spent nuclear fuel, the site may need to house a separate repository for other long-lived waste. This possibility has been considered in

  9. SR 97 - Waste, repository design and sites. Background report to SR 97 SKB

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1999-10-01

    SR 97 is a comprehensive analysis of long-term safety of a deep repository for spent nuclear fuel. The repository is assumed to be designed according to the KBS-3 method. Assessments are performed in SR 97 for three fictitious sites: Aberg, Beberg and Ceberg. One premise is that data used for assessment of the fictitious sites are to be taken from sites that have previously been investigated. The spent nuclear fuel is enclosed in copper canisters with an insert of cast iron. The canisters are emplaced in bored holes in the floor of the deposition tunnels. Around each canister, bentonite blocks are stacked which, after absorbing water and swelling, will isolate the canister from groundwater, hold the canister in place and retard transport of radionuclides from the canister to the surrounding rock. The spent nuclear fuel will emit heat fora long time, due to the decay heat. The maximum permissible temperature on the canister surface has been chosen at 100 deg C. The spacing between the deposition holes and between the deposition tunnels is adjusted site-specifically to meet this requirement. The thermal properties of the rock and the buffer material are of importance for how closely the deposition holes and tunnels can be spaced. After deposition, the deposition tunnels are backfilled with a mixture of bentonite and crushed rock. SR 97 examines above all the consequences of various scenarios and the handling of various types of uncertainties. The different repository sites illustrate normal properties for Swedish bedrock which are of importance for safety. To facilitate the work, the repositories on the three sites are configured as similarly as possible, which means for example that they are located at roughly the same depth and are fitted into the bedrock in a relatively similar fashion. Apart from the siting of a repository for spent nuclear fuel, the site may need to house a separate repository for other long-lived waste. This possibility has been considered in

  10. Epitope-based peptide vaccine design and target site depiction against Ebola viruses: an immunoinformatics study.

    Science.gov (United States)

    Khan, M A; Hossain, M U; Rakib-Uz-Zaman, S M; Morshed, M N

    2015-07-01

    Ebola viruses (EBOVs) have been identified as an emerging threat in recent year as it causes severe haemorrhagic fever in human. Epitope-based vaccine design for EBOVs remains a top priority because a mere progress has been made in this regard. Another reason is the lack of antiviral drug and licensed vaccine although there is a severe outbreak in Central Africa. In this study, we aimed to design an epitope-based vaccine that can trigger a significant immune response as well as to prognosticate inhibitor that can bind with potential drug target sites using various immunoinformatics and docking simulation tools. The capacity to induce both humoral and cell-mediated immunity by T cell and B cell was checked for the selected protein. The peptide region spanning 9 amino acids from 42 to 50 and the sequence TLASIGTAF were found as the most potential B and T cell epitopes, respectively. This peptide could interact with 12 HLAs and showed high population coverage up to 80.99%. Using molecular docking, the epitope was further appraised for binding against HLA molecules to verify the binding cleft interaction. In addition with this, the allergenicity of the epitopes was also evaluated. In the post-therapeutic strategy, docking study of predicted 3D structure identified suitable therapeutic inhibitor against targeted protein. However, this computational epitope-based peptide vaccine designing and target site prediction against EBOVs open up a new horizon which may be the prospective way in Ebola viruses research; the results require validation by in vitro and in vivo experiments. © 2015 John Wiley & Sons Ltd.

  11. Forced draft wet cooling systems

    International Nuclear Information System (INIS)

    Daubert, A.; Caudron, L.; Viollet, P.L.

    1975-01-01

    The disposal of the heat released from a 1000MW power plant needs a natural draft tower of about 130m of diameter at the base, and 170m height, or a cooling system with a draft forced by about forty vans, a hundred meters in diameter, and thirty meters height. The plumes from atmospheric cooling systems form, in terms of fluid mechanics, hot jets in a cross current. They consist in complex flows that must be finely investigated with experimental and computer means. The study, currently being performed at the National Hydraulics Laboratory, shows that as far as the length and height of visible plumes are concerned, the comparison is favorable to some types of forced draft cooling system, for low and medium velocities, (below 5 or 6m/s at 10m height. Beyond these velocities, the forced draft sends the plume up to smaller heights, but the plume is generally more dilute [fr

  12. Issues and recent advances in optimal experimental design for site investigation (Invited)

    Science.gov (United States)

    Nowak, W.

    2013-12-01

    This presentation provides an overview over issues and recent advances in model-based experimental design for site exploration. The addressed issues and advances are (1) how to provide an adequate envelope to prior uncertainty, (2) how to define the information needs in a task-oriented manner, (3) how to measure the expected impact of a data set that it not yet available but only planned to be collected, and (4) how to perform best the optimization of the data collection plan. Among other shortcomings of the state-of-the-art, it is identified that there is a lack of demonstrator studies where exploration schemes based on expert judgment are compared to exploration schemes obtained by optimal experimental design. Such studies will be necessary do address the often voiced concern that experimental design is an academic exercise with little improvement potential over the well- trained gut feeling of field experts. When addressing this concern, a specific focus has to be given to uncertainty in model structure, parameterizations and parameter values, and to related surprises that data often bring about in field studies, but never in synthetic-data based studies. The background of this concern is that, initially, conceptual uncertainty may be so large that surprises are the rule rather than the exception. In such situations, field experts have a large body of experience in handling the surprises, and expert judgment may be good enough compared to meticulous optimization based on a model that is about to be falsified by the incoming data. In order to meet surprises accordingly and adapt to them, there needs to be a sufficient representation of conceptual uncertainty within the models used. Also, it is useless to optimize an entire design under this initial range of uncertainty. Thus, the goal setting of the optimization should include the objective to reduce conceptual uncertainty. A possible way out is to upgrade experimental design theory towards real-time interaction

  13. 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

  14. 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.

  15. Design of NPP of new generation being constructed at Novovoronezh NPP site

    International Nuclear Information System (INIS)

    Afrov, A.; Berkovich, V.; Generalov, V.; Dragunov, Yu.; Krushelnitskij, V.

    2000-01-01

    The design of a new-generation nuclear power plant with advanced WWER-1000 units, currently under construction at Novovoronezh, is dealt with in considerable detail. Information is given on the general layout of the power plant, and the monoblock comprising the four-loop reactor plant with double containment, the turbine hall with two turbine-driven feedwater pumps and safety and auxiliary systems is described. In a separate building at the power plant site, a new fuel storage facility is located designed for extreme external effects. The operations involved in fuel handling, in both the storage facility and the reactor department, are mentioned. The management of various types of radioactive waste is highlighted. The basic principles of the engineering solutions pertaining to the plant's electrical part are outlined. The concept of the instrumentation and control system is explained. Information is also given on the double containment system. A considerable part of the presentation is devoted to the philosophy and concept of the power plant safety, to the results of safety evaluation and to the research carried out in this respect. The paper is concluded with a discussion of the experiments and analyses performed with the aim to justify the design solutions as regards the passive heat removal system. (A.K.)

  16. 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

  17. Designing artificial 2D crystals with site and size controlled quantum dots.

    Science.gov (United States)

    Xie, Xuejun; Kang, Jiahao; Cao, Wei; Chu, Jae Hwan; Gong, Yongji; Ajayan, Pulickel M; Banerjee, Kaustav

    2017-08-30

    Ordered arrays of quantum dots in two-dimensional (2D) materials would make promising optical materials, but their assembly could prove challenging. Here we demonstrate a scalable, site and size controlled fabrication of quantum dots in monolayer molybdenum disulfide (MoS 2 ), and quantum dot arrays with nanometer-scale spatial density by focused electron beam irradiation induced local 2H to 1T phase change in MoS 2 . By designing the quantum dots in a 2D superlattice, we show that new energy bands form where the new band gap can be controlled by the size and pitch of the quantum dots in the superlattice. The band gap can be tuned from 1.81 eV to 1.42 eV without loss of its photoluminescence performance, which provides new directions for fabricating lasers with designed wavelengths. Our work constitutes a photoresist-free, top-down method to create large-area quantum dot arrays with nanometer-scale spatial density that allow the quantum dots to interfere with each other and create artificial crystals. This technique opens up new pathways for fabricating light emitting devices with 2D materials at desired wavelengths. This demonstration can also enable the assembly of large scale quantum information systems and open up new avenues for the design of artificial 2D materials.

  18. Novel implant design improves implant survival in multirooted extraction sites: a preclinical pilot study.

    Science.gov (United States)

    Sivan-Gildor, Adi; Machtei, Eli E; Gabay, Eran; Frankenthal, Shai; Levin, Liran; Suzuki, Marcelo; Coelho, Paulo G; Zigdon-Giladi, Hadar

    2014-10-01

    The primary aim is to evaluate clinical, radiographic, and histologic parameters of novel implants with "three roots" design that were inserted into fresh multirooted extraction sockets. A secondary aim is to compare this new implant to standard root-form dental implants. Immediate implantation of novel or standard design 6 × 6-mm implants was performed bilaterally into multirooted sockets in mandibles of mini-pigs. Twelve weeks later, clinical, radiographic, stability, histomorphometric, and microcomputed tomography (micro-CT) analyses were performed. Survival rates were significantly higher in the test implants compared with control (92.8% versus 33.3%, respectively; P micro-CT analyses demonstrated bone fill in the inner part of the test implants. Moreover, bone-to-implant contact was higher in the test implants (55.50% ± 3.68% versus 42.47% ± 9.89%). Contrary to the clinical, radiographic, and histomorphometric results, resonance frequency analysis measurements were greater in the control group (77.74 ± 3.21 implant stability quotient [ISQ]) compared with the test group (31.09 ± 0.28 ISQ), P = 0.008. The novel design implants resulted in significantly greater survival rate in multirooted extraction sites. Further studies will be required to validate these findings.

  19. 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

  20. Readability of Online Patient Educational Resources Found on NCI-Designated Cancer Center Web Sites.

    Science.gov (United States)

    Rosenberg, Stephen A; Francis, David; Hullett, Craig R; Morris, Zachary S; Fisher, Michael M; Brower, Jeffrey V; Bradley, Kristin A; Anderson, Bethany M; Bassetti, Michael F; Kimple, Randall J

    2016-06-01

    The NIH and Department of Health & Human Services recommend online patient information (OPI) be written at a sixth grade level. We used a panel of readability analyses to assess OPI from NCI-Designated Cancer Center (NCIDCC) Web sites. Cancer.gov was used to identify 68 NCIDCC Web sites from which we collected both general OPI and OPI specific to breast, prostate, lung, and colon cancers. This text was analyzed by 10 commonly used readability tests: the New Dale-Chall Readability Formula, Flesch Reading Ease scale, Flesch-Kinaid Grade Level, FORCAST scale, Fry Readability Graph, Simple Measure of Gobbledygook test, Gunning Frequency of Gobbledygook index, New Fog Count, Raygor Readability Estimate Graph, and Coleman-Liau Index. We tested the hypothesis that the readability of NCIDCC OPI was written at the sixth grade level. Secondary analyses were performed to compare readability of OPI between comprehensive and noncomprehensive centers, by region, and to OPI produced by the American Cancer Society (ACS). A mean of 30,507 words from 40 comprehensive and 18 noncomprehensive NCIDCCs was analyzed (7 nonclinical and 3 without appropriate OPI were excluded). Using a composite grade level score, the mean readability score of 12.46 (ie, college level: 95% CI, 12.13-12.79) was significantly greater than the target grade level of 6 (middle-school: Preadability metrics (P<.05). ACS OPI provides easier language, at the seventh to ninth grade level, across all tests (P<.01). OPI from NCIDCC Web sites is more complex than recommended for the average patient. Copyright © 2016 by the National Comprehensive Cancer Network.

  1. Design of quality assurance surveillance of geotechnical investigation in evaluation of nuclear power plants siting

    International Nuclear Information System (INIS)

    Made Pramayuni; Haendra Subekti

    2011-01-01

    System of building Nuclear Power Plants (NPP) is built above ground surface and rocks. Therefore, the geotechnical aspects evaluation of NPP siting in particular must be implemented properly and accurately. The successful of the design and construction of the building system is influenced by geotechnical conditions in the vicinity of NPP will be built. To be able to perform geotechnical analysis is good and true; it's required data of surface/underground completely. These data can be obtained directly not only from the geotechnical field investigations, but also can be obtained from the laboratory tests results. To ensure that geotechnical investigations are conducted effectively and efficiently, produce accurate data, as well as meeting the requirements of safety, health, safety, environmental, quality and economic, then the Quality Assurance Program (QAP) should be established and implemented. Supervision of the QAP implementation is required to ensure the work is done according to QAP that have been established and applicable requirement. (author)

  2. Cold shock to aquatic organisms: guidance for power-plant siting, design, and operation

    International Nuclear Information System (INIS)

    Coutant, C.C.

    1977-01-01

    Problems of cold-shock damages to aquatic organisms have arisen at some condenser cooling-water discharges of thermal power stations when the warm-water releases have suddenly terminated. The basis for such damage lies in the exposure of resident organisms to a rapid decrease in temperature and a sustained exposure to low temperature that induces abnormal behavioral or physiological performance and often leads to death. Although some spectacular fish kills from cold shock have occurred, the present knowledge of the hydraulic and biological processes involved can provide guidance for the siting, design, and operation of power-plant cooling systems to minimize the likelihood of significant cold-shock effects. Preventing cold-shock damages is one consideration in minimizing overall environmental impacts of power-plant cooling and in balancing plant costs with environmental benefits

  3. Design principle of TVO's final repository and preliminary adaptation to site specific conditions

    International Nuclear Information System (INIS)

    Salo, J-P.; Reikkola, R.

    1995-01-01

    Teollisuuden Voima Oy (TVO) is responsible for the management of spent fuel produced by the Olkiluoto power plant. TVO's current programme of spent fuel management is based on the guidelines and time schedule set by the Finnish Government. TVO has studied a final disposal concept in which the spent fuel bundles are encapsulated in copper canisters and emplaced in Finnish bedrock. According to the plan the final repository for spent fuel will be in operation by 2020. TVO's updated technical plans for the disposal of spent fuel together with a performance analysis (TVO-92) were submitted to the authorities in 1992. The paper describes the design principle of TVO's final repository and preliminary adaptation of the repository to site specific conditions. (author). 10 refs., 5 figs

  4. 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.

  5. 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

  6. 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

  7. 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.

  8. Design of multiligand inhibitors for the swine flu H1N1 neuraminidase binding site

    Directory of Open Access Journals (Sweden)

    Narayanan MM

    2013-08-01

    Full Text Available Manoj M Narayanan,1,2 Chandrasekhar B Nair,2 Shilpa K Sanjeeva,2 PV Subba Rao,2 Phani K Pullela,1,2 Colin J Barrow11Centre for Chemistry and Biotechnology, Deakin University, Geelong, VIC, Australia; 2Bigtec Pvt Ltd, Rajajinagar, Bangalore, IndiaAbstract: Viral neuraminidase inhibitors such as oseltamivir and zanamivir prevent early virus multiplication by blocking sialic acid cleavage on host cells. These drugs are effective for the treatment of a variety of influenza subtypes, including swine flu (H1N1. The binding site for these drugs is well established and they were designed based on computational docking studies. We show here that some common natural products have moderate inhibitory activity for H1N1 neuraminidase under docking studies. Significantly, docking studies using AutoDock for biligand and triligand forms of these compounds (camphor, menthol, and methyl salicylate linked via methylene bridges indicate that they may bind in combination with high affinity to the H1N1 neuraminidase active site. These results also indicate that chemically linked biligands and triligands of these natural products could provide a new class of drug leads for the prevention and treatment of influenza. This study also highlights the need for a multiligand docking algorithm to understand better the mode of action of natural products, wherein multiple active ingredients are present.Keywords: neuraminidase, influenza, H1N1, multiligand, binding energy, molecular docking, virus

  9. Design basis for resistance to shock and vibration of radioactive material packages greater than one ton in truck transport (draft standard for trial use and comment)

    International Nuclear Information System (INIS)

    Anon.

    1984-01-01

    This standard specifies minimum design values for shock and vibration in highway transport, by truck or by tractor-trailer combination, for fuel and irradiation experiments when package weight exceeds one ton. Shock values correspond to normal transport over rough roads and to minor accidents such as backing into a loading dock. Vibration values correspond to normal transport; any large-amplitude vibration resulting from rough road conditions or a minor accident is treated as shock. This standard includes recommended methods of application to the design of packaging and tiedown systems

  10. Design, synthesis, and characterization of novel fine-particle, unsupported catalysts for coal liquefaction. Technical progress report, October 25, 1990--October 24, 1991: Draft

    Energy Technology Data Exchange (ETDEWEB)

    Klein, M.T.

    1991-12-30

    The purpose of this work is to investigate the kinetics-assisted design, synthesis and characterization of fme-pardcle, unsupported catalysts for coal liquefaction. The goal is to develop a fundamental understanding of coal catalysis and catalysts that will, in turn, allow for the specification of a novel optimal catalyst for coal liquefaction.

  11. 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

  12. 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.

  13. 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

  14. 75 FR 1048 - Notice of Public Hearings on the Draft Tank Closure and Waste Management Environmental Impact...

    Science.gov (United States)

    2010-01-08

    ... Draft Tank Closure and Waste Management Environmental Impact Statement for the Hanford Site, Richland..., Office of Environmental Compliance, Office of Environmental Management. [FR Doc. 2010-224 Filed 1-7-10; 8... DEPARTMENT OF ENERGY Notice of Public Hearings on the Draft Tank Closure and Waste Management...

  15. 77 FR 68816 - Notice of Availability of the Draft Environmental Impact Statement for the Proposed Sun Valley to...

    Science.gov (United States)

    2012-11-16

    ...; AZA35079] Notice of Availability of the Draft Environmental Impact Statement for the Proposed Sun Valley to... Proposed Sun Valley to Morgan 500/230-kilovolt (kV) Transmission Line Project (Project) and Draft Bradshaw... comments by any of the following methods: Web site: http://www.blm.gov/az/st/en.html . Email: SunValley...

  16. Preliminary application of the draft code case for alloy 617 for a high temperature component

    International Nuclear Information System (INIS)

    Lee, Hyeong Yeon; Kim, Yong Wan; Song, Kee Nam

    2008-01-01

    The ASME draft Code Case for Alloy 617 was developed in the late 1980s for the design of very-high-temperature gas cooled reactors. The draft Code Case was patterned after the ASME Code Section III Subsection NH and was intended to cover Ni-Cr-Co-Mo Alloy 617 to 982 .deg. C (1800 .deg. F). But the draft Code Case is still in an incomplete status, lacking necessary material properties and design data. In this study, a preliminary evaluation on the creep-fatigue damage for a high temperature hot duct pipe structure has been carried out according to the draft Code Case. The evaluation procedures and results according to the draft Code Case for Alloy 617 material were compared with those of the ASME Subsection NH and RCC-MR for Alloy 800H material. It was shown that many data including material properties, fatigue and creep data should be supplemented for the draft Code Case. However, when the evaluation results on the creep-fatigue damage according to the draft Code Case, ASME-NH and RCC-MR were compared based on the preliminary evaluation, it was shown that the Alloy 617 results from the draft Code Case tended to be more resistant to the creep damage while less resistant to the fatigue damage than those from the ASME-NH and RCC-MR

  17. 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

  18. Spatiotemporally Representative and Cost-Efficient Sampling Design for Validation Activities in Wanglang Experimental Site

    Directory of Open Access Journals (Sweden)

    Gaofei Yin

    2017-11-01

    Full Text Available Spatiotemporally representative Elementary Sampling Units (ESUs are required for capturing the temporal variations in surface spatial heterogeneity through field measurements. Since inaccessibility often coexists with heterogeneity, a cost-efficient sampling design is mandatory. We proposed a sampling strategy to generate spatiotemporally representative and cost-efficient ESUs based on the conditioned Latin hypercube sampling scheme. The proposed strategy was constrained by multi-temporal Normalized Difference Vegetation Index (NDVI imagery, and the ESUs were limited within a sampling feasible region established based on accessibility criteria. A novel criterion based on the Overlapping Area (OA between the NDVI frequency distribution histogram from the sampled ESUs and that from the entire study area was used to assess the sampling efficiency. A case study in Wanglang National Nature Reserve in China showed that the proposed strategy improves the spatiotemporally representativeness of sampling (mean annual OA = 74.7% compared to the single-temporally constrained (OA = 68.7% and the random sampling (OA = 63.1% strategies. The introduction of the feasible region constraint significantly reduces in-situ labour-intensive characterization necessities at expenses of about 9% loss in the spatiotemporal representativeness of the sampling. Our study will support the validation activities in Wanglang experimental site providing a benchmark for locating the nodes of automatic observation systems (e.g., LAINet which need a spatially distributed and temporally fixed sampling design.

  19. Contribution towards a draft revision of recommendations 681: Propagation data required for the design of Earth-space land mobile telecommunications systems

    Science.gov (United States)

    Davarian, Faramaz; Bishop, Dennis

    1993-01-01

    Propagation models that can be used for the design of earth-space land mobile-satellite telecommunications systems are presented. These models include: empirical roadside shadowing, attenuation frequency scaling, fade and non-fade duration distribution, multipath in a mountain environment, and multipath in a roadside tree environment. Propagation data from helicopter-mobile and satellite-mobile measurements in Australia and the United States were used to develop the models.

  20. Contribution Towards a Draft Revision of Recommendation 681 Propogation Data Required for the Design of Earth-Space Land Mobile Telecommunications Systems

    Science.gov (United States)

    Davarian, F.; Bishop, D.

    1993-01-01

    Propogation models that can be used for the design of Earth-space land mobile-satellite telecommunications systems are presented. These models include: empirical roadside shadowing, attenuation frequency scaling, fade and non-fade duration distribution, multipath in a mountain environment, and multipath in a roadside tree environment. Propogation data from helicopter-mobile and satellite-mobile measurements in Australia and the United States were used to develop the models.

  1. 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

  2. Draft Transportaion Business Plan

    International Nuclear Information System (INIS)

    1985-08-01

    The Office of Civilian Radioactive Waste Management (OCRWM) is responsible for establishing a transportation system to support shipment of spent fuel and high-level radioactive waste to repositories and storage facilities developed under the Nuclear Waste Policy Act of 1982 (NWPA). An element that assists in fulfilling that responsibility is a business plan for acquiring and operating a transportation system. The Draft Transportation Business Plan is an interim step in the process of procuring the transportation system. It sets the context for business strategy decisions by providing pertinent background information, describing the legislation and policies governing transportation under the NWPA, and with establishing the transportation system. It also serves as an instrument for initiating communication between OCRWM and other interested parties. Included in the docuument are strategies for procuring shipping casks and transportation support services. Additionally, in the spirit of the NWPA directive to utilize the private sector to the maximum extent possible, opportunities for business ventures are obvious throughout the system development cycle

  3. Analysis of the Kaplan turbine draft tube effect

    Energy Technology Data Exchange (ETDEWEB)

    Motycak, L; Skotak, A; Obrovsky, J, E-mail: motycak.vhs@cbeng.c [CKD Blansko Engineering, a.s., Capkova 2357/5, Blansko 67801 (Czech Republic)

    2010-08-15

    The aim of this paper is to present information about possible problems and errors which can appear during numerical analyses of low head Kaplan turbines with a view to the runner - draft tube interaction. The setting of numerical model, grid size, used boundary conditions are the interface definition between runner and draft tube are discussed. There are available data from physical model tests which gives a great opportunity to compare CFD and experiment results and on the basis of this comparison to determine the approach to the CFD flow modeling. The main purpose for the Kaplan turbine model measurement was to gather the information about real flow field. The model tests were carried out in new hydraulic laboratory of CKD Blansko Engineering. The model tests were focused on the detailed velocity measurements downstream of the runner by differential pressure probe and on the velocity measurement downstream of the draft tube elbow by Particle Image Velocimetry method (PIV). The data from CFD simulation were compared to the velocity measurement results. In the paper also the design of the original draft tube modification due to flow improvement is discussed in the case of the Kaplan turbine uprating project. The results of the draft tube modification were confirmed by model tests in the hydraulic laboratory as well.

  4. Analysis of the Kaplan turbine draft tube effect

    Science.gov (United States)

    Motycak, L.; Skotak, A.; Obrovsky, J.

    2010-08-01

    The aim of this paper is to present information about possible problems and errors which can appear during numerical analyses of low head Kaplan turbines with a view to the runner - draft tube interaction. The setting of numerical model, grid size, used boundary conditions are the interface definition between runner and draft tube are discussed. There are available data from physical model tests which gives a great opportunity to compare CFD and experiment results and on the basis of this comparison to determine the approach to the CFD flow modeling. The main purpose for the Kaplan turbine model measurement was to gather the information about real flow field. The model tests were carried out in new hydraulic laboratory of CKD Blansko Engineering. The model tests were focused on the detailed velocity measurements downstream of the runner by differential pressure probe and on the velocity measurement downstream of the draft tube elbow by Particle Image Velocimetry method (PIV). The data from CFD simulation were compared to the velocity measurement results. In the paper also the design of the original draft tube modification due to flow improvement is discussed in the case of the Kaplan turbine uprating project. The results of the draft tube modification were confirmed by model tests in the hydraulic laboratory as well.

  5. Analysis of the Kaplan turbine draft tube effect

    International Nuclear Information System (INIS)

    Motycak, L; Skotak, A; Obrovsky, J

    2010-01-01

    The aim of this paper is to present information about possible problems and errors which can appear during numerical analyses of low head Kaplan turbines with a view to the runner - draft tube interaction. The setting of numerical model, grid size, used boundary conditions are the interface definition between runner and draft tube are discussed. There are available data from physical model tests which gives a great opportunity to compare CFD and experiment results and on the basis of this comparison to determine the approach to the CFD flow modeling. The main purpose for the Kaplan turbine model measurement was to gather the information about real flow field. The model tests were carried out in new hydraulic laboratory of CKD Blansko Engineering. The model tests were focused on the detailed velocity measurements downstream of the runner by differential pressure probe and on the velocity measurement downstream of the draft tube elbow by Particle Image Velocimetry method (PIV). The data from CFD simulation were compared to the velocity measurement results. In the paper also the design of the original draft tube modification due to flow improvement is discussed in the case of the Kaplan turbine uprating project. The results of the draft tube modification were confirmed by model tests in the hydraulic laboratory as well.

  6. 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

  7. Components of the primary circuit of LWRs. Design, construction and calculation. Draft. Komponenten des Primaerkreises von Leichtwasserreaktoren. Auslegung, Konstruktion und Berechnung. Entwurf

    Energy Technology Data Exchange (ETDEWEB)

    1979-10-01

    This standard is to be applied to components made of metallic materials, operated at design temperatures of up to 673/sup 0/K (400/sup 0/C). The primary circuit as the pressure continement of the reactor coolant comprises: Reactor pressure vessel (without internals), steam generator (primary loop), pressurizer, reactor coolant pump housing, interconnecting pipings between the components mentioned above and appropriate various valve and instrument casings, pipings branding off from the above components and interconnecting pipings, including the appropriate instrument casings, up to and including the first isolating valve, pressure shielding of control rod drives.

  8. Investigation of layered covers designed to limit infiltration at waste disposal sites

    International Nuclear Information System (INIS)

    Johnson, T.M.; Herzog, B.L.; Cartwright, K.; Larson, T.H.

    1983-01-01

    Layered soils of highly contrasting texture have been shown to act as a barrier to infiltration because of differences in unsaturated hydraulic properties. Water infiltrating into a fine-grained soil overlying an unsaturated gravel will not enter the gravel until the overlying material is nearly saturated. As a result of what is commonly called the wick effect, moisture will flow laterally through the fine-grained soil above the gravel layer. Layered covers of compacted soil materials utilizing this phenomenon have been proposed to limit infiltration at waste disposal sites. A study funded by the US Nuclear Regulatory Commission is underway to evaluate the potential use of layered trench covers to minimize infiltration at low-level radioactive waste disposal sites. Moisture movement through layered covers consisting of compacted fine-grained soils and sand or gravel was modeled, using a one-dimensional finite-difference model to compare with laboratory column experiments and a two-dimensional finite-element model for field-scale simulations. Soil-moisture characteristic data were obtained from laboratory experiments and the hydraulic conductivity was calculated as a function of capillary pressure. The numerical simulations indicate that layered covers using various combinations of compacted fine-grained soils and coarse-grained material are able to substantially reduce infiltration. Laboratory column experiments using a dual-gamma ray attenuation system to measure moisture content and density simultaneously have been used to observe the behavior of layered soils and to select materials for field testing. Currently underway are field-scale studies of alternative cover designs selected on the basis of two-dimensional modeling

  9. Site Identification by Ligand Competitive Saturation (SILCS) simulations for fragment-based drug design.

    Science.gov (United States)

    Faller, Christina E; Raman, E Prabhu; MacKerell, Alexander D; Guvench, Olgun

    2015-01-01

    Fragment-based drug design (FBDD) involves screening low molecular weight molecules ("fragments") that correspond to functional groups found in larger drug-like molecules to determine their binding to target proteins or nucleic acids. Based on the principle of thermodynamic additivity, two fragments that bind nonoverlapping nearby sites on the target can be combined to yield a new molecule whose binding free energy is the sum of those of the fragments. Experimental FBDD approaches, like NMR and X-ray crystallography, have proven very useful but can be expensive in terms of time, materials, and labor. Accordingly, a variety of computational FBDD approaches have been developed that provide different levels of detail and accuracy.The Site Identification by Ligand Competitive Saturation (SILCS) method of computational FBDD uses all-atom explicit-solvent molecular dynamics (MD) simulations to identify fragment binding. The target is "soaked" in an aqueous solution with multiple fragments having different identities. The resulting computational competition assay reveals what small molecule types are most likely to bind which regions of the target. From SILCS simulations, 3D probability maps of fragment binding called "FragMaps" can be produced. Based on the probabilities relative to bulk, SILCS FragMaps can be used to determine "Grid Free Energies (GFEs)," which provide per-atom contributions to fragment binding affinities. For essentially no additional computational overhead relative to the production of the FragMaps, GFEs can be used to compute Ligand Grid Free Energies (LGFEs) for arbitrarily complex molecules, and these LGFEs can be used to rank-order the molecules in accordance with binding affinities.

  10. Rational Catalyst Design of Titanium-Silica Materials Aided by Site-Specific Titration Tools

    Science.gov (United States)

    Eaton, Todd Robert

    between particle and crystal size, as obtained from XRD. In the course of establishing these relationships we've gained the knowledge of how to control TiO x structure, which enables the design of new and better catalysts. Understanding the synthesis-structure-function relationships allow for the design of a tandem photo/thermocatalytic reaction system for producing and consuming H2O2. By partially overcoating a TiO 2 photocatalyst with a ˜2 nm silica layer we observe a 56-fold rate improvement compared to bare-TiO2 for H2O2 synthesis from the proton-assisted reduction of O2. Addition of metal-SiO2 thermocatalysts (metal=Ti, Nb, or Ta) with sites needed for H2O2 activation creates a tandem system wherein the H2O2 produced in situ is utilized for alkene epoxidation. Compared to a thermocatalytic-only system, the tandem system accelerates epoxidation for cis-cyclooctene(11x faster), styrene(20x) and 1-octene(30x). This approach demonstrates a means for epoxidation with O2 that avoids H2O2 purification and transport, simplifies the total process, provides new opportunities for control by independent H2O2 production and consumption in the same reactor, and enhances rates relative to thermocatalytic-only epoxidation by intimately coupling H2O2 generation and consumption. Critically, establishment of titanium-silica synthesis-structure-function relationships enables the design of new catalysts and systems that are less energy- and material-intensive, leading towards more sustainable chemistry.

  11. 76 FR 62087 - Draft Conservation Plan and Draft Environmental Assessment; Dunes Sagebrush Lizard, Texas

    Science.gov (United States)

    2011-10-06

    ...] Draft Conservation Plan and Draft Environmental Assessment; Dunes Sagebrush Lizard, Texas AGENCY: Fish... draft Texas Conservation Plan for the Dunes Sagebrush Lizard (TCP). The draft TCP will function as a... the Applicant for the dunes sagebrush lizard (Sceloporus arenicolus) throughout its range in Texas...

  12. 76 FR 34097 - Notice of Availability of the Draft Environmental Impact Statement, Including a Draft...

    Science.gov (United States)

    2011-06-10

    ... Impact Statement, Including a Draft Programmatic Agreement, for the Clark, Lincoln, and White Pine...) has prepared a Draft Environmental Impact Statement (EIS) and a Draft Programmatic Agreement (PA.... 100 N., Nephi Beaver Library, 55 W. Center St., Beaver. The Draft EIS describes and analyzes SNWA's...

  13. Design of a natural draft air-cooled condenser and its heat transfer characteristics in the passive residual heat removal system for 10 MW molten salt reactor experiment

    International Nuclear Information System (INIS)

    Zhao, Hangbin; Yan, Changqi; Sun, Licheng; Zhao, Kaibin; Fa, Dan

    2015-01-01

    As one of the Generation IV reactors, Molten Salt Reactor (MSR) has its superiorities in satisfying the requirements on safety. In order to improve its inherent safety, a concept of passive residual heat removal system (PRHRS) for the 10 MW Molten Salt Reactor Experiment (MSRE) was put forward, which mainly consisted of a fuel drain tank, a feed water tank and a natural draft air-cooled condenser (NDACC). Besides, several valves and pipes are also included in the PRHRS. A NDACC for the PRHRS was preliminarily designed in this paper, which contained a finned tube bundle and a chimney. The tube bundle was installed at the bottom of the chimney for increasing the velocity of the air across the bundle. The heat transfer characteristics of the NDACC were investigated by developing a model of the PRHRS using C++ code. The effects of the environmental temperature, finned tube number and chimney height on heat removal capacity of the NDACC were analyzed. The results show that it has sufficient heat removal capacity to meet the requirements of the residual heat removal for MSRE. The effects of these three factors are obvious. With the decay heat reducing, the heat dissipation power declines after a short-time rise in the beginning. The operation of the NDACC is completely automatic without the need of any external power, resulting in a high safety and reliability of the reactor, especially once the accident of power lost occurs to the power plant. - Highlights: • A model to study the heat transfer characteristics of the NDACC was developed. • The NDACC had sufficient heat removal capacity to remove the decay heat of MSRE. • NDACC heat dissipation power depends on outside temperature and condenser geometry. • As time grown, the effects of outside temperature and condenser geometry diminish. • The NDACC could automatically adjust its heat removal capacity

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

    International Nuclear Information System (INIS)

    1996-08-01

    This document contains the page changes for Attachment 3, Ground Water Hydrology Report dated August, 1996 for the Remedial Action Plan and Site Design for Stabilization of the Inactive Uranium Mill Tailings at Slick Rock, Colorado. This portion of Attachment 3 contains the Table of Contents pages i and ii, and pages numbered 3-3 through 3-56 of the Ground Water Hydrology Report. Also included are the cover sheets for Appendix A, B, and C to Attachment 3

  15. Design-Basis Flood Estimation for Site Characterization at Nuclear Power Plants in the United States of America

    Energy Technology Data Exchange (ETDEWEB)

    Prasad, Rajiv; Hibler, Lyle F.; Coleman, Andre M.; Ward, Duane L.

    2011-11-01

    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.

  16. 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.

  17. Remedial action plan and site design for stabilization of the inactive uranium mill tailings site at Lakeview, Oregon: Volume 1, Text and appendices A through D

    International Nuclear Information System (INIS)

    Chernoff, A.R.

    1992-07-01

    The Lakeview inactive uranium processing site is in Lake County, Oregon, approximately one mile northwest of the town of Lakeview, sixteen miles north of the California-Oregon border, and 96 miles east of Klamath Falls. The total designated site covers an area of 258 acres consisting of a tailings pile (30 acres). seven evaporation ponds (69 acres), the mill buildings, and related structures. The mill buildings and other structures have been decontaminated and are currently being used by Goose Lake Lumber Company. The tailings pile at the processing site was originally stabilized by Atlantic Richfield with an earthen cover 18--24 inches thick. The average depth of the tailings, including the cover, varied from six to eight feet. There were estimated to be 662,000 cubic yards of tailings, windblown contaminated materials, and vicinity property materials. During remedial action under the Uranium Mill Tailings Remedial Action (UMTRA) Project, approximately 264,000 cubic yards of additional contaminated materials were identified from excavations required to remove thorium- and arsenic-contaminated soils. The remedial action for the Lakeview site consisted of the cleanup, relocation, consolidation, and stabilization of all residual radioactive materials and thorium- and arsenic-contaminated materials in a partially below-grade disposal cell at a location approximately seven miles northwest of the tailings site, identified as the Collins Ranch site. A cover, including a radon/infiltration barrier and rock layer for protection from erosion, was Placed on top of the tailings. A rock-soil matrix covers the topslope and provides a growth medium for vegetation. The US Department of Energy (DOE) will retain the license and surveillance and maintenance responsibilities for the final restricted site of 13 acres

  18. 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

  19. Design concepts for an integrated control room used as a site-wide operations facility

    International Nuclear Information System (INIS)

    Simon, B.H.; Raghavan, R.; Ujita, H.; Utena, S.; Sakuma, A.; Itoh, T.; Fukura, M.; Ono, I.

    1995-01-01

    The concept of an Integrated Main Control Room (IMCR) evolved from surveys conducted by Tokyo Electric Power Company (TEPCO) with plant managers and workers as their existing GE-type boiling water reactors (BWRs) on the need for improved operating conditions in a new generation of reactors being developed for the next century (around 2010). These reactors will be a further enhancement of the advanced boiling water reactors (ABWRs) now being constructed at the Kashiwazaki-Kariwa site in Japan (no.6 and no.7). TEPCO also saw a need for new thinking on control room design because of projected social conditions in Japan for the 21st century. These projections forecast a smaller number of skilled engineering graduates and those graduates less willing to work in nuclear power because such work is seen as unappealing, conducted in remote geographical locations, and requiring extensive night duty. As one solution to reducing operator burden and decreasing the night shift staff, while making nuclear plant operation more interesting for the operators and reducing labor and construction costs, the IMCR was conceived. (author)

  20. Shape optimization of draft tubes for Agnew microhydro turbines

    International Nuclear Information System (INIS)

    Shojaeefard, Mohammad Hasan; Mirzaei, Ammar; Babaei, Ali

    2014-01-01

    Highlights: • The draft tube of Agnew microhydro turbine was optimized. • Pareto optimal solutions were determined by neural networks and NSGA-II algorithm. • The pressure recovery factor increases with height and angle over design ranges. • The loss coefficient reaches the minimum values at angles about 2 o . • Swirl of the incoming flow has great influence on the optimization results. - Abstract: In this study, the shape optimization of draft tubes utilized in Agnew type microhydro turbines has been discussed. The design parameters of the draft tube such as the cone angle and the height above the tailrace are considered in defining an optimization problem whose goal is to maximize the pressure recovery factor and minimize the energy loss coefficient of flow. The design space is determined by considering the experimental constraints and parameterized by the method of face-centered uniform ascertain distribution. The numerical simulations are performed using the boundary conditions found from laboratory tests and the obtained results are analyzed to create and validate a feed-forward neural network model, which is implemented as a surrogate model. The optimal Pareto solutions are finally determined using the NSGA-II evolutionary algorithm and compared for different inlet conditions. The results predict that the high swirl of the incoming flow drastically reduces the performance of the draft tube

  1. Draft 1988 mission plan amendment

    International Nuclear Information System (INIS)

    1988-06-01

    This draft 1988 amendment to the Mission Plan for the Civilian Radioactive Waste Management Program has been prepared by the US Department of Energy (DOE). The purpose is to inform the Congress of the DOE's plans for implementing the provisions of the Nuclear Waste Policy Amendments Act of 1987 (P.L. 100-203) for the Civilian Radioactive Waste Management Program. This document is being submitted in draft form to Federal agencies, states, previously affected Indian Tribes, affected units of local government, and the public. After the consideration of comments, this amendment will be revised as appropriate and submitted to the Congress. 39 refs., 7 figs., 4 tabs

  2. 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

  3. Draft revision of human factors guideline HF-010

    International Nuclear Information System (INIS)

    Lee, Hyun Chul; Lee, Yong Hee; Oh, In Seok; Lee, Jung Woon; Cha, Woo Chang; Lee, Dhong Ha

    2003-05-01

    The Application of Human Factors to the design of Man-Machine Interfaces System(MMIS) in the nuclear power plant is essential to the safety and productivity of the nuclear power plants, human factors standards and guidelines as well as human factors analysis methods and experiments are weightily used to the design application. A Korean engineering company has developed a human factors engineering guideline, so-call HF-010, and has used it for human factors design, however the revision of HF-010 is necessary owing to lack of the contents related to the advanced MMI(Man-Machine Interfaces). As the results of the reviews of HF-010, it is found out that the revision of Section 9. Computer Displays of HF-010 is urgent, thus the revision was drafted on the basis of integrated human factors design guidelines for VDT, human factors design guidelines for PMAS SPADES display, human factors design guidelines for PMAS alarm display, and human factors design guidelines for electronic displays developed by the surveillance and operation support project of KOICS. The draft revision of HF-010 Section 9 proposed in this report can be utilized for the human factors design of the advanced MMI, and the high practical usability of the draft can be kept up through the continuous revision according to the advancement of digital technology

  4. Remedial Action Plan and site design for stabilization of the inactive uranium mill tailings site at Durango, Colorado: Attachment 6, Supplemental standard for Durango processing site

    International Nuclear Information System (INIS)

    1991-12-01

    Excavation control to the 15 pCi/g radium-226 (Ra-226) standard at certain areas along the Animas River on the Durango Site would require extensive engineering and construction support. Elevated Ra-226 concentrations have been encountered immediately adjacent to the river at depths in excess of 7 feet below the present river stage. Decontamination to such depths to ensure compliance with the EPA standards will, in our opinion, become unreasonable. This work does not appear to be in keeping with the intent of the standards. Because the principal reason for radium removal is reduction of radon daughter concentrations (RDC) in homes to be built onsite, and because radon produced at depth will be attenuated in clean fill cover before entering such homes, it is appropriate to calculate the depth of excavation needed under a home to reduce RDC to acceptable levels. Potential impact was assessed through radon emanation estimation, using the RAECOM computer model. Elevated Ra-226 concentrations were encountered during final radium excavation of the flood plain below the large tailings pile, adjacent to the slag area. Data from 7 test pits excavated across the area were analyzed to provide an estimate of the Ra-226 concentration profile. Results are given in this report

  5. 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

  6. 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.

  7. Data for the geochemical investigation of UMTRAP designated site at Monument Valley, Arizona

    International Nuclear Information System (INIS)

    Markos, G.; Bush, K.J.

    1983-09-01

    This report contains the geochemical data and the methods of data collection from the former tailings site at Monument Valley, Arizona. Data are from a one-time sampling of waters and solid material from the background, the area adjacent to the site, and the site. Selected solid samples are water extracted to remove easily soluble salts. The waters and extracts of solid samples were analyzed for selected major and trace elements. 3 refs., 2 figs., 1 tab

  8. Plasmin substrate binding site cooperativity guides the design of potent peptide aldehyde inhibitors.

    Science.gov (United States)

    Swedberg, Joakim E; Harris, Jonathan M

    2011-10-04

    Perioperative bleeding is a cause of major blood loss and is associated with increased rates of postoperative morbidity and mortality. To combat this, antifibrinolytic inhibitors of the serine protease plasmin are commonly used to reduce bleeding during surgery. The most effective and previously widely used of these is the broad range serine protease inhibitor aprotinin. However, adverse clinical outcomes have led to use of alternative serine lysine analogues to inhibit plasmin. These compounds suffer from low selectivity and binding affinity. Consequently, a concerted effort to discover potent and selective plasmin inhibitors has developed. This study used a noncombinatorial peptide library to define plasmin's extended substrate specificity and guide the design of potent transition state analogue inhibitors. The various substrate binding sites of plasmin were found to exhibit a higher degree of cooperativity than had previously been appreciated. Peptide sequences capitalizing on these features produced high-affinity inhibitors of plasmin. The most potent of these, Lys-Met(sulfone)-Tyr-Arg-H [KM(O(2))YR-H], inhibited plasmin with a K(i) of 3.1 nM while maintaining 25-fold selectivity over plasma kallikrein. Furthermore, 125 nM (0.16 μg/mL) KM(O(2))YR-H attenuated fibrinolysis in vitro with an efficacy similar to that of 15 nM (0.20 μg/mL) aprotinin. To date, this is the most potent peptide inhibitor of plasmin that exhibits selectivity against plasma kallikrein, making this compound an attractive candidate for further therapeutic development.

  9. Program management strategies for following EPA guidance for remedial design/remedial action at DOE sites

    International Nuclear Information System (INIS)

    Hopper, J.P.; Chew, J.R.; Kowalski, T.E.

    1991-01-01

    At the US Department of Energy (DOE) facilities, environmental restoration is being conducted in accordance with Federal Facilities Compliance Agreements (or Interagency Agreements). These agreements establish a cooperative working relationship and often define roles, responsibilities and authorities for conduct and oversight of the Remedial Action Programs. The US Environmental Protection Agency (EPA) has guidelines on how to initiate and perform remedial actions for sites they are remediating under the Comprehensive Environmental Response Compensation and Liability Act (CERCLA) as amended by the Superfund Amendments and Re-Authorization Act (SARA). This paper addresses some of the difference and commonalities between the DOE project management procedures and EPA guidance documents. This report covers only the RD/RA phase of environmental restoration. On the surface, there are many apparent differences between the DOE and EPA project management processes. Upon closer review, however, many of the differences are the result of applying different terminology to the same phase of a project. By looking for the similarities in the two processes rather than hunting for differences, many communication problems are avoided. Understanding both processes also aids in figuring out when, how and to what extent EPA should participate in the RD/RA phase for DOE lead cleanup activities. The DOE Remedial Design and Remedial Action process is discussed in a stepwise manner and compared to the EPA process. Each element of the process is defined. Activities common to both the EPA and DOE are correlated. The annual DOE budget cycle for remediation projects and the four-year cycle for appropriation of remediation funds are discussed, and the constraints of this process examined. DOE orders as well as other requirements for RD/RA activities are summarized and correlated to EPA regulations where this is possible

  10. Long-term cover design for low-level radioactive and hazardous waste sites as applied to the Rocky Flats Environmental Technology Site solar evaporation ponds

    International Nuclear Information System (INIS)

    Stenseng, S.E.; Nixon, P.A.

    1996-01-01

    The US Department of Energy (DOE) operated five lined solar evaporation ponds (SEPs) at the Rocky Flats Environmental Technology Site (RFETS) in Jefferson County, Colorado from 1953 until 1986. The SEPs were used primarily to store and evaporate low-level radioactive and hazardous process wastes. Operation of the SEPs has resulted in contamination of the surrounding soils, and may also provide a source of groundwater contamination. The DOE proposes to close the SEPs by consolidating the contaminated material beneath an engineered cover. The primary objective of the closure of such hazardous and radioactive sites is to limit the exposure of the general public to the contaminants for time periods ranging from 100 to 10,000 years. The goal of the SEPs engineered cover is to isolate hazardous and low-level radioactive soils for a minimum of 1,000 years. Since there is currently no existing regulatory design guidance for a 1,000-year engineered cover, the proposed design of the SEPs engineered cover is based on research and testing that has been conducted for many years at various DOE facilities in the US. This paper discusses the main design theories of the proposed engineered cover for the closure of the SEPs, and how the research and test results of these other programs have been used to arrive at the final cover configuration, the material selections, the component layering, layer thicknesses, and the balance and interaction between components to establish an overall effective cover system

  11. Preliminary thermal/thermomechanical analyses of the Site Characterization Plan's Conceptual Design for a repository containing horizontally emplaced waste packages at the Deaf Smith County site

    International Nuclear Information System (INIS)

    Ghantous, N.Y.; Raines, G.E.

    1987-10-01

    This report presents thermal/thermomechanical analyses of the Site Characterization Plan Conceptual Design for horizontal package emplacement at the Deaf Smith County site, Texas. The repository was divided into three geometric regions. Then two-dimensional finite-element models were set up to approximate the three-dimensional nature of each region. Thermal and quasistatic thermomechanical finite-element analyses were performed to evaluate the thermal/thermomechanical responses of the three regions. The exponential-time creep law was used to represent the creep behavior of salt rock. The repository design was evaluated by comparing the thermal/thermomechanical responses obtained for the three regions with interim performance constraints. The preliminary results show that all the performance constraints are met except for those of the waste package. The following factors were considered in interpreting these results: (1) the qualitative description of the analytical responses; (2) the limitations of the analyses; and (3) either the conclusions based on overall evaluation of limitations and analytical results or the conclusions based on the fact that the repository design may be evaluated only after further analyses. Furthermore, a parametric analysis was performed to estimate the effect of material parameters on the predicted thermal/thermomechanical response. 23 refs., 34 figs., 9 tabs

  12. RCA annual report 1996. Draft

    International Nuclear Information System (INIS)

    1997-02-01

    In accordance with Article VII.4 of the Regional Co-operative Agreement for Research, Development and Training Related to Nuclear Science and Technology 1987 and extended in 1992, a draft report of activities for the calendar year 1996 is submitted

  13. AGILE DRAFTING OF OUTSOURCING CONTRACTS

    DEFF Research Database (Denmark)

    Schlichter, Bjarne Rerup; Storgaard, Kristian

    2015-01-01

    and in several parallel tracks using different competencies. By the use of an illustrative case-study, this paper explores how scrum can be applied to enhance the process of drafting outsourcing contracts. The analysis indicates that the use of an agile method, such as Scrum, can be beneficial in this context...

  14. Olympic Dam project: draft environmental impact statement

    International Nuclear Information System (INIS)

    1982-10-01

    The Olympic Dam deposit, South Australia, is estimated to contain at least 2,000 million tonnes of mineralized material, with an average grade of about 1.6% copper, 0.6 Kg/t of uranium oxide and 0.6 g/t of gold. The objective of the project is to extract and process the ore for the production and sale of copper, uranium oxide and the associated gold and silver. Facilities required are an underground mine, an on-site processing plant, associated facilities including a tailings retention system, a town to accommodate up to 9,000 people and other infrastructure. Chapters in the draft E.I.S. contain information on the environment, land use, aboriginal environment, geology, tailings retention system, radiation assessment, project infrastructure, social effects and economic effects

  15. Beverley project: draft environmental impact statement

    International Nuclear Information System (INIS)

    1982-07-01

    The Beverley deposit is located on the northern Lake Frome Plains, South Australia, 520km north of Adelaide. It is proposed to mine the deposit by in-situ leaching and to process the solution on the surface to produce an estimated 11,600t of yellowcake from about 6 million tonnes of 0.27% ore over approximately 23 years. The draft environmental impact statement is intended to cover all stages of the development from the pilot plant to final rehabilitation. Sections include the existing environment (geology, climate and meteorology, soils, hydrology, ecology, radionuclide base levels, land use, population and sites of Aboriginal and archaeological significance), the proposed development (solution mining, waste management, water management and mining and processing options), rehabilitation, environmental impact and environmental management and monitoring

  16. 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.

  17. 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...

  18. 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

  19. 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

  20. User-Interface Design Characteristics of Fortune 500 B2C E-Commerce Sites and Industry Differences

    Science.gov (United States)

    Zhao, Jensen J.; Truell, Allen D.; Alexander, Melody W.

    2006-01-01

    This study examined the user-interface design characteristics of 107 Fortune 500 B2C e-commerce Web sites and industry differences. Data were collected from corporate homepages, B2C product/service pages, B2C interactive shopping pages, as well as customer satisfaction of 321 online shoppers. The findings indicate that (a) to attract online…

  1. Natura2000 : information and communication on the designation and management of Natura2000 sites : main report 3: towards integrated management

    NARCIS (Netherlands)

    Kruk, R.W.; Blust, de G.; Apeldoorn, van R.C.; Bouwma, I.M.; Sier, A.R.J.

    2010-01-01

    Natura2000 : information and communication on the designation and management of Natura2000 sites. For all member states information will be collected describing the necessary management approaches, their legal framework, public consultation procedures as well as timing, structure and content of

  2. 77 FR 63312 - Notice of Intent: Designation of an Ocean Dredged Material Disposal Site (ODMDS) in Eastern Long...

    Science.gov (United States)

    2012-10-16

    ... Material Disposal Site (ODMDS) in Eastern Long Island Sound; Connecticut, New York, and Rhode Island AGENCY... (ODMDS) to serve the eastern Long Island Sound region (Connecticut, New York, and Rhode Island). SUMMARY... Environmental Impact Statement that supported the designation of the Central and Western Long Island Sound...

  3. 75 FR 38129 - Freescale Semiconductor, Inc., Hardware/Software Design and Manufacturing A Including On-Site...

    Science.gov (United States)

    2010-07-01

    ... Manufacturing A, Austin, Texas. The notice was published in the Federal Register on May 28, 2010 (75 FR 30070...Logic, Inc., Austin, TX; Amended Certification Regarding Eligibility To Apply for Worker Adjustment..., Design Solutions, Inc., Veriseo, SilconElite and MicroLogic, Inc. were employed on-site at the Austin...

  4. Design of a permanent Cd-shielded epithermal neutron irradiation site in the Syrian Miniature Neutron Source Reactor

    International Nuclear Information System (INIS)

    Khattab, K.; Haddad, Kh.; Haj-Hassan, H.

    2008-01-01

    A Cd-shield (cylindrical shell 1 mm in thickness, 34 mm in diameter and 180 mm in length) was used to design a permanent epithermal neutron irradiation site for epithermal neutron activation analysis (ENAA) in the Syrian Miniature Neutron Source Reactor (MNSR). This site was achieved by shielding the surface of the aluminum tube of one of the outer irradiation sites. The calculated depression ratio of thermal neutron flux was 1/10. Homogeneity of the neutron flux in the first outer irradiation site has been found numerically using the WIMSD4 and CITATION codes and experimentally by irradiating five short copper wires using the outer irradiation capsule. Good agreement was obtained between the calculated and the measured results of the neutron flux distributions. (author)

  5. Design of a permanent Cd-shielded epithermal neutron irradiation site in the Syrian Miniature Neutron Source Reactor

    International Nuclear Information System (INIS)

    Khattab, K.; Haddad, Kh.; Haj-Hassan, H.

    2009-01-01

    A Cd-shield (cylindrical shell 1 mm in thickness, 34 mm in diameter and 180 mm in length) was used to design a permanent epithermal neutron irradiation site for epithermal neutron activation analysis (ENAA) in the Syrian Miniature Neutron Source Reactor (MNSR). This site was achieved by shielding the surface of the aluminum tube of one of the outer irradiation sites. The calculated depression ratio of thermal neutron flux was 1/10. Homogeneity of the neutron flux in the first outer irradiation site has been found numerically using the WIMSD4 and CITATION codes and experimentally by irradiating five short copper wires using the outer irradiation capsule. Good agreement was obtained between the calculated and the measured results of the neutron flux distributions. (author)

  6. 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

  7. 78 FR 20690 - Draft Environmental Impact Statement, Draft Habitat Conservation Plan, Draft Programmatic...

    Science.gov (United States)

    2013-04-05

    .... Background The Fowler Ridge application is unusual in that 355 wind turbines are already in place and have... Agreement, and Draft Implementing Agreement; Application for an Incidental Take Permit, Fowler Ridge Wind... application from Fowler Ridge Wind Farm LLC, Fowler Ridge II Wind Farm LLC, Fowler Ridge III Wind Farm LLC...

  8. Design and integration of components for site specific control of fertilizer application

    NARCIS (Netherlands)

    Bergeijk, van J.

    2001-01-01

    Keywords: Precision Agriculture, Site Specific Agriculture, Global Positioning System, GPS, Fertilizer Application, Information System.

    Spatial and temporal variability in soil, crop and climate characteristics results in non optimal use of fertilizers when the application

  9. A Low Cost Shading Analyzer and Site Evaluator Design to Determine Solar Power System Installation Area

    Directory of Open Access Journals (Sweden)

    Selami Kesler

    2015-01-01

    Full Text Available Shading analyzer systems are necessary for selecting the most suitable installation site to sustain enough solar power. Afterwards, changes in solar data throughout the year must be evaluated along with the identification of obstructions surrounding the installation site in order to analyze shading effects on productivity of the solar power system. In this study, the shading analysis tools are introduced briefly, and a new and different device is developed and explained to analyze shading effect of the environmental obstruction on the site on which the solar power system will be established. Thus, exposure duration of the PV panels to the sunlight can be measured effectively. The device is explained with an application on the installation area selected as a pilot site, Denizli, in Turkey.

  10. 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)

  11. Public comments on the draft generic environmental impact statement for management of commercially generated radioactive waste

    International Nuclear Information System (INIS)

    Kreiter, M.R.; Unruh, C.M.; McCallum, R.F.

    1980-01-01

    The US Department of Energy has the responsibility for developing the technology required for managing commercial radioactive wastes in an environmentally acceptable manner. As part of this responsibility, DOE has prepared a draft environmental impact statement on the management of commercially generated radioactive waste. The draft was issued for public comment in April of 1979; five public hearings were held. The draft GEIS is intended to provide environmental input for the selection of an appropriate program strategy for the permanent isolation of commercially generated high-level and transuranic wastes. The scope of such a strategy includes research and development into alternative treatment processes and emplacement media, site investigations into candidate media, and the examination of advanced waste management technologies. The draft statement describes the commercial radioactive wastes that would have to be managed for very long periods of time from an assumed nuclear generation scenario of 10,000 GWe-yr of power over a 65-year period ending in 2040

  12. 75 FR 22162 - Draft NIJ Duty Holster Retention Standard for Law Enforcement

    Science.gov (United States)

    2010-04-27

    ...In an effort to obtain comments from interested parties, the U.S. Department of Justice, Office of Justice Programs, National Institute of Justice will make available to the general public two draft documents: (1) A draft standard entitled, ``NIJ Duty Holster Retention Standard for Law Enforcement'' and (2) a draft companion document entitled, ``NIJ Duty Holster Retention Certification Program Requirements.'' The opportunity to provide comments on these two documents is open to industry technical representatives, law enforcement agencies and organizations, research, development and scientific communities, and all other stakeholders and interested parties. Those individuals wishing to obtain and provide comments on the draft documents under consideration are directed to the following Web site: http://www.justnet.org.

  13. Draft At-Depth Study Plan for an exploratory shaft facility in salt: Revision 1

    International Nuclear Information System (INIS)

    1988-03-01

    This draft At-Depth Study Plan describes a program of at-depth monitoring and testing in the bedded salt deposits of a candidate high-level nuclear waste repository site in Deaf Smith County, Texas. The test program will be undertaken within an At-Depth Facility (ADF) constructed at the candidate repository horizon. The purpose of the program is to assist with site characterization in support of determination of site suitability for development as a repository and for preparation of licensing documentation, and to provide information in support of repository design and performance assessment evaluation. The program includes a variety of geological, geophysical, geomechanical, thermochemical, and geohydrological monitoring and testing. The program is presented as a series of separate studies concerned with geological, geomechanical, and geohydrological site characterization, and with evaluating the mechanical and hydrological response of the site to construction of the ADF. The various studies, and associated test or monitoring methods, are included. Specific large-scale tests concerned with evaluating the performance of engineered components of the repository system (i.e., rooms, waste package, bulkhead and backfill seals) will be performed in the ADF but are described separately in individual Study Plan. 53 refs., 54 figs., 24 tabs

  14. 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.

  15. 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. 

  16. Numerical and Experimental Study on a Model Draft Tube with Vortex Generators

    Directory of Open Access Journals (Sweden)

    Tian Xiaoqing

    2013-01-01

    Full Text Available A model water turbine draft tube containing vortex generators (VG was studied. Numerical simulations were performed to investigate 55 design variations of the vortex generators in a draft tube. After analyzing the shapes of streamlines and velocity distributions in the tube and comparing static pressure recovery coefficients (SPRC in different design variations, an optimum vortex generator layout, which can raise SPRC of the draft tube by 4.8 percent, was found. To verify the effectiveness of the vortex generator application, a series of experiments were carried out. The results show that by choosing optimal vortex generator parameters, such as the installation type, installation position, blade-to-blade distance, and blade inclination angle, the draft tube equipped vortex generators can effectively raise their SPRC andworking stability.

  17. Design of NPP of new generation being constructed at the Novovoronezh NPP site

    International Nuclear Information System (INIS)

    Afrov, A.; Berkovich, V.; Generalov, V.; Dragunov, Yu.; Krushelnitsky, V.

    1999-01-01

    The design of a new generation NPP is described, underscoring advances in physical attributes and passive safety systems based on experiences with earlier designs at operating NPPs. This paper elaborates on systems for handling and storing radioactive wastes, on refinements in containment measures and on experimental and analytic validation of critical design factors. (author)

  18. Site characterization plan: Conceptual design report: Volume 4, Appendices F-O: Nevada Nuclear Waste Storage Investigations Project

    Energy Technology Data Exchange (ETDEWEB)

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

    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, 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. Volume 4 contains Appendices F to O.

  19. Site characterization plan: Conceptual design report: Volume 4, Appendices F-O: Nevada Nuclear Waste Storage Investigations Project

    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, 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. Volume 4 contains Appendices F to O

  20. ICRPfinder: a fast pattern design algorithm for coding sequences and its application in finding potential restriction enzyme recognition sites

    Directory of Open Access Journals (Sweden)

    Stafford Phillip

    2009-09-01

    Full Text Available Abstract Background Restriction enzymes can produce easily definable segments from DNA sequences by using a variety of cut patterns. There are, however, no software tools that can aid in gene building -- that is, modifying wild-type DNA sequences to express the same wild-type amino acid sequences but with enhanced codons, specific cut sites, unique post-translational modifications, and other engineered-in components for recombinant applications. A fast DNA pattern design algorithm, ICRPfinder, is provided in this paper and applied to find or create potential recognition sites in target coding sequences. Results ICRPfinder is applied to find or create restriction enzyme recognition sites by introducing silent mutations. The algorithm is shown capable of mapping existing cut-sites but importantly it also can generate specified new unique cut-sites within a specified region that are guaranteed not to be present elsewhere in the DNA sequence. Conclusion ICRPfinder is a powerful tool for finding or creating specific DNA patterns in a given target coding sequence. ICRPfinder finds or creates patterns, which can include restriction enzyme recognition sites, without changing the translated protein sequence. ICRPfinder is a browser-based JavaScript application and it can run on any platform, in on-line or off-line mode.

  1. The design and implementation of web mining in web sites security

    Science.gov (United States)

    Li, Jian; Zhang, Guo-Yin; Gu, Guo-Chang; Li, Jian-Li

    2003-06-01

    The backdoor or information leak of Web servers can be detected by using Web Mining techniques on some abnormal Web log and Web application log data. The security of Web servers can be enhanced and the damage of illegal access can be avoided. Firstly, the system for discovering the patterns of information leakages in CGI scripts from Web log data was proposed. Secondly, those patterns for system administrators to modify their codes and enhance their Web site security were provided. The following aspects were described: one is to combine web application log with web log to extract more information, so web data mining could be used to mine web log for discovering the information that firewall and Information Detection System cannot find. Another approach is to propose an operation module of web site to enhance Web site security. In cluster server session, Density-Based Clustering technique is used to reduce resource cost and obtain better efficiency.

  2. 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.

  3. Geochemical investigation of UMTRAP designated site at Salt Lake City, Utah

    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 Salt Lake City, Utah. This is one in a series of site specific geochemical investigations performed on the inactive uranium mill tailings included in the Uranium Mill Tailings Remedial Action 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 were water extracted to remove easily soluble salts and acid extracted to remove carbonates and hydroxides. The water extracts and solid samples were anlyzed for the major and trace elements. The report includes the methods of sampling, sample processing, analysis, and data interpretation. Four major conclusions are: (1) sediments in the ditches and creeks adjacent to the site contain tailings, however, the waters were generally not contaminated; (2) tailings are mixed with the soils within a meter below the tailings in some locations, however, water-soluble contaminants decrease to below background levels within 30 cm below the tailings; (3) there has not been significant acid seepage into the soils below the tailings; and (4) salt crusts on the tailings contain trace elements, with the elements that form chloride complexes having the greatest accumulation

  4. Draft Mission Plan Amendment

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1991-09-01

    The Department of Energy`s Office Civilian Radioactive Waste Management has prepared this document to report plans for the Civilian Radioactive Waste Management Program, whose mission is to manage and dispose of the nation`s spent fuel and high-level radioactive waste in a manner that protects the health and safety of the public and of workers and the quality of the environment. The Congress established this program through the Nuclear Waste Policy Act of 1982. Specifically, the Congress directed us to isolate these wastes in geologic repositories constructed in suitable rock formations deep beneath the surface of the earth. In the Nuclear Waste Policy Amendments Act of 1987, the Congress mandated that only one repository was to be developed at present and that only the Yucca Mountain candidate site in Nevada was to be characterized at this time. The Amendments Act also authorized the construction of a facility for monitored retrievable storage (MRS) and established the Office of the Nuclear Waste Negotiator and the Nuclear Waste Technical Review Board. After a reassessment in 1989, the Secretary of Energy restructured the program, focusing the repository effort scientific evaluations of the Yucca Mountain candidate site, deciding to proceed with the development of an MRS facility, and strengthening the management of the program. 48 refs., 32 figs.

  5. Draft Mission Plan Amendment

    International Nuclear Information System (INIS)

    1991-09-01

    The Department of Energy's Office Civilian Radioactive Waste Management has prepared this document to report plans for the Civilian Radioactive Waste Management Program, whose mission is to manage and dispose of the nation's spent fuel and high-level radioactive waste in a manner that protects the health and safety of the public and of workers and the quality of the environment. The Congress established this program through the Nuclear Waste Policy Act of 1982. Specifically, the Congress directed us to isolate these wastes in geologic repositories constructed in suitable rock formations deep beneath the surface of the earth. In the Nuclear Waste Policy Amendments Act of 1987, the Congress mandated that only one repository was to be developed at present and that only the Yucca Mountain candidate site in Nevada was to be characterized at this time. The Amendments Act also authorized the construction of a facility for monitored retrievable storage (MRS) and established the Office of the Nuclear Waste Negotiator and the Nuclear Waste Technical Review Board. After a reassessment in 1989, the Secretary of Energy restructured the program, focusing the repository effort scientific evaluations of the Yucca Mountain candidate site, deciding to proceed with the development of an MRS facility, and strengthening the management of the program. 48 refs., 32 figs

  6. Design basis of off-site emergency response plans for fuel cycle installations

    International Nuclear Information System (INIS)

    Rzepka, J.P.; Dubiau, Ph.; Jouve, A.C.; Charles, T.; Mercier, J.P.

    1995-01-01

    In France, the term 'off-site emergency response plan' refers to all the arrangements which should be made by the government authorities to protect the population in the event of an accident affecting the installations of the site considered. The outline of the method of defining typical accidents, evaluation of 'source-terms' and health consequences is presented. Two applications to installations from the front-end and from the back-end of the fuel cycle are discussed. (K.A.). 1 tab

  7. Department of Energy Programmatic Spent Nuclear Fuel Management and Idaho National Engineering Laboratory Environmental Restoration and Waste Management Programs Draft Environmental Impact Statement; Volume 1, Appendix F, Nevada Test Site and Oak Ridge Reservation Spent Nuclear Fuel Management Programs

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1994-06-01

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

  8. 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,

  9. Conceptual design of a large heavy water reactor for US siting

    International Nuclear Information System (INIS)

    Shapiro, N.L.; Jesick, J.F.; Molin, A.T.; Daniel, J.A.

    1979-09-01

    Information on the PHWR type reactor is presented concerning design characteristics; fuel management and resource utilization; economic evaluations; safety, licensing, and environmental impact; and commercial introduction

  10. In Brief: Geoengineering draft statement

    Science.gov (United States)

    Showstack, Randy

    2009-04-01

    The American Meteorological Society (AMS) has prepared a draft policy statement on geoengineering the climate system, which the AMS Council is considering for approval. The statement notes, “Geoengineering will not substitute for either aggressive mitigation or proactive adaptation. It could contribute to a comprehensive risk management strategy to slow climate change and alleviate its negative impacts, but the potential for adverse and unintended consequences implies a need for adequate research, appropriate regulation, and transparent consideration.” The statement, if adopted, indicates that AMS recommends enhanced research on the scientific and technological potential for geoengineering the climate system; additional study of the historical, ethical, legal, political, and societal aspects of the geoengineering issues; and the development and analysis of policy options to promote transparency and international cooperation in exploring geoengineering options along with restrictions on reckless efforts to manipulate the climate system. AMS is accepting comments on the draft statement until 23 April. For more information, visit http://ametsoc.org/policy/draftstatements/index.html#draft.

  11. 78 FR 29687 - Ocean Dumping; Atchafalaya-West Ocean Dredged Material Disposal Site Designation

    Science.gov (United States)

    2013-05-21

    ... 228.5 and 40 CFR 228.6(a)). General Selection Criteria 1. The dumping of materials into the ocean will... maintenance material dredged from the ARBC by hydraulic cutterhead pipeline dredging and hopper dredging. If... site. Additionally, several large natural gas pipelines cross the ODMDS-West. Because of the dispersive...

  12. 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.…

  13. Effects of sampling design on age ratios of migrants captured at stopover sites

    Science.gov (United States)

    Jeffrey F. Kelly; Deborah M. Finch

    2000-01-01

    Age classes of migrant songbirds often differ in migration timing. This difference creates the potential for age-ratios recorded at stopover sites to vary with the amount and distribution of sampling effort used. To test for these biases, we sub-sampled migrant capture data from the Middle Rio Grande Valley of New Mexico. We created data sets that reflected the age...

  14. 31 CFR 500.406 - Drafts under irrevocable letters of credit; documentary drafts.

    Science.gov (United States)

    2010-07-01

    ... 31 Money and Finance: Treasury 3 2010-07-01 2010-07-01 false Drafts under irrevocable letters of credit; documentary drafts. 500.406 Section 500.406 Money and Finance: Treasury Regulations Relating to... ASSETS CONTROL REGULATIONS Interpretations § 500.406 Drafts under irrevocable letters of credit...

  15. 31 CFR 515.406 - Drafts under irrevocable letters of credit; documentary drafts.

    Science.gov (United States)

    2010-07-01

    ... 31 Money and Finance: Treasury 3 2010-07-01 2010-07-01 false Drafts under irrevocable letters of credit; documentary drafts. 515.406 Section 515.406 Money and Finance: Treasury Regulations Relating to... CONTROL REGULATIONS Interpretations § 515.406 Drafts under irrevocable letters of credit; documentary...

  16. 75 FR 63519 - Notice of Availability of Draft Environmental Assessment and Draft Finding of No Significant...

    Science.gov (United States)

    2010-10-15

    ... reduced for certain environmental resource areas (i.e., for transportation, public and occupational health... NUCLEAR REGULATORY COMMISSION [NRC-2009-0435] Notice of Availability of Draft Environmental... of Availability of Draft Environmental Assessment and Draft Finding of No Significant Impact; Notice...

  17. 78 FR 64493 - Juneau Hydropower, Inc.; Notice of Subsequent Draft License Application (DLA) and Draft...

    Science.gov (United States)

    2013-10-29

    ... Hydropower, Inc.; Notice of Subsequent Draft License Application (DLA) and Draft Preliminary Draft... Hydropower, Inc. e. Name of Project: Sweetheart Lake Hydroelectric Project. f. Location: At the confluence of..., Business Manager, Juneau Hydropower, Inc., P.O. Box 22775, Juneau, AK 99802; 907-789-2775, email: duff...

  18. 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)

  19. Teaching E-Commerce Web Page Evaluation and Design: A Pilot Study Using Tourism Destination Sites

    Science.gov (United States)

    Susser, Bernard; Ariga, Taeko

    2006-01-01

    This study explores a teaching method for improving business students' skills in e-commerce page evaluation and making Web design majors aware of business content issues through cooperative learning. Two groups of female students at a Japanese university studying either tourism or Web page design were assigned tasks that required cooperation to…

  20. LEGAL DRAFTING IN CROATIA - CASE STUDY

    Directory of Open Access Journals (Sweden)

    Dario Đerđa

    2017-01-01

    Full Text Available This paper highlights the importance of legal drafting and its essential elements, which has not drawn a lot of attention in the Republic of Croatia so far. The paper emphasises the importance of proportionality in the simplicity and legal distinctness of a legal text in the process of drafting for the purpose of its clarity. The paper also presents objective requirements necessary for quality legal drafting, as well as subjective qualities of the drafters. With the purpose of drawing attention to imperfections in the legal drafting in Croatia, some defi ciencies are presented in the process of drafting and amending of the Utility Services Act. The process of drafting and amending of this Act is a good example of the way how legal drafting should not be done. It contains a lot of defi ciencies and failures that are the result of legal drafting mistakes. At the end, authors expect that the adoption of the Uniform methodology and nomotechnical rules for the drafting of acts enacted by Parliament should contribute to the higher quality of legal texts and to their full adjustment to the general requirements of legal certainty and rule of law.