WorldWideScience

Sample records for design description final

  1. TPX: Contractor preliminary design review. Volume 1, Presentation and design description. Final report

    International Nuclear Information System (INIS)

    Hartman, D.; Naumovich; Walstrom, P.; Clarkson, I.; Schultheiss, J.; Burger, A.

    1995-01-01

    This first volume of the five volume set begins with a CPDR overview and then details the PF magnet system, manufacturing R ampersand D, Westinghouse R ampersand D, the central solenoid, the PF 5 ring coil, the PF 6/7 ring coil, quality assurance, and the system design description

  2. Fort Hood Solar Total Energy Project. Volume II. Preliminary design. Part 1. System criteria and design description. Final report

    Energy Technology Data Exchange (ETDEWEB)

    None,

    1979-01-01

    This volume documents the preliminary design developed for the Solar Total Energy System to be installed at Fort Hood, Texas. Current system, subsystem, and component designs are described and additional studies which support selection among significant design alternatives are presented. Overall system requirements which form the system design basis are presented. These include program objectives; performance and output load requirements; industrial, statutory, and regulatory standards; and site interface requirements. Material in this section will continue to be issued separately in the Systems Requirements Document and maintained current through revision throughout future phases of the project. Overall system design and detailed subsystem design descriptions are provided. Consideration of operation and maintenance is reflected in discussion of each subsystem design as well as in an integrated overall discussion. Included are the solar collector subsystem; the thermal storage subsystem, the power conversion sybsystem (including electrical generation and distribution); the heating/cooling and domestic hot water subsystems; overall instrumentation and control; and the STES building and physical plant. The design of several subsystems has progressed beyond the preliminary stage; descriptions for such subsystems are therefore provided in more detail than others to provide complete documentation of the work performed. In some cases, preliminary design parameters require specific verificaton in the definitive design phase and are identified in the text. Subsystem descriptions will continue to be issued and revised separately to maintain accuracy during future phases of the project. (WHK)

  3. Content of system design descriptions

    International Nuclear Information System (INIS)

    1998-10-01

    A System Design Description (SDD) describes the requirements and features of a system. This standard provides guidance on the expected technical content of SDDs. The need for such a standard was recognized during efforts to develop SDDs for safety systems at DOE Hazard Category 2 nonreactor nuclear facilities. Existing guidance related to the corresponding documents in other industries is generally not suitable to meet the needs of DOE nuclear facilities. Across the DOE complex, different contractors have guidance documents, but they vary widely from site to site. While such guidance documents are valuable, no single guidance document has all the attributes that DOE considers important, including a reasonable degree of consistency or standardization. This standard is a consolidation of the best of the existing guidance. This standard has been developed with a technical content and level of detail intended to be most applicable to safety systems at DOE Hazard Category 2 nonreactor nuclear facilities. Notwithstanding that primary intent, this standard is recommended for other systems at such facilities, especially those that are important to achieving the programmatic mission of the facility. In addition, application of this standard should be considered for systems at other facilities, including non-nuclear facilities, on the basis that SDDs may be beneficial and cost-effective

  4. Fusion engineering device design description

    International Nuclear Information System (INIS)

    Flanagan, C.A.; Steiner, D.; Smith, G.E.

    1981-12-01

    The US Magnetic Fusion Engineering Act of 1980 calls for the operation of a Fusion Engineering Device (FED) by 1990. It is the intent of the Act that the FED, in combination with other testing facilities, will establish the engineering feasibility of magnetic fusion energy. During 1981, the Fusion Engineering Design Center (FEDC), under the guidance of a Technical Management Board (TMB), developed a baseline design for the FED. This design is summarized herein

  5. Fusion engineering device design description

    Energy Technology Data Exchange (ETDEWEB)

    Flanagan, C.A.; Steiner, D.; Smith, G.E.

    1981-12-01

    The US Magnetic Fusion Engineering Act of 1980 calls for the operation of a Fusion Engineering Device (FED) by 1990. It is the intent of the Act that the FED, in combination with other testing facilities, will establish the engineering feasibility of magnetic fusion energy. During 1981, the Fusion Engineering Design Center (FEDC), under the guidance of a Technical Management Board (TMB), developed a baseline design for the FED. This design is summarized herein.

  6. Fusion Engineering Device design description

    Energy Technology Data Exchange (ETDEWEB)

    Flanagan, C.A.; Steiner, D.; Smith, G.E.

    1981-12-01

    The US Magnetic Fusion Engineering Act of 1980 calls for the operation of a Fusion Engineering Device (FED) by 1990. It is the intent of the Act that the FED, in combination with other testing facilities, will establish the engineering feasibility of magnetic fusion energy. During 1981, the Fusion Engineering Design Center (FEDC), under the guidance of a Technical Management Board (TMB), developed a baseline design for the FED. This design is summarized herein.

  7. MINIMARS conceptual design: Final report

    Energy Technology Data Exchange (ETDEWEB)

    Lee, J.D. (ed.)

    1986-09-01

    This volume contains the following sections: (1) fueling systems; (2) blanket; (3) alternative blanket concepts; (4) halo scraper/direct converter system study and final conceptual design; (5) heat-transport and power-conversion systems; (6) tritium systems; (7) minimars air detritiation system; (8) appropriate radiological safety design criteria; and (9) cost estimate. (MOW)

  8. MINIMARS conceptual design: Final report

    International Nuclear Information System (INIS)

    Lee, J.D.

    1986-09-01

    This volume contains the following sections: (1) fueling systems; (2) blanket; (3) alternative blanket concepts; (4) halo scraper/direct converter system study and final conceptual design; (5) heat-transport and power-conversion systems; (6) tritium systems; (7) minimars air detritiation system; (8) appropriate radiological safety design criteria; and (9) cost estimate

  9. Reference Design Description for a Geologic Repository

    Energy Technology Data Exchange (ETDEWEB)

    NA

    2000-10-07

    One of the current major national environmental problems is the safe disposal of large quantities of spent nuclear fuel and high-level radioactive waste materials, which are rapidly accumulating throughout the country. These radioactive byproducts are generated as the result of national defense activities and from the generation of electricity by commercial nuclear power plants. At present, spent nuclear fuel is accumulating at over 70 power plant sites distributed throughout 33 states. The safe disposal of these high-level radioactive materials at a central disposal facility is a high national priority. This Reference Design Description explains the current design for a potential geologic repository that may be located at Yucca Mountain in Nevada for the disposal of spent nuclear fuel and high-level radioactive waste materials. This document describes a possible design for the three fundamental parts of a repository: a surface facility, subsurface repository, and waste packaging. It also presents the current conceptual design of the key engineering systems for the final four phases of repository processes: operations, monitoring, closure, and postclosure. In accordance with current law, this design does not include an interim storage option. In addition, this Reference Design Description reviews the expected long-term performance of the potential repository. It describes the natural barrier system which, together with the engineered systems, achieves the repository objectives. This design will protect the public and the environment by allowing the safe disposal of radioactive waste received from government-owned custodial spent fuel sites, high-level radioactive waste sites, and commercial power reactor sites. All design elements meet or exceed applicable regulations governing the disposal of high-level radioactive waste. The design will provide safe disposal of waste materials for at least a 10,000 year period. During this time interval, natural radioactive decay

  10. Reference Design Description for a Geologic Repository

    International Nuclear Information System (INIS)

    2000-01-01

    One of the current major national environmental problems is the safe disposal of large quantities of spent nuclear fuel and high-level radioactive waste materials, which are rapidly accumulating throughout the country. These radioactive byproducts are generated as the result of national defense activities and from the generation of electricity by commercial nuclear power plants. At present, spent nuclear fuel is accumulating at over 70 power plant sites distributed throughout 33 states. The safe disposal of these high-level radioactive materials at a central disposal facility is a high national priority. This Reference Design Description explains the current design for a potential geologic repository that may be located at Yucca Mountain in Nevada for the disposal of spent nuclear fuel and high-level radioactive waste materials. This document describes a possible design for the three fundamental parts of a repository: a surface facility, subsurface repository, and waste packaging. It also presents the current conceptual design of the key engineering systems for the final four phases of repository processes: operations, monitoring, closure, and postclosure. In accordance with current law, this design does not include an interim storage option. In addition, this Reference Design Description reviews the expected long-term performance of the potential repository. It describes the natural barrier system which, together with the engineered systems, achieves the repository objectives. This design will protect the public and the environment by allowing the safe disposal of radioactive waste received from government-owned custodial spent fuel sites, high-level radioactive waste sites, and commercial power reactor sites. All design elements meet or exceed applicable regulations governing the disposal of high-level radioactive waste. The design will provide safe disposal of waste materials for at least a 10,000 year period. During this time interval, natural radioactive decay

  11. System Design Description PFP Thermal Stabilization

    International Nuclear Information System (INIS)

    RISENMAY, H.R.

    2000-01-01

    The purpose of this document is to provide a system design description (SDD) and design basis for the Plutonium Finishing Plant (PFP) Thermal Stabilization project. The chief objective of the SDD is to document the Structures, Systems, and Components (SSCs) that establish and maintain the facility Safety Envelope necessary for normal safe operation of the facility; as identified in the FSAR, the OSRs, and Safety Assessment Documents (SADs). This safety equipment documentation should satisfy guidelines for the SDD given in WHC-SD-CP-TI-18 1, Criteria for Identification and Control of Equipment Necessary for Preservation of the Safety Envelope and Safe Operation of PFP. The basis for operational, alarm response, maintenance, and surveillance procedures are also identified and justified in this document. This document and its appendices address the following elements of the PFP Thermal Stabilization project: Functional and design requirements; Design description; Safety Envelope Analysis; Safety Equipment Class; and Operational, maintenance and surveillance procedures

  12. Advanced Design Studies. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Steiner, Don [Rensselaer Polytechnic Institute, Troy, NY (United States)

    2012-12-01

    The ARIES-CS project was a multi-year multi-institutional project to assess the feasibility of a compact stellarator as a fusion power plant. The work herein describes efforts to help design one aspect of the device, the divertor, which is responsible for the removal of particle and heat flux from the system, acting as the first point of contact between the magnetically confined hot plasma and the outside world. Specifically, its location and topology are explored, extending previous work on the sub ject. An optimized design is determined for the thermal particle flux using a suite of 3D stellarator design codes which trace magnetic field lines from just inside the confined plasma edge to their strike points on divertor plates. These divertor plates are specified with a newly developed plate design code. It is found that a satisfactory thermal design exists which maintains the plate temperature and heat load distribution below tolerable engineering limits. The design is unique, including a toroidal taper on the outboard plates which was found to be important to our results. The maximum thermal heat flux for the final design was 3.61 M W/m2 and the maximum peaking factor was 10.3, below prescribed limits of 10 M W/m2 and 15.6, respectively. The median length of field lines reaching the plates is about 250 m and their average angle of inclination to the surface is 2 deg. Finally, an analysis of the fast alphas, resulting from fusion in the core, which escape the plasma was performed. A method is developed for obtaining the mapping from magnetic coordinates to real-space coordinates for the ARIES-CS. This allows the alpha exit locations to be identified in real space for the first time. These were then traced using the field line algorithm as well as a guiding center routine accounting for their mass, charge, and specific direction and energy. Results show that the current design is inadequate for accommodating the alpha heat flux, capturing at most 1/3 of lost alphas

  13. Microprocessor Design Using Hardware Description Language

    Science.gov (United States)

    Mita, Rosario; Palumbo, Gaetano

    2008-01-01

    The following paper has been conceived to deal with the contents of some lectures aimed at enhancing courses on digital electronic, microelectronic or VLSI systems. Those lectures show how to use a hardware description language (HDL), such as the VHDL, to specify, design and verify a custom microprocessor. The general goal of this work is to teach…

  14. Network architecture functional description and design

    Energy Technology Data Exchange (ETDEWEB)

    Stans, L.; Bencoe, M.; Brown, D.; Kelly, S.; Pierson, L.; Schaldach, C.

    1989-05-25

    This report provides a top level functional description and design for the development and implementation of the central network to support the next generation of SNL, Albuquerque supercomputer in a UNIX{reg sign} environment. It describes the network functions and provides an architecture and topology.

  15. The LSST Dome final design

    Science.gov (United States)

    DeVries, J.; Neill, D. R.; Barr, J.; De Lorenzi, Simone; Marchiori, Gianpietro

    2016-07-01

    The Large Synoptic Survey Telescope (LSST) is a large (8.4 meter) wide-field (3.5 degree) survey telescope, which will be located on the Cerro Pachón summit in Chile 1. As a result of the Telescope wide field of view, the optical system is unusually susceptible to stray light 2. In addition, balancing the effect of wind induced telescope vibrations with Dome seeing is crucial. The rotating enclosure system (Dome) includes a moving wind screen and light baffle system. All of the Dome vents include hinged light baffles, which provide exceptional Dome flushing, stray light attenuation, and allows for vent maintenance access from inside the Dome. The wind screen also functions as a light screen, and helps define a clear optical aperture for the Telescope. The Dome must operate continuously without rotational travel limits to accommodate the Telescope cadence and travel. Consequently, the Azimuth drives are located on the fixed lower enclosure to accommodate glycol water cooling without the need for a utility cable wrap. An air duct system aligns when the Dome is in its parked position, and this provides air cooling for temperature conditioning of the Dome during the daytime. A bridge crane and a series of ladders, stairs and platforms provide for the inspection, maintenance and repair of all of the Dome mechanical systems. The contract to build the Dome was awarded to European Industrial Engineering in Mestre, Italy in May 2015. In this paper, we present the final design of this telescope and site sub-system.

  16. COG Software Architecture Design Description Document

    Energy Technology Data Exchange (ETDEWEB)

    Buck, R M; Lent, E M

    2009-09-21

    This COG Software Architecture Design Description Document describes the organization and functionality of the COG Multiparticle Monte Carlo Transport Code for radiation shielding and criticality calculations, at a level of detail suitable for guiding a new code developer in the maintenance and enhancement of COG. The intended audience also includes managers and scientists and engineers who wish to have a general knowledge of how the code works. This Document is not intended for end-users. This document covers the software implemented in the standard COG Version 10, as released through RSICC and IAEA. Software resources provided by other institutions will not be covered. This document presents the routines grouped by modules and in the order of the three processing phases. Some routines are used in multiple phases. The routine description is presented once - the first time the routine is referenced. Since this is presented at the level of detail for guiding a new code developer, only the routines invoked by another routine that are significant for the processing phase that is being detailed are presented. An index to all routines detailed is included. Tables for the primary data structures are also presented.

  17. MINIMARS conceptual design: Final report

    International Nuclear Information System (INIS)

    Lee, J.D.

    1986-09-01

    This volume of the conceptual design report contains detailed information on the following: (1) plasma engineering, (2) tandem mirror optimization code, (3) configuration, (4) assembly and maintenance, (5) availability, (6) site and facilities, (7) magnet design, (8) end-cell shielding, (9) drift pumping system, (10) rf systems, (11) negative-ion neutral beam injection system, (12) sloshing-ion beamline, and (13) power balance and electrical systems

  18. LANL environmental restoration site ranking system: System description. Final report

    International Nuclear Information System (INIS)

    Merkhofer, L.; Kann, A.; Voth, M.

    1992-01-01

    The basic structure of the LANL Environmental Restoration (ER) Site Ranking System and its use are described in this document. A related document, Instructions for Generating Inputs for the LANL ER Site Ranking System, contains detailed descriptions of the methods by which necessary inputs for the system will be generated. LANL has long recognized the need to provide a consistent basis for comparing the risks and other adverse consequences associated with the various waste problems at the Lab. The LANL ER Site Ranking System is being developed to help address this need. The specific purpose of the system is to help improve, defend, and explain prioritization decisions at the Potential Release Site (PRS) and Operable Unit (OU) level. The precise relationship of the Site Ranking System to the planning and overall budget processes is yet to be determined, as the system is still evolving. Generally speaking, the Site Ranking System will be used as a decision aid. That is, the system will be used to aid in the planning and budgetary decision-making process. It will never be used alone to make decisions. Like all models, the system can provide only a partial and approximate accounting of the factors important to budget and planning decisions. Decision makers at LANL will have to consider factors outside of the formal system when making final choices. Some of these other factors are regulatory requirements, DOE policy, and public concern. The main value of the site ranking system, therefore, is not the precise numbers it generates, but rather the general insights it provides

  19. LANL environmental restoration site ranking system: System description. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Merkhofer, L.; Kann, A.; Voth, M. [Applied Decision Analysis, Inc., Menlo Park, CA (United States)

    1992-10-13

    The basic structure of the LANL Environmental Restoration (ER) Site Ranking System and its use are described in this document. A related document, Instructions for Generating Inputs for the LANL ER Site Ranking System, contains detailed descriptions of the methods by which necessary inputs for the system will be generated. LANL has long recognized the need to provide a consistent basis for comparing the risks and other adverse consequences associated with the various waste problems at the Lab. The LANL ER Site Ranking System is being developed to help address this need. The specific purpose of the system is to help improve, defend, and explain prioritization decisions at the Potential Release Site (PRS) and Operable Unit (OU) level. The precise relationship of the Site Ranking System to the planning and overall budget processes is yet to be determined, as the system is still evolving. Generally speaking, the Site Ranking System will be used as a decision aid. That is, the system will be used to aid in the planning and budgetary decision-making process. It will never be used alone to make decisions. Like all models, the system can provide only a partial and approximate accounting of the factors important to budget and planning decisions. Decision makers at LANL will have to consider factors outside of the formal system when making final choices. Some of these other factors are regulatory requirements, DOE policy, and public concern. The main value of the site ranking system, therefore, is not the precise numbers it generates, but rather the general insights it provides.

  20. Plutonium Protection System (PPS). Volume 2. Hardware description. Final report

    International Nuclear Information System (INIS)

    Miyoshi, D.S.

    1979-05-01

    The Plutonium Protection System (PPS) is an integrated safeguards system developed by Sandia Laboratories for the Department of Energy, Office of Safeguards and Security. The system is designed to demonstrate and test concepts for the improved safeguarding of plutonium. Volume 2 of the PPS final report describes the hardware elements of the system. The major areas containing hardware elements are the vault, where plutonium is stored, the packaging room, where plutonium is packaged into Container Modules, the Security Operations Center, which controls movement of personnel, the Material Accountability Center, which maintains the system data base, and the Material Operations Center, which monitors the operating procedures in the system. References are made to documents in which details of the hardware items can be found

  1. Optimal Conventional and Semi-Natural Treatments for the Upper Yakima Spring Chinook Salmon Supplementation Project; Treatment Definitions and Descriptions and Biological Specifications for Facility Design, 1995-1999 Final Report.

    Energy Technology Data Exchange (ETDEWEB)

    Hager, Robert C. (Hatchery Operations Consulting); Costello, Ronald J. (Mobrand Biometrics, Inc., Vashon Island, WA)

    1999-10-01

    This report describes the Yakima Fisheries Project facilities (Cle Elum Hatchery and acclimation satellites) which provide the mechanism to conduct state-of-the-art research for addressing questions about spring chinook supplementation strategies. The definition, descriptions, and specifications for the Yakima spring chinook supplementation program permit evaluation of alternative fish culture techniques that should yield improved methods and procedures to produce wild-like fish with higher survival that can be used to rebuild depleted spring chinook stocks of the Columbia River Basin. The definition and description of three experimental treatments, Optimal Conventional (OCT), Semi-Natural (SNT), Limited Semi-Natural (LSNT), and the biological specifications for facilities have been completed for the upper Yakima spring chinook salmon stock of the Yakima Fisheries Project. The task was performed by the Biological Specifications Work Group (BSWG) represented by Yakama Indian Nation, Washington Department of Fish and Wildlife, National Marine Fisheries Service, and Bonneville Power Administration. The control and experimental variables of the experimental treatments (OCT, SNT, and LSNT) are described in sufficient detail to assure that the fish culture facilities will be designed and operated as a production scale laboratory to produce and test supplemented upper Yakima spring chinook salmon. Product specifications of the treatment groups are proposed to serve as the generic templates for developing greater specificity for measurements of product attributes. These product specifications will be used to monitor and evaluate treatment effects, with respect to the biological response variables (post release survival, long-term fitness, reproductive success and ecological interactions).

  2. Optimal Conventional and Semi-Natural Treatments for the Upper Yakima Spring Chinook Salmon Supplementation Project, Treatment Definitions and Descriptions, and Biological Specifications for Facility Design, Final Report 1999

    International Nuclear Information System (INIS)

    Hager, Robert C.; Costello, Ronald J.

    1999-01-01

    This report describes the Yakima Fisheries Project facilities (Cle Elum Hatchery and acclimation satellites) which provide the mechanism to conduct state-of-the-art research for addressing questions about spring chinook supplementation strategies. The definition, descriptions, and specifications for the Yakima spring chinook supplementation program permit evaluation of alternative fish culture techniques that should yield improved methods and procedures to produce wild-like fish with higher survival that can be used to rebuild depleted spring chinook stocks of the Columbia River Basin. The definition and description of three experimental treatments, Optimal Conventional (OCT), Semi-Natural (SNT), Limited Semi-Natural (LSNT), and the biological specifications for facilities have been completed for the upper Yakima spring chinook salmon stock of the Yakima Fisheries Project. The task was performed by the Biological Specifications Work Group (BSWG) represented by Yakama Indian Nation, Washington Department of Fish and Wildlife, National Marine Fisheries Service, and Bonneville Power Administration. The control and experimental variables of the experimental treatments (OCT, SNT, and LSNT) are described in sufficient detail to assure that the fish culture facilities will be designed and operated as a production scale laboratory to produce and test supplemented upper Yakima spring chinook salmon. Product specifications of the treatment groups are proposed to serve as the generic templates for developing greater specificity for measurements of product attributes. These product specifications will be used to monitor and evaluate treatment effects, with respect to the biological response variables (post release survival, long-term fitness, reproductive success and ecological interactions)

  3. Final design of ITER thermal shield manifold

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Kyung-Kyu [Mecha T& S, Jinju-si 52811 (Korea, Republic of); Noh, Chang Hyun, E-mail: chnoh@nfri.re.kr [National Fusion Research Institute, Daejeon 34133 (Korea, Republic of); Kim, Yun-Kyu; Park, Sungwoo [Mecha T& S, Jinju-si 52811 (Korea, Republic of); Nam, Kwanwoo [National Fusion Research Institute, Daejeon 34133 (Korea, Republic of); Chung, Wooho [Mecha T& S, Jinju-si 52811 (Korea, Republic of); Kang, Dongkwon; Kang, Kyung-O. [National Fusion Research Institute, Daejeon 34133 (Korea, Republic of); Park, Sungmun [SFA Engineering Corporation, Hwaseong-si 10060 (Korea, Republic of); Bae, Jing Do [Korea Marine Equipment Research Institute, Busan 49111 (Korea, Republic of)

    2016-11-01

    Highlights: • Engineering design of thermal shield manifold is finalized. • Pipe routing, support design and flow balance are verified by analysis. • Mock-ups are fabricated to verify the design. - Abstract: The ITER thermal shield is actively cooled by 80 K pressurized helium gas. The helium coolant flows from the cold valve box to the cooling tubes on the TS panels via manifold piping. This paper describes the final design of thermal shield manifold. Pipe design to accommodate the thermal contraction considering interface with adjacent components and detailed design of support structure are presented. R&D for the pipe branch connection is carried out to find a feasible manufacturing method. Global structural behavior and structural integrity of the manifold including pipe supports are investigated by a finite element analysis based on ASME B31.3 code. Flow analyses are performed to check the flow distribution.

  4. Tokamak Physics EXperiment (TPX): Toroidal field magnet design, development and manufacture. SDRL 15, System design description. Volume 1

    International Nuclear Information System (INIS)

    1995-01-01

    This System Design Description, prepared in accordance with the TPX Project Management Plan provides a summary or TF Magnet System design features at the conclusion of Phase I, Preliminary Design and Manufacturing Research. The document includes the analytical and experimental bases for the design, and plans for implementation in final design, manufacturing, test, and magnet integration into the tokamak. Requirements for operation and maintenance are outlined, and references to sources of additional information are provided

  5. Tokamak Physics EXperiment (TPX): Toroidal field magnet design, development and manufacture. SDRL 15, System design description. Volume 1

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-09-22

    This System Design Description, prepared in accordance with the TPX Project Management Plan provides a summary or TF Magnet System design features at the conclusion of Phase I, Preliminary Design and Manufacturing Research. The document includes the analytical and experimental bases for the design, and plans for implementation in final design, manufacturing, test, and magnet integration into the tokamak. Requirements for operation and maintenance are outlined, and references to sources of additional information are provided.

  6. Computer Programs for LB/TS Test Design: Technical Description, Usage Instructions and Source Code Listings

    Science.gov (United States)

    1995-09-01

    this subprogram defines the relationship bet~een the ·actuator position c louver angle and open area for the end vend of the LB /TS RWE c c...ARMY RESEARCH UBORA TORY Computer Programs for LB {fS Test Design: Technical Description, Usage Instructions and Source Code Listings ARL-MR-260...COVERED Final, Oct 94 - May 95 4. TITLE AND SUBTITLE 5. FUNDING NUMBERS Computer Programs for LB /TS Test Design: Technical Description, Usage

  7. KBS-3H design description 2007

    International Nuclear Information System (INIS)

    Autio, J.; Hagros, A.; Johansson, E.

    2008-12-01

    The presented KBS-3H design work was carried out in KBS-3H project in 2004 - 2007, which was a joint project between Svensk Kaernbraenslehantering AB (SKB) in Sweden and Posiva Oy in Finland. The overall objectives of the project phase were to demonstrate that the horizontal deposition alternative is technically feasible and to demonstrate that it fulfils the same long-term safety requirements as the reference design KBS-3V. The KBS-3H design is a variant of the KBS-3 method and an alternative to the KBS-3V design. In the KBS-3H design alternative, multiple canisters containing spent fuel are emplaced at about 420 m depth in bedrock in parallel, 100 - 300 m long, approximately horizontal deposition drifts whereas the KBS-3V design calls for vertical emplacement of the canisters in individual deposition holes. As a result of design work, the two previous KBS-3H repository candidate designs called Basic Design (BD) and design based on Drainage, Artificial Watering and air Evacuation (DAWE) were developed on two different functional principles. At later phase of the project the BD alternative was found not to be robust in drifts with several large inflows and therefore a third less mature alternative called Semi Tight Compartments design (STC) was introduced to function in these conditions. Significant effort was made in the project to resolve studies and testing the functional uncertainties related to buffer behaviour which could e.g. cause piping, erosion, displacement and rupture of distance blocks. Major work was also carried for the design of supercontainer, development of large-scale post-grouting device, Mega-Packer, for grouting of rock, excavation of deposition drifts, layout design and evaluation of residual materials. This report also summarizes and highlights differences between different design alternatives and gives reasoning why DAWE design alternative is seen as the most interesting for future development together with novel less mature STC

  8. ITER isotope separation system conceptual design description

    International Nuclear Information System (INIS)

    Busigin, A.; Sood, S.K.; Kveton, O.K.; Dinner, P.J.; Murdoch, D.K.; Leger, D.

    1989-05-01

    This paper presents integrated Isotope Separation System (ISS) designs for ITER based on requirements for plasma exhaust processing, neutral beam injection deuterium cleanup, pellet injector propellant detritiation, waste water detritiation, and breeding blanket detritiation. Specific ISS designs are developed for a machine with an aqueous lithium salt blanket (ALSB) and a machine with a solid ceramic breeding blanket (SBB). The differences in the ISS designs arising from the different blanket concepts are highlighted. It is found that the ISS designs for the two blanket concepts considered are very similar, with the only major difference being the requirements for an additional large water distillation column for ALSB water detritiation. The fact that the cryogenic distillation portions of the two ISS designs are almost identical, indicates that the cryogenic distillation cascade design is very flexible and can readily accommodate significant changes in processing requirements without requiring significant redesign. The front-end process for extraction of tritium from the ALSB is based on flash evaporation to separate the blanket water from the dissolved Li salt, with the tritiated water then being fed to the ISS for detritiation. This technology is considered to be relatively well understood in comparison to front-end processes for SBB detritiation. In the design of the cryogenic distillation portion of the ISS, it was found that the tritium inventory could be very large (> 600g) unless specific design measures were taken to reduce it. In the designs which are presented, the tritium inventory has been reduced to about 180g, which is less than the ITER single-failure release limit of 200g. Further design optimization and isolation of components is expected to reduce the inventory further

  9. Sodium immersible high temperature microphone design description

    International Nuclear Information System (INIS)

    Gavin, A.P.; Anderson, T.T.; Janicek, J.J.

    1975-02-01

    Argonne National Laboratory has developed a rugged high-temperature (HT) microphone for use as a sodium-immersed acoustic monitor in Liquid Metal Fast Breeder Reactors (LMFBRs). Microphones of this design have been extensively tested in room temperature water, in air up to 1200 0 F, and in sodium up to 1200 0 F. They have been successfully installed and employed as acoustic monitors in several operating liquid metal systems. The design, construction sequence, calibration, and testing of these microphones are described. 6 references. (U.S.)

  10. Description, Modelling and Design of Production Systems

    DEFF Research Database (Denmark)

    Jacobsen, Peter; Rudolph, Carsten

    1997-01-01

    Design of production systems are rarely an activity in which decision makers in most production companies have much experience. In future, this activity is to be more recurrent due to more and more frequent changes in the production task. Consequently, the decision makers are in need of better ma...

  11. Granular Data Description: Designing Ellipsoidal Information Granules.

    Science.gov (United States)

    Zhu, Xiubin; Pedrycz, Witold; Li, Zhiwu

    2017-12-01

    Granular computing (GrC) has emerged as a unified conceptual and processing framework. Information granules are fundamental constructs that permeate concepts and models of GrC. This paper is concerned with a design of a collection of meaningful, easily interpretable ellipsoidal information granules with the use of the principle of justifiable granularity by taking into consideration reconstruction abilities of the designed information granules. The principle of justifiable granularity supports designing of information granules based on numeric or granular evidence, and aims to achieve a compromise between justifiability and specificity of the information granules to be constructed. A two-stage development strategy behind the construction of justifiable information granules is considered. First, a collection of numeric prototypes is determined with the use of fuzzy clustering. Second, the lengths of the semi-axes of ellipsoidal information granules to be formed around such prototypes are optimized. Two optimization criteria are introduced and studied. Experimental studies involving synthetic data set and data sets coming from the machine learning repository are reported.

  12. Plasma source by microwaves: design description

    International Nuclear Information System (INIS)

    Camps, E.; Olea, O.; Andrade, R.; Anguiano, G.

    1992-03-01

    The design of a device for the formation of a plasma with densities of the order of 10 12 cm - 3 and low temperatures (T e ∼ 40 eV) is described. For such purpose it was carried out in the device a microwave discharge (f o = 2.45 GHz) in a resonator of high Q factor, immersed in a static external magnetic field. The device worked in the regime ω ce ≤ ω o /2 (ω ce - cyclotron frequency of the electrons, (ω o = 2 π f o ) where is possible the excitement of non lineal phenomena of waves transformation. (Author)

  13. System Design Description PFP Thermal Stabilization

    Energy Technology Data Exchange (ETDEWEB)

    RISENMAY, H.R.

    2000-01-27

    DOE has authorized in their letter of August 2, 1999, the operation of these three furnaces, quote ''Operation of the three uncompleted muffle furnaces (No.3, No.4, and No.5) located in Room 235B is authorized, using the same feed charge limits as the two existing furnaces (No.1, and No.2) located in Room 230C,''. The above statement incorrectly refers to Room 230C whereas the correct location is Room 230A. The current effort is directed to initiate the operation and to complete the design activities DOE authorized the operation of the furnaces based on their Safety Evaluation Report (SER). Based on analogy and the principle of similarity, the risks and consequences of accidents both onsite and offsite due to operation of three furnaces are not significantly larger than those already evaluated with the two operating furnaces. Thermal stabilization operations and the material of feed for furnaces in Glovebox HA-21 I are essentially the same as those currently being stabilized in furnaces in Glovebox HC-21 C. Therefore the accident analysis has utilized identical accident scenarios in evaluation and no additional failure modes are introduced by HA-21 I muffle furnace operation that would enhance the consequences of accidents. Authorization Basis documents as referenced below (PFP FSAR and DOE Letter authorizing the operation) appear to contradict each other, i.e. one allows and authorizes the operation and the other imposes the restriction on the operation. The purpose of the PFP FSAR restrictions was to review thoroughly the design and installation of three furnaces and perform acceptance testing before approving the startup for operation. With the experience of operating the two furnaces in Glovebox HC-21C, and the knowledge of risks and hazards the facility operation, the plant is adequately prepared to operate these additional furnaces. ECN 653595 has been prepared to incorporate operation of the muffle furnaces in Glovebox HA-21 I into the

  14. Preparation of plant and system design description documents

    International Nuclear Information System (INIS)

    1989-01-01

    This standard prescribes the purpose, scope, organization, and content of plant design requirements (PDR) documents and system design descriptions (SDDs), to provide a unified approach to their preparation and use by a project as the principal means to establish the plant design requirements and to establish, describe, and control the individual system designs from conception and throughout the lifetime of the plant. The Electric Power Research Institute's Advanced Light Water Reactor (LWR) Requirements Document should be considered for LWR plants

  15. System design description for master equipment list, phase I

    International Nuclear Information System (INIS)

    Sandoval, J.D.

    1997-01-01

    This System Design Description (SDD) is for the Master Equipment List Phase I (MEL). It has been prepared following the WI-IC-CM-3-10, ''Software Practices,'' (Ref. 6). This SDD describes the internal design for implementation of the MEL Phase I

  16. Description of sampling designs using a comprehensive data structure

    Science.gov (United States)

    John C. Byrne; Albert R. Stage

    1988-01-01

    Maintaining permanent plot data with different sampling designs over long periods within an organization, as well as sharing such information between organizations, requires that common standards be used. A data structure for the description of the sampling design within a stand is proposed. It is based on the definition of subpopulations of trees sampled, the rules...

  17. Design review report for multiport riser final design review

    Energy Technology Data Exchange (ETDEWEB)

    McWethy, L.M.; Sheen, E.M.

    1994-05-01

    This design review examined the design documents contained in a notebook prepared for the final design review of the multiport riser assembly. This assembly will support the Hydrogen Mitigation Test program for mitigation of safety issues for Hanford Waste Tank 241-SY-101. The purpose of the Multiport Riser is to provide multiple access ports of several diameters in a single 42 inch riser for simultaneous access of test and support equipment. The notebook was titled: {open_quotes}Multiport Riser Final Design Review.{close_quotes} The review was conducted using a database comment registration system whereby the reviewer comments were entered into the database and each comment was given a unique identifier. During the review, each comment was referred to by its identifier. Changes to comments, responses, and actions needed were made with the agreement of the committee and the reviewers at the formal design review meeting held March 1, 1994. When the structural analyses were available, they were distributed for review which allowed closure of all design review comments. Approval of the design was achieved and supporting documents are included in this report.

  18. A coherent description of the process of design

    DEFF Research Database (Denmark)

    Hertz, Kristian Dahl

    1992-01-01

    , and others. Doing so, a corresponding number of philosophical problems are solved, and the description becomes a coherent theory. The author has shown that it is possible to make a computer program for conceptual modelling based on the theory presented, and the principles of a CAD system including......A description of the creative design process is given based on Empiricism and using the theory of sets on conceptual and subconscious representations of the human mind. Definitions that are more precise are given of a number of common concepts such as association, synthesis, culture, creation, art...... the program and supporting the creative process of the designer is described....

  19. Control of hydrogen sulfide emission from geothermal power plants. Volume III. Final report: demonstration plant equipment descriptions, test plan, and operating instructions

    Energy Technology Data Exchange (ETDEWEB)

    Brown, F.C.; Harvey, W.W.; Warren, R.B.

    1977-01-01

    The elements of the final, detailed design of the demonstration plant for the copper sulfate process for the removal of hydrogen sulfide from geothermal steam are summarized. Descriptions are given of all items of equipment in sufficient detail that they can serve as purchase specifications. The process and mechanical design criteria which were used to develop the specifications, and the process descriptions and material and energy balance bases to which the design criteria were applied are included. (MHR)

  20. Waste receiving and processing plant control system; system design description

    International Nuclear Information System (INIS)

    LANE, M.P.

    1999-01-01

    The Plant Control System (PCS) is a heterogeneous computer system composed of numerous sub-systems. The PCS represents every major computer system that is used to support operation of the Waste Receiving and Processing (WRAP) facility. This document, the System Design Description (PCS SDD), includes several chapters and appendices. Each chapter is devoted to a separate PCS sub-system. Typically, each chapter includes an overview description of the system, a list of associated documents related to operation of that system, and a detailed description of relevant system features. Each appendice provides configuration information for selected PCS sub-systems. The appendices are designed as separate sections to assist in maintaining this document due to frequent changes in system configurations. This document is intended to serve as the primary reference for configuration of PCS computer systems. The use of this document is further described in the WRAP System Configuration Management Plan, WMH-350, Section 4.1

  1. Waste receiving and processing plant control system; system design description

    Energy Technology Data Exchange (ETDEWEB)

    LANE, M.P.

    1999-02-24

    The Plant Control System (PCS) is a heterogeneous computer system composed of numerous sub-systems. The PCS represents every major computer system that is used to support operation of the Waste Receiving and Processing (WRAP) facility. This document, the System Design Description (PCS SDD), includes several chapters and appendices. Each chapter is devoted to a separate PCS sub-system. Typically, each chapter includes an overview description of the system, a list of associated documents related to operation of that system, and a detailed description of relevant system features. Each appendice provides configuration information for selected PCS sub-systems. The appendices are designed as separate sections to assist in maintaining this document due to frequent changes in system configurations. This document is intended to serve as the primary reference for configuration of PCS computer systems. The use of this document is further described in the WRAP System Configuration Management Plan, WMH-350, Section 4.1.

  2. BWR consolidation system final design report

    International Nuclear Information System (INIS)

    Garner, G.L.; Kelly, M.J.; Larsen, W.R.

    1993-05-01

    Because of delays in the opening of a permanent geologic repository to accept spent fuel from nuclear reactor plants, several utilities are seeking additional off-site storage to avert premature shutdown. Fuel rod consolidation is a proven, viable option for pressurized water reactor (PWR) plants, but until now, no consolidation system addressed boiling water reactor (BWR) spent-fuel assemblies.The purpose of this project, jointly funded by the Empire State Electric Energy Research Company (ESEERCO) and the Electric Power Research Institute (EPRI), is to develop a system for consolidating BWR spent fuel assemblies. This design will provide more efficient storage in reactor spent-fuel pools. The design goal is a 2:1 consolidation of the fuel rods and a minimum 10:1 compaction of the non-fuel bearing components. in addition, the consolidation system must be operationally compatible with BWR reactor plants and be economically viable with other forms of supplementary on-site storage. The work began in Lynchburg, Virginia on May 6, 1991 and concluded on September 30, 1992 with the delivery of the final report. The design achieves all of the project goals. Furthermore, consolidation of BWR spent-fuel assemblies is feasible, compatible with reactor plant operations and potentially the lowest cost option for a utility seeking to add oil-site storage capacity

  3. LTA Physics Design: Description of All MOX Pin LTA Design

    International Nuclear Information System (INIS)

    Pavlovichev, A.M.

    2001-01-01

    In this document issued according to Work Release 02.P.99-1b the results of neutronics studies of > MOX LTA design are presented. The parametric studies of infinite MOX-UOX grids, MOX-UOX core fragments and of VVER-1000 core with 3 MOX LTAs are performed. The neutronics parameters of MOX fueled core have been performed for the chosen design MOX LTA using the Russian 3D code BIPR-7A and 2D code PERMAK-A with the constants prepared by the cell spectrum code TVS-M

  4. CDMS: CAD data set system design description. Revision 1

    International Nuclear Information System (INIS)

    Gray, E.L.

    1994-01-01

    This document is intended to formalize the program design of the CAD Data Set Management System (CDMS) and to be the vehicle to communicate the design to the Engineering, Design Services, and Configuration Management organizations and the WHC IRM Analysts/Programmers. The SDD shows how the software system will be structured to satisfy the requirements identified in the WHC-SD-GN-CSRS-30005 CDMS Software Requirement Specification (SRS). It is a description of the software structure, software components, interfaces, and data that make up the CDMS System. The design descriptions contained within this document will describe in detail the software product that will be developed to assist the aforementioned organizations for the express purpose of managing CAD data sets associated with released drawings, replacing the existing locally developed system and laying the foundation for automating the configuration management

  5. Los Angeles-Gateway Freight Advanced Traveler Information System : final system design and architecture for FRATIS prototype.

    Science.gov (United States)

    2013-05-01

    This Final Architecture and Design report has been prepared to describe the structure and design of all the system : components for the LA-Gateway FRATIS Demonstration Project. More specifically, this document provides: : Detailed descriptions of...

  6. Exterior insulating shutter final prototype design. Final report, Phase II

    Energy Technology Data Exchange (ETDEWEB)

    Dike, G.A.; Kinney, L.F.

    1982-12-01

    The final prototype shutter described uses sliding panels composed of inch-thick thermax sandwiched between 60 mil thick ultraviolet-resistant plastic on the outside, and 20 mil stryrene on the inside. The shuter system was shown to have an effective R-value of 6 using ASHRAE procedures to convert from still air conditions to 15 mph wind conditions in a simulated cold environment. Tests were performed for cyclical operation, vulnerability to ice and wind, thermal performance, and air infiltration. Marketing efforts are described. Cost effectiveness is determined via present value analysis. (LEW)

  7. Optical description and design method with annularly stitched aspheric surface.

    Science.gov (United States)

    Cheng, De-Wen; Chen, Xue-Jiao; Xu, Chen; Hu, Yuan; Wang, Yong-Tian

    2015-12-01

    The relentless pressure for designs with new optical functions, small volume, and light weight has greatly increased the importance of aspheric surfaces. In this paper, we propose an annularly stitched aspheric surface (ASAS) description method to increase the freedom and flexibility of imaging system design. The rotationally symmetric ASAS consists of a circular central zone and one or more annular zones. Two neighboring zones are constrained to have the same derivatives on their joint curve, and this means the ASAS is C1 continuous. This finding is proved and verified by the mathematical deduction of the surface formulas. Two optimization strategies and two design methods with the C1 continuous constraints are also discussed. This surface can greatly facilitate the design and even achieve some previously impossible designs without increasing the fabrication difficulty. Two different systems with the proposed ASAS are optimized and the results are presented. The design results verified the practicability of the ASAS.

  8. Spent nuclear fuel project cold vacuum drying facility vacuum and purge system design description

    Energy Technology Data Exchange (ETDEWEB)

    IRWIN, J.J.

    1998-11-30

    This document provides the System Design Description (SDD) for the Cold Vacuum Drying Facility (CVDF) Vacuum and Purge System (VPS) . The SDD was developed in conjunction with HNF-SD-SNF-SAR-O02, Safety Analysis Report for the Cold Vacuum Drying Facility, Phase 2, Supporting Installation of Processing Systems (Garvin 1998), The HNF-SD-SNF-DRD-002, 1998, Cold Vacuum Drying Facility Design Requirements, and the CVDF Design Summary Report. The SDD contains general descriptions of the VPS equipment, the system functions, requirements and interfaces. The SDD provides references for design and fabrication details, operation sequences and maintenance. This SDD has been developed for the SNFP Operations Organization and shall be updated, expanded, and revised in accordance with future design, construction and startup phases of the CVDF until the CVDF final ORR is approved.

  9. Spent nuclear fuel project cold vacuum drying facility vacuum and purge system design description

    International Nuclear Information System (INIS)

    IRWIN, J.J.

    1998-01-01

    This document provides the System Design Description (SDD) for the Cold Vacuum Drying Facility (CVDF) Vacuum and Purge System (VPS) . The SDD was developed in conjunction with HNF-SD-SNF-SAR-O02, Safety Analysis Report for the Cold Vacuum Drying Facility, Phase 2, Supporting Installation of Processing Systems (Garvin 1998), The HNF-SD-SNF-DRD-002, 1998, Cold Vacuum Drying Facility Design Requirements, and the CVDF Design Summary Report. The SDD contains general descriptions of the VPS equipment, the system functions, requirements and interfaces. The SDD provides references for design and fabrication details, operation sequences and maintenance. This SDD has been developed for the SNFP Operations Organization and shall be updated, expanded, and revised in accordance with future design, construction and startup phases of the CVDF until the CVDF final ORR is approved

  10. The surface physics work station: final design

    International Nuclear Information System (INIS)

    Landers, R.; Kleiman, G.G.; Castro, S.G.C. de; Douglas, R.A.; Nascente, P.A.P.

    1996-01-01

    Thanks to funding from FAPESP we will be installing in the beginning of 1997 a work station for electron spectroscopy designed for the study of clean solid surfaces and the modification of these surfaces by deposition in situ of ultra thin metallic films. The main analytical tool will be a high resolution hemispherical analyzer made by VSW-Omicrom (EA 125 HR) which is capable of better than 5 meV resolution and high transmission due to its five channeltron multi detection system. The system will also have a Rear View LEED Optics for single crystal studies. The system will be housed in a 16'' cylindrical chamber with mu metal magnetic shielding having two levels for analysis. The upper level will contain instruments for technique which do not require photons such as LEED and sample cleaning. The lower level will have the electron analyzer, conventional X-ray source (Al/Mg), electron gun for Auger, e-beam evaporators for thin film deposition and ports for the future addition of different detectors. We will have a manipulator with 5 degrees of freedom (thre translation and two rotational) and sample heating and LN cooling. Finally we will have a fast entry/preparation chamber. The pumping system will have a combination of turbomolecular and ion pumps for the main chamber and a turbo for the fast entr/prep chamber. The system will be used initially for the study of surface alloys by XPS and Photoelectron Diffraction but as soon as it is properly characterized it will be open for collaborations with other groups interested in using its capabilities. (author)

  11. Final design and performance of in situ testing in Grimsel

    International Nuclear Information System (INIS)

    Fuentes-Cantillana, J.L.; Garcia-SiNeriz, J.L.

    1998-01-01

    This report is focused on the design, engineering, and construction aspects of the in situ test carried out at the Grimsel underground laboratory in Switzerland. This reproduces the AGP-granite concept of ENRESA for HLW repositories in crystalline rock. Two heaters, similar in dimensions and weight to the canisters in the reference concept, have been placed in a horizontal drift with a 2.28-m diameter, a total test length of 17.4 m, and backfilled with a total of 115.7 † of highly-compacted bentonite blocks. The backfilled area has been closed with a concrete plug which is 2.7 m thick. More than 600 sensors have been installed in the test to monitor different parameters such as temperature, pressures, humidity, etc., within both the buffer material and the host rock. The installation was completed and commissioned in February 1997, and then the heating phase, which will last for at least 3 years, was started. During this period, the test will basically be operated in an automatic mode, controlled and monitored from Spain via modem. The report is the Final Report from AITEMIN for Phase 4 of the project and includes a description of the test configuration and layout; the design, engineering, and manufacturing aspects of the different test components and equipment; the emplacement operation; and the as built information regarding the final position of the main components and the sensors. (Author)

  12. [Tampa Electric Company IGCC project]. Final public design report; Technical progress report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-07-01

    This final Public Design Report (PDR) provides completed design information about Tampa Electric Company`s Polk Power Station Unit No. 1, which will demonstrate in a commercial 250 MW unit the operating parameters and benefits of the integration of oxygen-blown, entrained-flow coal gasification with advanced combined cycle technology. Pending development of technically and commercially viable sorbent for the Hot Gas Cleanup System, the HGCU also is demonstrated. The report is organized under the following sections: design basis description; plant descriptions; plant systems; project costs and schedule; heat and material balances; general arrangement drawings; equipment list; and miscellaneous drawings.

  13. Safety culture in design. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Macchi, L.; Pietikaeinen, E.; Liinasuo, M.; Savioja, P.; Reiman, T.; Wahlstroem, M. [VTT Technical Research Centre of Finland, Espoo (Finland); Kahlbom, U. [Risk Pilot AB, Stockholm (Sweden); Rollenhagen, C. [Vattenfall, Stockholm, (Sweden)

    2013-04-15

    In this report we approach design from a safety culture approach As this research area is new and understudied, we take a wide scope on the issue. Different theoretical perspectives that can be taken when improving safety of the design process are considered in this report. We suggest that in the design context the concept of safety culture should be expanded from an organizational level to the level of the network of organizations involved in the design activity. The implication of approaching the design process from a safety culture perspective are discussed and the results of the empirical part of the research are presented. In the interview study in Finland and Sweden we identified challenges and opportunities in the design process from safety culture perspective. Also, a small part of the interview study concentrated on state of the art human factors engineering (HFE) practices in Finland and the results relating to that are presented. This report provide a basis for future development of systematic good design practices and for providing guidelines that can lead to safe and robust technical solutions. (Author)

  14. Safety culture in design. Final report

    International Nuclear Information System (INIS)

    Macchi, L.; Pietikaeinen, E.; Liinasuo, M.; Savioja, P.; Reiman, T.; Wahlstroem, M.; Kahlbom, U.; Rollenhagen, C.

    2013-04-01

    In this report we approach design from a safety culture approach As this research area is new and understudied, we take a wide scope on the issue. Different theoretical perspectives that can be taken when improving safety of the design process are considered in this report. We suggest that in the design context the concept of safety culture should be expanded from an organizational level to the level of the network of organizations involved in the design activity. The implication of approaching the design process from a safety culture perspective are discussed and the results of the empirical part of the research are presented. In the interview study in Finland and Sweden we identified challenges and opportunities in the design process from safety culture perspective. Also, a small part of the interview study concentrated on state of the art human factors engineering (HFE) practices in Finland and the results relating to that are presented. This report provide a basis for future development of systematic good design practices and for providing guidelines that can lead to safe and robust technical solutions. (Author)

  15. Solar heating system final design package

    Science.gov (United States)

    1979-01-01

    The system is composed of a warm air collector, a logic control unit and a universal switching and transport unit. The collector was originally conceived and designed as an integrated roof/wall system and therefore provides a dual function in the structure. The collector serves both as a solar energy conversion system and as a structural weather resistant skin. The control unit provides totally automatic control over the operation of the system. It receives input data from sensor probes in collectors, storage and living space. The logic was designed so as to make maximum use of solar energy and minimize use of conventional energy. The transport and switching unit is a high-efficiency air-handling system equipped with gear motor valves that respond to outputs from the control system. The fan unit was designed for maximum durability and efficiency in operation, and has permanently lubricated ball bearings and excellent air-handling efficiency.

  16. The completed design of the SLC Final Focus System

    International Nuclear Information System (INIS)

    Murray, J.J.; Brown, K.L.; Fieguth, T.

    1987-02-01

    The design of the SLC Final Focus System has evolved from its initial conceptual design into its final form. This final design is described including a review of the critical decisions influencing the adoption of particular features. The creation of a feasible design has required that these decisions be tempered by practical considerations such as site constraints, correction of optical errors caused by imperfections, and accommodations requested by engineers and particle detector physicists. As this is the first such system to be built, it is hoped that the experience gained will be useful for the design of future systems

  17. Tokamak blanket design study, final report

    International Nuclear Information System (INIS)

    1980-08-01

    A cylindrical module concept was developed, analyzed, and incorporated in a tokamak blanket system that includes piping systems, vacuum boundary sealing, and support structures. The design is based on the use of state-of-the-art structural materials (20% cold-worked type 316 stainless steel), lithium as the breeding material, and pressurized helium as the coolant. The module design consists of nested concentric cylinders (with an outer diameter of 10 cm) and features direct wall cooling by helium flowing between the outer (first-wall) cylinder and the inner (lithium-containing) cylinder. Each cylinder can withstand full coolant pressure, thus enhancing reliability. Results show that stainless steel is a viable material for a first wall subjected to a neutron wall loading of 4 MW/m 2 and a particle heat flux of 1 MW/m 2 . Lifetime analysis shows that the first-wall design meets the goal of operating at 20-min cycles with 95% duty for 100,000 cycles. To reduce system complexity, a larger 20-cm-diam module also was analyzed for incorporation in the blanket assembly. Reliability assessment indicates that it may be possible to double the module in size from 10 to 20 cm in diameter. With a modest increase in coolant pumping power, a blanket assembly comprising 20-cm-diam modules can still achieve 100,000 operating cycles - equivalent to a 3.6-year design lifetime - with only one or two helium coolant leaks into the plasma

  18. Advanced Design Program (ARIES) Final Report

    Energy Technology Data Exchange (ETDEWEB)

    Tillack, Mark [Univ. of California, San Diego, CA (United States)

    2016-02-16

    Progress is reported for the ARIES 3-year research program at UC San Diego, including three main tasks: 1. Completion of ARIES research on PMI/PFC issues. 2. Detailed engineering design and analysis of divertors and first wall/blankets. 3. Mission & requirements of FNSF.

  19. Cold Vacuum Drying Instrument Air System Design Description. System 12

    International Nuclear Information System (INIS)

    SHAPLEY, B.J.; TRAN, Y.S.

    2000-01-01

    This system design description (SDD) addresses the instrument air (IA) system of the spent nuclear fuel (SNF). This IA system provides instrument quality air to the Cold Vacuum Drying (CVD) Facility. The IA system is a general service system that supports the operation of the heating, ventilation, and air conditioning (HVAC) system, the process equipment skids, and process instruments in the CVD Facility. The following discussion is limited to the compressor, dryer, piping, and valving that provide the IA as shown in Drawings H-1-82222, Cold Vacuum Drying Facility Mechanical Utilities Compressed and Instrument Air PandID, and H-1.82161, Cold Vacuum Drying Facility Process Equipment Skid PandID MCO/Cusk Interface. Figure 1-1 shows the physical location of the 1A system in the CVD Facility

  20. Final focus designs for crab waist colliders

    CERN Document Server

    AUTHOR|(CDS)2084369; Levichev, Evgeny; Piminov, Pavel

    2016-01-01

    The crab waist collision scheme promises significant luminosity gain. The successful upgrade of the DA$\\Phi$NE collider proved the principle of crab waist collision and increased luminosity 3 times. Therefore, several new projects try to implement the scheme. The paper reviews interaction region designs with the crab waist collision scheme for already existent collider DA$\\Phi$NE and SuperKEKB, presently undergoing commissioning, for the projects of SuperB in Italy, CTau in Novosibirsk and FCC-ee at CERN.

  1. Final focus designs for crab waist colliders

    Directory of Open Access Journals (Sweden)

    A. Bogomyagkov

    2016-12-01

    Full Text Available The crab waist collision scheme promises significant luminosity gain. The successful upgrade of the DAΦNE collider proved the principle of crab waist collision and increased luminosity 3 times. Therefore, several new projects try to implement the scheme. The paper reviews interaction region designs with the crab waist collision scheme for already existent collider DAΦNE and SuperKEKB, presently undergoing commissioning, for the projects of SuperB in Italy, CTau in Novosibirsk and FCC-ee at CERN.

  2. New Brunswick Market Design Committee : final report

    International Nuclear Information System (INIS)

    2002-04-01

    This report presents a plan for implementing New Brunswick's electricity restructuring. It includes two resolutions and 95 recommendations to help achieve the main policy objectives of the White Paper, the New Brunswick Energy Policy. The most significant policy goal outlined in the White Paper is the restructuring of the electricity sector, with initial competition being only at the wholesale and large industrial retail level. The Board of Commissioners of Public Utilities will regulate many aspects of the new electricity market. In addition, green pricing options will be made available. The Market Design Committee recommends that the government set up a bilateral contract market for wholesale and large industrial customers to contract with alternate providers for electrical power. Power generators would have the freedom to sell by contract to customers both within and outside the province. The report describes the requirements for establishing a bilateral contract market and how it functions. The Committee also recommends designating a Heritage Pool of electricity available from the existing generation assets in the province. Other recommendations include the creation of programs that will help meet environmental protection goals. The programs include net metering, support of embedded generation, renewable portfolio standards, energy efficiency programs, green pricing, broad-based carbon dioxide emissions trading, emission performance standards, and the promotion of cogeneration. 37 refs., 2 figs

  3. Retrievable surface storage facility conceptual system design description

    Energy Technology Data Exchange (ETDEWEB)

    1977-03-01

    The studies evaluated several potentially attractive methods for processing and retrievably storing high-level radioactive waste after delivery to the Federal repository. These studies indicated that several systems could be engineered to safely store the waste, but that the simplest and most attractive concept from a technical standpoint would be to store the waste in a sealed stainless steel canister enclosed in a 2 in. thick carbon steel cask which in turn would be inserted into a reinforced concrete gamma-neutron shield, which would also provide the necessary air-cooling through an air annulus between the cask and the shield. This concept best satisfies the requirements for safety, long-term exposure to natural phenomena, low capital and operating costs, retrievability, amenability to incremental development, and acceptably small environmental impact. This document assumes that the reference site would be on ERDA's Hanford reservation. This document is a Conceptual System Design Description of the facilities which could satisfy all of the functional requirements within the established basic design criteria. The Retrievable Surface Storage Facility (RSSF) is planned with the capacity to process and store the waste received in either a calcine or glass/ceramic form. The RSSF planning is based on a modular development program in which the modular increments are constructed at rates matching projected waste receipts.

  4. Retrievable surface storage facility conceptual system design description

    International Nuclear Information System (INIS)

    1977-03-01

    The studies evaluated several potentially attractive methods for processing and retrievably storing high-level radioactive waste after delivery to the Federal repository. These studies indicated that several systems could be engineered to safely store the waste, but that the simplest and most attractive concept from a technical standpoint would be to store the waste in a sealed stainless steel canister enclosed in a 2 in. thick carbon steel cask which in turn would be inserted into a reinforced concrete gamma-neutron shield, which would also provide the necessary air-cooling through an air annulus between the cask and the shield. This concept best satisfies the requirements for safety, long-term exposure to natural phenomena, low capital and operating costs, retrievability, amenability to incremental development, and acceptably small environmental impact. This document assumes that the reference site would be on ERDA's Hanford reservation. This document is a Conceptual System Design Description of the facilities which could satisfy all of the functional requirements within the established basic design criteria. The Retrievable Surface Storage Facility (RSSF) is planned with the capacity to process and store the waste received in either a calcine or glass/ceramic form. The RSSF planning is based on a modular development program in which the modular increments are constructed at rates matching projected waste receipts

  5. A Novel Final Focus Design for Future Linear Colliders

    Energy Technology Data Exchange (ETDEWEB)

    Seryi, Andrei

    2000-05-30

    The length, complexity and cost of the present Final Focus designs for linear colliders grows very quickly with the beam energy. In this letter, a novel final focus system is presented and compared with the one proposed for NLC. This new design is simpler, shorter and cheaper, with comparable bandwidth, tolerances and tunability. Moreover, the length scales slower than linearly with energy allowing for a more flexible design which is applicable over a much larger energy range.

  6. Space transfer concepts and analysis for exploration missions. Implementation plan and element description document (draft final). Volume 5: Nuclear electric propulsion vehicle

    Science.gov (United States)

    1991-01-01

    The nuclear electric propulsion (NEP) concept design developed in support of the Space Transfer Concepts and Analysis for Exploration Missions (STCAEM) study is presented. The evolution of the NEP concept is described along with the requirements, guidelines, and assumptions for the design. Operating modes and options are defined and a systems description of the vehicle is presented. Artificial gravity configuration options and space and ground support systems are discussed. Finally, an implementation plan is presented which addresses technology needs, schedules, facilities and costs.

  7. Final Project Report; Final Internal Evaluation: PROJECT DESIGN. Interagency Planning for Urban Educational Needs.

    Science.gov (United States)

    Fresno City Unified School District, CA.

    This document contains the final progress report and final internal evaluation for PROJECT DESIGN, funded under ESEA Title III. The first section describes the project's major activities leading to development of a master plan for education in Fresno, California. Significant modifications of operational plans are described and supplementary…

  8. Laser fusion systems design study. Final technical report

    International Nuclear Information System (INIS)

    1975-06-01

    This document is an addendum to Perkin-Elmer Report No. 12486, Final Technical Report, Laser Fusion System Analysis. Contained herein are the budgetary cost estimates prepared for the baseline design described in the Final Technical Report. Cost tradeoffs performed during the study are covered. (U.S.)

  9. General method for final focus system design for circular colliders

    Directory of Open Access Journals (Sweden)

    Riccardo de Maria

    2008-03-01

    Full Text Available Colliders use final focus systems to reduce the transverse beam sizes at the interaction point in order to increase collision event rates. The maximum focal strength (gradient of the quadrupoles, and the maximum beam size in them, together limit the beam size reduction that is possible. The goal of a final focus system design is to find the best compromise between quadrupole aperture and quadrupole gradient, for the magnet technology that is used. This paper develops a design method that identifies the intrinsic limitations of a final focus system, validates the results of the method against realistic designs, and reports its application to the upgrade of the Large Hadron Collider final focus.

  10. 30 CFR 250.413 - What must my description of well drilling design criteria address?

    Science.gov (United States)

    2010-07-01

    ... drilling design criteria address? Your description of well drilling design criteria must address: (a) Pore... 30 Mineral Resources 2 2010-07-01 2010-07-01 false What must my description of well drilling design criteria address? 250.413 Section 250.413 Mineral Resources MINERALS MANAGEMENT SERVICE...

  11. Computer software design description for the integrated control and data acquisition system LDUA system

    International Nuclear Information System (INIS)

    Aftanas, B.L.

    1998-01-01

    This Computer Software Design Description (CSDD) document provides the overview of the software design for all the software that is part of the integrated control and data acquisition system of the Light Duty Utility Arm System (LDUA). It describes the major software components and how they interface. It also references the documents that contain the detailed design description of the components

  12. Summary of the ITER final design report. July 2001

    International Nuclear Information System (INIS)

    2001-01-01

    This document is a summary of the ITER final design report foreseen during the current, Engineering Design Activities (EDA), phase of the ITER project. The report presents the results of collaborative design and supporting technical work undertaken by the ITER Joint Central team (JCT) and the Home Teams (HT) of the parties to the agreement on co-operation in the Engineering Design Activities for ITER (the ITER EDA Agreement). This report marks the achievement of the full technical scope of activities indicated in the ITER EDA Agreement, with a final design which meets the programmatic objective defined in the Agreement and satisfies detailed scientific, technical and costing objectives set by ITER Council in 1998

  13. Spent nuclear fuel project cold vacuum drying facility tempered water and tempered water cooling system design description

    International Nuclear Information System (INIS)

    IRWIN, J.J.

    1998-01-01

    This document provides the System Design Description (SDD) for the Cold Vacuum Drying Facility (CVDF) Tempered Water (TW) and Tempered Water Cooling (TWC) System . The SDD was developed in conjunction with HNF-SD-SNF-SAR-002, Safety Analysis Report for the Cold Vacuum Drying Facility, Phase 2, Supporting Installation of Processing Systems (Garvin 1998), The HNF-SD-SNF-DRD-O02, 1998, Cold Vacuum Drying Facility Design Requirements, and the CVDF Design Summary Report. The SDD contains general descriptions of the TW and TWC equipment, the system functions, requirements and interfaces. The SDD provides references for design and fabrication details, operation sequences and maintenance. This SOD has been developed for the SNFP Operations Organization and shall be updated, expanded, and revised in accordance with future design, construction and startup phases of the CVDF until the CVDF final ORR is approved

  14. Spent nuclear fuel project cold vacuum drying facility tempered water and tempered water cooling system design description

    Energy Technology Data Exchange (ETDEWEB)

    IRWIN, J.J.

    1998-11-30

    This document provides the System Design Description (SDD) for the Cold Vacuum Drying Facility (CVDF) Tempered Water (TW) and Tempered Water Cooling (TWC) System . The SDD was developed in conjunction with HNF-SD-SNF-SAR-002, Safety Analysis Report for the Cold Vacuum Drying Facility, Phase 2, Supporting Installation of Processing Systems (Garvin 1998), The HNF-SD-SNF-DRD-O02, 1998, Cold Vacuum Drying Facility Design Requirements, and the CVDF Design Summary Report. The SDD contains general descriptions of the TW and TWC equipment, the system functions, requirements and interfaces. The SDD provides references for design and fabrication details, operation sequences and maintenance. This SOD has been developed for the SNFP Operations Organization and shall be updated, expanded, and revised in accordance with future design, construction and startup phases of the CVDF until the CVDF final ORR is approved.

  15. Practical Design of Delta-Sigma Multiple Description Audio Coding

    DEFF Research Database (Denmark)

    Leegaard, Jack Højholt; Østergaard, Jan; Jensen, Søren Holdt

    2014-01-01

    It was recently shown that delta-sigma quantization (DSQ) can be used for optimal multiple description (MD) coding of Gaussian sources. The DSQ scheme combined oversampling, prediction, and noise-shaping in order to trade off side distortion for central distortion in MD coding. It was shown that ...

  16. Northern Sotho grammatical descriptions: the design of a tokeniser ...

    African Journals Online (AJOL)

    With tokenisation, this ambiguity is removed as the position of the morpheme in the token allows for more accurate analysis of the morpheme. This article focuses on the description of the verbal segment in current Northern Sotho grammars. The different types of verbal elements are investigated as well as all the verbal ...

  17. A RECIPE FOR LINEAR COLLIDER FINAL FOCUS SYSTEM DESIGN

    International Nuclear Information System (INIS)

    Seryi, Andrei

    2003-01-01

    The design of Final Focus systems for linear colliders is challenging because of the large demagnifications needed to produce nanometer-sized beams at the interaction point. Simple first- and second-order matrix matching have proven insufficient for this task, and minimization of third- and higher-order aberrations is essential. An appropriate strategy is required for the latter to be successful. A recipe for Final Focus design, and a set of computational tools used to implement this approach, are described herein. An example of the use of this procedure is given

  18. Vehicle infrastructure integration proof of concept : technical description--vehicle : final report

    Science.gov (United States)

    2009-05-19

    This report provides the technical description of the VII system developed for the Cooperative Agreement VII Program between the USDOT and the VII Consortium. The basic architectural elements are summarized and detailed descriptions of the hardware a...

  19. Treatment results in qualitative designs. Application of Descriptive Analysis

    Directory of Open Access Journals (Sweden)

    Héctor Blas Lahitte

    2014-04-01

    It discusses two examples from the Ethology and Psychology, applying methodological strategy Descriptive Analysis. They show that the codification that allows this method takes into account on the one hand, the knowledge base and information relating to a particular disciplinary domain; and on the other hand, it allows to make evident the inferences followed in the reasoning and the rules of interpretation used in reaching new knowledge.

  20. Final design review report for K basin dose reduction project

    International Nuclear Information System (INIS)

    Blackburn, L.D.

    1996-01-01

    The strategy for reducing radiation dose originating from radionuclides absorbed in the K East Basin concrete is to raise the pool water level to provide additional shielding. This report documents a final design review for cleaning/coating basin walls and modifying other basin components where appropriate. The conclusion of this review was that the documents developed constitute an acceptable design for the Dose Reduction Project

  1. A conceptual design of Final Focus Systems for linear colliders

    International Nuclear Information System (INIS)

    Brown, K.L.

    1987-06-01

    Linear colliders are a relatively recent development in the evolution of particle accelerators. This report discusses some of the approaches that have been considered for the design of Final Focus Systems to demagnify the beam exiting from a linac to the small size suitable for collisions at the interaction point. The system receiving the most attention is the one adopted for the SLAC Linear Collider. However, the theory and optical techniques discussed should be applicable to the design efforts for future machines

  2. SIAM Conference on Geometric Design and Computing. Final Technical Report

    Energy Technology Data Exchange (ETDEWEB)

    None

    2002-03-11

    The SIAM Conference on Geometric Design and Computing attracted 164 domestic and international researchers, from academia, industry, and government. It provided a stimulating forum in which to learn about the latest developments, to discuss exciting new research directions, and to forge stronger ties between theory and applications. Final Report

  3. Towards health care process description framework: an XML DTD design.

    Science.gov (United States)

    Staccini, P; Joubert, M; Quaranta, J F; Aymard, S; Fieschi, D; Fieschi, M

    2001-01-01

    The development of health care and hospital information systems has to meet users needs as well as requirements such as the tracking of all care activities and the support of quality improvement. The use of process-oriented analysis is of-value to provide analysts with: (i) a systematic description of activities; (ii) the elicitation of the useful data to perform and record care tasks; (iii) the selection of relevant decision-making support. But paper-based tools are not a very suitable way to manage and share the documentation produced during this step. The purpose of this work is to propose a method to implement the results of process analysis according to XML techniques (eXtensible Markup Language). It is based on the IDEF0 activity modeling language (Integration DEfinition for Function modeling). A hierarchical description of a process and its components has been defined through a flat XML file with a grammar of proper metadata tags. Perspectives of this method are discussed.

  4. ITER hydrogen isotope separation system conceptual design description

    International Nuclear Information System (INIS)

    Busigin, A.; Sood, S.K.; Kveton, O.K.; Dinner, P.J.; Murdoch, D.K.; Leger, D.

    1990-01-01

    This paper presents integrated hydrogen Isotope Separation System (ISS) designs for ITER based on requirements for plasma exhaust processing, neutral beam injection deuterium cleanup, pellet injector propellant detritiation, waste water detritiation, and breeding blanket detritiation. Specific ISS designs are developed for a machine with an aqueous lithium salt blanket (ALSB) and a machine with a solid ceramic breeding blanket (SBB). The differences in the ISS designs arising from the different blanket concepts are highlighted. It is found that the ISS designs for the two blanket concepts considered are very similar with the only major difference being the requirement for an additional large water distillation column for ALSB water detritiation. The extraction of tritium from the ALSB is based on flash evaporation to separate the blanket water from the dissolved Li salt, with the tritiated water then being fed to the ISS for detritiation. This technology is considered to be relatively well understood in comparison to front-end processes for SBB detritiation. In the design of the cryogenic distillation portion of the ISS, it was found that the tritium inventory could be very large (> 600 g) unless specific design measures were taken to reduce it. In the designs which are presented, the tritium inventory has been reduced to about 180 g, which is less than the ITER single-failure release limit of 200 g. Further design optimization and isolation of components is expected to reduce the inventory further. (orig.)

  5. Description of from-reactor transportation cask designs

    International Nuclear Information System (INIS)

    Lake, W.H.

    1990-01-01

    This paper describes two from-reactor cask development program contracts. They are a contract for legal weight truck cask designs, and a contract for a rail/barge cask design. The paper also presents several general considerations affecting the cask development program. Two of these which are covered in some detail are the technical topics of burnup credit and source term evaluation

  6. System design description for the whole element furnace testing system

    International Nuclear Information System (INIS)

    Ritter, G.A.; Marschman, S.C.; MacFarlan, P.J.; King, D.A.

    1998-05-01

    This document provides a detailed description of the Hanford Spent Nuclear Fuel (SNF) Whole Element Furnace Testing System located in the Postirradiation Testing Laboratory G-Cell (327 Building). Equipment specifications, system schematics, general operating modes, maintenance and calibration requirements, and other supporting information are provided in this document. This system was developed for performing cold vacuum drying and hot vacuum drying testing of whole N-Reactor fuel elements, which were sampled from the 105-K East and K West Basins. The proposed drying processes are intended to allow dry storage of the SNF for long periods of time. The furnace testing system is used to evaluate these processes by simulating drying sequences with a single fuel element and measuring key system parameters such as internal pressures, temperatures, moisture levels, and off-gas composition

  7. Actuator Saturation and Control Design for Buildings Structural Systems with Improved Uncertainty Description

    Directory of Open Access Journals (Sweden)

    Y.C. Ding

    2013-01-01

    Full Text Available The problem of robustly active vibration control for a class of earthquake-excited structural systems with time-delay and saturation in the control input channel and parameter uncertainties appearing in all the mass, damping and stiffness matrices is concerned in this paper. The objective of the designing controllers is to guarantee the robust stability of the closed-loop system and attenuate the disturbance from earthquake excitation. Firstly, by using the linear combination of some matrices to deal with the system's uncertainties, a new system uncertainties description, namely rank-1 uncertainty description, is presented. Then, by introducing a linear varying parameter, the input saturation model is described as a linear parameter varying model. Furthermore, based on parameter-dependent Lyapunov theory and linear matrix inequality (LMI technique, the LMIs-based conditions for the closed-loop system to be stable are deduced. By solving those conditions, the controller, considering the actuator saturation, input delay and parameters uncertainties, is obtained. Finally, a three-storey linear building structure under earthquake excitation is considered and simulation results are given to show the effectiveness of the proposed controllers.

  8. Design finalization and start of construction of ITER vacuum vessel

    Energy Technology Data Exchange (ETDEWEB)

    Ioki, K., E-mail: Kimihiro.Ioki@iter.org [ITER Organization, Route de Vinon sur Verdon, 13115 St Paul Lez Durance (France); Barabash, V.; Choi, C.H.; Cordier, J.-J.; Daly, E.; Dani, S.; Davis, J.; Giraud, B.; Gribov, Y. [ITER Organization, Route de Vinon sur Verdon, 13115 St Paul Lez Durance (France); Heitzenroeder, Ph. [PPPL - MS 41, Princeton University, PO Box 451, Princeton, NJ 08543 (United States); Hamlyn-Harris, C.; Johnson, G. [ITER Organization, Route de Vinon sur Verdon, 13115 St Paul Lez Durance (France); Jones, L. [F4E, c/Josep Pla, n. 2, Torres Diagonal Litoral, Edificio B3, E-08019 Barcelona (Spain); Jun, C. [ITER Organization, Route de Vinon sur Verdon, 13115 St Paul Lez Durance (France); Kim, B.C. [NFRI, 52 Yeoeundong Yuseonggu, Daejeon 305-333 (Korea, Republic of); Kuzmin, E. [NTC ' Sintez' , Efremov Inst., 189631 Metallostroy, St. Petersburg (Russian Federation); Le Barbier, R. [ITER Organization, Route de Vinon sur Verdon, 13115 St Paul Lez Durance (France); Loesser, D. [PPPL - MS 41, Princeton University, PO Box 451, Princeton, NJ 08543 (United States); Martinez, J.-M.; Merola, M. [ITER Organization, Route de Vinon sur Verdon, 13115 St Paul Lez Durance (France)

    2011-10-15

    The vacuum vessel (VV) design is being finalized including interface components, such as the support rails and feedthroughs of coils for mitigation of edge localized modes (ELM) and vertical stabilization (VS) of the plasma (ELM/VS coils). It was necessary to make adjustments in the locations of the blanket supports and manifolds to accommodate the design modifications in the ELM/VS coils. The lower port gussets were reinforced to keep a sufficient margin under the increased VV load conditions. The VV support design is being finalized as well, with an emphasis on structure simplification. The design of the in-wall shielding (IWS) has progressed, considering assembly and required tolerances. The layout of ferritic steel plates and borated steel plates will be optimized based on on-going toroidal field ripple analysis. The VV instrumentation was defined in detail. Strain gauges, thermocouples, displacement meters and accelerometers shall be installed to monitor the status of the VV in normal and off-normal conditions to confirm all safety functions are performed correctly. The ITER VV design was preliminarily approved, and the VV materials including 316L(N) IG were already qualified by the Agreed Notified Body (ANB) according to the procedure of Nuclear Pressure Equipment Order.

  9. Final environmental impact statement, Beaufort Sea oil and gas development/Northstar Project. Appendix A: BP Exploration (Alaska) Inc. Final project description - Revision 1, March 27, 1997

    International Nuclear Information System (INIS)

    1999-02-01

    BP Exploration (Alaska) Inc. (BPXA) submitted a permit application to the US Army Engineer District, Alaska to initiate the review process for BPXA's plans to develop and produce oil and gas from the Northstar Unit. This report contains Appendix A of an Environmental Impact Statement which was undertaken to identify and evaluate the potential effects the proposed project may have on the environment. This document is the Northstar Development Project, Final Project Description, Revision 1 for BPXA Northstar Project

  10. Design Description of a Tentacle Based Scanning System

    Directory of Open Access Journals (Sweden)

    M. O. Afolayan

    2017-12-01

    Full Text Available A design of a tentacle-based 3D object scanning device is presented in this work. The dimensions of the device were 15 ×15×20 cm and a maximum weight of model that can be placed on its platform is 500g. The design requires that two red laser for distance measurement by triangulation be installed on the left and right side of a Charge Coupled Device (CCD camera. The camera takes the reading as well. The 3D scanner body is made up of polymer matrix for rigidity and dimensional stability. The main mechanism for the scanner is a lead screw and a turntable both managed by National Electrical Manufacturers Association (NEMA 17 stepper motors.

  11. Study Design and Cohort Description of DEFIB-WOMEN

    DEFF Research Database (Denmark)

    Pedersen, Susanne S.; Nielsen, Jens Cosedis; Riahi, Sam

    2016-01-01

    Disease: Clinical and Psychological outcomes in WOMEN) study to examine gender differences on (1) patient-reported outcomes (PROs), (2) procedure- and device-related complications, and (3) ventricular tachyarrhythmia and mortality. This presents the study design and baseline characteristics of the cohort....... METHODS: DEFIB-WOMEN is a national, multicenter, prospective, observational study. First-time implanted patients are asked to complete PROs at several time points. Information on baseline and follow-up characteristics are captured from patients' medical records, purpose-designed questions, and the Danish......-converting enzyme inhibitors, and psychotropic agents. Although women generally had a healthier clinical profile, they reported significantly more symptoms of anxiety and depression and ICD concerns (fear of shock) as compared to men. These differences were not only statistically significant but also clinically...

  12. SWEPP Gamma-Ray Spectrometer System software design description

    International Nuclear Information System (INIS)

    Femec, D.A.; Killian, E.W.

    1994-08-01

    To assist in the characterization of the radiological contents of contract-handled waste containers at the Stored Waste Examination Pilot Plant (SWEPP), the SWEPP Gamma-Ray Spectrometer (SGRS) System has been developed by the Radiation Measurements and Development Unit of the Idaho National Engineering Laboratory. The SGRS system software controls turntable and detector system activities. In addition to determining the concentrations of gamma-ray-emitting radionuclides, this software also calculates attenuation-corrected isotopic mass ratios of-specific interest. This document describes the software design for the data acquisition and analysis software associated with the SGRS system

  13. SWEPP Gamma-Ray Spectrometer System software design description

    Energy Technology Data Exchange (ETDEWEB)

    Femec, D.A.; Killian, E.W.

    1994-08-01

    To assist in the characterization of the radiological contents of contract-handled waste containers at the Stored Waste Examination Pilot Plant (SWEPP), the SWEPP Gamma-Ray Spectrometer (SGRS) System has been developed by the Radiation Measurements and Development Unit of the Idaho National Engineering Laboratory. The SGRS system software controls turntable and detector system activities. In addition to determining the concentrations of gamma-ray-emitting radionuclides, this software also calculates attenuation-corrected isotopic mass ratios of-specific interest. This document describes the software design for the data acquisition and analysis software associated with the SGRS system.

  14. System design description for surface moisture measurement system (SMMS)

    Energy Technology Data Exchange (ETDEWEB)

    Vargo, G.F.

    1996-09-23

    The SMMS has been developed to measure moisture in the top few centimeters of tank waste. The SMMS development was initiated by the preliminary findings of SAR-033, and does not necessarily fulfill any established DQO. After the SAR-033 is released, if no significant changes are made, moisture measurements in the organic waste tanks will rapidly become a DQO. The SMMS was designed to be installed in any 4 inch or larger riser, and to allow maximum adjustability for riser lengths, and is used to deploy a sensor package on the waste surface within a 6 foot radius about the azimuth. The first sensor package will be a neutron probe.

  15. Standard-D hydrogen monitoring system, system design description

    International Nuclear Information System (INIS)

    Schneider, T.C.

    1996-01-01

    During most of the year, it is assumed that the vapor space in the 177 radioactive waste tanks on the Hanford Project site contain a uniform mixture of gases. Several of these waste tanks (currently twenty-five, 6 Double Shell Tanks and 19 Single Shell Tanks) were identified as having the potential for the buildup of gasses to a flammable level. An active ventilation system in the Double Shell Tanks and a passive ventilation system in the Single Shell Tanks provides a method of expelling gasses from the tanks. A gas release from a tank causes a temporary rise in the tank pressure, and a potential for increased concentration of hydrogen gas in the vapor space. The gas is released via the ventilation systems until a uniform gas mixture in the vapor space is once again achieved. The Standard Hydrogen Monitoring System (SHMS) is designed to monitor and quantify the percent hydrogen concentration during these potential gas releases. This document describes the design of the Standard-D Hydrogen Monitoring System, (SHMS-D) and its components as it differs from the original SHMS

  16. Nuclear waste repository in basalt: a design description

    International Nuclear Information System (INIS)

    Ritchie, J.S.; Schmidt, B.

    1982-01-01

    The conceptual design of a nuclear waste repository in basalt is described. Nuclear waste packages are placed in holes drilled into the floor of tunnels at a depth of 3700 ft. About 100 miles of tunnels are required to receive 35,000 packages. Five shafts bring waste packages, ventilation air, excavated rock, personnel, material, and services to and from the subsurface. The most important surface facility is the waste handling building, located over the waste handling shaft, where waste is received and packaged for storage. Two independent ventilation systems are provided to avoid potential contamination of spaces that do not contain nuclear waste. Because of the high temperatures at depth, an elaborate air chilling system is provided. Because the waste packages deliver a considerable amount of heat energy to the rock mass, particular attention is paid to heat transfer and thermal stress studies. 3 references, 31 figures, 3 tables

  17. SHMS-E PLC computer software design description

    International Nuclear Information System (INIS)

    Schneider, T.C.

    1998-01-01

    The Standard Hydrogen Monitoring System (SHMS) is designed to monitor the volume percent hydrogen concentration during potential gas releases from the Hanford underground waste storage tanks. A flexible gas continuous monitoring system was needed that could be expanded to measure gas compositions at both high and low sensitivities. For these reasons, a modified version of the SHMS (entitled SHMS-E) has been developed. The SHMS-E analytical (often referred to as SHMS-E+) measures gas concentrations in selectable ranges of approximately: Hydrogen (3-100,000 ppm); Nitrous Oxide (10-4,000 ppm); Ammonia (10-10,000 ppm) and Methane (10-4,000 ppm). The SHMS-E basic will monitor Hydrogen using electrochemical cells, but will not have the Microsensor Technology Inc. (MTI) dual-column gas chromatograph, B and K photo-acoustic spectrometer, and associated computers installed though they may be installed with minimal hardware changes in the future if needed

  18. Final design of kaon beam K2 at KEK

    International Nuclear Information System (INIS)

    Kurokawa, Shin-ichi; Yamamoto, Akira.

    1977-09-01

    Final design of the 2.3 GeV/c kaon beam K2 is given. The K2 beam starts from the production target in slow extracted beam. Momentum range is 1 GeV/c through 2.3 GeV/c. Nominal total beam length is 27.9 m and solid-angle momentum acceptance is 6.25 msr%ΔP/P. Using a platinum target of diameter 3 mm and length 6 cm, 2.0 GeV/c beam fluxes of 1.0 x 10 6 K + and 5.2 x 10 5 K - per 10 12 13 GeV/c incident protons are expected at the final focus. (auth.)

  19. Standard-B Hydrogen Monitoring System, system design description

    International Nuclear Information System (INIS)

    Schneider, T.C.

    1995-01-01

    During most of the year, it is assumed that the vapor in the 177 radioactive waste tanks on the Hanford Project site contain a uniform mixture of gases. Several of these waste tanks (currently twenty five, 6 Double Shell Tanks and 19 Single Shell Tanks) were identified as having the potential for the buildup of gases to a flammable level. An active ventilation system in the Double Shell Tanks and a passive ventilation system in the Single Shell Tanks provides a method of expelling gases from the tanks. A gas release from a tank causes a temporary rise in the tank pressure, and a potential for increased concentration of hydrogen gas in the vapor space. The gas is released via the ventilation systems until a uniform gas mixture in the vapor space is once again achieved. This document describes the design of the Standard-B Hydrogen Monitoring System, (SHMS) and its components as it differs from the original SHMS. The differences are derived from changes made to improve the system performance but not implemented in all the installed enclosures

  20. SWEPP Assay System Version 2.0 software design description

    Energy Technology Data Exchange (ETDEWEB)

    East, L.V.; Marwil, E.S.

    1996-08-01

    The Idaho National Engineering Laboratory (INEL) Stored Waste Examination Pilot Plant (SWEPP) operations staff use nondestructive analysis methods to characterize the radiological contents of contact-handled radioactive waste containers. Containers of waste from Rocky Flats Environmental Technology Site and other Department of Energy (DOE) sites are currently stored at SWEPP. Before these containers can be shipped to the Waste Isolation Pilot Plant (WIPP), SWEPP must verify compliance with storage, shipping, and disposal requirements. This program has been in operation since 1985 at the INEL Radioactive Waste Management Complex (RWMC). One part of the SWEPP program measures neutron emissions from the containers and estimates the mass of plutonium and other transuranic (TRU) isotopes present. A Passive/Active Neutron (PAN) assay system developed at the Los Alamos National Laboratory is used to perform these measurements. A computer program named NEUT2 was originally used to perform the data acquisition and reduction functions for the neutron measurements. This program was originally developed at Los Alamos and extensively modified by a commercial vendor of PAN systems and by personnel at the INEL. NEUT2 uses the analysis methodology outlined, but no formal documentation exists on the program itself. The SWEPP Assay System (SAS) computer program replaced the NEUT2 program in early 1994. The SAS software was developed using an `object model` approach and is documented in accordance with American National Standards Institute (ANSI) and Institute of Electrical and Electronic Engineers (IEEE) standards. The new program incorporates the basic analysis algorithms found in NEUT2. Additional functionality and improvements include a graphical user interface, the ability to change analysis parameters without program code modification, an `object model` design approach and other features for improved flexibility and maintainability.

  1. Conceptual designs for modular OTEC SKSS. Final report

    Energy Technology Data Exchange (ETDEWEB)

    None

    1980-02-29

    This volume presents the results of the first phase of the Station Keeping Subsystem (SKSS) design study for 40 MW/sub e/ capacity Modular Experiment OTEC Platforms. The objectives of the study were: (1) establishment of basic design requirements; (2) verification of technical feasibility of SKSS designs; (3) identification of merits and demerits; (4) estimates of sizes for major components; (5) estimates of life cycle costs; (6) deployment scenarios and time/cost/risk assessments; (7) maintenance/repair and replacement scenarios; (8) identifications of interface with other OTEC subsystems; (9) recommendations for and major problems in preliminary design; and (10) applicability of concepts to commercial plant SKSS designs. A brief site suitability study was performed with the objective of determining the best possible location at the Punta Tuna (Puerto Rico) site from the standpoint of anchoring. This involved studying the vicinity of the initial location in relation to the prevailing bottom slopes and distances from shore. All subsequent studies were performed for the final selected site. The two baseline OTEC platforms were the APL BARGE and the G and C SPAR. The results of the study are presented in detail. The overall objective of developing two conceptual designs for each of the two baseline OTEC platforms has been accomplished. Specifically: (1) a methodology was developed for conceptual designs and followed to the extent possible. At this stage, a full reliability/performance/optimization analysis based on a probabilistic approach was not used due to the numerous SKSS candidates to be evaluated. A deterministic approach was used. (2) For both of the two baseline platforms, the APL BARGE and the G and C SPAR, all possible SKSS candidate concepts were considered and matrices of SKSS concepts were developed.

  2. Permian Basin, Texas: Volume 1, Text: Final preliminary design report

    International Nuclear Information System (INIS)

    1988-01-01

    This report is a description of the preliminary design for an Exploratory Shaft Facility (ESF) at the proposed 49 acre site located 21 miles north of Hereford, Texas in Deaf Smith County. Department of Energy must conduct in situ testing at depth to ascertain the engineering and environmental suitability of the site for further consideration for nuclear waste repository development. The ESF includes the construction of two 12-ft diameter engineered shafts for accessing the bedded salt horizon to conduct in situ tests to ascertain if the site should be considered a candidate site for the first High Level Nuclear Waste Repository. This report includes pertinent engineering drawings for two shafts and all support facilities necessary for shaft construction and testing program operation. Shafts will be constructed by conventional drill-and-blast methods employing ground freezing prior to shaft construction to stabilize the existing groundwater and soil conditions at the site. A watertight liner and seal system will be employed to prevent intermingling of aquifers and provide a stable shaft throughout its design life. 38 refs., 37 figs., 14 tabs

  3. WRAP Module 1 data management system (DMS) software design description (SDD)

    International Nuclear Information System (INIS)

    Weidert, J.R.

    1996-01-01

    Revision 2 of the Waste Receiving and Processing (WRAP) Module 1 Data Management System (DMS) Preliminary Software Design Description (PSDD) provides a high-level design description of the system. The WRAP 1 DMS is required to collect, store, and report data related to certification, tracking, packaging, repackaging, processing, and shipment of waste processed or stored at the WRAP 1 facility. The WRAP 1 DMS SDD is used as the primary medium for communication software design information. This release provides design descriptions for the following process modules produced under Phase 1 of the development effort: Receiving Drum or Box Containers Process Routing and Picklists; Waste Inventory by Location and/or Container Relationships; LLW Process Glovebox Facility Radiologic Material Inventory Check (partial); Shipping (partial production); Drum or Box NDE Operations; and Drum or Box NDA Operations Data Review (partial production). In addition, design descriptions are included for the following process modules scheduled for development under Phases 2 and 3: Activity Comment; LLW RWM Glovebox Sample Management; TRU Process Glovebox; TRU RWM Glovebox; and TRUPACT Processing. Detailed design descriptions for Reports and Facility Metrics have also been provided for in Revision 2 of this document

  4. Windows Calorimeter Control (WinCal) program computer software design description

    International Nuclear Information System (INIS)

    Pertzborn, N.F.

    1997-01-01

    The Windows Calorimeter Control (WinCal) Program System Design Description contains a discussion of the design details for the WinCal product. Information in this document will assist a developer in maintaining the WinCal system. The content of this document follows the guidance in WHC-CM-3-10, Software Engineering Standards, Standard for Software User Documentation

  5. Final design of thermal diagnostic system in SPIDER ion source

    Energy Technology Data Exchange (ETDEWEB)

    Brombin, M., E-mail: matteo.brombin@igi.cnr.it; Dalla Palma, M.; Pasqualotto, R.; Pomaro, N. [Consorzio RFX, Corso Stati Uniti 4, I-35127 Padova (Italy)

    2016-11-15

    The prototype radio frequency source of the ITER heating neutral beams will be first tested in SPIDER test facility to optimize H{sup −} production, cesium dynamics, and overall plasma characteristics. Several diagnostics will allow to fully characterise the beam in terms of uniformity and divergence and the source, besides supporting a safe and controlled operation. In particular, thermal measurements will be used for beam monitoring and system protection. SPIDER will be instrumented with mineral insulated cable thermocouples, both on the grids, on other components of the beam source, and on the rear side of the beam dump water cooled elements. This paper deals with the final design and the technical specification of the thermal sensor diagnostic for SPIDER. In particular the layout of the diagnostic, together with the sensors distribution in the different components, the cables routing and the conditioning and acquisition cubicles are described.

  6. FERMI(at)Elettra FEL Design Technical Optimization Final Report

    International Nuclear Information System (INIS)

    Fawley, William; Penn, Gregory; Allaria, Enrico; De Ninno, Giovanni; Graves, William

    2006-01-01

    This is the final report of the FEL Design Group for the Technical Optimization Study for the FERMI(at)ELETTRA project. The FERMI(at)ELETTRA project is based on the principle of harmonic upshifting of an initial ''seed'' signal in a single pass, FEL amplifier employing multiple undulators. There are a number of FEL physics principles which underlie this approach to obtaining short wavelength output: (1) the energy modulation of the electron beam via the resonant interaction with an external laser seed (2) the use of a chromatic dispersive section to then develop a strong density modulation with large harmonic overtones (3) the production of coherent radiation by the microbunched beam in a downstream radiator. Within the context of the FERMI project, we discuss each of these elements in turn

  7. Tidd PFBC Demonstration Project: Public final design report

    Energy Technology Data Exchange (ETDEWEB)

    1992-10-01

    This Public Final Design Report describes the 70 MW(e) Tidd PFBC Demonstration Plant under construction in Brilliant, Ohio. This project is receiving cost-sharing from the US Department of Energy (DOE), and is being administered by the Morgantown Energy Technology Center in accordance with DOE Cooperative Agreement No. DE-FC21-87 MC24132.000. The project is also receiving costsharing from the State of Ohio. This award is being administered by the Ohio Coal Development Office. The Tidd PFBC Demonstration Project is the first utility-scale demonstration project in the US. Its objective is to demonstrate that the Pressurized Fluidized Bed Combustion (PFBC) combined-cycle technology is an economic, reliable, and environmentally superior alternative to conventional technology in using high-sulfur coal to generate electricity. Detailed design of the plant began in May 1987, leading to the start of construction in April 1988. First coal fire occurred in November 1990, and the three-year test program began in February 1991.

  8. Northeast Oregon Hatchery Project conceptual design report. Final report

    International Nuclear Information System (INIS)

    1995-03-01

    This report presents the results of site analysis for the Bonneville Power Administration Northeast Oregon Hatchery Project. The purpose of this project is to provide engineering services for the siting and conceptual design of hatchery facilities for the Bonneville Power Administration. The hatchery project consists of artificial production facilities for salmon and steelhead to enhance production in three adjacent tributaries to the Columbia River in northeast Oregon: the Grande Ronde, Walla Walla, and Imnaha River drainage basins. Facilities identified in the master plan include adult capture and holding facilities; spawning incubation, and early rearing facilities; full-term rearing facilities; and direct release or acclimation facilities. The evaluation includes consideration of a main production facility for one or more of the basins or several smaller satellite production facilities to be located within major subbasins. The historic and current distribution of spring and fall chinook salmon and steelhead was summarized for the Columbia River tributaries. Current and future production and release objectives were reviewed. Among the three tributaries, forty seven sites were evaluated and compared to facility requirements for water and space. Site screening was conducted to identify the sites with the most potential for facility development. Alternative sites were selected for conceptual design of each facility type. A proposed program for adult holding facilities, final rearing/acclimation, and direct release facilities was developed

  9. Red River Stream Improvement Final Design Nez Perce National Forest.

    Energy Technology Data Exchange (ETDEWEB)

    Watershed Consulting, LLC

    2007-03-15

    This report details the final stream improvement design along the reach of Red River between the bridge below Dawson Creek, upstream for approximately 2 miles, Idaho County, Idaho. Geomorphic mapping, hydrologic profiles and cross-sections were presented along with existing fish habitat maps in the conceptual design report. This information is used to develop a stream improvement design intended to improve aquatic habitat and restore riparian health in the reach. The area was placer mined using large bucket dredges between 1938 and 1957. This activity removed most of the riparian vegetation in the stream corridor and obliterated the channel bed and banks. The reach was also cut-off from most valley margin tributaries. In the 50 years since large-scale dredging ceased, the channel has been re-established and parts of the riparian zone have grown in. However, the recruitment of large woody debris to the stream has been extremely low and overhead cover is poor. Pool habitat makes up more than 37% of the reach, and habitat diversity is much better than the project reach on Crooked River. There is little large woody debris in the stream to provide cover for spawning and juvenile rearing, because the majority of the woody debris does not span a significant part of the channel, but is mainly on the side slopes of the stream. Most of the riparian zone has very little soil or subsoil left after the mining and so now consists primarily of unconsolidated cobble tailings or heavily compacted gravel tailings. Knapweed and lodgepole pine are the most successful colonizers of these post mining landforms. Tributary fans which add complexity to many other streams in the region, have been isolated from the main reach due to placer mining and road building.

  10. A Technical Description of the Officer Procurement Model (TOPOPS). Final Report.

    Science.gov (United States)

    Akman, Allan; And Others

    The Total Objective Plan for the Officer Procurement System (TOPOPS) is an aggregate-level, computer-based model of the Air Force Officer procurement system developed to operate on the UNIVAC 1108 system. It is designed to simulate officer accession and training and achieve optimal solutions in terms of either cost minimization or accession…

  11. WRAP Module 1 data management system (DMS) software design description (SDD)

    Energy Technology Data Exchange (ETDEWEB)

    Talmage, P.A.

    1995-03-17

    The Waste Receiving and Processing (WRAP) Module 1 Data Management System (DMS) System Design Description (SDD) describes the logical and physical architecture of the system. The WRAP 1 DMS SDD formally partitions the elements of the system described in the WRAP 1 DMS Software requirements specification into design objects and describes the key properties and relationships among the design objects and interfaces with external systems such as the WRAP Plant Control System (PCS). The WRAP 1 DMS SDD can be thought of as a detailed blueprint for implementation activities. The design descriptions contained within this document will describe, in detail, the software products that will be developed to assist the Project W-026, Waste Receiving and Processing Module 1, in their management functions. The WRAP 1 DMS is required to collect, store, and report data related to certification, tracking, packaging, repackaging, processing, and shipment of waste processed or stored at the WRAP 1 facility.

  12. WRAP Module 1 data management system (DMS) software design description (SDD)

    International Nuclear Information System (INIS)

    Talmage, P.A.

    1995-01-01

    The Waste Receiving and Processing (WRAP) Module 1 Data Management System (DMS) System Design Description (SDD) describes the logical and physical architecture of the system. The WRAP 1 DMS SDD formally partitions the elements of the system described in the WRAP 1 DMS Software requirements specification into design objects and describes the key properties and relationships among the design objects and interfaces with external systems such as the WRAP Plant Control System (PCS). The WRAP 1 DMS SDD can be thought of as a detailed blueprint for implementation activities. The design descriptions contained within this document will describe, in detail, the software products that will be developed to assist the Project W-026, Waste Receiving and Processing Module 1, in their management functions. The WRAP 1 DMS is required to collect, store, and report data related to certification, tracking, packaging, repackaging, processing, and shipment of waste processed or stored at the WRAP 1 facility

  13. Contested collaboration: A descriptive model of intergroup communication in information system design

    DEFF Research Database (Denmark)

    Sonnenwald, D.H.

    1995-01-01

    support patterns of work activities, social groups, and personal beliefs. In these situations, design is fundamentally an interactive process that requires communication among users, designers, and developers. However, communication among these groups is often difficult although of paramount importance......Many information system design situations today include users, designers, and developers who, with their own unique group and individual perspectives, need to interact so that they can come to a working understanding of how the information system being developed will coexist with and ideally...... to design outcomes. Through a qualitative analysis of a house, expert system, and telecommunications network architecture and management system design situations, a descriptive model of design that characterizes communication among users, designers, and developers as they create an artifact was developed...

  14. Final report bridge design system analysis and modernization.

    Science.gov (United States)

    2016-09-27

    The Bridge Design System (BDS) is an in-house software program developed by the Michigan Department of Transportations : (MDOT) Bridge Design Unit. The BDS designs bridges according to the required specifications, and outputs corresponding design ...

  15. Cold Vacuum Dryer (CVD) Facility Security System Design Description. System 54

    International Nuclear Information System (INIS)

    WHITEHURST, R.

    2000-01-01

    This system design description (SDD) addresses the Cold Vacuum Drying (CVD) Facility security system. The system's primary purpose is to provide reasonable assurance that breaches of security boundaries are detected and assessment information is provided to protective force personnel. In addition, the system is utilized by Operations to support reduced personnel radiation goals and to provide reasonable assurance that only authorized personnel are allowed to enter designated security areas

  16. Cold Vacuum Drying facility civil - structural system design description (SYS 06)

    International Nuclear Information System (INIS)

    PITKOFF, C.C.

    1999-01-01

    This document describes the Cold Vacuum Drying (CVD) Facility civil - structural system. This system consists of the facility structure, including the administrative and process areas. The system's primary purpose is to provide for a facility to house the CVD process and personnel and to provide a tertiary level of containment. The document provides a description of the facility and demonstrates how the design meets the various requirements imposed by the safety analysis report and the design requirements document

  17. Cold Vacuum Drying facility civil structural system design description (SYS 06)

    Energy Technology Data Exchange (ETDEWEB)

    PITKOFF, C.C.

    1999-07-06

    This document describes the Cold Vacuum Drying (CVD) Facility civil - structural system. This system consists of the facility structure, including the administrative and process areas. The system's primary purpose is to provide for a facility to house the CVD process and personnel and to provide a tertiary level of containment. The document provides a description of the facility and demonstrates how the design meets the various requirements imposed by the safety analysis report and the design requirements document.

  18. Data derived from constitutive laws for description of shock wave propagation in concrete. Final report

    International Nuclear Information System (INIS)

    Eibl, J.; Ockert, J.

    1994-01-01

    Especially the need to design safe reactor containments, but also the necessity to protect facilities and human beings against impacts induced secondarily by explosions and detonations, demand simulations and design calculations of concrete under shock wave loading. The necessary computer codes are available, but the relevant constitutive laws for concrete with volumetric pressures up to more than 10000 MPa are lacking. Therefore shock wave tests have been carried out to develop such constitutive laws by loading concrete slabs with contact explosions. By the use of hot-molded carbon composition resistors shock waves propagating through the slab were measured. Pressures up to 13900 MPa were registered. Additionally shock wave velocities were determined from the different arrival times of the wave at the gages. By these two measured values and the conservation equations of mass and momentum the needed p-V relationship, the so called Hugoniot-Curve, was established up to 13900 MPa. Using the theory of Mie-Grueneisen and the so called P-α model the Hugoniot-Curve was extended to the equation of state for concrete. In a first step the deviatoric part of the constitutive law was attached from own static experiments considering the existing knowledge of strain rate effects since relevant dynamic tests under extreme loads are not available. With this constitutive law the analysis of the experiments then was backward verified in detail. (orig.) [de

  19. Waste Isolation Pilot Plant design validation: Final report

    International Nuclear Information System (INIS)

    1986-10-01

    This report provides documentation of actual underground conditions encountered as they relate to the design criteria, design bases, and design configurations for the reference design of the underground openings. It includes a selection of the more essential data collected during the design validation effort and an interpretation of these data

  20. Summary description of the Babcock and Wilcox integrated nuclear design system

    International Nuclear Information System (INIS)

    Wittkopf, W.A.

    1976-03-01

    The Babcock and Wilcox integrated nuclear design system is divided into three broad areas: basic nuclear data processing, applications data processing, and nuclear design calculations. In basic nuclear data processing, basic nuclear data are collected, evaluated, and processed into a specified fine-energy mesh multigroup data file called a Master Library. In applications data processing, data for selected materials are retrieved from the Master Library and processed into an optimally structured, multigroup Production Library. Using these data and input descriptions of cells or regions, neutron spectra are generated and few-group constants are computed and fitted as a function of fuel burnup, initial enrichment, temperature, etc. In nuclear design calculations, few-group cross-section fits and descriptions of each core region and core geometry are input to a diffusion-depletion program or a nodal program that computes core reactivity, core power distribution, control rod worth, fuel cycle studies, core operating limitations, etc

  1. Mirror fusion test facility magnet system. Final design report

    International Nuclear Information System (INIS)

    Henning, C.D.; Hodges, A.J.; VanSant, J.H.; Dalder, E.N.; Hinkle, R.E.; Horvath, J.A.; Scanlan, R.M.; Shimer, D.W.; Baldi, R.W.; Tatro, R.E.

    1980-01-01

    Information is given on each of the following topics: (1) magnet description, (2) superconducting manufacture, (3) mechanical behavior of conductor winding, (4) coil winding, (5) thermal analysis, (6) cryogenic system, (7) power supply system, (8) structural analysis, (9) structural finite element analysis refinement, (10) structural case fault analysis, and (11) structural metallurgy

  2. Mirror fusion test facility magnet system. Final design report

    Energy Technology Data Exchange (ETDEWEB)

    Henning, C.D.; Hodges, A.J.; VanSant, J.H.; Dalder, E.N.; Hinkle, R.E.; Horvath, J.A.; Scanlan, R.M.; Shimer, D.W.; Baldi, R.W.; Tatro, R.E.

    1980-09-03

    Information is given on each of the following topics: (1) magnet description, (2) superconducting manufacture, (3) mechanical behavior of conductor winding, (4) coil winding, (5) thermal analysis, (6) cryogenic system, (7) power supply system, (8) structural analysis, (9) structural finite element analysis refinement, (10) structural case fault analysis, and (11) structural metallurgy. (MOW)

  3. ATM Technology Demonstration-1 Phase II Boeing Configurable Graphical Display (CGD) Software Design Description

    Science.gov (United States)

    Wilber, George F.

    2017-01-01

    This Software Description Document (SDD) captures the design for developing the Flight Interval Management (FIM) system Configurable Graphics Display (CGD) software. Specifically this SDD describes aspects of the Boeing CGD software and the surrounding context and interfaces. It does not describe the Honeywell components of the CGD system. The SDD provides the system overview, architectural design, and detailed design with all the necessary information to implement the Boeing components of the CGD software and integrate them into the CGD subsystem within the larger FIM system. Overall system and CGD system-level requirements are derived from the CGD SRS (in turn derived from the Boeing System Requirements Design Document (SRDD)). Display and look-and-feel requirements are derived from Human Machine Interface (HMI) design documents and working group recommendations. This Boeing CGD SDD is required to support the upcoming Critical Design Review (CDR).

  4. Final Design Report for the RH LLW Disposal Facility (RDF) Project

    Energy Technology Data Exchange (ETDEWEB)

    Austad, S. L. [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2015-05-01

    The RH LLW Disposal Facility (RDF) Project was designed by AREVA Federal Services (AFS) and the design process was managed by Battelle Energy Alliance (BEA) for the Department of Energy (DOE). The final design report for the RH LLW Disposal Facility Project is a compilation of the documents and deliverables included in the facility final design.

  5. Final Design Report for the RH LLW Disposal Facility (RDF) Project

    Energy Technology Data Exchange (ETDEWEB)

    Austad, Stephanie Lee [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2015-09-01

    The RH LLW Disposal Facility (RDF) Project was designed by AREVA Federal Services (AFS) and the design process was managed by Battelle Energy Alliance (BEA) for the Department of Energy (DOE). The final design report for the RH LLW Disposal Facility Project is a compilation of the documents and deliverables included in the facility final design.

  6. A domain-independent descriptive design model and its application to structured reflection on design processes

    NARCIS (Netherlands)

    Reymen, Isabelle; Hammer, D.K.; Kroes, P.A.; van Aken, Joan Ernst; van Aken, J.E.; Dorst, C.H.; Bax, M.F.T.; Basten, T

    2006-01-01

    Domain-independent models of the design process are an important means for facilitating interdisciplinary communication and for supporting multidisciplinary design. Many so-called domain-independent models are, however, not really domain independent. We state that to be domain independent, the

  7. System requirements and design description for the environmental requirements management interface (ERMI)

    International Nuclear Information System (INIS)

    Biebesheimer, E.

    1997-01-01

    This document describes system requirements and the design description for the Environmental Requirements Management Interface (ERMI). The ERMI database assists Tank Farm personnel with scheduling, planning, and documenting procedure compliance, performance verification, and selected corrective action tracking activities for Tank Farm S/RID requirements. The ERMI database was developed by Science Applications International Corporation (SAIC). This document was prepared by SAIC and edited by LMHC

  8. Cold Vacuum Drying Facility Condensate Collection System Design Description. System 19

    International Nuclear Information System (INIS)

    PITKOFF, C.C.

    2000-01-01

    The Cold Vacuum Drying (CVD) Facility of Spent Nuclear Fuel (SNF) provides required process systems, supporting equipment, and facilities to support the SNF Project mission. This system design description (SDD) addresses the Condensate Collection System (CCS). This is a general service system. The CCS begins at the condensate outlet of the general process air-handling unit (AHU) and the condensate outlets for the active process bays AHUs. The system terminates at each condensate collection tank (5 total)

  9. Knowledge and Processes in Design. DPS Final Report.

    Science.gov (United States)

    Pirolli, Peter

    Four papers from a project concerning information-processing characterizations of the knowledge and processes involved in design are presented. The project collected and analyzed verbal protocols from instructional designers, architects, and mechanical engineers. A framework was developed for characterizing the problem spaces of design that…

  10. 280 GHz Gyro-BWO design study: Final report

    International Nuclear Information System (INIS)

    1988-07-01

    This report summarizes the results of a design study of a 280 GHz Gyro-BWO tunable source. The purpose of this study is to identify and propose viable design alternatives for any significant technological risk associated with building an operational BWO system. The tunable Gyro-BWO system will have three major components: a Gyro-BWO microwave tube, a superconducting magnet, and a power supply/modulator. The design tasks for this study in order of decreasing importance are: design and specification of the superconducting magnet; preliminary design and layout of a Gyro-BWO microwave tube; and specification for the power supply/modulator. 2 refs., 4 figs

  11. Final repository for spent nuclear fuel. Underground design Simpevarp, Layout D1

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2006-04-15

    This report is a compilation of the results of the underground design work carried out in design phase D1 of the Repository Design Project within the Deep Repository Project for the Simpevarp site. Similar reports are also being produced for the Laxemar and Forsmark sites. The design phase coincides with the initial site investigation phase. The main purpose of phase D1 is to answer the question 'Can a final repository be accommodated within the designated site', but also to test the design methodology and provide feedback to the modelling project. Design was carried out in accordance with the methodology described in UDP (Underground Design Premises), SKB R-04-60, and was based on preliminary data from various disciplines in the site modelling project. The preliminary input data used were then cross-checked against data in the final Site Descriptive Model SDM v 1.2 and significant differences were integrated in the design work. The design results from each design topic were presented by the designer at presentation meetings for SKB's design management and the reviewers engaged by SKB for the specific topic. After the presentation meeting the designer wrote up the work reports for the topic in question. The work reports were then reviewed by SKB's review team. The results of the review were compiled in a statement that was submitted to the designer to be dealt with. In the statement the designer documented which comments were dealt with and how. This report is a compilation of the entire design phase D1 for Simpevarp. The 3D layout with coordinate lists for deposition holes and tunnels that was drawn to illustrate a possible layout was used in the Preliminary safety evaluation of the Simpevarp subarea and the hydro modelling of the Open Repository, both activities within the Deep Repository Project. According to current plans for the Swedish nuclear programme, the minimum required number of canister positions in the repository is estimated to be

  12. Development of the ITER Continuous External Rogowski: From conceptual design to final design

    Energy Technology Data Exchange (ETDEWEB)

    Moreau, Philippe, E-mail: philippe.jacques.moreau@cea.fr [CEA, IRFM, F-13108 Saint-Paul-lez-Durance (France); Spuig, Pascal; Le-luyer, Alain; Malard, Philippe; Cantone, Bruno; Pastor, Patrick; Saint-Laurent, François [CEA, IRFM, F-13108 Saint-Paul-lez-Durance (France); Vayakis, George; Delhom, Dominique [ITER Organization, Route de Vinon-sur-Verdon, CS 90 046, 13067 St. Paul Lez Durance Cedex (France); Arshad, Shakeib [Fusion for Energy, Josep Pla 2, Torres Diagonal Litoral B3, 08019 Barcelona (Spain); Lister, Jonathan; Toussaint, Matthieu; Marmillod, Philippe; Testa, Duccio; Schlatter, Christian [Ecole polytechnique fédérale de Lausanne, Centre de Recherches en Physique des Plasmas, 1015 Lausanne (Switzerland); Peruzzo, Simone [Consorzio RFX, C.so Stati Uniti 4, 35127 Padova (Italy)

    2015-10-15

    Highlights: • ITER Continuous External Rogowskis are designed for plasma current measurement. • CER are located in the casing of Toroidal Field Coils and will operate at 4.5 K. • The design of the sensors has been completed and validated through prototypes. • Detailed assembly procedure inside the toroidal field coil casing has been defined. • The CER has passed all the ITER and F4E design review procedures. - Abstract: In ITER, an accurate measurement of plasma current, with high reliability, is mandatory as this parameter is used to demonstrate licensing compliance with regulatory limits. For that purpose, several independent measurements based on magnetic diagnostics have been proposed. Rogowski coils are standard inductive sensors for current measurement in many applications. In ITER, three continuous external Rogowski coils are to be installed in the casing of the toroidal field coils. These sensors are remarkable from several points of view: overall length is about 40 m, high sensitivity needed, located in the toroidal field coil casing at 4.5 K and complex 3D routing with tight bending radius of 50 mm. Since 2005 an extensive work has been carried out to develop and analyze several design options complying with ITER specifications. Prototypes of a selected continuous external Rogowski design were built and tested successfully in terms of electrical, thermal, mechanical and vacuum characteristics. Finally a detailed assembly procedure inside the toroidal field coil casing has been defined according to the coil manufacturing and assembly constraints.

  13. Empirical pillar design methods review report: Final report

    International Nuclear Information System (INIS)

    1988-02-01

    This report summarizes and evaluates empirical pillar design methods that may be of use during the conceptual design of a high-level nuclear waste repository in salt. The methods are discussed according to category (i.e, main, submain, and panel pillars; barrier pillars; and shaft pillars). Of the 21 identified for main, submain, and panel pillars, one method, the Confined Core Method, is evaluated as being most appropriate for conceptual design. Five methods are considered potentially applicable. Of six methods identified for barrier pillars, one method based on the Load Transfer Distance concept is considered most appropriate for design. Based on the evaluation of 25 methods identified for shaft pillars, an approximate sizing criterion is proposed for use in conceptual design. Aspects of pillar performance relating to creep, ground deformation, interaction with roof and floor rock, and response to high temperature environments are not adequately addressed by existing empirical design methods. 152 refs., 22 figs., 14 tabs

  14. Toward Meaningful Manufacturing Variation Data in Design - Feature Based Description of Variation in Manufacturing Processes

    DEFF Research Database (Denmark)

    Eifler, Tobias; Boorla, Srinivasa Murthy; Howard, Thomas J.

    2016-01-01

    a lack of objective variation data in design. As a result, variation analyses and tolerancing activities rely on numerous assumptions made to fill the gaps of missing or incomplete data. To overcome this hidden subjectivity, a schema for a consistent and standardised description of manufacturing...... variation is suggested. It extends existing ISO GPS annotation by information about influences on the manufacturability of a chosen design solution and in this way enables the systematic acquisition of variation data meaningful for design practice.......The need to mitigate the effects of manufacturing variation already in design is nowadays commonly acknowledged and has led to a wide use of predictive modeling techniques, tolerancing approaches, etc. in industry. The trustworthiness of corresponding variation analyses is, however, not ensured...

  15. IMS Learning Design Version 1.0 Final Specification

    NARCIS (Netherlands)

    Koper, Rob; Manderveld, Jocelyn; Sloep, Peter; Hummel, Hans; Vogten, Hubert; Brouns, Francis; Tattersall, Colin

    2006-01-01

    The IMS Learning Design specification supports the use of a wide range of pedagogies in online learning. Rather than attempting to capture the specifics of many pedagogies, it does this by providing a generic and flexible language. This language is designed to enable many different pedagogies to be

  16. Inertial Fusion Energy reactor design studies: Prometheus-L, Prometheus-H. Volume 2, Final report

    Energy Technology Data Exchange (ETDEWEB)

    Waganer, L.M.; Driemeyer, D.E.; Lee, V.D.

    1992-03-01

    This report contains a review of design studies for Inertial Confinement reactor. This second of three volumes discussions is some detail the following: Objectives, requirements, and assumptions; rationale for design option selection; key technical issues and R&D requirements; and conceptual design selection and description.

  17. Work zone design and operation enhancements : final report, March 2010.

    Science.gov (United States)

    2010-02-01

    Oregon Department of Transportation contractors are required to implement Traffic Control Plans (TCPs) to protect and direct traffic through work zones. The design and implementation of TCPs have shown variation from project-to-project across the Sta...

  18. Gas recombination device design and cost study. Final report

    Energy Technology Data Exchange (ETDEWEB)

    1980-07-01

    Under a contract with Argonne National Laboratory, VARTA Batterie AG. conducted a design and cost study of hydrogen-oxygen recombination devices (HORD) for use with utility load-leveling lead-acid cells. Design specifications for the devices, through extensive calculation of the heat-flow conditions of the unit, were developed. Catalyst and condenser surface areas were specified. The exact dimensions can, however, be adjusted to the cell dimension and the space available above the cell. Design specifications were also developed for additional components required to ensure proper function of the recombination device, including metal hydride compound decomposer, aerosol retainer, and gas storage component. Costs for HORD were estimated to range from $4 to $10/kWh cell capacity for the production of a large number of units (greater than or equal to 10,000 units). The cost is a function of cell size and positive grid design. 21 figures, 2 tables.

  19. Large pool LMFBR design. Final report. Volume 1

    Energy Technology Data Exchange (ETDEWEB)

    Wett, J. F.; Churchill, J. R.

    1979-03-01

    The design effort reported is an extension on past design effort and continuous concentration on those parts of the nuclear island unique to a commercial size pool type LMFBR. In particular, the work covers the reactor vessel, deck, rotating plugs, upper and lower internals, internal plenum separator system, IHX, pumps, cold traps, intermediate system layout, containment/confinement system, plot plan, and residual heat removal systems. Preliminary thermal, hydraulic, stress, and system analyses are also presented.

  20. The Reification of Patterns in the Design of Description-Driven Systems

    CERN Document Server

    Le Goff, J M; Kovács, Z; McClatchey, R

    2001-01-01

    To address the issues of reusability and evolvability in designing self- describing systems, this paper proposes a pattern-based, object-oriented, description-driven system architecture. The proposed architecture embodies four pillars - first, the adoption of a multi-layered meta-modeling architecture and reflective meta-level architecture, second, the identification of four data modeling relationships that must be made explicit such that they can be examined and modified dynamically, third, the identification of five design patterns which have emerged from practice and have proved essential in providing reusable building blocks for data management, and fourth, the encoding of the structural properties of the five design patterns by means of one pattern, the Graph pattern. The CRISTAL research project served as the basis onto which the pattern-based meta-object approach has been applied. The proposed architecture allows the realization of reusability and adaptability, and is fundamental in the specification o...

  1. Feasibility design study. Land-based OTEC plants. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Brewer, J. H.; Minor, J.; Jacobs, R.

    1979-01-01

    The purpose of this study has been to determine the feasibility of installing 10 MWe (MegaWatt-electric) and 40 MWe land-based OTEC demonstration power plants at two specific sites: Keahole Point on the western shore of the island of Hawaii; and Punta Tuna, on the southeast coast of the main island of Puerto Rico. In addition, the study has included development of design parameters, schedules and budgets for the design, construction and operation of these plants. Seawater systems (intake and discharge pipes) were to be sized so that flow losses were equivalent to those expected with a platform-based OTEC power plant. The power module (components and general arrangement was established based on the TRW design. Results are presented in detail. (WHK)

  2. Conceptual design of advanced central receiver power system. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Tracey, T. R.

    1978-09-01

    The design of a 300 MWe tower focus power plant which uses molten salt heat transfer fluids and sensible heat storage is described in detail. The system consists of nine heliostat fields with 7711 heliostats in each. Four cavity receivers are located at the top of a 155-meter tower. Tasks include: (1) review and analysis of preliminary specification; (2) parametric analysis; (3) selection of preferred configuration; (4) commercial plant conceptual design; (5) assessment of commercial-sized advanced central power system; (6) development plan; (7) program plan; (8) reports and data; (9) program management; (10) safety analysis; and (11) material study and test program. (WHK)

  3. Design and synthesis of reactive separation systems. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Doherty, M.F.

    1992-12-31

    During the last decade there has been a rapid upturn in interest in reactive distillation. The chemical process industry recognizes the favorable economics of carrying out reaction simultaneously with distillation for certain classes of reacting systems, and many new processes have been built based on this technology. Interest is also increasing by academics and software vendors. Systematic design methods for reactive distillation systems have only recently begun to emerge. In this report we survey the available design techniques and point out the contributions made by our group at the University of Massachusetts.

  4. Enhanced Internet firewall design using stateful filters final report

    Energy Technology Data Exchange (ETDEWEB)

    Hutchins, J.A. [Sandia National Labs., Livermore, CA (United States). Infrastructure and Networking Research Dept.; Simons, R.W. [Sandia National Labs., Albuquerque, NM (United States). Decision Support Systems Architectures

    1997-08-01

    The current state-of-the-art in firewall design provides a lot of security for company networks, but normally at the expense of performance and/or functionality. Sandia researched a new approach to firewall design which incorporates a highly stateful approach, allowing much more flexibility for protocol checking and manipulation while retaining performance. A prototype system was built and multiple protocol policy modules implemented to test the concept. The resulting system, though implemented on a low-power workstation, performed almost at the same performance as Sandia`s current firewall.

  5. AGC-1 Experiment and Final Preliminary Design Report

    Energy Technology Data Exchange (ETDEWEB)

    Robert L. Bratton; Tim Burchell

    2006-08-01

    This report details the experimental plan and design as of the preliminary design review for the Advanced Test Reactor Graphite Creep-1 graphite compressive creep capsule. The capsule will contain five graphite grades that will be irradiated in the Advanced Test Reactor at the Idaho National Laboratory to determine the irradiation induced creep constants. Seven other grades of graphite will be irradiated to determine irradiated physical properties. The capsule will have an irradiation temperature of 900 C and a peak irradiation dose of 5.8 x 10{sup 21} n/cm{sup 2} [E > 0.1 MeV], or 4.2 displacements per atom.

  6. Baseload Nitrate Salt Central Receiver Power Plant Design Final Report

    Energy Technology Data Exchange (ETDEWEB)

    Tilley, Drake [Abengoa Solar LLC, Lakewood, CO (United States); Kelly, Bruce [Abengoa Solar LLC, Lakewood, CO (United States); Burkholder, Frank [Abengoa Solar LLC, Lakewood, CO (United States)

    2014-12-12

    The objectives of the work were to demonstrate that a 100 MWe central receiver plant, using nitrate salt as the receiver coolant, thermal storage medium, and heat transport fluid in the steam generator, can 1) operate, at full load, for 6,400 hours each year using only solar energy, and 2) satisfy the DOE levelized energy cost goal of $0.09/kWhe (real 2009 $). To achieve these objectives the work incorporated a large range of tasks relating to many different aspects of a molten salt tower plant. The first Phase of the project focused on developing a baseline design for a Molten Salt Tower and validating areas for improvement. Tasks included a market study, receiver design, heat exchanger design, preliminary heliostat design, solar field optimization, baseline system design including PFDs and P&IDs and detailed cost estimate. The baseline plant met the initial goal of less than $0.14/kWhe, and reinforced the need to reduce costs in several key areas to reach the overall $0.09/kWhe goal. The major improvements identified from Phase I were: 1) higher temperature salt to improve cycle efficiency and reduce storage requirements, 2) an improved receiver coating to increase the efficiency of the receiver, 3) a large receiver design to maximize storage and meet the baseload hours objective, and 4) lower cost heliostat field. The second Phase of the project looked at advancing the baseline tower with the identified improvements and included key prototypes. To validate increasing the standard solar salt temperature to 600 °C a dynamic test was conducted at Sandia. The results ultimately proved the hypothesis incorrect and showed high oxide production and corrosion rates. The results lead to further testing of systems to mitigate the oxide production to be able to increase the salt temperature for a commercial plant. Foster Wheeler worked on the receiver design in both Phase I and Phase II looking at both design and lowering costs utilizing commercial fossil boiler

  7. 75 FR 52860 - Final Airworthiness Design Standards for Acceptance Under the Primary Category Rule; Orlando...

    Science.gov (United States)

    2010-08-30

    ... DEPARTMENT OF TRANSPORTATION Federal Aviation Administration 14 CFR Part 21 Final Airworthiness Design Standards for Acceptance Under the Primary Category Rule; Orlando Helicopter Airways (OHA), Inc... Existence of Proposed Airworthiness Design Standards for Acceptance Under the Primary Category Rule; Orlando...

  8. Fifth SIAM conference on geometric design 97: Final program and abstracts. Final technical report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-12-31

    The meeting was divided into the following sessions: (1) CAD/CAM; (2) Curve/Surface Design; (3) Geometric Algorithms; (4) Multiresolution Methods; (5) Robotics; (6) Solid Modeling; and (7) Visualization. This report contains the abstracts of papers presented at the meeting. Proceding the conference there was a short course entitled ``Wavelets for Geometric Modeling and Computer Graphics``.

  9. System requirements and design description for the document basis database interface (DocBasis)

    International Nuclear Information System (INIS)

    Lehman, W.J.

    1997-01-01

    This document describes system requirements and the design description for the Document Basis Database Interface (DocBasis). The DocBasis application is used to manage procedures used within the tank farms. The application maintains information in a small database to track the document basis for a procedure, as well as the current version/modification level and the basis for the procedure. The basis for each procedure is substantiated by Administrative, Technical, Procedural, and Regulatory requirements. The DocBasis user interface was developed by Science Applications International Corporation (SAIC)

  10. Cold Vacuum Drying Facility Crane and Hoist System Design Description. System 14

    International Nuclear Information System (INIS)

    TRAN, Y.S.

    2000-01-01

    This system design description (SDD) is for the Cold Vacuum Drying (CVD) Facility overhead crane and hoist system. The overhead crane and hoist system is a general service system. It is located in the process bays of the CVD Facility, supports the processes required to drain the water and dry the spent nuclear fuel (SNF) contained in the multi-canister overpacks (MCOs) after they have been removed from the K-Basins. The location of the system in the process bay is shown

  11. Design and implementation of an XML based object-oriented detector description database for CMS

    International Nuclear Information System (INIS)

    Liendl, M.

    2003-04-01

    This thesis deals with the development of a detector description database (DDD) for the compact muon solenoid (CMS) experiment at the large hadron collider (LHC) located at the European organization for nuclear research (CERN). DDD is a fundamental part of the CMS offline software with its main applications, simulation and reconstruction. Both are in need of different models of the detector in order to efficiently solve their specific tasks. In the thesis the requirements to a detector description database are analyzed and the chosen solution is described in detail. It comprises the following components: an XML based detector description language, a runtime system that implements an object-oriented transient representation of the detector, and an application programming interface to be used by client applications. One of the main aspects of the development is the design of the DDD components. The starting point is a domain model capturing concisely the characteristics of the problem domain. The domain model is transformed into several implementation models according to the guidelines of the model driven architecture (MDA). Implementation models and appropriate refinements thereof are foundation for adequate implementations. Using the MDA approach, a fully functional prototype was realized in C++ and XML. The prototype was successfully tested through seamless integration into both the simulation and the reconstruction framework of CMS. (author)

  12. Prototypical spent nuclear fuel rod consolidation equipment: Phase 2, Final design report: Volume 3, Appendices: Part 2

    International Nuclear Information System (INIS)

    1987-01-01

    The purpose of this report is to identify and analyze a range of credible events and accident occurrences (from minor to the design basis accidents) and their causes and consequences. For each situation, the considerations to prevent or mitigate the event or accident are to be addressed. The report includes a description of the approach used to identify the potential events or accidents (Section 3.0), a discussion of Off-Normal Events (Section 4.0), and finally a discussion of Accidents (Section 5.0)

  13. Dedicated medical ion accelerator design study. Final report

    International Nuclear Information System (INIS)

    1977-12-01

    Results and conclusions are reported from a design study for a dedicated medical accelerator. Basing efforts on the current consensus regarding medical requirements, the resulting demands on accelerator and beam delivery systems were analyzed, and existing accelerator technology was reviewed to evaluate the feasibility of meeting these demands. This general analysis was augmented and verified by preparing detailed preliminary designs for sources of therapeutic beams of neutrons, protons and heavy ions. The study indicates that circular accelerators are the most desirable and economical solutions for such sources. Synchrotrons are clearly superior for beams of helium and heavier ions, while synchrotrons and cyclotrons seem equally well suited for protons although they have different strengths and weaknesses. Advanced techniques of beam delivery are of utmost importance in fully utilizing the advantages of particle beams. Several issues are invloved here. First, multi-treatment room arrangements are essential for making optimal use of the high dose rate capabilities of ion accelerators. The design of corresponding beam switching systems, the principles of which are already developed for physics experimental areas, pose no problems. Second, isocentric beam delivery substantially enhances flexibility of dose delivery. After several designs for such devices were completed, it was concluded that high field magnets are necessary to keep size, bulk and cost acceptable. Third, and most important, is the generation of large, homogeneous radiation fields. This is presently accomplished with the aid of scattering foils, occluding rings, collimators, ridge filters, and boluses. A novel approach, three-dimensional beam scanning, was developed here, and the most demanding components of such a system (fast-scanning magnet and power supply) were built and tested

  14. Photovoltaic subsystem optimization and design tradeoff study. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Stolte, W.J.

    1982-03-01

    Tradeoffs and subsystem choices are examined in photovoltaic array subfield design, power-conditioning sizing and selection, roof- and ground-mounted structure installation, energy loss, operating voltage, power conditioning cost, and subfield size. Line- and self-commutated power conditioning options are analyzed to determine the most cost-effective technology in the megawatt power range. Methods for reducing field installation of flat panels and roof mounting of intermediate load centers are discussed, including the cost of retrofit installations.

  15. Final design of the generic upper port plug structure for ITER diagnostic systems

    NARCIS (Netherlands)

    Pak, S.; Feder, R.; Giacomin, T.; Guirao, J.; Iglesias, S.; Josseaume, F.; Kalish, M.; Loesser, D.; Maquet, P.; Ronden, D.; Ordieres, J.; Panizo, M.; Pitcher, S.; M. Portalès,; Proust, M.; Serikov, A.; Suarez, A.; Tanchuk, V.; Udintsev, V.; Vacas, C.; Walsh, M.; Zhai, Y.

    2016-01-01

    The generic upper port plug (GUPP) structure in ITER is a 6 m long metal box which deploys diagnostic components into the vacuum vessel. This structure is commonly used for all the diagnostic upper ports. The final design of the GUPP structure, which has successfully passed the final design review

  16. Cold Vacuum Drying facility personnel monitoring system design description (SYS 12); FINAL

    International Nuclear Information System (INIS)

    PITKOFF, C.C.

    1999-01-01

    This document describes the Cold Vacuum Drying Facility (CVDF) instrument air (IA) system that provides instrument quality air to the CVDF. The IA system provides the instrument quality air used in the process, HVAC, and HVAC instruments. The IA system provides the process skids with air to aid in the purging of the annulus of the transport cask. The IA system provides air for the solenoid-operated valves and damper position controls for isolation, volume, and backdraft in the HVAC system. The IA system provides air for monitoring and control of the HVAC system, process instruments, gas-operated valves, and solenoid-operated instruments. The IA system also delivers air for operating hand tools in each of the process bays

  17. High quality Danish design with intelligent LED light. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Petersen, Paul Michael; Dam-Hansen, C.; Thestrup, B.; Pedersen, Henrik (Technical Univ. of Denmark, DTU Fotonik, Roskilde (Denmark)); Olsen, Jesper (JesperOlsen ApS, Frederiksberg (Denmark)); Falleboe, H.; Andersen, Jakob (MORFOSO, Copenhagen (Denmark))

    2010-02-15

    Based on the results achieved in a previous project, which enabled a number of designers to be trained in the potential of LED lighting technology, this project developed intelligent LED fixtures for work purposes and for private homes. The two types of fixtures both meet the original project objective of good colour rendition with Ra indices above 90 and colour temperatures variable within the interval 3,300 to 4,400 K. Furthermore, with luminous efficacies of 60 lumen/W, both fixtures have energy efficiencies exceeding that of an average energy-friendly light source. (ln)

  18. Laser fusion systems design study. Final technical report

    International Nuclear Information System (INIS)

    1975-06-01

    This study investigated: (1) the formulation and evaluation of an alignment system to accomplish pointing, focusing, centering and translation for the 20-arm SHIVA laser, (2) the formulation and evaluation of concepts for the correction of static phase distortions introduced by the accumulated optical elements in the laser chains, (3) the formulation and evaluation of concepts for the correction of optical path length differences between the arms of the SHIVA system, and (4) the conceptual design of appropriate control system hardware. (U.S.)

  19. Cold Vacuum Dryer (CVD) Facility Fire Protection System Design Description (SYS 24)

    Energy Technology Data Exchange (ETDEWEB)

    SINGH, G.

    2000-10-17

    This system design description (SDD) addresses the Cold Vacuum Drying (CVD) Facility fire protection system (FPS). The primary features of the FPS for the CVD are a fire alarm and detection system, automatic sprinklers, and fire hydrants. The FPS also includes fire extinguishers located throughout the facility and fire hydrants to assist in manual firefighting efforts. In addition, a fire barrier separates the operations support (administrative) area from the process bays and process bay support areas. Administrative controls to limit combustible materials have been established and are a part of the overall fire protection program. The FPS is augmented by assistance from the Hanford Fire Department (HED) and by interface systems including service water, electrical power, drains, instrumentation and controls. This SDD, when used in conjunction with the other elements of the definitive design package, provides a complete picture of the FPS for the CVD Facility.

  20. VHTR engineering design study: intermediate heat exchanger program. Final report

    Energy Technology Data Exchange (ETDEWEB)

    None

    1976-11-01

    The work reported is the result of a follow-on program to earlier Very High Temperature Reactor (VHTR) studies. The primary use of the VHTR is to provide heat for various industrial processes, such as hydrocarbon reforming and coal gasification. For many processes the use of an intermediate heat transfer barrier between the reactor coolant and the process is desirable; for some processes it is mandatory. Various intermediate heat exchanger (IHX) concepts for the VHTR were investigated with respect to safety, cost, and engineering design considerations. The reference processes chosen were steam-hydrocarbon reforming, with emphasis on the chemical heat pipe, and steam gasification of coal. The study investigates the critically important area of heat transfer between the reactor coolant, helium, and the various chemical processes.

  1. VHTR engineering design study: intermediate heat exchanger program. Final report

    International Nuclear Information System (INIS)

    1976-11-01

    The work reported is the result of a follow-on program to earlier Very High Temperature Reactor (VHTR) studies. The primary use of the VHTR is to provide heat for various industrial processes, such as hydrocarbon reforming and coal gasification. For many processes the use of an intermediate heat transfer barrier between the reactor coolant and the process is desirable; for some processes it is mandatory. Various intermediate heat exchanger (IHX) concepts for the VHTR were investigated with respect to safety, cost, and engineering design considerations. The reference processes chosen were steam-hydrocarbon reforming, with emphasis on the chemical heat pipe, and steam gasification of coal. The study investigates the critically important area of heat transfer between the reactor coolant, helium, and the various chemical processes

  2. Thermal hydraulic design features for the BNCT application. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Blue, T.E.; Vafai, K.

    1993-06-01

    This project report is based on our investigations for thermal design of a heat pipe for removing generated heat resulting from Proton bombardments of a Lithium target for a BNCT application. In our investigation, an integral analysis was employed to investigate the vapor an liquid flow in a flat plate heat pipe heated asymmetrically for removal of the 75 kW generated from the BNCT application. The flat plate heat pipe configuration will be used for removing the heat which is generated as a result of proton bombardment of the lithium target. The working fluid in the heat pipe occurs in two phase namely liquid and vapor. The wick contains all the liquid phase and the vapor phase is mainly in the core region. Heat is applied by an external source at the evaporator section which vaporizes the working fluid in this section. This results in a pressure difference which drives the vapor to the condenser section where condenses and releases latent heat of vaporization to a heat sink in the condense section. Due to the vaporization of liquid in the evaporator, the liquid-vapor interface enters into the wick surface and hence capillary pressure is developed there. This capillary pressure causes the condensed liquid in the condenser to be pumped back to the evaporator again. The results of our investigation have enabled us to correlate such diverse information as; the thickness of the wick, the diameter of the heat pipe, the wetting angle, the capillary radius, the surface tension, the latent heat of evaporation, the permeability and porosity of the chosen wick, the length of the heat pipe, and the viscosity and density of the two phases; with the heat removal capabilities of the heat pipe. Expressions for the pressure and velocity distributions are obtained and discussed in relation to our application to BNCT. The present design clearly shows that it is possible to attain temperatures well below the melting temperature of the lithium in the BNCT application.

  3. General Description of the Mechanic Design of the Pressure Vessel and the Internal Mechanical Component of the CAREM Reactor

    International Nuclear Information System (INIS)

    Diez, F.; Horro, R.

    2000-01-01

    This paper presents a brief description of the CAREM reactor pressure vessel and its main internal mechanical components and summarizes the functional requirements and approaches applied for their design, together with a review of the normative applicable in each case

  4. Preliminary designs for modular OTEC platform station-keeping subsystems. Final report. MR and S Report No. 6042-6

    Energy Technology Data Exchange (ETDEWEB)

    None

    1980-02-29

    This volume of the report presents the results of the third through the sixth tasks of the Station Keeping Subsystem (SKSS) design studies for 10/40 MW/sub e/ capacity OTEC Modular Experiment platforms (MEP). Tasks 3 through 6 are: (3) complete preliminary designs for one SKSS for each of the two platforms (SPAR and BARGE); (4) development and testing recommendations for the MEP SKSS; (5) cost-time analysis; and (6) commercial plant recommendations. The overall conclusions and recommendations for the modular, as well as the commercial, OTEC platform station keeping subsystems are delineated. The basic design assumptions made during the process, the technical approach followed, and the results of design iterations, reliability and performance analyses are given. A complete description of the preliminary design SKSS concept is presented. The summary cost estimates for each of the alternative SKSS concepts considered are presented and a time schedule for the recommended concept is provided. The effects of varying some of the important parameters used in SKSS design on the performance and cost of the mooring system are investigated and results presented. The tests required and other developmental recommendations in order to verify and confirm the basic design assumptions are discussed. Finally, the experience gained in the MEP preliminary designs are extended to future commercial OTEC plants' SKSS designs. (WHK)

  5. Design description and performance analyses of the European HCPB test blanket system in ITER feat

    Energy Technology Data Exchange (ETDEWEB)

    Boccaccini, L.V. E-mail: lorenzo.boccaccini@irs.fzk.de; Bekris, N.; Chen, Y.; Fischer, U.; Gordeev, S.; Hermsmeyer, S.; Hutter, E.; Kleefeldt, K.; Malang, S.; Schleisiek, K.; Schmuck, I.; Schnauder, H.; Tsige-Tamirat, H

    2002-11-01

    The helium cooled pebble bed (HCPB) blanket is one of the two European DEMO blanket concepts proposed for testing in international thermonuclear experimental reactor (ITER). The purpose of the tests is to validate the design principles and the operational feasibility for the demonstration blanket system. This includes the basic support functions like tritium extraction, helium cooling and heat transport, and helium purification. In addition, the basic properties and operating characteristics of the system's materials will be validated. Safety, reliability, maintenance and dismantling will be equally addressed. To assess these qualities, the ITER horizontal ports will be used to provide a relevant fusion plasma and the appropriate nuclear environment. At conclusion of the ITER feat EDA phase (July 2001), a revised design of the HCPB test blanket system have been completed to adapt the previous design (for ITER FDR) to the new operational conditions of ITER and to a new strategy for the blanket testing in this reactor. Design description, performance and safety analyses are presented in this paper.

  6. The family of standard hydrogen monitoring system computer software design description: Revision 2

    International Nuclear Information System (INIS)

    Bender, R.M.

    1994-01-01

    In March 1990, 23 waste tanks at the Hanford Nuclear Reservation were identified as having the potential for the buildup of gas to a flammable or explosive level. As a result of the potential for hydrogen gas buildup, a project was initiated to design a standard hydrogen monitoring system (SHMS) for use at any waste tank to analyze gas samples for hydrogen content. Since it was originally deployed three years ago, two variations of the original system have been developed: the SHMS-B and SHMS-C. All three are currently in operation at the tank farms and will be discussed in this document. To avoid confusion in this document, when a feature is common to all three of the SHMS variants, it will be referred to as ''The family of SHMS.'' When it is specific to only one or two, they will be identified. The purpose of this computer software design document is to provide the following: the computer software requirements specification that documents the essential requirements of the computer software and its external interfaces; the computer software design description; the computer software user documentation for using and maintaining the computer software and any dedicated hardware; and the requirements for computer software design verification and validation

  7. Blade System Design Study. Part II, final project report (GEC).

    Energy Technology Data Exchange (ETDEWEB)

    Griffin, Dayton A. (DNV Global Energy Concepts Inc., Seattle, WA)

    2009-05-01

    As part of the U.S. Department of Energy's Low Wind Speed Turbine program, Global Energy Concepts LLC (GEC)1 has studied alternative composite materials for wind turbine blades in the multi-megawatt size range. This work in one of the Blade System Design Studies (BSDS) funded through Sandia National Laboratories. The BSDS program was conducted in two phases. In the Part I BSDS, GEC assessed candidate innovations in composite materials, manufacturing processes, and structural configurations. GEC also made recommendations for testing composite coupons, details, assemblies, and blade substructures to be carried out in the Part II study (BSDS-II). The BSDS-II contract period began in May 2003, and testing was initiated in June 2004. The current report summarizes the results from the BSDS-II test program. Composite materials evaluated include carbon fiber in both pre-impregnated and vacuum-assisted resin transfer molding (VARTM) forms. Initial thin-coupon static testing included a wide range of parameters, including variation in manufacturer, fiber tow size, fabric architecture, and resin type. A smaller set of these materials and process types was also evaluated in thin-coupon fatigue testing, and in ply-drop and ply-transition panels. The majority of materials used epoxy resin, with vinyl ester (VE) resin also used for selected cases. Late in the project, testing of unidirectional fiberglass was added to provide an updated baseline against which to evaluate the carbon material performance. Numerous unidirectional carbon fabrics were considered for evaluation with VARTM infusion. All but one fabric style considered suffered either from poor infusibility or waviness of fibers combined with poor compaction. The exception was a triaxial carbon-fiberglass fabric produced by SAERTEX. This fabric became the primary choice for infused articles throughout the test program. The generally positive results obtained in this program for the SAERTEX material have led to its

  8. Description of research design of articles published in four Brazilian physical therapy journals.

    Science.gov (United States)

    Saragiotto, Bruno T; Costa, Lucíola C M; Oliveira, Ronaldo F; Lopes, Alexandre D; Moseley, Anne M; Costa, Leonardo O P

    2014-01-01

    While the research design of articles published in medical journals and in some physical therapy journals has already been evaluated, this has not been investigated in Brazilian physical therapy journals. Objective : To describe the research design used in all articles published in Brazilian scientific journals that are freely available, have high Qualis rankings, and are relevant to physical therapy over a 7-year period. We extracted the bibliometric data, research design, research type (human or animal), and clinical area for all articles published. The articles were grouped into their level of evidence, and descriptive analyses were performed. We calculated the frequency, proportions of articles, and 95% confidence interval of these proportions with each research design in each journal. We cross-tabulated the clinical areas with research designs (expressed as number and percentages). A total of 1,458 articles from four Brazilian journals were found: Revista Brasileira de Fisioterapia, Revista Fisioterapia em Movimento, Revista Fisioterapia e Pesquisa, and Revista Acta Fisiátrica. The majority of articles were classified as level II of evidence (60%), followed by level III (29%) and level I (10%). The most prevalent research designs were cross-sectional studies (38%), single-case or case-series studies, and narrative reviews. Most articles reported human research and were in the musculoskeletal, neurologic, and cardiothoracic areas. Most of the research published in Brazilian physical therapy journals used levels II and III of evidence. Increasing the publication rate of systematic reviews and randomized controlled trials would provide more high-quality evidence to guide evidence-based physical therapy practice.

  9. Computer system design description for SY-101 hydrogen mitigation test project data acquisition and control system (DACS-1)

    Energy Technology Data Exchange (ETDEWEB)

    Ermi, A.M.

    1997-05-01

    Description of the Proposed Activity/REPORTABLE OCCURRENCE or PIAB: This ECN changes the computer systems design description support document describing the computers system used to control, monitor and archive the processes and outputs associated with the Hydrogen Mitigation Test Pump installed in SY-101. There is no new activity or procedure associated with the updating of this reference document. The updating of this computer system design description maintains an agreed upon documentation program initiated within the test program and carried into operations at time of turnover to maintain configuration control as outlined by design authority practicing guidelines. There are no new credible failure modes associated with the updating of information in a support description document. The failure analysis of each change was reviewed at the time of implementation of the Systems Change Request for all the processes changed. This document simply provides a history of implementation and current system status.

  10. Computer system design description for SY-101 hydrogen mitigation test project data acquisition and control system (DACS-1)

    International Nuclear Information System (INIS)

    Ermi, A.M.

    1997-01-01

    Description of the Proposed Activity/REPORTABLE OCCURRENCE or PIAB: This ECN changes the computer systems design description support document describing the computers system used to control, monitor and archive the processes and outputs associated with the Hydrogen Mitigation Test Pump installed in SY-101. There is no new activity or procedure associated with the updating of this reference document. The updating of this computer system design description maintains an agreed upon documentation program initiated within the test program and carried into operations at time of turnover to maintain configuration control as outlined by design authority practicing guidelines. There are no new credible failure modes associated with the updating of information in a support description document. The failure analysis of each change was reviewed at the time of implementation of the Systems Change Request for all the processes changed. This document simply provides a history of implementation and current system status

  11. The ITER ECH & CD Upper Launcher: Steps towards final design of the first confinement system

    NARCIS (Netherlands)

    Spaeh, P.; Aiello, G.; Bertizzolo, R.; Chavan, R.; Gessner, R.; Goodman, T.; Grossetti, G.; Henderson, M.; Krause, A.; Landis, J. D.; Meier, A.; Ronden, D.; Saibene, G.; Scherer, T.; Schreck, S.; Serikov, A.; Strauss, D.; Vaccaro, A.; Weinhorst, B.

    2013-01-01

    The ITER Electron Cyclotron Heating and Current Drive (ECH&CD) Upper Launcher, whose preliminary design was approved in 2009, is on its way towards the final design. The design work is being done by a consortium of several European research institutes in tight collaboration with F4E. The main

  12. Exercise in completing design information questionnaire for model research reactor: model description, notes, questionnaire

    International Nuclear Information System (INIS)

    Bellinger, J.; Ho, T.

    1989-01-01

    The document which defines the inspection measures which the IAEA can deploy at any given nuclear facility is known as the Facility Attachment. For the Agency to negotiate an effective Facility Attachment it must have available certain design information, including the facility's identity, capacity and location; the form, location and flow of nuclear material and the layout of important items of equipment; and a description of the features and procedures relating to nuclear material accountancy, containment and surveillance. In practice such information is solicited in a format, standardized for each facility type, known as the Design Information Questionnaire or the D.I.Q. The nuclear activities used as a model in this course are those of a fictitious country called Pacifica. These nuclear activities bear some resemblance to those at the Australian Atomic Energy Commission's Research Establishment at Lucas Heights. Specifically, Pacifica has a 10 MW heavy water cooled and moderated research reactor using enriched uranium fuel which is very similar to the HIFAR reactor. The reactor and the associated laboratories are described and the Design Information Questionnaire for them is completed. figs., tabs

  13. Passive solar commercial buildings: design assistance and demonstration program. Phase 1. Final report

    Energy Technology Data Exchange (ETDEWEB)

    None

    1981-01-26

    The final design of the Mount Airy Public Library is given. Incremental passive design costs are discussed. Performance and economic analyses are made and the results reported. The design process is thoroughly documented. Considerations discussed are: (1) building energy needs; (2) site energy potentials, (3) matching energy needs with site energy potentials, (4) design indicators for best strategies and concepts, (5) schematic design alternatives, (6) performance testing of the alternatives, (7) design selection, and (8) design development. Weather data and Duke Power electric rates are included. (LEW)

  14. Planning, design, and construction of nuclear power plants: an overview. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Rhodes, D.A.; Rad, P.F.

    1977-12-01

    Chapters are included on generation system descriptions and alternative energy sources; load forecasting and growth projections; utility studies, program development, and analytical models; organizational alternatives and contract arrangements; project control in the design and construction phase; site management activities; construction activities; and startup and testing.

  15. Planning, design, and construction of nuclear power plants: an overview. Final report

    International Nuclear Information System (INIS)

    Rhodes, D.A.; Rad, P.F.

    1977-12-01

    Chapters are included on generation system descriptions and alternative energy sources; load forecasting and growth projections; utility studies, program development, and analytical models; organizational alternatives and contract arrangements; project control in the design and construction phase; site management activities; construction activities; and startup and testing

  16. A self-description data framework for Tokamak control system design

    International Nuclear Information System (INIS)

    Zhang, Ming; Zhang, Jing; Zheng, Wei; Hu, Feiran; Zhuang, Ge

    2015-01-01

    Highlights: • The SDD framework can be applied to different Tokamak devices. • We explain how configuration settings of control systems are described in SDD models, namely components and connections. • Evolving SDD models are stored in a dynamic schema database. • The SDD editor supports plug-and-play SDD models. - Abstract: A Tokamak device consists of numerous control systems, which need to be integrated. CODAC (Control, Data Access and Communication) system requires the configuration settings of these control systems to carry out the integration smoothly. SDD (Self-description data) is designed to describe the static configuration of control systems. ITER CODAC group has released an SDD software package for control system designers to manage the static configuration, but it is specific for ITER plant control systems. Following the idea of ITER SDD, we developed a flexible and scalable SDD framework to develop SDD software for J-TEXT and other sophisticated devices. The SDD framework describes the configuration settings of various control systems, including physical and logical elements and their relation information, in SDD models which are classified into Components and Connections. The framework is composed of three layers: the MongoDB database, an open-source, dynamic schema, NoSQL (Not Only SQL) database; the SDD service, which maps SDD models to MongoDB and handles the transaction and business logic; the SDD applications, which can be used to create and maintain SDD information, and generate various kinds of output using the stored SDD information.

  17. A self-description data framework for Tokamak control system design

    Energy Technology Data Exchange (ETDEWEB)

    Zhang, Ming; Zhang, Jing [State Key Laboratory of Advanced Electromagnetic Engineering and Technology, Huazhong University of Science and Technology, Wuhan 430074 (China); School of Electrical and Electronic Engineering, Huazhong University of Science and Technology, Wuhan 430074 (China); Zheng, Wei, E-mail: zhengwei@hust.edu.cn [State Key Laboratory of Advanced Electromagnetic Engineering and Technology, Huazhong University of Science and Technology, Wuhan 430074 (China); School of Electrical and Electronic Engineering, Huazhong University of Science and Technology, Wuhan 430074 (China); Hu, Feiran; Zhuang, Ge [State Key Laboratory of Advanced Electromagnetic Engineering and Technology, Huazhong University of Science and Technology, Wuhan 430074 (China); School of Electrical and Electronic Engineering, Huazhong University of Science and Technology, Wuhan 430074 (China)

    2015-10-15

    Highlights: • The SDD framework can be applied to different Tokamak devices. • We explain how configuration settings of control systems are described in SDD models, namely components and connections. • Evolving SDD models are stored in a dynamic schema database. • The SDD editor supports plug-and-play SDD models. - Abstract: A Tokamak device consists of numerous control systems, which need to be integrated. CODAC (Control, Data Access and Communication) system requires the configuration settings of these control systems to carry out the integration smoothly. SDD (Self-description data) is designed to describe the static configuration of control systems. ITER CODAC group has released an SDD software package for control system designers to manage the static configuration, but it is specific for ITER plant control systems. Following the idea of ITER SDD, we developed a flexible and scalable SDD framework to develop SDD software for J-TEXT and other sophisticated devices. The SDD framework describes the configuration settings of various control systems, including physical and logical elements and their relation information, in SDD models which are classified into Components and Connections. The framework is composed of three layers: the MongoDB database, an open-source, dynamic schema, NoSQL (Not Only SQL) database; the SDD service, which maps SDD models to MongoDB and handles the transaction and business logic; the SDD applications, which can be used to create and maintain SDD information, and generate various kinds of output using the stored SDD information.

  18. College students' perceptions of sexual orientation and gender given job descriptions and titles for interior decoration, interior design, and architecture.

    Science.gov (United States)

    Wood-Nartker, B Jeanneane; Sepanski, Jungsywan; McCrady, Joe; Gligor, Andreea

    2007-06-01

    To examine perceptions of design professionals, this study was designed to examine possible gender-bias based on job title and description and whether there is a relationship between the two perceptions. A respondent's sex was significantly related to perceptions of a design professional's sex. Both respondents' sex and the perceived sex of the design professional had significant effects on the perceived sexual orientation of the design professionals. Furthermore, the results also indicated that if the design professional was perceived to be male, there was a higher tendency that he would be perceived as homosexual, especially by a male respondent.

  19. Technical basis for the ITER final design report, cost review and safety analysis (FDR)

    International Nuclear Information System (INIS)

    1998-01-01

    The ITER final design report, cost review and safety analysis (FDR) is the 4th major milestone, representing the progress made in the ITER Engineering Design Activities. With the approval of the Detailed Design Report (DDR), the design work was concentrated on the requirements of operation, with only relatively minor changes to design concepts of major components. The FDR is the culmination of almost 6 years collaborative design and supporting technical work by the ITER Joint Central Team and Home Teams under the terms of the ITER EDA Agreement

  20. Modifications of the design of the final transformer in the FFS to accommodate lower gradients in the final quadrupole triplet

    International Nuclear Information System (INIS)

    Murray, J.J.

    1983-01-01

    The final transformer of the FFS includes the soft bend magnet and two symmetric quadrupole triplets. It ends at the IP. It is a telescopic transformer (meaning that its transfer matrix is diagonal) with a magnification of -1/5 in both planes. In the current design, L*, the distance between the downstream end of Q1 and the IP, is equal to 7.25 feet (2.21 m) and space is provided upstream of Q6 to accommodate a 27 foot long soft bend magnet. Satisfaction of the foregoing conditions leads to field gradients of about 19.8 kg/cm in Q1 and Q3 and 18.1 kg/cm in Q2. It now appears that it would be very difficult to attain such gradients. For practical superconducting quad designs, meaning iron-free, 5 cm bore, two-layer windings and 4.2 0 K, experts have estimated that gradients of at least 14 kg/cm would be reasonable. This raises the question, can the final transformer in the FFS be modified to accommodate gradients of 14 kg/cm or less and if so at what price in performance

  1. Material control in nuclear fuel fabrication facilities. Part I. Fuel descriptions and fabrication processes, P.O. 1236909 Final report

    International Nuclear Information System (INIS)

    Borgonovi, G.M.; McCartin, T.J.; Miller, C.L.

    1978-12-01

    The report presents information on foreign nuclear fuel fabrication facilities. Fuel descriptions and fuel fabrication information for three basic reactor types are presented: The information presented for LWRs assumes that Pu--U Mixed Oxide Fuel (MOX) will be used as fuel

  2. Material control in nuclear fuel fabrication facilities. Part I. Fuel descriptions and fabrication processes, P. O. 1236909 Final report

    Energy Technology Data Exchange (ETDEWEB)

    Borgonovi, G.M.; McCartin, T.J.; Miller, C.L.

    1978-12-01

    The report presents information on foreign nuclear fuel fabrication facilities. Fuel descriptions and fuel fabrication information for three basic reactor types are presented: The information presented for LWRs assumes that Pu--U Mixed Oxide Fuel (MOX) will be used as fuel.

  3. Experimental and Theoretical Progress of Linear Collider Final Focus Design and ATF2 Facility

    CERN Document Server

    Seryi, Andrei; Zimmermann, Frank; Kubo, Kiyoshi; Kuroda, Shigeru; Okugi, Toshiyuki; Tauchi, Toshiaki; Terunuma, Nobuhiro; Urakawa, Junji; White, Glen; Woodley, Mark; Angal-Kalinin, Deepa

    2014-01-01

    In this brief overview we will reflect on the process of the design of the linear collider (LC) final focus (FF) optics, and will also describe the theoretical and experimental efforts on design and practical realisation of a prototype of the LC FF optics implemented in the ATF2 facility at KEK, Japan, presently being commissioned and operated.

  4. 77 FR 56241 - Notice of Withdrawal of Final Design Approval; Westinghouse Electric Company; Advanced Passive 1000

    Science.gov (United States)

    2012-09-12

    ... No. ML060110467, referenced Revision 15 of the AP1000 design control document (DCD). As amended on... versions of the AP1000 design--an FDA for Revision 15 of the AP1000 DCD and a DCR for Revision 19 of the... reflect the version of the DCD approved and incorporated by reference as part of the final DC rulemaking...

  5. DESCRIPTION OF MODELING ANALYSES IN SUPPORT OF THE 200-ZP-1 REMEDIAL DESIGN/REMEDIAL ACTION

    Energy Technology Data Exchange (ETDEWEB)

    VONGARGEN BH

    2009-11-03

    The Feasibility Study/or the 200-ZP-1 Groundwater Operable Unit (DOE/RL-2007-28) and the Proposed Plan/or Remediation of the 200-ZP-1 Groundwater Operable Unit (DOE/RL-2007-33) describe the use of groundwater pump-and-treat technology for the 200-ZP-1 Groundwater Operable Unit (OU) as part of an expanded groundwater remedy. During fiscal year 2008 (FY08), a groundwater flow and contaminant transport (flow and transport) model was developed to support remedy design decisions at the 200-ZP-1 OU. This model was developed because the size and influence of the proposed 200-ZP-1 groundwater pump-and-treat remedy will have a larger areal extent than the current interim remedy, and modeling is required to provide estimates of influent concentrations and contaminant mass removal rates to support the design of the aboveground treatment train. The 200 West Area Pre-Conceptual Design/or Final Extraction/Injection Well Network: Modeling Analyses (DOE/RL-2008-56) documents the development of the first version of the MODFLOW/MT3DMS model of the Hanford Site's Central Plateau, as well as the initial application of that model to simulate a potential well field for the 200-ZP-1 remedy (considering only the contaminants carbon tetrachloride and technetium-99). This document focuses on the use of the flow and transport model to identify suitable extraction and injection well locations as part of the 200 West Area 200-ZP-1 Pump-and-Treat Remedial Design/Remedial Action Work Plan (DOEIRL-2008-78). Currently, the model has been developed to the extent necessary to provide approximate results and to lay a foundation for the design basis concentrations that are required in support of the remedial design/remediation action (RD/RA) work plan. The discussion in this document includes the following: (1) Assignment of flow and transport parameters for the model; (2) Definition of initial conditions for the transport model for each simulated contaminant of concern (COC) (i.e., carbon

  6. Solar Pilot Plant, Phase I. Preliminary design report. Volume II. System description and system analysis. CDRL item 2

    Energy Technology Data Exchange (ETDEWEB)

    None

    1977-05-01

    Honeywell conducted a parametric analysis of the 10-MW(e) solar pilot plant requirements and expected performance and established an optimum system design. The main analytical simulation tools were the optical (ray trace) and the dynamic simulation models. These are described in detail in Books 2 and 3 of this volume under separate cover. In making design decisions, available performance and cost data were used to provide a design reflecting the overall requirements and economics of a commercial-scale plant. This volume contains a description of this analysis/design process and resultant system/subsystem design and performance.

  7. Implementing a Description Grammar Interpreter : A Notation for Descriptions and Description Rules

    NARCIS (Netherlands)

    Stouffs, R.M.F.

    2015-01-01

    Description grammars represent a formalism for generating verbal descriptions of designs, used in conjunction with shape grammars. A description grammar constitutes a set of description rules that define a language of descriptions. A description grammar interpreter implements the mechanisms to

  8. How does sustainability certification affect the design process? Mapping final design projects at an architectural office

    DEFF Research Database (Denmark)

    Landgren, Mathilde; Jensen, Lotte Bjerregaard

    2017-01-01

    , derived from the sustainability certification system itself, and to apply it even in the early design process. This perspective emphasises all phases of the life cycle of a building. The goal of the present study was to map how a Danish architectural office approached sustainability in the projects...... they undertook in the course of a year. All the projects concerned were intended to conform to the German Sustainability Certification System DGNB. We developed a mapping tool to document these case projects and found that different sets of certification criteria were used in each project. This demonstrates...... process and informing the industry of them. This has led to optimised design processes such as Integrated Energy Design, in which many decisions related to energy consumption and indoor climate are made in the early design stages. The current tendency is to use an expanded notion of sustainability...

  9. Feed-pump hydraulic performance and design improvement, Phase I: research program design. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Brown, W.H.; Gopalakrishnan, S.; Fehlau, R.; Thompson, W.E.; Wilson, D.G.

    1982-03-01

    As a result of prior EPRI-sponsored studies, it was concluded that a research program should be designed and implemented to provide an improved basis for the design, procurement, testing, and operation of large feed pumps with increased reliability and stability over the full range of operating conditions. This two-volume report contains a research plan which is based on a review of the present state of the art and which defines the necessary R and D program and estimates the benefits and costs of the program. The recommended research program consists of 30 interrelated tasks. It is designed to perform the needed research; to verify the results; to develop improved components; and to publish computer-aided design methods, pump specification guidelines, and a troubleshooting manual. Most of the technology proposed in the research plan is applicable to nuclear power plants as well as to fossil-fired plants. This volume discusses the design, performance and failures of feed pumps, and recommendations for research on pump dynamics, design, and specifications.

  10. 19 CFR 11.13 - False designations of origin and false descriptions; false marking of articles of gold or silver.

    Science.gov (United States)

    2010-04-01

    ... descriptions; false marking of articles of gold or silver. 11.13 Section 11.13 Customs Duties U.S. CUSTOMS AND... gold or silver. (a) Articles which bear, or the containers which bear, false designations of origin, or.... 1405q, and shall be detained. (b) Articles made in whole or in part of gold or silver or alloys thereof...

  11. The development, description and appraisal of an emergent multimethod research design to study workforce changes in integrated care interventions

    NARCIS (Netherlands)

    Busetto, L.; Luijkx, K.G.; Calciolari, S.; González-ortiz, L.G.; Vrijhoef, H.J.M.

    In this paper, we provide a detailed and explicit description of the processes and decisions underlying and shaping the emergent multimethod research design of our study on workforce changes in integrated chronic care. The study was originally planned as mixed method research consisting of a pre-

  12. A job analysis design for the rail industry : description and model analysis of the job of freight conductor.

    Science.gov (United States)

    2013-10-01

    This document provides a step-by-step description of the design and execution of a strategic job analysis, using the position of Freight Conductor as an example. This document was created to be useful for many different needs, and can be used as an e...

  13. NSSS design and cycle 1 operating history data for Arkansas Nuclear One, Unit-2. Final report

    International Nuclear Information System (INIS)

    Gagne, P.A.

    1981-03-01

    This report contains design and cycle 1 operating data for the Arkansas Nuclear One, Unit-2 nuclear steam supply system. The design data include descriptions of the reactor core, reactor coolant system, and control systems which are a part of the nuclear steam supply system. Operating history data are provided for the period of December 1978 through January 1980. The most important operating history data provided include reactor power, cumulative fuel burnup, control rod position, primary coolant temperature, and a series of power distribution state points

  14. Feed-pump hydraulic performance and design improvement, Phase I: research program design. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Brown, W.H.; Gopalakrishnan, S.; Fehlau, R.; Thompson, W.E.; Wilson, D.G.

    1982-03-01

    As a result of prior EPRI-sponsored studies, it was concluded that a research program should be designed and implemented to provide an improved basis for the design, procurement, testing, and operation of large feed pumps with increased reliability and stability over the full range of operating conditions. This two-volume report contains a research plan which is based on a review of the present state of the art and which defines the necessary R and D program and estimates the benefits and costs of the program. The recommended research program consists of 30 interrelated tasks. It is designed to perform the needed research; to verify the results; to develop improved components; and to publish computer-aided design methods, pump specification guidelines, and a troubleshooting manual. Most of the technology proposed in the research plan is applicable to nuclear power plants as well as to fossil-fired plants. This volume contains appendixes on pump design, cavitation damage, performance testing, hydraulics, two-phase flow in pumps, flow stability, and rotor dynamics.

  15. Final repository for spent nuclear fuel. Underground design Forsmark, Layout D1

    Energy Technology Data Exchange (ETDEWEB)

    Brantberger, Martin; Zetterqvist, Anders [Ramboell Sweden AB, Stockholm (Sweden); Arnbjerg-Nielsen, Torben [Ramboell Denmark A/S, Virum (Denmark); Olsson, Tommy [IandT Olsson AB, Uppsala (Sweden); Outters, Nils [Golder Associates AB, Uppsala (Sweden); Syrjaenen, Pauli [Gridpoint Oy, Helsinki (Sweden)

    2006-04-15

    This report comprises the design step D1 related to the underground design for a deep repository located at the Forsmark site. The design is based on the Site Descriptive Model Forsmark v1.2. All studies have been focussed at an area southeast of the Forsmark nuclear plant, which has been considered to be the most promising area for hosting the repository. SKB has developed guidelines for the design of the repository, which further describes the methodology applied for the studies. From these guidelines the following basic objectives for the design step D1 are summarized: to determine whether the final repository can be accommodated within the studied site; to identify site-specific facility critical issues; to test and evaluate the design methodology; to provide feedback to: the design organisation regarding additional studies that needs to be done; the site investigation and modelling organization regarding further investigations required; and the safety assessment team. The possible locations for a tentative deep repository are analysed in Chapter 3 of the report. The most promising area for the repository (denoted 'priority site') has been defined by SKB to be located southeast of the Forsmark nuclear plant and northwest of the gently dipping deformation zone ZFMNE00A2. Regarding the repository depth, present knowledge acquired from the site investigations indicates that it is possible to locate the repository at all stipulated depths according to SKB, that is between 400 m and 700 m depth. The preliminary assessment made in Chapter 3 clearly demonstrates that the repository can be accommodated within the 'priority site'. The potential to accommodate the repository is essentially the same for both 400 m and 500 m depths. The design of the deposition areas is reported in Chapter 4, which includes the design of layout features for all tunnels and deposition holes, orientation of tunnels, calculation of anticipated loss of deposition holes due

  16. Final design review report for K Basin Dose Reduction Project Clean and Coat Task

    International Nuclear Information System (INIS)

    Blackburn, L.D.

    1996-02-01

    The strategy for reducing radiation dose originating from radionuclides absorbed in the concrete is to raise the pool water level to provide additional shielding. The concrete walls need to be coated to prevent future radionuclide absorption into the walls. This report documents a final design review of equipment to clean and coat basin walls. The review concluded that the design presented was acceptable for release for fabrication

  17. Analysis of airborne radiometric data. Volume 2. Description, listing, and operating instructions for the code DELPHI/MAZAS. Final report

    International Nuclear Information System (INIS)

    Sperling, M.; Shreve, D.C.

    1978-01-01

    The computer code DELPHI is an interactive English language command system for the analysis of airborne radiometric data. The code includes modules for data reduction, data simulation, time filtering, data adjustment and graphical presentation of the results. DELPHI is implemented in FORTRAN on a DEC-10 computer. This volume gives a brief set of operations instructions, samples of the output obtained from hard copies of the display on a Tektronix terminal and finally a listing of the code

  18. Analysis of airborne radiometric data. Volume 2. Description, listing, and operating instructions for the code DELPHI/MAZAS. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Sperling, M.; Shreve, D.C.

    1978-12-01

    The computer code DELPHI is an interactive English language command system for the analysis of airborne radiometric data. The code includes modules for data reduction, data simulation, time filtering, data adjustment and graphical presentation of the results. DELPHI is implemented in FORTRAN on a DEC-10 computer. This volume gives a brief set of operations instructions, samples of the output obtained from hard copies of the display on a Tektronix terminal and finally a listing of the code.

  19. Reflections on the Final Year Learning Experience –Designing a Capstone Experience

    Directory of Open Access Journals (Sweden)

    Keith Thomas

    2013-05-01

    Full Text Available Cross-sector educational reform to be implemented in 2012 in Hong Kong (HK is intended principally to prepare students for the future workplace. One of the explicit requirements for the new four-year undergraduate curriculum is the inclusion of a capstone course for final year students. This paper explores the uptake and reported effect of the capstone- liked final year project using participating students’ experience (voice in existing undergraduate study programmes in the Chinese University of Hong Kong (CUHK. Semi-structured interviews were used to collect student feedback; findings revealed considerations in terms of the core design elements highlighted in literature. The paper highlights students’ lack of readiness to successful transition into the workplace, linked to the current academic focus of projects. A framework that includes learning activities preferred by students is proposed for the final year learning experience. Findings from this study will be useful for curriculum development and evaluation of the final-year curriculum.

  20. Inertial confinement fusion driver enhancements: Final focusing systems and compact heavy-ion driver designs

    International Nuclear Information System (INIS)

    Bieri, R.L.

    1991-01-01

    Required elements of an inertial confinement fusion power plant are modeled and discussed. A detailed analysis of two critical elements of candidate drivers is done, and new component designs are proposed to increase the credibility and feasibility of each driver system. An analysis of neutron damage to the final elements of a laser focusing system is presented, and multilayer -- dielectric mirrors are shown to have damage lifetimes which axe too short to be useful in a commercial power plant. A new final-focusing system using grazing incidence metal mirrors to protect sensitive laser optics is designed and shown to be effective in extending the lifetime of the final focusing system. The reflectivities and damage limits of grazing incidence metal mirrors are examined in detail, and the required mirror sizes are shown to be compatible with the beam sizes and illumination geometries currently envisioned for laser drivers. A detailed design and analysis is also done for compact arrays of superconducting magnetic quadrupoles, which are needed in a multi-beam heavy-ion driver. The new array model is developed in more detail than some previous conceptual designs and models arrays which are more compact than arrays scaled from existing single -- quadrupole designs. The improved integrated model for compact arrays is used to compare the effects of various quadrupole array design choices on the size and cost of a heavy-ion driver. Array design choices which significantly affect the cost of a heavy-ion driver include the choice of superconducting material and the thickness of the collar used to support the winding stresses. The effect of these array design choices on driver size and cost is examined and the array model is used to estimate driver cost savings and performance improvements attainable with aggressive quadrupole array designs with high-performance superconductors

  1. Description of the final instar of Trichomalopsis peregrina (Hymenoptera, Pteromalidae), with data and comments on the preimaginal stages

    International Nuclear Information System (INIS)

    Tormos, J.; Asis, J.D.; Frago, E.; Selfa, J.; Pujade-Villar, J.; Guara, M.

    2007-01-01

    The preimaginal stages of T. peregrina are described. The egg displays a sculptured chorion, which is found only on those deposited externally. The immature larvae are characterized by their peculiarities in (a) a setose ring on the thoracic and abdominal segments, (b) an anal notch and (c) size and the sensory structures of the head capsule. The final instar is described and illustrated. Morphological structures of diagnostic value are discussed. The most salient character shown by the mature larva of this species lies in the epistoma, which is complete. (author) [es

  2. ITER final design report, cost review and safety analysis (FDR) and relevant documents

    International Nuclear Information System (INIS)

    1999-01-01

    This volume contains the fourth major milestone report and documents associated with its acceptance, review and approval. This ITER Final Design Report, Cost Review and Safety Analysis was presented to the ITER Council at its 13th meeting in February 1998 and was approved at its extraordinary meeting on 25 June 1998. The contents include an outline of the ITER objectives, the ITER parameters and design overview as well as operating scenarios and plasma performance. Furthermore, design features, safety and environmental characteristics and schedule and cost estimates are given

  3. Conceptual design study of 1985 commercial tilt rotor transports. Volume 3. STOL design summary. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Sambell, K.W.

    1976-04-01

    A conceptual design study is presented of 1,985 commercial tilt rotor STOL transports for a NASA 200 n. mi. (370 km) STOL Mission. A 100-passenger STOL Variant (Bell D313) of the Phase I VTOL Tilt Rotor Aircraft is defined. Aircraft characteristics are given; with the aircraft redesigned to meet 2,000-foot (610 m) field criteria, with emphasis on low fuel consumption and low direct operating cost. The 100-passenger STOL Tilt Rotor Aircraft was analyzed for performance, weights, economics, handling qualities, noise footprint and aeroelastic stability. (GRA)

  4. Photodetachment neutralizer development: Laser window design study: Volume 2, Window design details: Final report

    International Nuclear Information System (INIS)

    1987-01-01

    During 1983, TRW conducted a photodetachment neutralizer development (PDN) - Laser Resonator study. The emphasis of this contract was to assess a technology base of the PDN concept. Three technology assessments were conducted: Mirror Technology assessments, Window Engineering Analysis/Technology assessment, and COIL medium modeling with emphasis on PDN issues. Based on the results of these technology assessments the follow-on contract was funded to develop a technology verification. Due to funding limitations this technology verification program was divided into two separate follow-on contracts. Under this follow-on contract, the following tasks were performed: Measure Attenuation Coefficient of 3M FC-104, FC-77, FC-43 with temperature and attenuation coefficient of sapphire, generate finite element/finite difference thermal/structural model of the HEX double window, determine thermal/structural response from the proposed operating conditions, develop option response data from the deflection/stress inputs, recommend design and operating parameters for demonstrator and operational HEX double window, generate Level 1 layouts and drawings of double paned demonstrator window and window mount/manifold, and generate preliminary layout drawings of shutter. Thermal and structural analyses were conducted for both the operational and demonstrator window heat exchanger (HEX) designs and operating conditions

  5. Electric utility engineer`s FGD manual -- Volume 1: FGD process design. Final report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-03-04

    Part 1 of the Electric Utility Engineer`s Flue Gas Desulfurization (FGD) Manual emphasizes the chemical and physical processes that form the basis for design and operation of lime- and limestone-based FGD systems applied to coal- or oil-fired steam electric generating stations. The objectives of Part 1 are: to provide a description of the chemical and physical design basis for lime- and limestone-based wet FGD systems; to identify and discuss the various process design parameters and process options that must be considered in developing a specification for a new FGD system; and to provide utility engineers with process knowledge useful for operating and optimizing a lime- or limestone-based wet FGD system.

  6. Design of a modular digital computer system, CDRL no. D001, final design plan

    Science.gov (United States)

    Easton, R. A.

    1975-01-01

    The engineering breadboard implementation for the CDRL no. D001 modular digital computer system developed during design of the logic system was documented. This effort followed the architecture study completed and documented previously, and was intended to verify the concepts of a fault tolerant, automatically reconfigurable, modular version of the computer system conceived during the architecture study. The system has a microprogrammed 32 bit word length, general register architecture and an instruction set consisting of a subset of the IBM System 360 instruction set plus additional fault tolerance firmware. The following areas were covered: breadboard packaging, central control element, central processing element, memory, input/output processor, and maintenance/status panel and electronics.

  7. FINAL DESIGN REVIEW REPORT Subcritical Experiments Gen 2, 3-ft Confinement Vessel Weldment

    Energy Technology Data Exchange (ETDEWEB)

    Romero, Christopher [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2017-09-28

    A Final Design Review (FDR) of the Subcritical Experiments (SCE) Gen 2, 3-ft. Confinement Vessel Weldment was held at Los Alamos National Laboratory (LANL) on September 14, 2017. The review was a focused review on changes only to the confinement vessel weldment (versus a system design review). The changes resulted from lessons-learned in fabricating and inspecting the current set of confinement vessels used for the SCE Program. The baseline 3-ft. confinement vessel weldment design has successfully been used (to date) for three (3) high explosive (HE) over-tests, two (2) fragment tests, and five (5) integral HE experiments. The design team applied lessons learned from fabrication and inspection of these vessel weldments to enhance fit-up, weldability, inspection, and fitness for service evaluations. The review team consisted of five (5) independent subject matter experts with engineering design, analysis, testing, fabrication, and inspection experience. The

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

    Energy Technology Data Exchange (ETDEWEB)

    Kaminsky, Jacob; Hrabak, Robert; Jacobs, Robert; Ryder, Richard; Schultz, Robert; Reimann, Robert G.; Paulo, Frances X.; Crandall, David B.; Belle, John; Pavliv, Mark; Seanor, Arthur; Chandler, Marty; Till, Howard B.; Lester, William; O' Brien, Michael; Rediowski, Jan; Phillips, Howard; Cahill, Michael; Matteson, Eric; Cathey, John

    1979-12-01

    A case study of project planning and design for energy conservation at Radisson New Community, Baldwinsville, New York is described. The new community includes a 95-acre residential site and a 51-acre town center. Energy-conserving plans developed for both sites have focused on passive measures to reduce energy use for space heating. Utility systems options have been identified for both sites. The case study overview contains data on location, climatology, local meteorology. Development plans for both the residential and town center areas are described. After a description of the team structure, methodological considerations, and impediments to implementation, the implementation program is given. (MCW)

  9. Osiris and SOMBRERO inertial confinement fusion power plant designs. Volume 2, Designs, assessments, and comparisons, Final report

    Energy Technology Data Exchange (ETDEWEB)

    Meier, W.R.; Bieri, R.L.; Monsler, M.J.

    1992-03-01

    The primary objective of the of the IFE Reactor Design Studies was to provide the Office of Fusion Energy with an evaluation of the potential of inertial fusion for electric power production. The term reactor studies is somewhat of a misnomer since these studies included the conceptual design and analysis of all aspects of the IFE power plants: the chambers, heat transport and power conversion systems, other balance of plant facilities, target systems (including the target production, injection, and tracking systems), and the two drivers. The scope of the IFE Reactor Design Studies was quite ambitious. The majority of our effort was spent on the conceptual design of two IFE electric power plants, one using an induction linac heavy ion beam (HIB) driver and the other using a Krypton Fluoride (KrF) laser driver. After the two point designs were developed, they were assessed in terms of their (1) environmental and safety aspects; (2) reliability, availability, and maintainability; (3) technical issues and technology development requirements; and (4) economics. Finally, we compared the design features and the results of the assessments for the two designs.

  10. Advances in the Design of the SuperB Final Doublet

    Energy Technology Data Exchange (ETDEWEB)

    Paoloni, E.; Carmignani, N.; Pilo, F.; /Pisa U. /INFN, Pisa; Bettoni, S.; /CERN; Fabbricatore, P.; Farinon, S.; Musenich, R.; /INFN, Genoa; Bosi, F.; /INFN, Pisa; Biagini, M.E.; Raimondi, P.; /Frascati; Sullivan, M.; /SLAC

    2012-04-26

    SuperB is an asymmetric energy e{sup +}e{sup -} collider operating at the {Upsilon}(4S) peak with a design peak luminosity of 10{sup 36} Hz/cm{sup 2} to be built in Italy in the very near future. The design luminosity is almost a factor hundred higher than that of the present generation comparable facilities. To get the design luminosity a novel collision scheme, the so called 'large Piwinski angle with crab waist', has been designed. The scheme requires a short focus final doublet to reduce the vertical beta function down to {beta}*{sub y} = 0.2mm at the interaction point (IP). The final doublet will be composed by a set of permanent and superconducting (SC) quadrupoles. The SC quadrupole doublets QD0/QF1 will be placed as close to the IP as possible. This layout is critical because the space available for the doublets is very small. An advanced design of the quadrupole has been developed, based on the so-called helical coil concept. The paper discusses the design concept, the construction and the results of test of a model of the superconducting quadrupole based on NbTi technology. Future developments are also presented.

  11. The Development, Description and Appraisal of an Emergent Multimethod Research Design to Study Workforce Changes in Integrated Care Interventions

    Directory of Open Access Journals (Sweden)

    Loraine Busetto

    2017-03-01

    Full Text Available Introduction: In this paper, we provide a detailed and explicit description of the processes and decisions underlying and shaping the emergent multimethod research design of our study on workforce changes in integrated chronic care. Theory and methods: The study was originally planned as mixed method research consisting of a pre- liminary literature review and quantitative check of these findings via a Delphi panel. However, when the findings of the literature review were not appropriate for quantitative confirmation, we chose to continue our qualitative exploration of the topic via qualitative questionnaires and secondary analysis of two best practice case reports. Results: The resulting research design is schematically described as an emergent and interactive mul- timethod design with multiphase combination timing. In doing so, we provide other researchers with a set of theory- and experience-based options to develop their own multimethod research and provide an example for more detailed and structured reporting of emergent designs. Conclusion and discussion: We argue that the terminology developed for the description of mixed methods designs should also be used for multimethod designs such as the one presented here.

  12. System design description for the SY-101 hydrogen mitigation test project data acquisition and control system (DACS-1)

    Energy Technology Data Exchange (ETDEWEB)

    Ermi, A.M.

    1998-03-02

    There is no new activity or procedure associated with the updating of this reference document. The updating of this system design description maintains an agreed upon documentation program initiated within the test program and carried into operations at time of turnover to maintain configuration control as outlined by design authority practicing guidelines. Any changes made to controlled components in the field will be updated after the time of implementation to support the engineers and operators understand, maintain, train to and operate the system. There are no new credible failure modes associated with the updating of information in a support description document. The failure analysis of each change was reviewed at the time of implementation of the Systems Change Request for all the processes changed. This document simply provides a history of implementation and current system status. The incorporation of the two documents, Computer Systems Design Description (HNF-SD-WMCSDD-008) and the Input/Output Channel List (HNF-SD-WM-EL-001), as appendices allow for fewer errors in changes. Because the documents are all together, they will be approved as one document, not three separate entities which could be updated at different times, creating a situation which does not accurately depict field conditions.

  13. System design description for the SY-101 hydrogen mitigation test project data acquisition and control system (DACS-1)

    International Nuclear Information System (INIS)

    Ermi, A.M.

    1998-01-01

    There is no new activity or procedure associated with the updating of this reference document. The updating of this system design description maintains an agreed upon documentation program initiated within the test program and carried into operations at time of turnover to maintain configuration control as outlined by design authority practicing guidelines. Any changes made to controlled components in the field will be updated after the time of implementation to support the engineers and operators understand, maintain, train to and operate the system. There are no new credible failure modes associated with the updating of information in a support description document. The failure analysis of each change was reviewed at the time of implementation of the Systems Change Request for all the processes changed. This document simply provides a history of implementation and current system status. The incorporation of the two documents, Computer Systems Design Description (HNF-SD-WMCSDD-008) and the Input/Output Channel List (HNF-SD-WM-EL-001), as appendices allow for fewer errors in changes. Because the documents are all together, they will be approved as one document, not three separate entities which could be updated at different times, creating a situation which does not accurately depict field conditions

  14. System Design Description and Requirements for Modeling the Off-Gas Systems for Fuel Recycling Facilities

    Energy Technology Data Exchange (ETDEWEB)

    Daryl R. Haefner; Jack D. Law; Troy J. Tranter

    2010-08-01

    This document provides descriptions of the off-gases evolved during spent nuclear fuel processing and the systems used to capture the gases of concern. Two reprocessing techniques are discussed, namely aqueous separations and electrochemical (pyrochemical) processing. The unit operations associated with each process are described in enough detail so that computer models to mimic their behavior can be developed. The document also lists the general requirements for the desired computer models.

  15. Virtual World, Real Education: A Descriptive Study of Instructional Design in Second Life

    Science.gov (United States)

    Kingston, Linda S.

    2011-01-01

    Virtual worlds like Second Life are emerging technologies that have gained popularity among educators. As these worlds emerged, greater focus has been placed on the design of the environments themselves rather than the design of instruction within them. Educators have begun using these environments for teaching and instructional designers are now…

  16. Design, construction and conditions of the application of unreinforced concrete final lining in conventionally driven tunnels

    Science.gov (United States)

    Faltýnek, Jan; Hořejší, Jiří; Mařík, Libor; Růžička, Pavel

    2017-09-01

    The way to an economic design in the final lining in conventionally driven tunnels lies in structural analysing based on the actually encountered geotechnical conditions. Regarding reinforced concrete structures, many standards and regulations applicable to designing and building structures and taking them over by the client before their commissioning and before the end of the warranty period respectively exist in the Czech Republic. If the local conditions allow it, it is possible to design the final lining as an unreinforced concrete structure. In such a case it is necessary to take the differences into consideration in the structural design and in the possibilities of the lining behaviour and to set criteria for taking over the lining allowing for its use. Setting too stringent criteria for cracking can lead to an increase in the contract price, either because of the necessity for reinforcing the lining or because of the fact that the contractor reduces the risk by incorporating the assumed cost of repairs into the total cost. The paper describes basic differences in the approach to reinforced concrete and unreinforced concrete linings, the possibilities of limiting formation of cracks by means of the concrete mix design, by selection of the technological procedure of the work and the method of curing after stripping. The text contains a comparison of criteria for assessing the surface of an unreinforced concrete lining with criteria in foreign regulations.

  17. Newman Unit 1 advanced solar repowering advanced conceptual design. Final report

    Energy Technology Data Exchange (ETDEWEB)

    None

    1982-04-01

    The Newman Unit 1 solar repowering design is a water/steam central receiver concept supplying superheated steam. The work reported is to develop a refined baseline conceptual design that has potential for construction and operation by 1986, makes use of existing solar thermal technology, and provides the best economics for this application. Trade studies performed in the design effort are described, both for the conceptual design of the overall system and for the subsystem conceptual design. System-level functional requirements, design, operation, performance, cost, safety, environmental, institutional, and regulatory considerations are described. Subsystems described include the collector, receiver, fossil energy, electrical power generating, and master control subsystems, site and site facilities. The conceptual design, cost, and performance of each subsystem is discussed at length. A detailed economic analysis of the repowered unit is made to realistically assess the economics of the first repowered unit using present cost data for a limited production level for solar hardware. Finally, a development plan is given, including the design, procurement, construction, checkout, startup, performance validation, and commercial operation. (LEW)

  18. Grid-Connected Integrated Community Energy System. Phase II: detailed feasibility analysis and preliminary design. Final report, Stage 2

    Energy Technology Data Exchange (ETDEWEB)

    1978-11-01

    The purpose of this study was to determine the economic and environmental feasibility of a Grid-Connected Integrated Community Energy System (ICES) based on a multifuel (gas, oil, treated solid wastes, and coal) design with which to serve any or all the institutions within the Louisiana Medical Complex in cooperation with the Health Education Authority of Louisiana (HEAL). In this context, a preliminary design is presented which consists of ICES plant description and engineering analyses. This demonstration system is capable of meeting 1982 system demands by providing 10,000 tons of air conditioning and, from a boiler plant with a high-pressure steam capacity of 200,000 lb/h, approximately 125,000 lb/h of 185 psig steam to the HEAL institutions, and at the same time generating up to 7600 kW of electrical power as byproduct energy. The plant will consist of multiple-fuel steam boilers, turbine generator, turbine driven chillers and necessary auxiliaries and ancillary systems. The preliminary design for these systems and for the building to house the central plant systems are presented along with equipment and instrumentation schedules and outline specifications for major components. Costs were updated to reflect revised data. The final preliminary cost estimate includes allowances for contingencies and escalation, as well as cost for the plant site and professional fees. This design is for a facility specifically with coal burning capability, recognizing that it is more capital-intensive than a gas/oil facility. In the opinion of the Louisiana Department of Natural Resources (DNR), the relatively modest allocations made for scrubbing and ash removal involve less than is implied in standard industry (EPRI) cost increments of over 30% for these duties. The preliminary environmental assessment is included. (LCL)

  19. Evaluation of different design space description methods for analysing combustion engine operation limits

    NARCIS (Netherlands)

    Kieft, Nataša

    2014-01-01

    Over the last 20 years large efforts have been made in developing and optimising modelling techniques for DoE usage in engine calibration. A prerequisite for optimally applying DoE test designs is the detailed knowledge of the engine’s operating boundaries enclosing the ‘design space’. Known

  20. A Description Grid to Support the Design of Learning Role-Play Games

    Science.gov (United States)

    Mariais, Christelle; Michau, Florence; Pernin, Jean-Philippe

    2012-01-01

    To strengthen the motivation of learners, the professional training sector is focusing more and more on game-based learning. In this context, the authors have become interested in the design of Learning Role-Play Game (LRPG) scenarios. The aim of this article is to improve the designers' confidence in the validity of the game-based learning…

  1. Final design of a free-piston hydraulic advanced Stirling conversion system

    Science.gov (United States)

    Wallace, D. A.; Noble, J. E.; Emigh, S. G.; Ross, B. A.; Lehmann, G. A.

    1991-01-01

    Under the US Department of Energy's (DOEs) Solar Thermal Technology Program, Sandia National Laboratories is evaluating heat engines for solar distributed receiver systems. The final design is described of an engineering prototype advanced Stirling conversion system (ASCS) with a free-piston hydraulic engine output capable of delivering about 25 kW of electric power to a utility grid. The free-piston Stirling engine has the potential for a highly reliable engine with long life because it has only a few moving parts, has noncontacting bearings, and can be hermetically sealed. The ASCS is designed to deliver maximum power per year over a range of solar input with a design life of 30 years (60,000 h). The system includes a liquid Nak pool boiler heat transport system and a free-piston Stirling engine with high-pressure hydraulic output, coupled with a bent axis variable displacement hydraulic motor and a rotary induction generator.

  2. Grid fault and design-basis for wind turbines - Final report

    DEFF Research Database (Denmark)

    Hansen, Anca Daniela; Cutululis, Nicolaos Antonio; Markou, Helen

    This is the final report of a Danish research project “Grid fault and design-basis for wind turbines”. The objective of this project has been to assess and analyze the consequences of the new grid connection requirements for the fatigue and ultimate structural loads of wind turbines....... The fulfillment of the grid connection requirements poses challenges for the design of both the electrical system and the mechanical structure of wind turbines. The development of wind turbine models and novel control strategies to fulfill the TSO’s requirements are of vital importance in this design. Dynamic...... approach for the quantification of the wind turbines structural loads caused by the fault ride-through grid requirement, has been proposed and exemplified for the case of an active stall wind turbine. This approach relies on the combination of knowledge from complimentary simulation tools, which have...

  3. Design and implementation of fuzzy logic controllers. Thesis Final Report, 27 Jul. 1992 - 1 Jan. 1993

    Science.gov (United States)

    Abihana, Osama A.; Gonzalez, Oscar R.

    1993-01-01

    The main objectives of our research are to present a self-contained overview of fuzzy sets and fuzzy logic, develop a methodology for control system design using fuzzy logic controllers, and to design and implement a fuzzy logic controller for a real system. We first present the fundamental concepts of fuzzy sets and fuzzy logic. Fuzzy sets and basic fuzzy operations are defined. In addition, for control systems, it is important to understand the concepts of linguistic values, term sets, fuzzy rule base, inference methods, and defuzzification methods. Second, we introduce a four-step fuzzy logic control system design procedure. The design procedure is illustrated via four examples, showing the capabilities and robustness of fuzzy logic control systems. This is followed by a tuning procedure that we developed from our design experience. Third, we present two Lyapunov based techniques for stability analysis. Finally, we present our design and implementation of a fuzzy logic controller for a linear actuator to be used to control the direction of the Free Flight Rotorcraft Research Vehicle at LaRC.

  4. Preliminary design for hot dirty-gas control-valve test facility. Final report

    Energy Technology Data Exchange (ETDEWEB)

    1980-01-01

    This report presents the results of a preliminary design and cost estimating effort for a facility for the testing of control valves in Hot Dirty Gas (HDGCV) service. This design was performed by Mittelhauser Corporation for the United States Department of Energy's Morgantown Energy Technology Center (METC). The objective of this effort was to provide METC with a feasible preliminary design for a test facility which could be used to evaluate valve designs under simulated service conditions and provide a technology data base for DOE and industry. In addition to the actual preliminary design of the test facility, final design/construction/operating schedules and a facility cost estimate were prepared to provide METC sufficient information with which to evaluate this design. The bases, assumptions, and limitations of this study effort are given. The tasks carried out were as follows: METC Facility Review, Environmental Control Study, Gas Generation Study, Metallurgy Review, Safety Review, Facility Process Design, Facility Conceptual Layout, Instrumentation Design, Cost Estimates, and Schedules. The report provides information regarding the methods of approach used in the various tasks involved in the completion of this study. Section 5.0 of this report presents the results of the study effort. The results obtained from the above-defined tasks are described briefly. The turnkey cost of the test facility is estimated to be $9,774,700 in fourth quarter 1979 dollars, and the annual operating cost is estimated to be $960,000 plus utilities costs which are not included because unit costs per utility were not available from METC.

  5. Computer system design description for the spare pump mini-dacs data acquisition and control system

    International Nuclear Information System (INIS)

    Vargo, G.F. Jr.

    1994-01-01

    The attached document outlines the computer software design for the mini data acquisition and control system (DACS), that supports the testing of the spare pump for Tank 241-SY-101, at the maintenance and storage facility (MASF)

  6. Computer system design description for the spare pump mini-dacs data acquisition and control system

    Energy Technology Data Exchange (ETDEWEB)

    Vargo, G.F. Jr.

    1994-09-29

    The attached document outlines the computer software design for the mini data acquisition and control system (DACS), that supports the testing of the spare pump for Tank 241-SY-101, at the maintenance and storage facility (MASF).

  7. A low-power photovoltaic system with energy storage for radio communications: Description and design methodology

    Science.gov (United States)

    Chapman, C. P.; Chapman, P. D.; Lewison, A. H.

    1982-01-01

    A low power photovoltaic system was constructed with approximately 500 amp hours of battery energy storage to provide power to an emergency amateur radio communications center. The system can power the communications center for about 72 hours of continuous nonsun operation. Complete construction details and a design methodology algorithm are given with abundant engineering data and adequate theory to allow similar systems to be constructed, scaled up or down, with minimum design effort.

  8. High-level waste canister storage final design, installation, and testing. Topical report

    Energy Technology Data Exchange (ETDEWEB)

    Connors, B.J.; Meigs, R.A.; Pezzimenti, D.M.; Vlad, P.M.

    1998-04-01

    This report is a description of the West Valley Demonstration Project`s radioactive waste storage facility, the Chemical Process Cell (CPC). This facility is currently being used to temporarily store vitrified waste in stainless steel canisters. These canisters are stacked two-high in a seismically designed rack system within the cell. Approximately 300 canisters will be produced during the Project`s vitrification campaign which began in June 1996. Following the completion of waste vitrification and solidification, these canisters will be transferred via rail or truck to a federal repository (when available) for permanent storage. All operations in the CPC are conducted remotely using various handling systems and equipment. Areas adjacent to or surrounding the cell provide capabilities for viewing, ventilation, and equipment/component access.

  9. High-level waste canister storage final design, installation, and testing. Topical report

    International Nuclear Information System (INIS)

    Connors, B.J.; Meigs, R.A.; Pezzimenti, D.M.; Vlad, P.M.

    1998-04-01

    This report is a description of the West Valley Demonstration Project's radioactive waste storage facility, the Chemical Process Cell (CPC). This facility is currently being used to temporarily store vitrified waste in stainless steel canisters. These canisters are stacked two-high in a seismically designed rack system within the cell. Approximately 300 canisters will be produced during the Project's vitrification campaign which began in June 1996. Following the completion of waste vitrification and solidification, these canisters will be transferred via rail or truck to a federal repository (when available) for permanent storage. All operations in the CPC are conducted remotely using various handling systems and equipment. Areas adjacent to or surrounding the cell provide capabilities for viewing, ventilation, and equipment/component access

  10. Computer system design description for SY-101 hydrogen mitigation test project data acquisition and control system (DACS-1). Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    Truitt, R.W. [Westinghouse Hanford Co., Richland, WA (United States)

    1994-08-24

    This document provides descriptions of components and tasks that are involved in the computer system for the data acquisition and control of the mitigation tests conducted on waste tank SY-101 at the Hanford Nuclear Reservation. The system was designed and implemented by Los alamos National Laboratory and supplied to Westinghouse Hanford Company. The computers (both personal computers and specialized data-taking computers) and the software programs of the system will hereafter collectively be referred to as the DACS (Data Acquisition and Control System).

  11. Computer system design description for SY-101 hydrogen mitigation test project data acquisition and control system (DACS-1). Revision 1

    International Nuclear Information System (INIS)

    Truitt, R.W.

    1994-01-01

    This document provides descriptions of components and tasks that are involved in the computer system for the data acquisition and control of the mitigation tests conducted on waste tank SY-101 at the Hanford Nuclear Reservation. The system was designed and implemented by Los alamos National Laboratory and supplied to Westinghouse Hanford Company. The computers (both personal computers and specialized data-taking computers) and the software programs of the system will hereafter collectively be referred to as the DACS (Data Acquisition and Control System)

  12. Efficient design of two-dimensional recursive digital filters. Final report

    International Nuclear Information System (INIS)

    Twogood, R.E.; Mitra, S.K.

    1980-01-01

    This report outlines the research progress during the period August 1978 to July 1979. This work can be divided into seven basic project areas. Project 1 deals with a comparative study of 2-D recursive and nonrecursive digital filters. The second project addresses a new design technique for 2-D half-plane recursive filters, and Projects 3 thru 5 deal with implementation issues. The sixth project presents our recent study of the applicability of array processors to 2-D digital signal processing. The final project involves our investigation into techniques for incorporating symmetry constraints on 2-D recursive filters in order to yield more efficient implementations

  13. Mechanical design of a pre-isolator for the CLIC final focusing magnets

    CERN Document Server

    Gaddi, A; Ramos, F; Siegrist, N

    2012-01-01

    Due to the very small vertical beam sizes, the final focusing elements at the future CLIC linear collider need to be stable against vibrations to below 0.15 nanometres at frequencies above about 4 Hz. One of the key elements in the strategy to achieve such a stable environment is a passive, heavy pre-isolator. In this report, the results from the dynamic finite element analyses of the proposed design for such a passive preisolator are summarized. Furthermore, the results from a low frequency, heavy mass passive vibration isolation test set-up used to validate the calculations are shown.

  14. The AGP-Project conceptual design for a Spanish HLW final disposal facility

    International Nuclear Information System (INIS)

    Biurrun, E.; Engelmann, H.-J.; Huertas, F.; Ulibarri, A.

    1992-01-01

    Within the framework of the AGP Project a Conceptual Design for a HLW Final Disposal Facility to be eventually built in an underground salt formation in Spain has been developed. The AGP Project has the character of a system analysis. In the current project phase I several alternatives has been considered for different subsystems and/or components of the repository. The system variants, developed to such extent as to allow a comparison of their advantages and disadvantages, will allow the selection of a reference concept, which will be further developed to technical maturity in subsequent project phases. (author)

  15. Design of automata theory of cubical complexes with applications to diagnosis and algorithmic description

    Science.gov (United States)

    Roth, J. P.

    1972-01-01

    The following problems are considered: (1) methods for development of logic design together with algorithms, so that it is possible to compute a test for any failure in the logic design, if such a test exists, and developing algorithms and heuristics for the purpose of minimizing the computation for tests; and (2) a method of design of logic for ultra LSI (large scale integration). It was discovered that the so-called quantum calculus can be extended to render it possible: (1) to describe the functional behavior of a mechanism component by component, and (2) to compute tests for failures, in the mechanism, using the diagnosis algorithm. The development of an algorithm for the multioutput two-level minimization problem is presented and the program MIN 360 was written for this algorithm. The program has options of mode (exact minimum or various approximations), cost function, cost bound, etc., providing flexibility.

  16. System design description for the LDUA high resolution stereoscopic video camera system (HRSVS)

    International Nuclear Information System (INIS)

    Pardini, A.F.

    1998-01-01

    The High Resolution Stereoscopic Video Camera System (HRSVS), system 6230, was designed to be used as an end effector on the LDUA to perform surveillance and inspection activities within a waste tank. It is attached to the LDUA by means of a Tool Interface Plate (TIP) which provides a feed through for all electrical and pneumatic utilities needed by the end effector to operate. Designed to perform up close weld and corrosion inspection roles in US T operations, the HRSVS will support and supplement the Light Duty Utility Arm (LDUA) and provide the crucial inspection tasks needed to ascertain waste tank condition

  17. Design, construction and testing of a DC bioeffects test enclosure for small animals. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Frazier, M J; Preache, M M

    1980-11-01

    This final report describes both the engineering development of a DC bioeffects test enclosure for small laboratory animals, and the biological protocol for the use of such enclosures in the testing of animals to determine possible biological effects of the environment associated with HVDC transmission lines. The test enclosure which has been designed is a modular unit, which will house up to eight rat-sized animals in individual compartments. Multiple test enclosures can be used to test larger numbers of animals. A prototype test enclosure has been fabricated and tested to characterize its electrical performance characteristics. The test enclosure provides a simulation of the dominant environment associated with HVDC transmission lines; namely, a static electric field and an ion current density. A biological experimental design has been developed for assessing the effects of the dominant components of the HVDC transmission line environment.

  18. Designing the central knowledge base for the purposes of final works in architecture

    Directory of Open Access Journals (Sweden)

    Aleksić Ljiljana

    2014-01-01

    Full Text Available The solution for many issues related to the selection of construction products, currently present on the market, could be a Central knowledge base, consisting of verified and reliable data of construction products. Beside previous participants: investor, architect and contractor, that were involved in the processes of design and construction, herein is equally introduced manufacturer construction materials and products. The Central knowledge base consists of: a catalog sheets of the graphics base, alphanumeric base and base with textual data, and represents a flexible system that is subject to amendments. It is built to support architects during processes design and construction, as well as for education of students attending subject Final works at the Faculty of Civil Engineering in Subotica.

  19. Design and Manufacture of a Hybrid Final Focus Quadrupole Model for CLIC

    CERN Document Server

    Modena, Michele; Vorozhtsov, Alexey

    2012-01-01

    A tunable hybrid quadrupole magnet design has been proposed for the final focus in the Compact Linear Collider (CLIC) that is currently under study. The proposed design is a combination of an iron dominated electromagnetic quadrupole with a bore diameter of 8.25 mm with permanent magnet blocks placed between the poles made of soft magnetic CoFe alloy "Permendur". The possibility of using Sm2Co17 and Nd2Fe14B as material for the permanent magnet blocks has been investigated. It is shown that a very high field gradient of 530 T/m (Sm2Co17) and 590 T/m (Nd2Fe14B) can be achieved.

  20. Design finalization and material qualification towards procurement of the ITER vacuum vessel

    Energy Technology Data Exchange (ETDEWEB)

    Ioki, K., E-mail: Kimihiro.Ioki@iter.org [ITER Organization, CS 90 046, 13067 St. Paul-lez-Durance CEDEX (France); Barabash, V.; Bachmann, C.; Chappuis, P.; Choi, C.H.; Cordier, J-J.; Giraud, B.; Gribov, Y. [ITER Organization, CS 90 046, 13067 St. Paul-lez-Durance CEDEX (France); Heitzenroeder, Ph. [PPPL MS41, Princeton University, PO Box 451, Princeton, NJ 08543 (United States); Her, N.; Johnson, G. [ITER Organization, CS 90 046, 13067 St. Paul-lez-Durance CEDEX (France); Jones, L. [F4E, c/Josep Pla, n.2, Torres Diagonal Litoral, Edificio B3, E-08019, Barcelona (Spain); Jun, C. [ITER Organization, CS 90 046, 13067 St. Paul-lez-Durance CEDEX (France); Kim, B.C. [NFRI, 52 Yeoeundong Yuseonggu, Daejeon 305-333 (Korea, Republic of); Kuzmin, E. [NTC ' Sintez' , Efremov Inst., 189631 Metallostroy, St. Petersburg (Russian Federation); Loesser, D. [PPPL MS41, Princeton University, PO Box 451, Princeton, NJ 08543 (United States); Martin, A.; Merola, M. [ITER Organization, CS 90 046, 13067 St. Paul-lez-Durance CEDEX (France); Pathak, H. [IPR, Near Indira Bridge, Bhat, Gandhinagar 382 428 (India); Readman, P. [ITER Organization, CS 90 046, 13067 St. Paul-lez-Durance CEDEX (France)

    2011-10-01

    Procurement arrangements for ITER key components including the vacuum vessel (VV) have been signed and the ITER activities are now fully devoted towards construction. Final design reviews have been carried out for the main vessel and ports. One of the design review topics is the selection of materials, material procurement, and assessment of material performance during operation. The width of the inner shell splice plates was increased from 120 mm to 160 mm to minimize risk during the assembly of the Thermal shields and the VV. Instead of facet shaping, 3D shaping was introduced for the outboard inner shell. The material qualification procedures have been started for VV structural materials such as 316L(N) IG for licensing as a nuclear pressure equipment component. In accordance with the regulatory requirements and quality requirements for operation, common material specifications have been prepared in collaboration with the domestic agencies.

  1. Design of optics for the final focus test beam at SLAC

    International Nuclear Information System (INIS)

    Oide, Katsunobu.

    1989-05-01

    The goal of the Final Focus Test Beam experiment (FFTB) is to produce an electron beam spot of 1 μm by 60 nm in transverse dimensions. In the future linear collider of TeV region (TLC), a typical spot size of 100 nm by 1 nm at the interaction point is required to get luminosity of 1 /times/ 10 34 cm/sup /minus/2/s/sup /minus/1/. This spot size is about 1/1000 of the SLC in the vertical dimension, and is demanding for an optics design, alignments, beam diagnostics, and tuning procedures. The spot size of the FFTB will be an important next step from the SLC toward the TLC. This paper describes the design of the beam optics. 11 refs., 2 figs., 1 tab

  2. System design description for ``Mini-DACS`` data acquisition and control system

    Energy Technology Data Exchange (ETDEWEB)

    Ermi, A.M.

    1996-10-01

    This document describes the computer software design and associated hardware for the Mini-DACS (Data Acquisition and Control System) in support of testing the second spare pump (HMR-3) for tank 241SY101. The testing of HMR-3 was conducted at the Maintenance and Storage Facility (MASF).

  3. Ethical Design of Intelligent Assistive Technologies for Dementia: A Descriptive Review.

    Science.gov (United States)

    Ienca, Marcello; Wangmo, Tenzin; Jotterand, Fabrice; Kressig, Reto W; Elger, Bernice

    2017-09-22

    The use of Intelligent Assistive Technology (IAT) in dementia care opens the prospects of reducing the global burden of dementia and enabling novel opportunities to improve the lives of dementia patients. However, with current adoption rates being reportedly low, the potential of IATs might remain under-expressed as long as the reasons for suboptimal adoption remain unaddressed. Among these, ethical and social considerations are critical. This article reviews the spectrum of IATs for dementia and investigates the prevalence of ethical considerations in the design of current IATs. Our screening shows that a significant portion of current IATs is designed in the absence of explicit ethical considerations. These results suggest that the lack of ethical consideration might be a codeterminant of current structural limitations in the translation of IATs from designing labs to bedside. Based on these data, we call for a coordinated effort to proactively incorporate ethical considerations early in the design and development of new products.

  4. Suicide prevention e-learning modules designed for gatekeepers: A descriptive review

    NARCIS (Netherlands)

    Ghoncheh, R.; Kerkhof, A.; Koot, H.M.

    2014-01-01

    Background: E-learning modules can be a useful method for educating gatekeepers in suicide prevention and awareness. Aims: To review and provide an overview of e-learning modules on suicide prevention designed for gatekeepers and assess their effectiveness. Method: Two strategies were used. First,

  5. ERTS-B (Earth Resources Technology Satellite). [spacecraft design remote sensor description, and technology utilization

    Science.gov (United States)

    1975-01-01

    Mission plans and objectives of the ERTS 2 Satellite are presented. ERTS 2 follow-on investigations in various scientific disciplines including agriculture, meteorology, land-use, geology, water resources, oceanography, and environment are discussed. Spacecraft design and its sensors are described along with the Delta launch vehicle and launch operations. Applications identified from ERTS 1 investigations are summarized.

  6. Design optimization of the International Linear Collider Final Focus System with a long L*

    CERN Document Server

    Plassard, Fabien

    This Master's Thesis work has been done in the Aerospace Engineering master's programme framework and carried out at the European Organization for Nuclear Research (CERN). It was conducted under the 500 GeV e-e+ International Linear Collider (ILC) study and focused on the design and performance optimization of the Final Focus System (FFS). The purpose of the final focus system of the future linear colliders (ILC and CLIC) is to demagnify the beam to the required transverse size at the interaction point (IP). The FFS is designed for a flat-beam in a compact way based on a local chromaticity correction which corrects both horizontal and vertical chromaticities simultaneously. An alternative FFS configuration based on the traditional scheme with two dedicated chromatic correction sections for horizontal and vertical chromaticities and a long L * option has been developed. A longer free space between the last quadrupole and the IP allows to place the last quadrupole on a stable ground, with fewer engineering ...

  7. Testing a discrete choice experiment including duration to value health states for large descriptive systems: addressing design and sampling issues.

    Science.gov (United States)

    Bansback, Nick; Hole, Arne Risa; Mulhern, Brendan; Tsuchiya, Aki

    2014-08-01

    There is interest in the use of discrete choice experiments that include a duration attribute (DCETTO) to generate health utility values, but questions remain on its feasibility in large health state descriptive systems. This study examines the stability of DCETTO to estimate health utility values from the five-level EQ-5D, an instrument with depicts 3125 different health states. Between January and March 2011, we administered 120 DCETTO tasks based on the five-level EQ-5D to a total of 1799 respondents in the UK (each completed 15 DCETTO tasks on-line). We compared models across different sample sizes and different total numbers of observations. We found the DCETTO coefficients were generally consistent, with high agreement between individual ordinal preferences and aggregate cardinal values. Keeping the DCE design and the total number of observations fixed, subsamples consisting of 10 tasks per respondent with an intermediate sized sample, and 15 tasks with a smaller sample provide similar results in comparison to the whole sample model. In conclusion, we find that the DCETTO is a feasible method for developing values for larger descriptive systems such as EQ-5D-5L, and find evidence supporting important design features for future valuation studies that use the DCETTO. Copyright © 2014 The Authors. Published by Elsevier Ltd.. All rights reserved.

  8. Light weight radioisotope heater unit (LWRHU): a technical description of the reference design

    International Nuclear Information System (INIS)

    Tate, R.E.

    1982-01-01

    The Light Weight Radioisotope Heater Unit (LWRHU), a new radioisotope heater unit for use in space missions, is a 238 PuO 2 -fueled unit designed to provide a thermal watt in dispersed locations on a spacecraft. The LWRHU is required to maintain the temperature of a component at a level where the component will function reliably in space. Two major constraints are placed on the unit's design; it must be as light as possible and must provide enough protection to immobilize the plutonium fuel to the maximum extent in all phases of the unit's lifetime. The four components are pelletized fuel, platinum-alloy encapsulation, pyrolytic graphite thermal insulation, and high-technology graphite ablation shell. The LWRHU is a cylinder 32 mm (1.26 in.) high and 26 mm (1.02 in.) in diameter. It weighs slightly less than 40 g

  9. Final design of an air core, compulsator driven, 0.60 caliber railgun system

    International Nuclear Information System (INIS)

    Kitzmiller, J.R.; Faidley, R.W.; Fuller, R.L.; Headifen, G.R.; Pratap, S.B.; Spann, M.L.; Thelen, R.F.

    1991-01-01

    The Center for Electromechanics at The University of Texas at Austin (CEM-UT), is currently in the manufacturing phase of a laboratory based small caliber electromagnetic (EM) launcher and compulsator power supply. The objective of the 29-month program is to develop a compact, lightweight test bed capable of accelerating 32-g masses to 2 km/s at a rate of 10 Hz. Both the power supply and launcher feature significant component design advances which will allow the system to operate at considerably higher energy and power densities than previously demonstrated. The 750-kg compulsator will generate 2.2 kV and the Silicon- controlled rectifier (SCR) switch will commutate 386-kA pulses into the 1.6-m long, 0.60 caliber augmented solid armature railgun. This paper describes the final design and predicted operating characteristics of the compulsator system. Overall system performance parameters are reported, including results from the optimization code used to aid in the design of the compulsator system. A system design overview is presented with emphasis on new materials and state-of-the-art machine components to be used for the first time in a compulsator

  10. Perspectives on the Final Design Review process from the US ITER DRGA team

    Science.gov (United States)

    Biewer, T. M.; Klepper, C. C.; Devan, W.; Graves, V.; Marcus, C.; Andrew, P.; Johnson, D. W.

    2014-10-01

    Among the ITER procurements awarded to the US ITER Domestic Agency, and subsequently to the ORNL Fusion & Materials for Nuclear Systems Division, is the design and fabrication of the Diagnostic Residual Gas Analyzer (DRGA) system. The DRGA system reached the Final Design Review (FDR) in July 2014, and is the first US-credited diagnostic system to achieve this milestone. The design effort has focused on the vacuum and mechanical interface of the DRGA gas sampling tube with the ITER vacuum vessel and cyrostat. In addition to technical issues needed to negotiate the mechanical interface, a significant number of procedural issues at US ITER and the ITER IO were encountered to navigate the DRGA project to this milestone. The process has been beneficial to both the DRGA project, and in-turn to US ITER, by illuminating the procedures in practice. This presentation will highlight some of the issues encountered and relay perspectives for designing hardware for ITER. This work was supported by the US. D.O.E. Contract DE-AC05-00OR22725.

  11. A Basic Robotic Excavator (the Glenn Digger): Description, Design, and Initial Operation

    Science.gov (United States)

    Bauman, Steve; Newman, Paul; Izadnegahdar, Alain; Johnson, Kyle; Abel, Phillip

    2016-01-01

    This paper describes the design, commercial part selections, fabrication, assembly, installation, and initial operation of a two degree of freedom robotic excavator. Colloquially referred to as "the NASA Glenn Digger," it was designed specifically to be mounted onto, and to operate with, the then newly developed Centaur 2 robotic mobility base. The excavator, when mounted to Centaur 2, is designed to scoop loose regolith from the terrain, raise its loaded bucket up and dump the load into a hopper of at least a 1-m-height. The hopper represents the input to a machine that would process the raw material, such as to produce oxygen from lunar regolith as would be required for long-term lunar habitation. This equipment debuted at the annual Research and Technology Studies ("Desert RATS", Ref. 1) event held north of Flagstaff, Arizona, in September of 2010, when the Digger was successfully joined to Centaur 2 and the shoveling articulation was demonstrated. During 2011, the hardware was modified for added strength, strain gauges were added to measure loads, and the controls were improved in preparation for the 2011 Desert RATS event, where additional "field operations" experience was gained.

  12. Design description of the Large Coil Test Facility pulse-coil support and transport system

    International Nuclear Information System (INIS)

    Queen, C.C.

    1981-01-01

    In order to simulate the transient fields which would be imposed on superconducting toroidal field coils in an operating tokamak reactor, the Large Coil Test Facility (LCTF) test stand includes a set of pulse coils. This set of pulse coils is designed to be moved from one test location to another within the LCTF vacuum vessel while the vessel is operating under vacuum and the test stand and test coils are at an operating temperature of 4.2K. This operating environment and the extremely high magnetic loads have necessitated some unique design features for the pulse coil support and transport system. The support structure for the pulse coil must react high overturning moments and axial loads induced on the pulse coil by the interaction of the pulse field with the field generated by the large test coils. These loads are reacted into the test stand support structure or spider frame by an arrangement of six pedestals and a support beam. In order to move the pulse coil set from one test location to another, the support beam containing the pulse coils must be driven across rollers mounted on the pedestals, then clamped securely to react the loads. Because these operations must be performed in a vacuum environment at cryogenic tmperature, special consideration was given to component design

  13. UAS-NAS Live Virtual Constructive Distributed Environment (LVC): LVC Gateway, Gateway Toolbox, Gateway Data Logger (GDL), SaaProc Software Design Description

    Science.gov (United States)

    Jovic, Srboljub

    2015-01-01

    This document provides the software design description for the two core software components, the LVC Gateway, the LVC Gateway Toolbox, and two participants, the LVC Gateway Data Logger and the SAA Processor (SaaProc).

  14. Advanced human-system interface design review guideline. General evaluation model, technical development, and guideline description

    International Nuclear Information System (INIS)

    O'Hara, J.M.

    1994-07-01

    Advanced control rooms will use advanced human-system interface (HSI) technologies that may have significant implications for plant safety in that they will affect the operator's overall role in the system, the method of information presentation, and the ways in which operators interact with the system. The U.S. Nuclear Regulatory Commission (NRC) reviews the HSI aspects of control rooms to ensure that they are designed to good human factors engineering principles and that operator performance and reliability are appropriately supported to protect public health and safety. The principal guidance available to the NRC, however, was developed more than ten years ago, well before these technological changes. Accordingly, the human factors guidance needs to be updated to serve as the basis for NRC review of these advanced designs. The purpose of this project was to develop a general approach to advanced HSI review and the human factors guidelines to support NRC safety reviews of advanced systems. This two-volume report provides the results of the project. Volume I describes the development of the Advanced HSI Design Review Guideline (DRG) including (1) its theoretical and technical foundation, (2) a general model for the review of advanced HSIs, (3) guideline development in both hard-copy and computer-based versions, and (4) the tests and evaluations performed to develop and validate the DRG. Volume I also includes a discussion of the gaps in available guidance and a methodology for addressing them. Volume 2 provides the guidelines to be used for advanced HSI review and the procedures for their use

  15. Advanced human-system interface design review guideline. General evaluation model, technical development, and guideline description

    Energy Technology Data Exchange (ETDEWEB)

    O`Hara, J.M.

    1994-07-01

    Advanced control rooms will use advanced human-system interface (HSI) technologies that may have significant implications for plant safety in that they will affect the operator`s overall role in the system, the method of information presentation, and the ways in which operators interact with the system. The U.S. Nuclear Regulatory Commission (NRC) reviews the HSI aspects of control rooms to ensure that they are designed to good human factors engineering principles and that operator performance and reliability are appropriately supported to protect public health and safety. The principal guidance available to the NRC, however, was developed more than ten years ago, well before these technological changes. Accordingly, the human factors guidance needs to be updated to serve as the basis for NRC review of these advanced designs. The purpose of this project was to develop a general approach to advanced HSI review and the human factors guidelines to support NRC safety reviews of advanced systems. This two-volume report provides the results of the project. Volume I describes the development of the Advanced HSI Design Review Guideline (DRG) including (1) its theoretical and technical foundation, (2) a general model for the review of advanced HSIs, (3) guideline development in both hard-copy and computer-based versions, and (4) the tests and evaluations performed to develop and validate the DRG. Volume I also includes a discussion of the gaps in available guidance and a methodology for addressing them. Volume 2 provides the guidelines to be used for advanced HSI review and the procedures for their use.

  16. Design description of a microprocessor based Engine Monitoring and Control unit (EMAC) for small turboshaft

    Science.gov (United States)

    Baez, A. N.

    1985-01-01

    Research programs have demonstrated that digital electronic controls are more suitable for advanced aircraft/rotorcraft turbine engine systems than hydromechanical controls. Commercially available microprocessors are believed to have the speed and computational capability required for implementing advanced digital control algorithms. Thus, it is desirable to demonstrate that off-the-shelf microprocessors are indeed capable of performing real time control of advanced gas turbine engines. The engine monitoring and control (EMAC) unit was designed and fabricated specifically to meet the requirements of an advanced gas turbine engine control system. The EMAC unit is fully operational in the Army/NASA small turboshaft engine digital research program.

  17. Characterizing Distributed Concurrent Engineering Teams: A Descriptive Framework for Aerospace Concurrent Engineering Design Teams

    Science.gov (United States)

    Chattopadhyay, Debarati; Hihn, Jairus; Warfield, Keith

    2011-01-01

    As aerospace missions grow larger and more technically complex in the face of ever tighter budgets, it will become increasingly important to use concurrent engineering methods in the development of early conceptual designs because of their ability to facilitate rapid assessments and trades in a cost-efficient manner. To successfully accomplish these complex missions with limited funding, it is also essential to effectively leverage the strengths of individuals and teams across government, industry, academia, and international agencies by increased cooperation between organizations. As a result, the existing concurrent engineering teams will need to increasingly engage in distributed collaborative concurrent design. This paper is an extension of a recent white paper written by the Concurrent Engineering Working Group, which details the unique challenges of distributed collaborative concurrent engineering. This paper includes a short history of aerospace concurrent engineering, and defines the terms 'concurrent', 'collaborative' and 'distributed' in the context of aerospace concurrent engineering. In addition, a model for the levels of complexity of concurrent engineering teams is presented to provide a way to conceptualize information and data flow within these types of teams.

  18. Description of a reference design tokamak for the Technology Test Assembly

    International Nuclear Information System (INIS)

    Haubenreich, P.N.

    1975-10-01

    Early conceptual studies for the Technology Test Assembly involved a reference conceptual design for a tokamak with superconducting toroidal field magnets. The TF magnet conductors are NbTi filaments in a copper matrix. The 24 TF coils and associated structure operate at 4--5 K and a maximum field (at the windings) of 75 kG. Principal dimensions of the machine are: TF coil bore, 1.8 x 2.4 m (oval); major radius, 2.25 m; plasma minor radius, 0.6 m. A preliminary but detailed cost estimate for the reference machine was prepared to serve as an anchor point for cost scaling for larger machines in subsequent TTA parameter studies

  19. Plasma source by microwaves: design description; Fuente de plasma por microondas: descripcion de diseno

    Energy Technology Data Exchange (ETDEWEB)

    Camps, E.; Olea, O.; Andrade, R.; Anguiano, G

    1992-03-15

    The design of a device for the formation of a plasma with densities of the order of 10{sup 12} cm{sup -} {sup 3} and low temperatures (T{sub e} {approx} 40 eV) is described. For such purpose it was carried out in the device a microwave discharge (f{sub o} = 2.45 GHz) in a resonator of high Q factor, immersed in a static external magnetic field. The device worked in the regime {omega}{sub ce} {<=} {omega}{sub o}/2 ({omega}{sub ce}- cyclotron frequency of the electrons, ({omega}{sub o} = 2 {pi} f{sub o}) where is possible the excitement of non lineal phenomena of waves transformation. (Author)

  20. Description and analysis of design and intended use for Epidemiologic Dynamic Data Collection Platform in China.

    Science.gov (United States)

    Qi, Xiaopeng; Egana, Nilva; Meng, Yujie; Chen, Qianqian; Peng, Zhiyong; Ma, Jiaqi

    2014-01-01

    Disease surveillance systems can be extremely valuable tools and a critical step in system implementation is data collection. In order to obtain quality data efficiently and align the public health business process, Epidemiologic Dynamic Data Collection platform (EDDC) was developed and applied in China. We describe the design of EDDC and assess the platform from six dimensions (service, system, information, use, users and benefit) under the DeLone and McLean Information System Success Model. Objective indicators were extracted from each dimension with the aim of describing the system in detail. The characteristics of functions, performances, usages and benefits of EDDC were reflected under the analysis framework. The limitations and future directions of EDDC are offered for wide use in public health data collection.

  1. System design description for the LDUA common video end effector system (CVEE)

    International Nuclear Information System (INIS)

    Pardini, A.F.

    1998-01-01

    The Common Video End Effector System (CVEE), system 62-60, was designed by the Idaho National Engineering Laboratory (INEL) to provide the control interface of the various video end effectors used on the LDUA. The CVEE system consists of a Support Chassis which contains the input and output Opto-22 modules, relays, and power supplies and the Power Chassis which contains the bipolar supply and other power supplies. The combination of the Support Chassis and the Power Chassis make up the CVEE system. The CVEE system is rack mounted in the At Tank Instrument Enclosure (ATIE). Once connected it is controlled using the LDUA supervisory data acquisition system (SDAS). Video and control status will be displayed on monitors within the LDUA control center

  2. Proceedings of the second international workshop on design and construction of final repositories

    International Nuclear Information System (INIS)

    Simmons, G.R.

    1995-11-01

    Many international radioactive waste disposal programs are in the design and construction phases for underground laboratories and repositories. To provide a forum for discussion Svensk Kaernbraenslehantering AB (SKB) in 1992 initiated an international workshop series in which the organizations considering disposal in hard crystalline rock could meet to discuss issues relevant to The Design and Construction of Final Repositories. The first workshop with the theme 'Excavation through water conducting major fracture zones' was hosted by SKB in Saestaholm, Sweden on 1993 March 30 to 31 and the workshop proceedings are SKB Technical Report 94-06. Atomic Energy of Canada Limited hosted the second workshop with the theme 'Factors influencing repository design and layout' in Winnipeg, Canada on 1994 February 15 to 17. Thirty-eight people from organizations in eight countries and representative of the European Community participated in the Workshop. This report is the summary of the second workshop. The discussions at the Workshop were recorded and reproduced in the summary. Some editorial license was used to provide the text that follows. The participants were given the opportunity to comment on the text prior to publication. Unfortunately some individual speakers could not be identified on the recording of the Workshop discussions and are labelled 'unidentified' in the text. (author)

  3. Design review report for the Hanford K East and K West Basins MCO loading system

    International Nuclear Information System (INIS)

    Brisbin, S.A.

    1997-01-01

    This design report presents the final design of the MCO Loading System. The report includes final design drawings, a system description, failure modes and recovery plans, a system operational description, and stress analysis. Design comments from the final design review have been incorporated

  4. Designing concept maps for a precise and objective description of pharmaceutical innovations

    Directory of Open Access Journals (Sweden)

    Iordatii Maia

    2013-01-01

    Full Text Available Abstract Background When a new drug is launched onto the market, information about the new manufactured product is contained in its monograph and evaluation report published by national drug agencies. Health professionals need to be able to determine rapidly and easily whether the new manufactured product is potentially useful for their practice. There is therefore a need to identify the best way to group together and visualize the main items of information describing the nature and potential impact of the new drug. The objective of this study was to identify these items of information and to bring them together in a model that could serve as the standard for presenting the main features of new manufactured product. Methods We developed a preliminary conceptual model of pharmaceutical innovations, based on the knowledge of the authors. We then refined this model, using a random sample of 40 new manufactured drugs recently approved by the national drug regulatory authorities in France and covering a broad spectrum of innovations and therapeutic areas. Finally, we used another sample of 20 new manufactured drugs to determine whether the model was sufficiently comprehensive. Results The results of our modeling led to three sub models described as conceptual maps representingi the medical context for use of the new drug (indications, type of effect, therapeutical arsenal for the same indications, ii the nature of the novelty of the new drug (new molecule, new mechanism of action, new combination, new dosage, etc., and iii the impact of the drug in terms of efficacy, safety and ease of use, compared with other drugs with the same indications. Conclusions Our model can help to standardize information about new drugs released onto the market. It is potentially useful to the pharmaceutical industry, medical journals, editors of drug databases and medical software, and national or international drug regulation agencies, as a means of describing the main

  5. Chemical Frustration. A Design Principle for the Discovery of New Complex Alloy and Intermetallic Phases, Final Report

    Energy Technology Data Exchange (ETDEWEB)

    Fredrickson, Daniel C [Univ. of Wisconsin, Madison, WI (United States)

    2015-06-23

    Final technical report for "Chemical Frustration: A Design Principle for the Discovery of New Complex Alloy and Intermetallic Phases" funded by the Office of Science through the Materials Chemistry Program of the Office of Basic Energy Sciences.

  6. Microgrid Design, Development and Demonstration - Final Report for Phase I and Phase II

    Energy Technology Data Exchange (ETDEWEB)

    Bose, Sumit [GE Global Research Center, Niskayuna, NY (United States); Krok, Michael [GE Global Research Center, Niskayuna, NY (United States)

    2011-02-08

    This document constitutes GE’s final report for the Microgrid Design, Development and Demonstration program for DOE’s Office of Electricity Delivery and Energy Reliability, Award DE-FC02-05CH11349. It contains the final report for Phase I in Appendix I, and the results the work performed in Phase II. The program goal was to develop and demonstrate a Microgrid Energy Management (MEM) framework for a broad set of Microgrid applications that provides unified controls, protection, and energy management. This project contributed to the achievement of the U.S. Department of Energy’s Renewable and Distributed Systems Integration Program goals by developing a fully automated power delivery microgrid network that: - Reduces carbon emissions and emissions of other air pollutants through increased use of optimally dispatched renewable energy, - Increases asset use through integration of distributed systems, - Enhances reliability, security, and resiliency from microgrid applications in critical infrastructure protection, constrained areas of the electric grid, etc. - Improves system efficiency with on-site, distributed generation and improved economic efficiency through demand-side management.

  7. Experimental evaluation and design of unfilled and concrete-filled FRP composite piles : Task 7 : final report : thesis.

    Science.gov (United States)

    2015-05-01

    The overall goal of this project is the experimental evaluation and design of unfilled and concrete-filled FRP composite piles for load-bearing in bridges. This report covers Task 7, Final Report - Thesis. : This final report covers Tasks 1, 2, 3, 5 ...

  8. Process description and plant design for preparing ceramic high-level waste forms

    International Nuclear Information System (INIS)

    Grantham, L.F.; McKisson, R.L.; Guon, J.; Flintoff, J.F.; McKenzie, D.E.

    1983-01-01

    The ceramics process flow diagram has been simplified and upgraded to utilize only two major processing steps - fluid-bed calcination and hot isostatic press consolidating. Full-scale fluid-bed calcination has been used at INEL to calcine high-level waste for 18 y; and a second-generation calciner, a fully remotely operated and maintained calciner that meets ALARA guidelines, started calcining high-level waste in 1982. Full-scale hot isostatic consolidation has been used by DOE and commercial enterprises to consolidate radioactive components and to encapsulate spent fuel elements for several years. With further development aimed at process integration and parametric optimization, the operating knowledge of full-scale demonstration of the key process steps should be rapidly adaptable to scale-up of the ceramic process to full plant size. Process flowsheets used to prepare ceramic and glass waste forms from defense and commercial high-level liquid waste are described. Preliminary layouts of process flow diagrams in a high-level processing canyon were prepared and used to estimate the preliminary cost of the plant to fabricate both waste forms. The estimated costs for using both options were compared for total waste management costs of SRP high-level liquid waste. Using our design, for both the ceramic and glass plant, capital and operating costs are essentially the same for both defense and commercial wastes, but total waste management costs are calculated to be significantly less for defense wastes using the ceramic option. It is concluded from this and other studies that the ceramic form may offer important advantages over glass in leach resistance, waste loading, density, and process flexibility. Preliminary economic calculations indicate that ceramics must be considered a leading candidate for the form to immobilize high-level wastes

  9. Final safety analysis report for the Galileo Mission: Volume 1, Reference design document

    Energy Technology Data Exchange (ETDEWEB)

    1988-05-01

    The Galileo mission uses nuclear power sources called Radioisotope Thermoelectric Generators (RTGs) to provide the spacecraft's primary electrical power. Because these generators contain nuclear material, a Safety Analysis Report (SAR) is required. A preliminary SAR and an updated SAR were previously issued that provided an evolving status report on the safety analysis. As a result of the Challenger accident, the launch dates for both Galileo and Ulysses missions were later rescheduled for November 1989 and October 1990, respectively. The decision was made by agreement between the DOE and the NASA to have a revised safety evaluation and report (FSAR) prepared on the basis of these revised vehicle accidents and environments. The results of this latest revised safety evaluation are presented in this document (Galileo FSAR). Volume I, this document, provides the background design information required to understand the analyses presented in Volumes II and III. It contains descriptions of the RTGs, the Galileo spacecraft, the Space Shuttle, the Inertial Upper Stage (IUS), the trajectory and flight characteristics including flight contingency modes, and the launch site. There are two appendices in Volume I which provide detailed material properties for the RTG.

  10. Cold Vacuum Drying (CVD) Facility Vacuum Purge System Chilled Water System Design Description. System 47-4

    International Nuclear Information System (INIS)

    IRWIN, J.J.

    2000-01-01

    This system design description (SDD) addresses the Vacuum Purge System Chilled Water (VPSCHW) system. The discussion that follows is limited to the VPSCHW system and its interfaces with associated systems. The reader's attention is directed to Drawings H-1-82162, Cold Vacuum Drying Facility Process Equipment Skid PandID Vacuum System, and H-1-82224, Cold Vacuum Drying Facility Mechanical Utilities Process Chilled Water PandID. Figure 1-1 shows the location and equipment arrangement for the VPSCHW system. The VPSCHW system provides chilled water to the Vacuum Purge System (VPS). The chilled water provides the ability to condense water from the multi-canister overpack (MCO) outlet gases during the MCO vacuum and purge cycles. By condensing water from the MCO purge gas, the VPS can assist in drying the contents of the MCO

  11. Design description and validation results for the IFMIF High Flux Test Module as outcome of the EVEDA phase

    Directory of Open Access Journals (Sweden)

    F. Arbeiter

    2016-12-01

    Full Text Available During the Engineering Validation and Engineering Design Activities (EVEDA phase (2007-2014 of the International Fusion Materials Irradiation Facility (IFMIF, an advanced engineering design of the High Flux Test Module (HFTM has been developed with the objective to facilitate the controlled irradiation of steel samples in the high flux area directly behind the IFMIF neutron source. The development process addressed included manufacturing techniques, CAD, neutronic, thermal-hydraulic and mechanical analyses complemented by a series of validation activities. Validation included manufacturing of 1:1 parts and mockups, test of prototypes in the FLEX and HELOKA-LP helium loops of KIT for verification of the thermal and mechanical properties, and irradiation of specimen filled capsule prototypes in the BR2 test reactor. The prototyping activities were backed by several R&D studies addressing focused issues like handling of liquid NaK (as filling medium and insertion of Small Specimen Test Technique (SSTT specimens into the irradiation capsules. This paper provides an up-todate design description of the HFTM irradiation device, and reports on the achieved performance criteria related to the requirements. Results of the validation activities are accounted for and the most important issues for further development are identified.

  12. Final evaluation of the `solar garden house`, a new concept for energy conscious design

    Energy Technology Data Exchange (ETDEWEB)

    Voorden, M. van der; Pel-Hoogendoorn, M.; Tilde, P. de [Building Physics Group, Faculty of Architecture, Delis University of Technology, Delft (Netherlands)

    1997-12-31

    The `Solar Garden House` is an example of a recently developed concept for Energy Conscious Building Design. One of the striking features of this house is a huge sun space connecting two small housing blocks. The sun space is meant as an air collector from which heated air can be conducted through a cavity wall in each of the mentioned housing blocks. The cavity wall is used as a component for storage of energy supplied by the heated air and can be used as a source for supplementary heating of inner spaces on both sides of the wall. A preliminary computational study, carried out at Dells University of Technology, indicated that the contribution of the cavity wall to energy savings was negligible. Therefore, as a follow-up the alternative use of the sun space as a device for pre-heating air for ventilation purposes has been investigated. This option turned out to be far more promising from the energy saving point of view. This presentation focuses on the original building concept. A final evaluation of the Solar Garden House will be given. The following aspects will be discussed: energy behaviour and thermal comfort, relevant design parameters and accuracy of obtained computational results. (orig.) 4 refs.

  13. The final design of the ATLAS Trigger/DAQ Readout-Buffer Input (ROBIN) Device

    CERN Document Server

    Kugel, A; Müller, M; Yu, M; Krause, E; Gorini, B; Joos, M; Petersen, J; Stancu, S; Green, B; Misiejuk, A; Kieft, G; Van Wasen, J; 10th Workshop on Electronics for LHC and Future Experiments

    2004-01-01

    The ATLAS readout subsystem (ROS) is the main interface between 1600 detector front-end readout links (ROL) and the high level (HLT) trigger farms. Its core device, the readout-buffer input (ROBIN), accepts event data on 3 readout links (ROLs) with a maximum rate of 100 kHz and a bandwidth of up to 160\\,MB/s per link. Incoming event data is temporarily buffered and delivered via PCI or Gigabit Ethernet on request. Two devices, a XILINX XC2V2000 FPGA and an IBM PowerPC 440, are present, implementing the ROBIN's functionality. Furthermore one 64 MB SDRAM event data buffer is available per ROL. The device supports the ATLAS baseline implementation, which foresees the PCI bus as the main communication path inside the ROS, as well as an optional data path using Gigabit Ethernet to increase scalability when needed. The paper presents the final design of the ATLAS ROBIN. Measurement results, obtained with a prototype device in PCI bus and Gigabit Ethernet setups, show the usability and approve the design choices.

  14. Test design description Volume 2, Part 1. IFR-1 metal fuel irradiation test (AK-181) element as-built data

    Energy Technology Data Exchange (ETDEWEB)

    Dodds, N. E.

    1986-06-01

    The IFR-1 Test, designated as the AK-181 Test Assembly, will be the first irradiation test of wire wrapped, sodium-bonded metallic fuel elements in the Fast Flux Test Facility (FFTF). The test is part of the Integral Fast Reactor (IFR) fuels program conducted by Argonne National Laboratory (ANL) in support of the Innovative Reactor Concepts Program sponsored by the US Department of Energy (DOE). One subassembly, containing 169 fuel elements, will be irradiated for 600 full power days to achieve 10 at.% burnup. Three metal fuel alloys (U-10Zr, U-8Pu-10Zr) will be irradiated in D9 cladding tubes. The metal fuel elements have a fuel-smeared density of 75% and each contains five slugs. The enriched zone contains three slugs and is 36-in. long. One 6.5-in. long depleted uranium axial blanket slug (DU-10Zr) was loaded at each end of the enriched zone. the fuel elements were fabricated at ANL-W and delivered to Westinghouse-Hanford for wirewrapping and assembly into the test article. This Test Design Description contains relevant data on compositions, densities, dimensions and weights for the cast fuel slugs and completed fuel elements. The elements conform to the requirements in MG-22, "Users` Guide for the Irradiation of Experiments in the FTR."

  15. Grid fault and design-basis for wind turbines. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Hansen, A.D.; Cutululis, N.A.; Markou, H.; Soerensen, Poul; Iov, F.

    2010-01-15

    This is the final report of a Danish research project 'Grid fault and design-basis for wind turbines'. The objective of this project has been to assess and analyze the consequences of the new grid connection requirements for the fatigue and ultimate structural loads of wind turbines. The fulfillment of the grid connection requirements poses challenges for the design of both the electrical system and the mechanical structure of wind turbines. The development of wind turbine models and novel control strategies to fulfill the TSO's requirements are of vital importance in this design. Dynamic models and different fault ride-through control strategies have been developed and assessed in this project for three different wind turbine concepts (active stall wind turbine, variable speed doublyfed induction generator wind turbine, variable speed multipole permanent magnet wind turbine). A computer approach for the quantification of the wind turbines structural loads caused by the fault ride-through grid requirement, has been proposed and exemplified for the case of an active stall wind turbine. This approach relies on the combination of knowledge from complimentary simulation tools, which have expertise in different specialized design areas for wind turbines. In order to quantify the impact of the grid faults and grid requirements fulfillment on wind turbines structural loads and thus on their lifetime, a rainflow and a statistical analysis for fatigue and ultimate structural loads, respectively, have been performed and compared for two cases, i.e. one when the turbine is immediately disconnected from the grid when a grid fault occurs and one when the turbine is equipped with a fault ride-through controller and therefore it is able to remain connected to the grid during the grid fault. Different storm control strategies, that enable variable speed wind turbines to produce power at wind speeds higher than 25m/s and up to 50m/s without substantially increasing

  16. Final design and mock-up of an ITER sector sub-assembly tool

    Energy Technology Data Exchange (ETDEWEB)

    Nam, Kyoungo, E-mail: namko@nfri.re.kr [National Fusion Research Institute (NFRI), 169-148 Gwahak-ro, Yuseong-gu, Daejeon 34133 (Korea, Republic of); Ha, Min-Su; Bae, Jinho; Kwon, Soun Pil [National Fusion Research Institute (NFRI), 169-148 Gwahak-ro, Yuseong-gu, Daejeon 34133 (Korea, Republic of); Moon, Jaewhan [SFA, 262 Yunposun-ro, Dunpo-myeon, Asan-si, Chungnam 31421 (Korea, Republic of); Park, Jihye [TSNE, 27 Seongsui-ro 7-gil, Seongsu-dong, Seongdong-gu, Seoul 04780 (Korea, Republic of); Noh, Jihoon [SFA, 262 Yunposun-ro, Dunpo-myeon, Asan-si, Chungnam 31421 (Korea, Republic of); Park, Chanhyung [MOROO Inc., 52-8 Oecheoncheoksan-gil, Nami-myeon, Cheongju-si, Chungcheongbuk-do 28182 (Korea, Republic of)

    2016-11-01

    The assembly and installation tools for the ITER Tokamak machine are special tools which are used to assemble and install ITER Tokamak machine components such as magnets, vessels and thermal shields. The sector sub-assembly tool, requiring six adjustable motions capable of movements in three directions and three-axis rotations for fine and precise alignments of the components of these tools, is a major and very large assembly tool with which to assemble vacuum vessels, thermal shields and two toroidal field coils in a 40° sector that forms the basic unit for the ITER Tokamak machine. To complete the 40° sector, the tool must maintain a sufficient degree of stiffness to support and handle heavy components which weigh up to 1200 tonnes. To meet the tooling requirements, the feasibility of the alignment system with regard to component adjustments in the sector sub-assembly tool was reviewed and verified in a mock-up test. In addition, a structural analysis using ANSYS to verify the structural stability levels under various analysis conditions was also carried out considering the safety factors and seismic load conditions according to the load specifications and codes. The sector sub-assembly sequence and the final design considering the results of the mock-up test and the structural analysis are presented.

  17. Advanced turbine systems program -- Conceptual design and product development. Final report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-07-26

    This Final Technical Report presents the accomplishments on Phase 2 of the Advanced Turbine Systems (ATS). The ATS is an advanced, natural gas fired gas turbine system that will represent a major advance on currently available industrial gas turbines in the size range of 1--20 MW. This report covers a market-driven development. The Market Survey reported in Section 5 identified the customer`s performance needs. This market survey used analyses performed by Solar turbine Incorporated backed up by the analyses done by two consultants, Research Decision Consultants (RDC) and Onsite Energy Corporation (Onsite). This back-up was important because it is the belief of all parties that growth of the ATS will depend both on continued participation in Solar`s traditional oil and gas market but to a major extent on a new market. This new market is distributed electrical power generation. Difficult decisions have had to be made to meet the different demands of the two markets. Available resources, reasonable development schedules, avoidance of schedule or technology failures, probable acceptance by the marketplace, plus product cost, performance and environmental friendliness are a few of the complex factors influencing the selection of the Gas Fired Advanced Turbine System described in Section 3. Section 4 entitled ``Conversion to Coal`` was a task which addresses the possibility of a future interruption to an economic supply of natural gas. System definition and analysis is covered in Section 6. Two major objectives were met by this work. The first was identification of those critical technologies that can support overall attainment of the program goals. Separate technology or component programs were begun to identify and parameterize these technologies and are described in Section 7. The second objective was to prepare parametric analyses to assess performance sensitivity to operating variables and to select design approaches to meet the overall program goals.

  18. Quality of reporting of descriptive studies in implant dentistry. Critical aspects in design, outcome assessment and clinical relevance

    NARCIS (Netherlands)

    Meijer, Henny J. A.; Raghoebar, Gerry M.

    Objectives: The aim of this study was to conduct a review on quality of reporting on descriptive studies in implant dentistry using the STROBE Statement and to analyse possible changes in quality of reporting on descriptive studies in implant dentistry over time. Material and Methods: A hand search

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

    Energy Technology Data Exchange (ETDEWEB)

    1978-12-18

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

  20. Safety Evaluation Report related to the final design approval of the GESSAR II BWR/6 Nuclear Island Design (Docket No. 50-447). Supplement No. 3

    International Nuclear Information System (INIS)

    1985-01-01

    Supplement 3 to the Safety Evaluation Report (SER) for the application filed by General Electric Company for the final design approval for the GE BWR/6 nuclear island design has been prepared by the Office of Nuclear Reactor Regulation of the Nuclear Regulatory Commission. This report supplements the GESSAR II SER (NUREG-0979), issued in April 1983, summarizing the results of the staff's safety review of the GESSAR II BWR/6 nuclear island design. Subject to favorable resolution of the items discussed in this supplement, the staff concludes that the GESSAR II design satisfactorily addresses the severe-accident concerns described in draft NUREG-1070

  1. Inertial Fusion Energy reactor design studies: Prometheus-L, Prometheus-H. Volume 1, Final report

    Energy Technology Data Exchange (ETDEWEB)

    Waganer, L.M.; Driemeyer, D.E.; Lee, V.D.

    1992-03-01

    This report contains a review of design studies for inertial confinement reactors. The first of three volumes briefly discusses the following: Introduction; Key objectives, requirements, and assumptions; Systems modeling and trade studies; Prometheus-L reactor plant design overview; Prometheus-H reactor plant design overview; Key technical issues and R&D requirements; Comparison of IFE designs; and study conclusions.

  2. Final design and progress of WEAVE: the next generation wide-field spectroscopy facility for the William Herschel Telescope

    NARCIS (Netherlands)

    Dalton, Gavin; Trager, Scott; Abrams, Don Carlos; Bonifacio, Piercarlo; Aguerri, J. Alfonso L.; Middleton, Kevin; Benn, Chris; Dee, Kevin; Sayède, Frédéric; Lewis, Ian; Pragt, Johannes; Pico, Sergio; Walton, Nic; Rey, Jeurg; Allende Prieto, Carlos; Peñate, José; Lhome, Emilie; Agócs, Tibor; Alonso, José; Terrett, David; Brock, Matthew; Gilbert, James; Schallig, Ellen; Ridings, Andy; Guinouard, Isabelle; Verheijen, Marc; Tosh, Ian; Rogers, Kevin; Lee, Martin; Steele, Iain; Stuik, Remko; Tromp, Niels; Jaskó, Attila; Carrasco, Esperanza; Farcas, Szigfrid; Kragt, Jan; Lesman, Dirk; Kroes, Gabby; Mottram, Chris; Bates, Stuart; Rodriguez, Luis Fernando; Gribbin, Frank; Delgado, José Miguel; Herreros, José Miguel; Martin, Carlos; Cano, Diego; Navarro, Ramon; Irwin, Mike; Lewis, Jim; Gonzalez Solares, Eduardo; Murphy, David; Worley, Clare; Bassom, Richard; O'Mahoney, Neil; Bianco, Andrea; Zurita, Christina; ter Horst, Rik; Molinari, Emilio; Lodi, Marcello; Guerra, José; Martin, Adrian; Vallenari, Antonella; Salasnich, Bernardo; Baruffolo, Andrea; Jin, Shoko; Hill, Vanessa; Smith, Dan; Drew, Janet; Poggianti, Bianca; Pieri, Mat; Dominquez Palmero, Lillian; Farina, Cecilia

    2016-01-01

    We present the Final Design of the WEAVE next-generation spectroscopy facility for the William Herschel Telescope (WHT), together with a status update on the details of manufacturing, integration and the overall project schedule now that all the major fabrication contracts are in place. We also

  3. A Description of Room Arrangement, Design, and Appearance in Title IV-A Day Care Centers in Philadelphia, 1974-1975. Report No. 7733.

    Science.gov (United States)

    Silber, Theodore J.

    This report describes the room arrangement, design, and appearance of 152 Title IV-A Day Care centers in Philadelphia. A series of 27 items on a section of the Daily Care, In-Room Observation Guide was used to provide an overall description of rooms in day care and to identify differences in features for different types of programs. Data were…

  4. Performance/Design Requirements and Detailed Technical Description for a Computer-Directed Training Subsystem for Integration into the Air Force Phase II Base Level System.

    Science.gov (United States)

    Butler, A. K.; And Others

    The performance/design requirements and a detailed technical description for a Computer-Directed Training Subsystem to be integrated into the Air Force Phase II Base Level System are described. The subsystem may be used for computer-assisted lesson construction and has presentation capability for on-the-job training for data automation, staff, and…

  5. Engineering Design Thinking and Information Gathering. Final Report. Research in Engineering and Technology Education

    Science.gov (United States)

    Mentzer, Nathan

    2011-01-01

    The objective of this research was to explore the relationship between information access and design solution quality of high school students presented with an engineering design problem. This objective is encompassed in the research question driving this inquiry: How does information access impact the design process? This question has emerged in…

  6. The AP600 advanced simplified nuclear power plant. Results of the test program and progress made toward final design approval

    International Nuclear Information System (INIS)

    Bruschi, H.J.

    1996-01-01

    At the 1994 Pacific Basin Conference, Mr. Bruschi presented a paper describing the AP600, Westinghouse's advanced light water reactor design with passive safety features. Since then, a rigorous test program was completed and AP600 became the most thoroughly tested advanced reactor system design in history. Westinghouse is now well on its way toward receiving Final Design Approval from the U.S. Nuclear Regulatory Commission for AP600. In this paper, the results of the test program will be discussed and an update on prospects for building the plant will be covered. (author)

  7. Safety Evaluation Report related to the final design approval of the GESSAR II BWR/6 Nuclear Island design, Docket No. 50-447

    International Nuclear Information System (INIS)

    1983-04-01

    The Safety Evaluation Report for the application filed by General Electric Company for the Final Design Approval for the General Electric Standard Safety Analysis Report (GESSAR II FSAR) has been prepared by the Office of Nuclear Reactor Regulation of the Nuclear Regulatory Commission. This report summarizes the results of the staff's safety review of the GESSAR II BWR/6 Nuclear Island Design. Subject to favorable resolution of items discussed in the Safety Evaluation Report, the staff concludes that the facilities referencing GESSAR II, subject to approval of the balance-of-plant design, can conform with the provisions of the Act and the regulations of the Nuclear Regulatory Commission

  8. Final design report for the sludge handling system SNF subproject A13B [SEC 1 THRU 3

    International Nuclear Information System (INIS)

    MCSHANE, D.S.

    2003-01-01

    This Final Design Report (FDR) presents a review of the definitive design of the Sludge Handling System (SHS), Spent Nuclear Fuel (SNF) Sub-project A. 13(b). The information presented in this document, and the Sludge Handling System Compliance Matrix (HNF 8767), demonstrates compliance with HNF-6579, Baseline Design Criteria for the Sludge Handling System. The SHS project provides the equipment necessary to receive, store, and maintain radioactive sludge at T Plant where the sludge will be stored until it can be treated to meet disposal site requirements. In keeping with the principles of ALARA, the systems supplied are designed to operate remotely. The sludge storage systems are designed to meet Toxic Substances Control Act (TSCA) requirements. In addition to the new equipment necessary to safely receive and store sludge, other existing T Plant systems were modified

  9. Systematic Process Synthesis and Design Methods for Cost Effective Waste Minimization. Final report

    International Nuclear Information System (INIS)

    Biegler, L.T.; Grossmann, I.E.; Westerberg, A.W.

    1998-01-01

    This report focuses on research done over the past four years under the grant with the above title. In addition, the report also includes a brief summary of work done before 1994 under grant DOE-DE-FG02-85ER13396. Finally, a complete list of publications that acknowledge support from this grant is listed at the end

  10. Systematic Process Synthesis and Design Methods for Cost Effective Waste Minimization. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Biegler, L.T.; Grossmann, I.E.; Westerberg, A.W.

    1998-02-14

    This report focuses on research done over the past four years under the grant with the above title. In addition, the report also includes a brief summary of work done before 1994 under grant DOE-DE-FG02-85ER13396. Finally, a complete list of publications that acknowledge support from this grant is listed at the end.

  11. Implementation of Distributed ADAMS Over Legion Using a Component DBMS Design. Final Report

    Energy Technology Data Exchange (ETDEWEB)

    Pfaltz, John L. [Univ. of Virginia, Charlottesville, VA (United States). Dept. of Computer Science; Orlandic, Ratko [Illinois Inst. of Tech., Chicago, IL (United States). Dept. of Computer Science

    2002-11-26

    There were four primary research areas reported in the final report for the original funding period They are: implementation of high dimensional data spaces; knowledge discovery in scientific databases; and mismatch between implementing components; demonstrate the utility of ADAMS in a specific domain science.

  12. 76 FR 66805 - Endangered and Threatened Wildlife and Plants: Final Rulemaking To Designate Critical Habitat for...

    Science.gov (United States)

    2011-10-27

    ... commenter stated that there are many species of plants and animals that deserve to be placed on the ESA list... of copper in the cooling water effluent of a nuclear power plant near Diablo Canyon, California, were... Atmospheric Administration 50 CFR Part 226 Endangered and Threatened Wildlife and Plants: Final Rulemaking To...

  13. Ocean thermal energy conversion (OTEC) power system development. Preliminary design report, Appendices, Part 1 (Final)

    Energy Technology Data Exchange (ETDEWEB)

    1978-12-04

    The objective of this project is the development of a preliminary design for a full-sized, closed cycle, ammonia power system module for the 100 MWe OTEC demonstration plant. In turn, this demonstration plant is to demonstrate, by 1984, the operation and performance of an Ocean Thermal Power Plant having sufficiently advanced heat exchanger design to project economic viability for commercial utilization in the late 1980's and beyond. Included in this power system development are the preliminary designs for a proof-of-concept pilot plant and test article heat exchangers which are scaled in such a manner as to support a logically sequential, relatively low-cost development of the full-scale power system module. The conceptual designs are presented for the demonstration plant power module, the proof-of-concept pilot plant, and for a pair of test article heat exchangers. Costs associated with the design, development, fabrication, checkout, delivery, installation, and operation are included. The accompanying design and producibilty studies on the full-scale power system module project the performance/economics for the commercial plant. This section of the report contains appendices on the developed computer models, water system dynamic studies, miscellaneous performance analysis, materials and processes, detailed equipment lists, turbine design studies, tube cleaner design, ammonia leak detection, and heat exchanger design supporting data. (WHK)

  14. Human-system interface design review guideline -- Process and guidelines: Final report. Revision 1, Volume 1

    International Nuclear Information System (INIS)

    1996-06-01

    NUREG-0700, Revision 1, provides human factors engineering (HFE) guidance to the US Nuclear Regulatory Commission staff for its: (1) review of the human system interface (HSI) design submittals prepared by licensees or applications for a license or design certification of commercial nuclear power plants, and (2) performance of HSI reviews that could be undertaken as part of an inspection or other type of regulatory review involving HSI design or incidents involving human performance. The guidance consists of a review process and HFE guidelines. The document describes those aspects of the HSI design review process that are important to the identification and resolution of human engineering discrepancies that could adversely affect plant safety. Guidance is provided that could be used by the staff to review an applicant's HSI design review process or to guide the development of an HSI design review plan, e.g., as part of an inspection activity. The document also provides detailed HFE guidelines for the assessment of HSI design implementations. NUREG-0700, Revision 1, consists of three stand-alone volumes. Volume 1 consists of two major parts. Part 1 describes those aspects of the review process of the HSI design that are important to identifying and resolving human engineering discrepancies. Part 2 contains detailed guidelines for a human factors engineering review which identify criteria for assessing the implementation of an applicant's or licensee's HSI design

  15. Human-system interface design review guideline -- Process and guidelines: Final report. Revision 1, Volume 1

    Energy Technology Data Exchange (ETDEWEB)

    None

    1996-06-01

    NUREG-0700, Revision 1, provides human factors engineering (HFE) guidance to the US Nuclear Regulatory Commission staff for its: (1) review of the human system interface (HSI) design submittals prepared by licensees or applications for a license or design certification of commercial nuclear power plants, and (2) performance of HSI reviews that could be undertaken as part of an inspection or other type of regulatory review involving HSI design or incidents involving human performance. The guidance consists of a review process and HFE guidelines. The document describes those aspects of the HSI design review process that are important to the identification and resolution of human engineering discrepancies that could adversely affect plant safety. Guidance is provided that could be used by the staff to review an applicant`s HSI design review process or to guide the development of an HSI design review plan, e.g., as part of an inspection activity. The document also provides detailed HFE guidelines for the assessment of HSI design implementations. NUREG-0700, Revision 1, consists of three stand-alone volumes. Volume 1 consists of two major parts. Part 1 describes those aspects of the review process of the HSI design that are important to identifying and resolving human engineering discrepancies. Part 2 contains detailed guidelines for a human factors engineering review which identify criteria for assessing the implementation of an applicant`s or licensee`s HSI design.

  16. Demonstration of a Basis for Tall Wind Turbine Design, EUDP Project Final Report

    DEFF Research Database (Denmark)

    Natarajan, Anand; Dimitrov, Nikolay Krasimirov; Madsen, Peter Hauge

    Wind turbine design using calibrated wind models have been proposed to be used in conjunction with load cases which lead to reduced uncertainties in the design of wind turbines with hub heights above 60m. These recommended wind profiles have been made for shear, wind directional change and turbul......Wind turbine design using calibrated wind models have been proposed to be used in conjunction with load cases which lead to reduced uncertainties in the design of wind turbines with hub heights above 60m. These recommended wind profiles have been made for shear, wind directional change...

  17. Quality of reporting of descriptive studies in implant dentistry. Critical aspects in design, outcome assessment and clinical relevance.

    Science.gov (United States)

    Meijer, Henny J A; Raghoebar, Gerry M

    2012-02-01

    The aim of this study was to conduct a review on quality of reporting on descriptive studies in implant dentistry using the STROBE Statement and to analyse possible changes in quality of reporting on descriptive studies in implant dentistry over time. A hand search to select descriptive studies was carried out in seven dental journals, which were thought to have interest in the field of dental implants. Issues of the years 1990, 1995, 2000, 2005 and 2010 were screened. The STROBE Statement with 22 criteria to match was used to determine the quality of an article. Totally 4657 titles and abstracts were screened; 260 of them were found to be reporting on a descriptive study. Percentages of properly addressed items were 46% in 1990, 56% in 1995, 54% in 2000, 59% in 2005 and 70% in 2010. From this review can be concluded that quality of reporting on descriptive studies in implant dentistry is low; there is some improvement from 1990 to 2010, but it does not exceed 70% coverage of the possible to address items. © 2012 John Wiley & Sons A/S.

  18. Safety Evaluation Report related to the final design approval of the GESSAR II BWR/6 nuclear island design (Docket No. 50-447). Supplement No. 4

    International Nuclear Information System (INIS)

    1985-07-01

    Supplement 4 to the Safety Evaluation Report (SER) for the application filed by General Electric Company for the final design approval for the GE BWR/6 nuclear island design (GESSAR II) has been prepared by the Office of Nuclear Reactor Regulation of the Nuclear Regulatory Commission. This report supplements the GESSAR II SER (NUREG-0979) issued in April 1983 summarizing the results of the staff's safety review of the GESSAR II BWR/6 nuclear island design; Supplement 1, issued in July 1983; Supplement 2, issued in November 1984; and Supplement 3, issued in January 1985. Subject to favorable resolution of the items discussed in this supplement, the staff concludes that the GESSAR II design satisfactorily addresses the severe-accident concerns described in the Commission's Policy Statement on Severe Reactor Accidents Regarding Future Designs and Existing Plants

  19. An ion-optical design study of a carbon-ion rotating gantry with a superconducting final bending magnet

    International Nuclear Information System (INIS)

    Bokor, J.; Pavlovič, M.

    2016-01-01

    Ion-optical designs of an isocentric ion gantry with a compact curved superconducting final bending magnet are presented. The gantry is designed for transporting carbon-therapy beams with nominal kinetic energy of 400 MeV/u, which corresponds to the penetration range of C 6+ beam in water of about 28 cm. In contrast to other existing designs, we present a “hybrid” beam transport system containing a single superconducting element – the last bending magnet. All other elements are based on conventional warm technology. Ion-optical properties of such a hybrid system are investigated in case of transporting non-symmetric (i.e. different emittance patterns in the horizontal and vertical plane) beams. Different conditions for transporting the non-symmetric beams are analyzed aiming at finding the optimal, i.e. the most compact, gantry version. The final gantry layout is presented including a 2D parallel scanning. The ion-optical and scanning properties of the final gantry design are described, discussed and illustrated by computer simulations performed by WinAGILE.

  20. BASELINE DESIGN/ECONOMICS FOR ADVANCED FISCHER-TROPSCH TECHNOLOGY; FINAL

    International Nuclear Information System (INIS)

    None

    1998-01-01

    Bechtel, along with Amoco as the main subcontractor, developed a Baseline design, two alternative designs, and computer process simulation models for indirect coal liquefaction based on advanced Fischer-Tropsch (F-T) technology for the U. S. Department of Energy's (DOE's) Federal Energy Technology Center (FETC)

  1. Preliminary design: duplex tube low-pressure saturated steam generator for large LMFBR plant. Final report

    International Nuclear Information System (INIS)

    Dawson, B.E.

    1979-10-01

    A preliminary design was completed for a steam generator which is applicable to a four loop LMFBR plant of 1000 MWe gross output employing dry and saturated steam conditions. Two steam generators of 364 MWt thermal capacity would be in each loop. The steam generator is a straight, duplex tube design with a shell bellows for thermal expansion and a single tubesheet with an integral leak detection system. The report outlines a proposed series of development tasks to provide additional design data for the duplex tube and to demonstrate the steam generator design with test modules. The design can be adapted readily as either the evaporator or the superheater for a superheated steam cycle with temperatures up to at least 430 0 C (800 0 F), which is below the creep range for the 2 1/4 Cr-1 Mo material

  2. Ocean thermal energy conversion (OTEC). Power system development. Preliminary design report, final

    Energy Technology Data Exchange (ETDEWEB)

    1978-12-04

    The preliminary design of the 10 MWe OTEC power module and the 200 kWe test articles is given in detail. System operation and performance; power system cost estimates; 10 MWe heat exchangers; 200 kWe heat exchanger articles; biofouling control;ammonia leak detection, and leak repair; rotating machinery; support subsystem; instrumentation and control; electrical subsystem; installation approach; net energy and resource analysis; and operability, maintainability, and safety are discussed. The conceptual design of the 40 MWe electrical power system includes four or five 10 MWe modules as designed for the 10 MWe pilot plant. (WHK)

  3. Economic Radioisotope Thermoelectric Generator (RTG) study. Volume I. ERTG design. Final report

    Energy Technology Data Exchange (ETDEWEB)

    1973-12-01

    The objectives of this study were: (1) to develop and evaluate an ERTG design for a high power, Curium-244 fueled system based on the tubular thermoelectric module technology; (2) to prepare a program plan for the development of a flight qualified ERTG; and (3) to estimate the costs associated with the production of one, ten and twenty flight qualified ERTG's. This volume presents the Reference Design ERTG approach, the results of the engineering trade studies leading to its selection, and the Second Generation ERTG Design proposed for development. (WHK)

  4. Detailed design, fabrication and testing of an engineering prototype compensated pulsed alternator. Final report

    International Nuclear Information System (INIS)

    Bird, W.L. Jr.; Woodson, H.H.

    1980-03-01

    The design, fabrication, and test results of a prototype compensated pulsed alternator are discussed. The prototype compulsator is a vertical shaft single phase alternator with a rotating armature and salient pole stator. The machine is designed for low rep rate pulsed duty and is sized to drive a modified 10 cm Beta amplifier. The load consists of sixteen 15 mm x 20 mm x 112 cm long xenon flashlamps connected in parallel. The prototype compulsator generates an open circuit voltage of 6 kV, 180 Hz, at a maximum design speed of 5400 rpm. At maximum speed, the inertial energy stored in the compulsator rotor is 3.4 megajoules

  5. Design of strong wooden box coated with fiberglass reinforced resin for shipping and burial of contaminated glove boxes. Final report

    International Nuclear Information System (INIS)

    1982-01-01

    The project scope of work included the complete decontamination and decommissioning (D and D) of the Westinghouse ARD Fuel Laboratories at the Cheswick Site in the shortest possible time. This has been accomplished in the following four phases: (1) preparation of documents and necessary paperwork; packaging and shipping of all special nuclear materials in an acceptable form to a reprocessing agency; (2) decontamination of all facilities, glove boxes and equipment; loading of generated waste into bins, barrels and strong wooden boxes; (3) shipping of al bins, barrels and boxes containing waste to the designated burial site; removal of all utility services from the laboratories; and (4) final survey of remaining facilities and certification for nonrestricted use; preparation of final report. This attachment contains design of strong wooden box coated with fiberglass reinforced resin for shipping and burial of contaminated glove boxes

  6. HMI-Design of System Solutions in Control Rooms. Description of a Working Process from a Human-Machine Perspective; MMI-design av systemloesningar i kontrollrum. Arbetsprocess foer utformning utifraan ett maenniska-maskinperspektiv

    Energy Technology Data Exchange (ETDEWEB)

    Bligaard, Lars-Ola; Andersson, Jonas; Thunberg, Anna; Osvalder, Anna-Lisa

    2008-01-15

    between operators and machines. The content can be used both for new development projects and for upgrading of already existing control room designs. The main target group for the report is the development engineers at the plant, who work close to the supplier, and the people who should plan and guide the development work in the control room. The purpose of the report is to deliver knowledge about how to consider a human-machine perspective in the development process. The report presents what is important to consider, but does not in detail show design solutions. The report is also a usable tool for those people who should do the actual screen designs, but then it should be used together with hand-book data and guide-lines referred to. The report begins with a description of basic concepts and definitions within the area of HMI. This is followed by a description of the HMI development working process. The working process includes five steps; planning, requirements, conceptual design, detailed design, and commissioning. The steps also include methodology for data collection and evaluation. Finally, the handbook also contains short summaries of the different steps in the working process, where important points to consider are brought forward

  7. Engineering at SLAC: Designing and constructing experimental devices for the Stanford Synchrotron Radiation Lightsource - Final Paper

    Energy Technology Data Exchange (ETDEWEB)

    Djang, Austin [SLAC National Accelerator Lab., Menlo Park, CA (United States)

    2015-08-22

    Thanks to the versatility of the beam lines at SSRL, research there is varied and benefits multiple fields. Each experiment requires a particular set of experiment equipment, which in turns requires its own particular assembly. As such, new engineering challenges arise from each new experiment. My role as an engineering intern has been to help solve these challenges, by designing and assembling experimental devices. My first project was to design a heated sample holder, which will be used to investigate the effect of temperature on a sample's x-ray diffraction pattern. My second project was to help set up an imaging test, which involved designing a cooled grating holder and assembling multiple positioning stages. My third project was designing a 3D-printed pencil holder for the SSRL workstations.

  8. Analysis of design attributes and crashes on the Oregon highway system : final report.

    Science.gov (United States)

    2001-08-01

    This report has investigated the statistical relationship between crash activity and roadway design attributes on the Oregon state : highway system. Crash models were estimated from highway segments distinguished by functional classification (freeway...

  9. Detail design of a 10.4-m stretched-membrane dish. Phase 2, Final report

    Energy Technology Data Exchange (ETDEWEB)

    1994-01-01

    This report describes efforts conducted under Tasks 3 and 4 of the second phase of the project to develop a single-element stretched-membrane dish concept to reduce the cost of a high-performance concentrating solar collector. We completed the detailed design for such a collector suitable to drive a 25-kWe Stirling motor generator. The design includes the collectors, optical element, the drive, and support systems. The aperture of the optical element was sized to provide the required energy to the engine based on test data and analytical models of the concentrator receiver, and engine. The design of the optical element was improved based on experience gained from the design, fabrication, and testing of several prototypes.

  10. Seismic site coefficients and acceleration design response spectra based on conditions in South Carolina : final report.

    Science.gov (United States)

    2014-11-15

    The simplified procedure in design codes for determining earthquake response spectra involves : estimating site coefficients to adjust available rock accelerations to site accelerations. Several : investigators have noted concerns with the site coeff...

  11. Pavement subgrade MR design values for Michigan's seasonal changes : final report.

    Science.gov (United States)

    2009-07-22

    The resilient modulus (MR) of roadbed soil plays an integral role in the design of pavement systems. Currently, the : various regions of the Michigan Department of Transportation (MDOT) use different procedures to determine the : MR values. Most of t...

  12. TIBER II/ETR final design report: Volume 2, 3.0 Engineering

    International Nuclear Information System (INIS)

    Lee, J.D.

    1987-09-01

    This paper discusses the design of the TIBER II Tokamak. This particular volume discusses: mechanical systems; electrical systems; shield nuclear analysis and tritium issues; reactor building facilities; and tritium systems

  13. Metal wastage design guidelines for bubbling fluidized-bed combustors. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Lyczkowski, R.W.; Podolski, W.F.; Bouillard, J.X.; Folga, S.M. [Argonne National Lab., IL (United States)

    1992-11-01

    These metal wastage design guidelines identify relationships between metal wastage and (1) design parameters (such as tube size, tube spacing and pitch, tube bundle and fluidized-bed height to distributor, and heat exchanger tube material properties) and (2) operating parameters (such as fluidizing velocity, particle size, particle hardness, and angularity). The guidelines are of both a quantitative and qualitative nature. Simplified mechanistic models are described, which account for the essential hydrodynamics and metal wastage processes occurring in bubbling fluidized beds. The empirical correlational approach complements the use of these models in the development of these design guidelines. Data used for model and guideline validation are summarized and referenced. Sample calculations and recommended design procedures are included. The influences of dependent variables on metal wastage, such as solids velocity, bubble size, and in-bed pressure fluctuations, are discussed.

  14. SUNSTORE 3. Phase 1. Project design and tender. Final report; SUNSTORE 3. Fase 1. Projektering og udbud. Slutrapport

    Energy Technology Data Exchange (ETDEWEB)

    Soerensen, P.A. (PlanEnergi, Skoerping (Denmark)); Moeller Nielsen, C. (Dronninglund Fjernvarme, Dronninglund (Denmark)); Baunwall, M. (NIRAS Aalborg (Denmark)); Munkholt, H. (GG-Construction, Aalborg (Denmark)); Paaske, B. (Teknologisk Institut, AArhus (Denmark)); Schmidt, T. (SOLITES, Stuttgart (Germany))

    2011-03-15

    The objective of the project has been to carry out detailed design and tendering for a heat production plant consisting of: - 35.000 m{sub 2} solar thermal collectors, - 60.000 m{sub 3} pit heat storage, - 3 MW{sub heat} heat pump, covering app. 50% of the heat production at Dronninglund district heating plant (Denmark). The final report for the project includes detailed design of the pit heat storage (a further development of a 10.000 m{sub 3} storage implemented in Marstal) and simulation of the total production system in the simulation software TRNSYS. (ln)

  15. Digital Smile Design concept delineates the final potential result of crown lengthening and porcelain veneers to correct a gummy smile.

    Science.gov (United States)

    Trushkowsky, Richard; Arias, David Montalvo; David, Steven

    Prior to initiating any treatment, it is necessary to visualize the desired outcomes. It then becomes possible to formulate the steps required to achieve this result. Digital Smile Design (DSD) utilizes patient input and information gathered through diagnostic procedures to create an esthetic treatment scheme. In the case presented here, the NYUCD Esthetic Evaluation Form, intraoral and extraoral photographs, mounted diagnostic casts, physical examination, and radiographs were the diagnostic modalities. The gathered information served as a starting point for a wax-up and intraoral mock-up. This case report demonstrates how the DSD served as a template for crown lengthening procedures and design of the final porcelain veneer restorations.

  16. Design, fabricate, and test a 1.06μ repetitively pulsed laser. Final report

    International Nuclear Information System (INIS)

    Eggleston, J.M.; Crawford, E.A.

    1985-01-01

    The results of a program to develop the Thomson scattering diagnostic laser are described. Background material and technical justification for the design approach are given. Principal results of the developmental program were the construction of a rep rated slab glass amplifier, and the accumulation of the design knowledge necessary to build such amplifiers for maximum performance. Significant advances were made in reducing second order optical distortions

  17. Final safety evaluation report related to the certification of the System 80+ design: Docket Number 52-002. Supplement 1

    International Nuclear Information System (INIS)

    1997-05-01

    This report supplements the final safety evaluation report (FSER) for the System 80+ standard design. The FSER was issued by the US Nuclear Regulatory Commission (NRC) staff as NUREG-1462 in August 1994 to document the NRC staff's review of the System 80+ design. The System 80+ design was submitted by Asea Brown Boveri-Combustion Engineering (ABB-CE), in accordance with the procedures of Subpart B to Part 52 of Title 10 of the Code of Federal Regulations. This supplement documents the NRC staff's review of the changes to the System 80+ design documentation since the issuance of the FSER. ABB-CE made these changes as a result of its review of the System 80+ design details. The NRC staff concludes that the changes to the System 80+ design documentation are acceptable, and that ABB-CE's application for design certification meets the requirements of Subpart B to 10 CFR Part 52 that are applicable and technically relevant to the System 80+ design

  18. Final Report for 'Design calculations for high-space-charge beam-to-RF conversion'

    International Nuclear Information System (INIS)

    Smithe, David N.

    2008-01-01

    Accelerator facility upgrades, new accelerator applications, and future design efforts are leading to novel klystron and IOT device concepts, including multiple beam, high-order mode operation, and new geometry configurations of old concepts. At the same time, a new simulation capability, based upon finite-difference 'cut-cell' boundaries, has emerged and is transforming the existing modeling and design capability with unparalleled realism, greater flexibility, and improved accuracy. This same new technology can also be brought to bear on a difficult-to-study aspect of the energy recovery linac (ERL), namely the accurate modeling of the exit beam, and design of the beam dump for optimum energy efficiency. We have developed new capability for design calculations and modeling of a broad class of devices which convert bunched beam kinetic energy to RF energy, including RF sources, as for example, klystrons, gyro-klystrons, IOT's, TWT's, and other devices in which space-charge effects are important. Recent advances in geometry representation now permits very accurate representation of the curved metallic surfaces common to RF sources, resulting in unprecedented simulation accuracy. In the Phase I work, we evaluated and demonstrated the capabilities of the new geometry representation technology as applied to modeling and design of output cavity components of klystron, IOT's, and energy recovery srf cavities. We identified and prioritized which aspects of the design study process to pursue and improve in Phase II. The development and use of the new accurate geometry modeling technology on RF sources for DOE accelerators will help spark a new generational modeling and design capability, free from many of the constraints and inaccuracy associated with the previous generation of 'stair-step' geometry modeling tools. This new capability is ultimately expected to impact all fields with high power RF sources, including DOE fusion research, communications, radar and other

  19. Conceptual design of a KrF scaling module. Final report

    International Nuclear Information System (INIS)

    1980-10-01

    A conceptual design of an angular multiplexed 50 kJ KrF laser module for Inertial Confinement Fusion is presented. Optical designs for encoding, beam packing and beam transfer between amplifier stages are developed; emphasis is placed on reducing prepulse problems and achieving acceptable optical quality. An axisymmetric optical design is identified as optimum in terms of simplicity, optical quality, cost and alignment. A kinetic code model was developed for the KrF amplifier and was used to derive scaling maps for the 50 kJ module. Attention was given to reducing parasitics, achieving acceptable extraction efficiency and accounting for amplified spontaneous emission effects. The size of the module is constrained by parasitic suppression and damage thresholds; the power gain is constrained by demanding 40% extraction efficiency in a double pass extraction geometry; and, the run time is constrained by the pulsed power technology (PFN or PFL) and acceptable values of g 0 L. The bounds imposed on the design by the pulsed power technology were examined. Both PFLs and PFNs were considered along with their associated diode, hibachi and guide field requirements. A base line design for a 50 kJ module including amplifier staging, layout and overall size is discussed. Cost analysis and scaling for optical components, pulsed power technology and the guide field are also presented

  20. Ocean Thermal Energy Conversion power system development. Phase I: preliminary design. Final report

    Energy Technology Data Exchange (ETDEWEB)

    1978-12-04

    Westinghouse has completed the Preliminary Desigh Phase for the Power System Development of the Ocean Thermal Energy Conversion (OTEC) Demonstration Plant project. This study included the development of a preliminary design for a Modular Application scaled power system (10MWe) and Heat Exchanger Test Articles, both based on the concept developed in the Conceptual Design Phase. The results of this study were used to improve the baseline design of the 50MWe module for the Commercial Size Power System, which was recommended for the demonstration plant by the conceptual design study. The 50MWe module was selected since it has the lowest cost, and since its size convincingly demonstrates that future economically viable commercial plants, having reliable operation with credible anticipated costs, are possible. Additional optimization studies on the size of the power system plus hull continue to identify 50MWe as the preferred minimum cost configuration. This study was limited to a closed cycle ammonia power system module, using a seawater temperature difference of 40/sup 0/F, and a surface platform/ship reference hull. This volume presents the preliminary design configuration and system optimization. (WHK)

  1. Ocean Thermal Energy Conversion power system development. Phase I: preliminary design. Final report

    Energy Technology Data Exchange (ETDEWEB)

    1978-12-04

    Westinghouse has completed the Preliminary Design Phase for the Power System Development of the Ocean Thermal Energy Conversion (OTEC) Demonstration Plant project. This study included the development of a preliminary design for a Modular Application scaled power system (10MWe) and Heat Exchanger Test Articles, both based on the concept developed in the Conceptual Design Phase. The results of this study were used to improve the baseline design of the 50MWe module for the Commercial Size Power System, which was recommended for the demonstration plant by the conceptual design study. The 50MWe module was selected since it has the lowest cost, and since its size convincingly demonstrates that future economically viable commercial plants, having reliable operation with credible anticipated costs, are possible. Additional optimization studies on the size of the power system plus hull continue to identify 50MWe as the preferred minimum cost configuration. This study was limited to a closed cycle ammonia power system module, using a seawater temperature difference of 40/sup 0/F, and a surface platform/ship reference hull. This volume describes system operation, a complete test program to verify mechanical reliability and thermal performance, fabrication and installation operations, and a cost analysis. (WHK)

  2. Radiological engineering services for the design of special contamination containments. Final report

    International Nuclear Information System (INIS)

    1996-01-01

    The purpose of this study was to provide radiological engineering services for the design of special contamination containments. These containments were to be used during the replacement of leaking and damaged gaskets on the glove boxes in Technical Area-55 (TA-55). The damaged gaskets involved 18 windows and 5 interconnecting spool pieces in fuel processing glove boxes. The work scope included the design and manufacture of special contamination containment enclosures (containments), the preparation of procedures and tool lists to support gasket replacement while using the containments, and the training of appropriate TA-55 personnel in the proper installation, operation and removal of the containments. It was originally anticipated that two basic containment designs would be required, one for the windows and one for spool pieces. Upon examination of the glove boxes it was evident that the individual space envelopes and interferences associated with each glove box would require uniquely designed containments for effective gasket replacement. This resulted in 13 individual containment designs that accommodated the interferences and allowed gasket replacement within the containment. Successful use of the containments for glove box gasket replacement was a significant accomplishment. The operation has proven that a properly managed containment program can enhance routine maintenance of the glove boxes while preventing a contamination release. The ability to perform these operations in containments reduces costs by preventing a contaminant release and eliminating the associated cleanup expenses, reduced radioactive waste and fuel processing down time

  3. Design and development of a continuously variable ratio transmission for automotive vehicles. Final report

    Energy Technology Data Exchange (ETDEWEB)

    None

    1978-09-30

    Work accomplished between July 1974 and October 1978 in a program directed toward the design and development of a continuously variable ratio transmission (CVT) for an automotive vehicle is reported. The following major accomplishments were achieved: the laboratory and mathematical projections establishing the viability of the program and the predicted attainment of the primary goal of fuel economy were verified; the proposed Concept Demonstration prototype hydromechanical transmission (HMT) was completed from design to operation; the HMT was thoroughly tested in the laboratory and on the road and its in-vehicle performance was verified by independent testing laboratories; and design of a second generation Pre-Production HMT has proceeded to the point of confirming the practicality of the automotive HMT size and weight; most of the necessary information has been generated which could permit its production cost/competitiveness to be evaluated. (LCL)

  4. Ocean thermal energy conversion power system development. Final design report: PSD-I, Phase II

    Energy Technology Data Exchange (ETDEWEB)

    None

    1980-06-30

    The PSD-I program provides a heat exchanger sytem consisting of an evaporator, condenser and various ancillaries with ammonia used as a working fluid in a closed simulated Rankine cycle. It is to be installed on the Chepachet Research Vessel for test and evaluation of a number of OTEC concepts in a true ocean environment. It is one of several test articles to be tested. Primary design concerns include control of biofouling, corrosion and erosion of aluminum tubes, selection of materials, and the development of a basis for scale-up to large heat exchangers so as to ultimately demonstrate economic feasibility on a commercial scale. The PSD-I test article is devised to verify thermodynamic, environmental, and mechanical performance of basic design concepts. The detailed design, development, fabrication, checklist, delivery, installation support, and operation support for the Test Article Heat Exchangers are described. (WHK)

  5. Tornado missile simulation and design methodology. Volume 1: simulation methodology, design applications, and TORMIS computer code. Final report

    International Nuclear Information System (INIS)

    Twisdale, L.A.; Dunn, W.L.

    1981-08-01

    A probabilistic methodology has been developed to predict the probabilities of tornado-propelled missiles impacting and damaging nuclear power plant structures. Mathematical models of each event in the tornado missile hazard have been developed and sequenced to form an integrated, time-history simulation methodology. The models are data based where feasible. The data include documented records of tornado occurrence, field observations of missile transport, results of wind tunnel experiments, and missile impact tests. Probabilistic Monte Carlo techniques are used to estimate the risk probabilities. The methodology has been encoded in the TORMIS computer code to facilitate numerical analysis and plant-specific tornado missile probability assessments. Sensitivity analyses have been performed on both the individual models and the integrated methodology, and risk has been assessed for a hypothetical nuclear power plant design case study

  6. Severe accident approach - final report. Evaluation of design measures for severe accident prevention and consequence mitigation.

    Energy Technology Data Exchange (ETDEWEB)

    Tentner, A. M.; Parma, E.; Wei, T.; Wigeland, R.; Nuclear Engineering Division; SNL; INL

    2010-03-01

    An important goal of the US DOE reactor development program is to conceptualize advanced safety design features for a demonstration Sodium Fast Reactor (SFR). The treatment of severe accidents is one of the key safety issues in the design approach for advanced SFR systems. It is necessary to develop an in-depth understanding of the risk of severe accidents for the SFR so that appropriate risk management measures can be implemented early in the design process. This report presents the results of a review of the SFR features and phenomena that directly influence the sequence of events during a postulated severe accident. The report identifies the safety features used or proposed for various SFR designs in the US and worldwide for the prevention and/or mitigation of Core Disruptive Accidents (CDA). The report provides an overview of the current SFR safety approaches and the role of severe accidents. Mutual understanding of these design features and safety approaches is necessary for future collaborations between the US and its international partners as part of the GEN IV program. The report also reviews the basis for an integrated safety approach to severe accidents for the SFR that reflects the safety design knowledge gained in the US during the Advanced Liquid Metal Reactor (ALMR) and Integral Fast Reactor (IFR) programs. This approach relies on inherent reactor and plant safety performance characteristics to provide additional safety margins. The goal of this approach is to prevent development of severe accident conditions, even in the event of initiators with safety system failures previously recognized to lead directly to reactor damage.

  7. Free-piston Stirling engine conceptual design and technologies for space power, Phase 1. Final Report

    International Nuclear Information System (INIS)

    Penswick, L.B.; Beale, W.T.; Wood, J.G.

    1990-01-01

    As part of the SP-100 program, a phase 1 effort to design a free-piston Stirling engine (FPSE) for a space dynamic power conversion system was completed. SP-100 is a combined DOD/DOE/NASA program to develop nuclear power for space. This work was completed in the initial phases of the SP-100 program prior to the power conversion concept selection for the Ground Engineering System (GES). Stirling engine technology development as a growth option for SP-100 is continuing after this phase 1 effort. Following a review of various engine concepts, a single-cylinder engine with a linear alternator was selected for the remainder of the study. The relationships of specific mass and efficiency versus temperature ratio were determined for a power output of 25 kWe. This parametric study was done for a temperature ratio range of 1.5 to 2.0 and for hot-end temperatures of 875 K and 1075 K. A conceptual design of a 1080 K FPSE with a linear alternator producing 25 kWe output was completed. This was a single-cylinder engine designed for a 62,000 hour life and a temperature ratio of 2.0. The heat transport systems were pumped liquid-metal loops on both the hot and cold ends. These specifications were selected to match the SP-100 power system designs that were being evaluated at that time. The hot end of the engine used both refractory and superalloy materials; the hot-end pressure vessel featured an insulated design that allowed use of the superalloy material. The design was supported by the hardware demonstration of two of the component concepts - the hydrodynamic gas bearing for the displacer and the dynamic balance system. The hydrodynamic gas bearing was demonstrated on a test rig. The dynamic balance system was tested on the 1 kW RE-1000 engine at NASA Lewis

  8. LF460 detail design final technical report on aircraft support activity

    Science.gov (United States)

    1973-01-01

    Various studies and analyses that were performed in support of the V/STOL research transport design effort are discussed. The propulsion system specified for these studies was the LF460/YJ97-GE-100 turbotip lift fan. Strong emphasis was placed on achieving low fan noise while maintaining the high thrust/weight capability of the high pressure ratio lift fan system. The work was divided into cycle analysis and performance studies, installation and systems support, acoustic analysis and preliminary or conceptual design studies.

  9. SP-100 planetary mission/system preliminary design study. Final report, technical information report

    Energy Technology Data Exchange (ETDEWEB)

    Jones, R.M. [ed.

    1986-02-01

    This report contains a discussion on many aspects of a nuclear electric propulsion planetary science mission and spacecraft using the proposed SP-100 nuclear power subsystem. A review of the science rationale for such missions is included. A summary of eleven nuclear electric propulsion planetary missions is presented. A conceptual science payload, mission design, and spacecraft design is included for the Saturn Ring Rendezvous mission. Spacecraft and mission costs have been estimated for two potential sequences of nuclear electric propulsion planetary missions. The integration issues and requirements on the proposed SP-100 power subsystems are identified.

  10. Design, engineering and evaluation of refractory liners for slagging gasifiers. Final report

    Energy Technology Data Exchange (ETDEWEB)

    deTineo, B J; Booth, G; Firestone, R F; Greaves, M J; Hales, C; Lamoureux, J P; Ledford, R R

    1982-08-01

    The contract for this program was awarded at the end of September 1978. Work was started on 1 October 1978, on Tasks A, B, and E. Task A, Conceptual Liner Designs, and Task B, Test System Design and Construction, were completed. Task C, Liner Tests, and Task D, Liner Design Evaluation, were to begin upon completion of Task B. Task E, Liner Model Development, is inactive after an initial data compilation and theoretical model development effort. It was to be activated as soon as data were available from Task D. Task F, Liner Design Handbook, was active along with Task A since the reports of both tasks were to use the same format. At this time, Tasks C, D, and F are not to be completed since funding of this project was phased out by DOE directive. The refractory text facility, which was constructed, was tested and found to perform satisfactorily. It is described in detail, including a hazard analysis which was performed. (LTN)

  11. Wildfire ignition resistant home design(WIRHD) program: Full-scale testing and demonstration final report.

    Energy Technology Data Exchange (ETDEWEB)

    Quarles, Stephen, L.; Sindelar, Melissa

    2011-12-13

    The primary goal of the Wildfire ignition resistant home design(WIRHD) program was to develop a home evaluation tool that could assess the ignition potential of a structure subjected to wildfire exposures. This report describes the tests that were conducted, summarizes the results, and discusses the implications of these results with regard to the vulnerabilities to homes and buildings.

  12. TIBER II/ETR final design report: Volume 1, 1. 0 Introduction; 2. 0 plasma engineering

    Energy Technology Data Exchange (ETDEWEB)

    Lee, J.D. (ed.)

    1987-09-01

    This paper discusses the design of the TIBER II tokamak test reactor. Specific topics discussed are the physics objectives for Tiber, magnetics, baseline operating point, pulsed inductive operation, edge physics and impurity control, fueling, disruption control, vertical stability and impurity flow reversal. (LSP)

  13. Evaluation of j-turn intersection design performance in Missouri, final report.

    Science.gov (United States)

    2013-12-01

    Research shows that a high percentage of crashes that take place on high-speed rural expressways occur at intersections : with minor roads. One low-cost alternative design for improving the safety of at-grade intersections on such expressways is : th...

  14. Review of the Office of Radiation Programs' national radon survey design. Final report

    International Nuclear Information System (INIS)

    1988-01-01

    The EPA Radiation Advisory Committee found that the document presented a valid approach to designing a national radon survey. In addition, the Committee felt that the study is important from a national health point of view and that all efforts must be made to insure that a survey of high quality is conducted. Major conclusions and recommendations are summarized in the report

  15. Hollow ceramic block: containment of water for thermal storage in passive solar design. Final technical report

    Energy Technology Data Exchange (ETDEWEB)

    Winship, C.T.

    1983-12-27

    The project activity has been the development of designs, material compositions and production procedures to manufacture hollow ceramic blocks which contain water (or other heat absorptive liquids). The blocks are designed to serve, in plurality, a dual purpose: as an unobtrusive and efficient thermal storage element, and as a durable and aesthetically appealing surface for floors and walls of passive solar building interiors. Throughout the grant period, numerous ceramic formulas have been tested for their workabilty, thermal properties, maturing temperatures and color. Blocks have been designed to have structural integrity, and textured surfaces. Methods of slip-casting and extrusion have been developed for manufacturing of the blocks. The thermal storage capacity of the water-loaded block has been demonstrated to be 2.25 times greater than that of brick and 2.03 times greater than that of concrete (taking an average of commonly used materials). Although this represents a technical advance in thermal storage, the decorative effects provided by application of the blocks lend them a more significant advantage by reducing constraints on interior design in passive solar architecture.

  16. Passive solar design strategies: Remodeling guidelines for conserving energy at home. [Final report

    Energy Technology Data Exchange (ETDEWEB)

    1991-12-31

    The idea of passive solar is simple, but applying it effectively does require information and attention to the details of design and construction. Some passive solar techniques are modest and low-cost, and require only small changes in remodeler`s typical practice. At the other end of the spectrum, some passive solar systems can almost eliminate a house`s need for purchased heating (and in some cases, cooling) energy -- but probably at a relatively high first cost. In between are a broad range of energy-conserving passive solar techniques. Whether or not they are cost-effective, practical and attractive enough to offer a market advantage to any individual remodeler depends on very specific factors such as local costs, climate, and market characteristics. Passive solar design strategies: Remodeling Guidelines For Conserving Energy At Homes is written to help give remodelers the information they need to make these decisions. Passive Solar Design Strategies is a package in three basic parts: The Guidelines contain information about passive solar techniques and how they work, and provides specific examples of systems which will save various percentages of energy; The Worksheets offer a simple, fill-in-the-blank method to pre-evaluate the performance of a specific design; The Worked Example demonstrates how to complete the worksheets for a typical residence.

  17. 78 FR 34918 - Direct Final Approval of Sewage Sludge Incinerators State Plan for Designated Facilities and...

    Science.gov (United States)

    2013-06-11

    ... Approval of Sewage Sludge Incinerators State Plan for Designated Facilities and Pollutants; Indiana AGENCY... to control air pollutants from ``Sewage Sludge Incinerators'' (SSI). The Indiana Department of... unit,'' in part, as any device that combusts sewage sludge for the purpose of reducing the volume of...

  18. Computer Assisted Instructional Design for Computer-Based Instruction. Final Report. Working Papers.

    Science.gov (United States)

    Russell, Daniel M.; Pirolli, Peter

    Recent advances in artificial intelligence and the cognitive sciences have made it possible to develop successful intelligent computer-aided instructional systems for technical and scientific training. In addition, computer-aided design (CAD) environments that support the rapid development of such computer-based instruction have also been recently…

  19. SEAFP cooling system design. Task M8 - water coolant option (final report)

    International Nuclear Information System (INIS)

    Stubley, P.; Natalizio, A.

    1994-01-01

    This report contains the ex-vessel portions of the outline designs for first wall, blanket and divertor cooling using water as the heat transport fluid. Equipment layout, key components and main system parameters are also described. (author). 7 tabs., 14 figs

  20. Ocean Thermal Energy Conversion (OTEC) platform configuration and integration. Volume II. Conceptual design. Final report

    Energy Technology Data Exchange (ETDEWEB)

    None

    1978-06-01

    The purpose of this project is to evaluate six candidate hullforms as candidates for the OTEC commercial plant. This volume is a summary of the conceptual design including facility requirements, cost, schedule, and site sensitivity. Two OTEC commercial plant configurations are considered in this study: the ship and the semi-submersible. Engineering drawings are presented. (WHR)

  1. Fellowship Program in the Design and Development of Instructional Materials. Final Report.

    Science.gov (United States)

    Fleming, Malcolm; Pett, Dennis

    A two-year graduate program leading to a specialists's degree was administered to train individuals in the design of instructional materials for elementary, secondary, vocational and special education curricula. The program sought to achieve a multiplier effect by placing its graduates in positions in which they could help other educators to…

  2. Paducah-Louisville Consortium; Project VIII: Focus on Dropouts... a New Design. Final Evaluation Report.

    Science.gov (United States)

    Paducah Public Schools, KY.

    Project VIII is an innovative behavioral science oriented educational program, funded under Title VIII Elementary Secondary Education Act, designed to attack the personal, social, and educational problems of children whose previous record of school failure and frustration has indicated high dropout potential. The program is operated as a…

  3. Design of Training Systems, Phase II-A Report. An Educational Technology Assessment Model. Final Report.

    Science.gov (United States)

    Miller, Robert B.; Duffy, Larry R.

    Study results and design for an Educational Technology Assessment Model (ETAM) are outlined, and conclusions and recommendations of the study are summarized. An eight-task procedure is provided to guide the assessor of a training innovation through the required data collection and analysis steps leading to a decision to accept, reject, or continue…

  4. Stilling basin design and operation for water quality : field testing, final report.

    Science.gov (United States)

    2008-06-15

    Many construction projects involve the need to pump turbid water from borrow pits or other excavations into stilling : basins or sediment bags prior to discharge. The design and operation of these basins needs to be optimized to : provide the best wa...

  5. Use of Solid Hydride Fuel for Improved long-Life LWR Core Designs. Final summary report

    International Nuclear Information System (INIS)

    Greenspan, E

    2006-01-01

    The primary objective of this project was to assess the feasibility of improving the performance of PWR and BWR cores by using solid hydride fuels instead of the commonly used oxide fuel. The primary measure of performance considered is the bus-bar cost of electricity (COE). Additional performance measures considered are safety, fuel bundle design simplicity in particular for BWR's, and plutonium incineration capability. It was found that hydride fuel can safely operate in PWR's and BWR's without restricting the linear heat generation rate of these reactors relative to that attainable with oxide fuel. A couple of promising applications of hydride fuel in PWR's and BWR's were identified: (1) Eliminating dedicated water moderator volumes in BWR cores thus enabling to significantly increase the cooled fuel rods surface area as well as the coolant flow cross section area in a given volume fuel bundle while significantly reducing the heterogeneity of BWR fuel bundles thus achieving flatter pin-by-pin power distribution. The net result is a possibility to significantly increase the core power density ? on the order of 30% and, possibly, more, while greatly simplifying the fuel bundle design. Implementation of the above modifications is, though, not straightforward; it requires a design of completely different control system that could probably be implemented only in newly designed plants. It also requires increasing the coolant pressure drop across the core. (2) Recycling plutonium in PWR's more effectively than is possible with oxide fuel by virtue of a couple of unique features of hydride fuel reduced inventory of U-238 and increased inventory of hydrogen. As a result, the hydride fueled core achieves nearly double the average discharge burnup and the fraction of the loaded Pu it incinerates in one pass is double that of the MOX fuel. The fissile fraction of the Pu in the discharged hydride fuel is only ∼2/3 that of the MOX fuel and the discharged hydride fuel is

  6. A product designed for final disposal of low and intermediate level radioactive wastes

    International Nuclear Information System (INIS)

    Baboescu, E.; Popescu, I. V.

    2001-01-01

    The product 'metallic barrel - concrete - low level radioactive wastes - 1' (ABBD - 1) was certified according to the company's standard SF ICN/1994, updated 1. The product ABBD -1 is produced according to the following certified technologies: - technology for processing and conditioning of low level radioactive solid wastes; - technology for processing and conditioning of waste ion exchangers from the TRIGA reactor; - technology for conditioning the β - γ radioactive compacts. The product is constituted of a protection shield, the concrete block - radioactive waste, securing high mechanical strength and a high degree of radionuclides retaining, thus ensuring the necessary condition for long time disposal and, finally, the metallic container fulfilling the National Standards of Nuclear Safety for Radioactive Materials Transportation. The metallic container is made of pickled slab, with a 220 l capacity, according to STAS 7683/88 standards. The main characteristics of the product 'ABBD - 1' are: - size: height, 915 ± 10 mm, diameter, 600 ± 5 mm; - mass, 300 - 600 kg; - maximum permissible activity, 6 x 10 9 Bq/ barrel (0.164 Ci/barrel); - equivalent dose rate for gamma radiation at barrel's wall, max. 1 mSv/h (200 mrem/h); - unfixed external contamination, 2 ; - compression strength of concrete block alone, > 5 x 10 6 N/m 2 ; - lixiviation rate, -3 cm/day; - the compact concrete block-radioactive waste is leak-proof and crack-free. The final product is transferred from INR Pitesti to National Repository for Radioactive Waste by railway and road transportation according to the provisions of the National Commission for Nuclear Activity Control as stipulated in the National Standards of Nuclear Safety of Radioactive Materials Transportation

  7. Quadrupole-free detector optics design for the Compact Linear Collider final focus system at 3 TeV

    Directory of Open Access Journals (Sweden)

    Fabien Plassard

    2018-01-01

    Full Text Available Aiming to simplify the machine detector interface of the Compact Linear Collider (CLIC, a new detector model has been designed allowing the last quadrupole QD0 of the final focus system (FFS to be located outside of the experiment with a distance L^{*} from the interaction point of 6 m. In this paper, the beam delivery system (BDS has been reoptimized, offering a luminosity performance that exceeds the design requirements by 11% for the total luminosity and by 7% in the energy peak. A simulation campaign has been carried out and has proved the feasibility of recovering the luminosity under realistic transverse misalignments of the FFS optics, by means of different orbit and aberration correction techniques, making this long L^{*} design a realistic candidate for the future CLIC BDS.

  8. Quadrupole-free detector optics design for the Compact Linear Collider final focus system at 3 TeV

    Science.gov (United States)

    Plassard, Fabien; Latina, Andrea; Marin, Eduardo; Tomás, Rogelio; Bambade, Philip

    2018-01-01

    Aiming to simplify the machine detector interface of the Compact Linear Collider (CLIC), a new detector model has been designed allowing the last quadrupole QD0 of the final focus system (FFS) to be located outside of the experiment with a distance L* from the interaction point of 6 m. In this paper, the beam delivery system (BDS) has been reoptimized, offering a luminosity performance that exceeds the design requirements by 11% for the total luminosity and by 7% in the energy peak. A simulation campaign has been carried out and has proved the feasibility of recovering the luminosity under realistic transverse misalignments of the FFS optics, by means of different orbit and aberration correction techniques, making this long L* design a realistic candidate for the future CLIC BDS.

  9. Application of characteristic time concepts for hydraulic fracture configuration design, control, and optimization. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Advani, S.H.; Lee, T.S. [Lehigh Univ., Bethlehem, PA (United States); Moon, H. [Ohio State Univ., Columbus, OH (United States)

    1992-10-01

    The analysis of pertinent energy components or affiliated characteristic times for hydraulic stimulation processes serves as an effective tool for fracture configuration designs optimization, and control. This evaluation, in conjunction with parametric sensitivity studies, provides a rational base for quantifying dominant process mechanisms and the roles of specified reservoir properties relative to controllable hydraulic fracture variables for a wide spectrum of treatment scenarios. Results are detailed for the following multi-task effort: (a) Application of characteristic time concept and parametric sensitivity studies for specialized fracture geometries (rectangular, penny-shaped, elliptical) and three-layered elliptic crack models (in situ stress, elastic moduli, and fracture toughness contrasts). (b) Incorporation of leak-off effects for models investigated in (a). (c) Simulation of generalized hydraulic fracture models and investigation of the role of controllable vaxiables and uncontrollable system properties. (d) Development of guidelines for hydraulic fracture design and optimization.

  10. HTGR process heat program design and analysis. Final report, FY-79

    International Nuclear Information System (INIS)

    1979-12-01

    This report summarizes the results of concept design studies at General Atomic Company during FY-79 for an 842-MW(t) Very High Temperature Reactor (VHTR) utilizing an intermediate helium heat transfer loop to provide thermal energy for the production of hydrogen or reducing gas (H 2 + CO) by steam-reforming of a light hydrocarbon. Basic carbon sources may be coal, residual oil, or oil shale. The report summarizes conceptual design tasks conducted on the prestressed concrete reactor vessel, thermal barrier, intermediate heat exchanger, reformer, and steam generator. The substantial completion of first generation programming for a performance/optimization code and the preparation of a topical safety report and other safety evaluation studies are reported. The completion of balance of plant criteria specifications and a balance of plant cost estimate is also reported

  11. AIFTDS-8000 - A next generation PCM system: Concept through final design

    Science.gov (United States)

    Trover, William F.

    The development of a new modular PCM system composed of nineteen different types of functional modules is reported. The system is based on the loaf-of-bread packaging concept eliminating the classical fixed size box. The successful design of this packaging concept has been made possible by the building and testing of proof-of-concept models. Thermally driven PC payouts using multilayer PC boards with copper planes for power distribution and heat transfer are essential in achieving the high-end operating temperature of 85 C with a significant margin of safety. The modularity of the design permits low-cost periodic upgrades of key system elements by slice replacement without obsolescence of the majority of the hardware.

  12. Finalizing the Dtag: implementation and testing of design improvements for reliability and availability

    Science.gov (United States)

    2016-10-14

    the sensors were more centrally located and the external polyethylene shell that formed the tag housing provided an additional layer of protection...robustness of the connector the current design now uses a pin header directly connected to the main electronics board. The header is first waterproofed with...illustrates the low viscosity epoxy and urethane used to provide pressure compensation and waterproofing . Dimensions in (mm). 1--- -------- 207

  13. Integrated coal preparation and CWF processing plant: Conceptual design and costing. Final technical report

    Energy Technology Data Exchange (ETDEWEB)

    McHale, E.T.; Paul, A.D.; Bartis, J.T. [Science Applications International Corp., McLean, VA (United States); Korkmaz, M. [Roberts and Schaefer Co., Salt Lake City, UT (United States)

    1992-12-01

    At the request of the US Department of Energy (DOE), Pittsburgh Energy Technology Center, a study was conducted to provide DOE with a reliable, documented estimate of the cost of producing coal-water fuel (CWF). The approach to the project was to specify a plant capacity and location, identify and analyze a suitable coal, and develop a conceptual design for an integrated coal preparation and CWF processing plant. Using this information, a definitive costing study was then conducted, on the basis of which an economic and sensitivity analysis was performed utilizing a financial evaluation model to determine a price for CWF in 1992. The design output of the integrated plant is 200 tons of coal (dry basis) per hour. Operating at a capacity factor of 83 percent, the baseline design yields approximately 1.5 million tons per year of coal on a dry basis. This is approximately equivalent to the fuel required to continuously generate 500 MW of electric power. The CWF produced by the plant is intended as a replacement for heavy oil or gas in electric utility and large industrial boilers. The particle size distribution, particularly the top size, and the ash content of the coal in the CWF are specified at significantly lower levels than is commonly found in typical pulverized coal grinds. The particle top size is 125 microns (vs typically 300m{mu} for pulverized coal) and the coal ash content is 3.8 percent. The lower top size is intended to promote complete carbon burnout at less derating in boilers that are not designed for coal firing. The reduced mineral matter content will produce ash of very fine particle size during combustion, which leads to less impaction and reduced fouling of tubes in convective passages.

  14. Design of a borehole data-acquisition/transmission system. Final report, Volume I

    International Nuclear Information System (INIS)

    Hancock, R.L.; Bowden, J.C.

    1981-06-01

    Objective of the BDATS program was to design, construct, and demonstrate a borehole probe and associated uphole modules that would allow downhole collection of data from any of several borehole probes and would allow digital transmission of that data uphole to a computer. Specifically, the system was electrically and mechanically configured to interface to six separate borehole probes and a computer in a R and D logging vehicle. However, the system can be used with other types of probes

  15. Supercritical water oxidation of colored smoke, dye, and pyrotechnic compositions. Final report: Pilot plant conceptual design

    Energy Technology Data Exchange (ETDEWEB)

    LaJeunesse, C.A.; Chan, Jennifer P.; Raber, T.N.; Macmillan, D.C.; Rice, S.F.; Tschritter, K.L.

    1993-11-01

    The existing demilitarization stockpile contains large quantities of colored smoke, spotting dye, and pyrotechnic munitions. For many years, these munitions have been stored in magazines at locations within the continental United States awaiting completion of the life-cycle. The open air burning of these munitions has been shown to produce toxic gases that are detrimental to human health and harmful to the environment. Prior efforts to incinerate these compositions have also produced toxic emissions and have been unsuccessful. Supercritical water oxidation (SCWO) is a rapidly developing hazardous waste treatment method that can be an alternative to incineration for many types of wastes. The primary advantage SCWO affords for the treatment of this selected set of obsolete munitions is that toxic gas and particulate emissions will not occur as part of the effluent stream. Sandia is currently designing a SCWO reactor for the US Army Armament Research, Development & Engineering Center (ARDEC) to destroy colored smoke, spotting dye, and pyrotechnic munitions. This report summarizes the design status of the ARDEC reactor. Process and equipment operation parameters, process flow equations or mass balances, and utility requirements for six wastes of interest are developed in this report. Two conceptual designs are also developed with all process and instrumentation detailed.

  16. Ocean thermal energy conversion cold water pipe preliminary design project. Appendices to final report

    Energy Technology Data Exchange (ETDEWEB)

    1979-11-20

    NOAA/DOE has selected three concepts for a baseline design of the cold water pipe (CWP) for OTEC plants: (1) a FRP CWP of sandwich wall construction suspended from the Applied Physical Laboratory/John Hopkins University (APL/JHU) barge at a site 200 miles east of the coast of Brazil using a horizontal deployment scheme; (2) an elastomer CWP suspended from the APL/JHU barge off the southeast coast of Puerto Rico using either a horizontal or vertical deployment scheme; and (3) a polyethylene CWP (single or multiple pipe) suspended from the Gibbs and Cox spar at the Puerto Rico site using a horizontal deployment scheme. TRW has developed a baseline design for each of these configurations. This volume of the report includes the following appendices: (A) fiberglass reinforced plastic cold water pipe (specification and drawingss); (B) specification for polyethylene CWP; (C) elastomer pipe drawings; (D) drawings for OTEC 10/40 hull/CWP transitions; (E) structural design of OTEC 10/40 CWP support and CWP transitions; (F) universal transition joint for CWP; (G) dynamic spherical seal of CWP; (H) at-sea deployment loads - surface towing loads; (I) OTEC 10/40 CWP deployment up-ending loads; (J) cost estimates for OTEC 10/40 hull/CWP transitions; and (K) OTEC 10/40 CWP deployment scenario and cost estimate. (WHK)

  17. Design of passive piezoelectric damping for space structures. Final Report Ph.D. Thesis

    Science.gov (United States)

    Hagood, Nesbitt W., IV; Aldrich, Jack B.; Vonflotow, Andreas H.

    1994-01-01

    Passive damping of structural dynamics using piezoceramic electromechanical energy conversion and passive electrical networks is a relatively recent concept with little implementation experience base. This report describes an implementation case study, starting from conceptual design and technique selection, through detailed component design and testing to simulation on the structure to be damped. About 0.5kg. of piezoelectric material was employed to damp the ASTREX testbed, a 500kg structure. Emphasis was placed upon designing the damping to enable high bandwidth robust feedback control. Resistive piezoelectric shunting provided the necessary broadband damping. The piezoelectric element was incorporated into a mechanically-tuned vibration absorber in order to concentrate damping into the 30 to 40 Hz frequency modes at the rolloff region of the proposed compensator. A prototype of a steel flex-tensional motion amplification device was built and tested. The effective stiffness and damping of the flex-tensional device was experimentally verified. When six of these effective springs are placed in an orthogonal configuration, strain energy is absorbed from all six degrees of freedom of a 90kg. mass. A NASTRAN finite element model of the testbed was modified to include the six-spring damping system. An analytical model was developed for the spring in order to see how the flex-tensional device and piezoelectric dimensions effect the critical stress and strain energy distribution throughout the component. Simulation of the testbed demonstrated the damping levels achievable in the completed system.

  18. Cell and stack design alternatives. Final report, August 1, 1978-December 31, 1979

    Energy Technology Data Exchange (ETDEWEB)

    Hoover, Jr., D. Q.; King, Robert B.

    1980-02-01

    The work described comprised the first phase of a planned six phase program to develop commercially viable phosphoric acid fuel cell (PAFC) driven on-site integrated energy systems (OS/IES). The Phase I effort was organized as three major technical tasks; (1) study of system design alternatives; (2) fuel cell design alternatives; and (3) methane conditioner study. It was decided that comprehensive modeling of one application would most effectively utilize the resources available for the study of systems design alternatives. A 48 unit apartment complex located in Albany, New York and built to HUD minimum standards was selected as being typical of the applications that will be served by the systems. The time varying space conditioning (HVAC) and electrical requirements including the effects of varying weather conditions, living habits and occupancy patterns were modeled. These requirements formed the basis for comparing the performance and cost of the alternative configurations with each other and with a conventional system. Five basic alternative OS/IES configurations plus four variations were selected from a preliminary list of 13 basic configurations for detailed performance nd cost evaluations. Study procedures and results are presented in detail. (WHK)

  19. Conceptual design and the simulation of final cooling section for a muon collider

    International Nuclear Information System (INIS)

    Skrinsky, A.N.; Zolkin, T.V.

    2009-01-01

    The scheme of final cooling for muon beams, based on using current-carrying liquid-lithium rods, is discussed. The dynamics of particles in the course of cooling taking into account the non-paraxial motion has been studied with the help of computer simulation. It is suggested to minimize the effective increase of the longitudinal emittance caused by fluctuations of ionization losses and large angular spread, by the rotation of the longitudinal phase-space portrait for arranging self-action. We have considered the non-dissipative multiple successive full emittance redistribution from the longitudinal dimension to transverse one, necessary for cooling of all degrees of freedom. This redistribution is based on special rotations of the particle six-dimensional phase space by the beam division in several streams and their consequent merging with the minimum increment of full emittance and minimal beam losses taking into account their local phase-space density. Some of the basic technical parameters of the cooling system elements have been estimated.

  20. OTEC heat exchanger design and producibility study. Part C. Appendixes G thru J. Final report

    Energy Technology Data Exchange (ETDEWEB)

    None

    1976-10-28

    Study results of a preliminary design and manufacturing study of 25-MW/sub e/ aluminium-tubed and titanium-tubed heat exchangers and 5-MW/sub e/ subscale heat exchangers for ocean thermal energy conversion are reported. Subcontractor engineering efforts are described including computer printout sheets from the optimization program; structural analysis of the pressure vessels, heat exchanger tubing, shell to tubesheet transition ring, vapor ports, and concrete pressure vessels; magnaforming of tube-to-tubesheets in aluminium; and explosion bonding and propellant swagging of tubes to tubesheets. (WHK)

  1. Experimental Design for CMIP6: Aerosol, Land Use, and Future Scenarios Final Report

    Energy Technology Data Exchange (ETDEWEB)

    Arnott, James [AGCI

    2015-10-30

    The Aspen Global Change Institute hosted a technical science workshop entitled, “Experimental design for CMIP6: Aerosol, Land Use, and Future Scenarios,” on August 3-8, 2014 in Aspen, CO. Claudia Tebaldi (NCAR) and Brian O’Neill (NCAR) served as co-chairs for the workshop. The Organizing committee also included Dave Lawrence (NCAR), Jean-Francois Lamarque (NCAR), George Hurtt (University of Maryland), & Detlef van Vuuren (PBL Netherlands Environmental Change). The meeting included the participation of 22 scientists representing many of the major climate modeling centers for a total of 110 participant days.

  2. Geomechanical Analysis and Design Considerations for Thin-Bedded Salt Caverns. Final Report

    International Nuclear Information System (INIS)

    Michael S. Bruno

    2005-01-01

    The bedded salt formations located throughout the United States are layered and interspersed with non-salt materials such as anhydrite, shale, dolomite and limestone. The salt layers often contain significant impurities. GRI and DOE have initialized this research proposal in order to increase the gas storage capabilities by providing operators with improved geotechnical design and operating guidelines for thin bedded salt caverns. Terralog has summarized the geologic conditions, pressure conditions, and critical design factors that may lead to: (1) Fracture in heterogeneous materials; (2) Differential deformation and bedding plane slip; (3) Propagation of damage around single and multiple cavern; and (4) Improved design recommendations for single and multiple cavern configurations in various bedded salt environments. The existing caverns within both the Permian Basin Complex and the Michigan and Appalachian Basins are normally found between 300 m to 1,000 m (1,000 ft to 3,300 ft) depth depending on local geology and salt dissolution depth. Currently, active cavern operations are found in the Midland and Anadarko Basins within the Permian Basin Complex and in the Appalachian and Michigan Basins. The Palo Duro and Delaware Basins within the Permian Basin Complex also offer salt cavern development potential. Terralog developed a number of numerical models for caverns located in thin bedded salt. A modified creep viscoplastic model has been developed and implemented in Flac3D to simulate the response of salt at the Permian, Michigan and Appalachian Basins. The formulation of the viscoplastic salt model, which is based on an empirical creep law developed for Waste Isolation Pilot Plant (WIPP) Program, is combined with the Drucker-Prager model to include the formation of damage and failure. The Permian salt lab test data provided by Pfeifle et al. 1983, are used to validate the assumptions made in the material model development. For the actual cavern simulations two

  3. IFMIF : International Fusion Materials Irradiation Facility Conceptual Design Activity: Final report

    Energy Technology Data Exchange (ETDEWEB)

    Martone, M. [ENEA, Centro Ricerche Frascati, Rome (Italy)

    1997-01-01

    This report documents the results of the Conceptual Design Activity (CDA) on the International Fusion Materials Irradiation Facility (IFMIF), conducted during 1995 and 1996. The activity is under the auspices of the International Energy Agency (IEA) Implementing Agreement for a Programme of Research and Development on Fusion Materials. An IEA Fusion Materials Executive Subcommittee was charged with overseeing the IFMIF-CDA work. Participants in the CDA are the European Union, Japan, and the United States, with the Russian Federation as an associate member.

  4. IFMIF : International Fusion Materials Irradiation Facility Conceptual Design Activity: Final report

    International Nuclear Information System (INIS)

    Martone, M.

    1997-01-01

    This report documents the results of the Conceptual Design Activity (CDA) on the International Fusion Materials Irradiation Facility (IFMIF), conducted during 1995 and 1996. The activity is under the auspices of the International Energy Agency (IEA) Implementing Agreement for a Programme of Research and Development on Fusion Materials. An IEA Fusion Materials Executive Subcommittee was charged with overseeing the IFMIF-CDA work. Participants in the CDA are the European Union, Japan, and the United States, with the Russian Federation as an associate member

  5. Quantitative description of a high Jc Nb-Ti superconductor during its final optimization strain. I. Microstructure, Tc, Hc2, and resistivity

    International Nuclear Information System (INIS)

    Meingast, C.; Lee, P.J.; Larbalestier, D.C.

    1989-01-01

    A most important step in the critical current density (J c ) optimization of Nb-Ti is the large final drawing strain, in which α-Ti precipitates, initially approximately equiaxed and 100--200 nm in diameter, are drawn into ribbons, whose thickness (1--2 nm) is less than the superconducting coherence length [ξ (4.2 K)∼5 nm]. Using transmission electron microscopy, the precipitate thickness, spacing, cross-sectional area, and circumference were measured over the whole final drawing strain range. Each of these parameters was found to have a simple power dependence on the wire diameter. T c , H c2 , and the resistivity (ρ n ) were also change considerably during the refinement of the precipitates. Directly after precipitation, T c increased, and (dH c2 /dT) T c and ρ n were reduced from the single-phase values. Drawing the wire returned these parameters to their single-phase values, as the precipitate thickness was reduced to less than ξ. This observation explains a long-standing peculiarity in this system, namely that the optimum H c2 of high J c conductors occurs for a composition close to Nb 46 wt.% Ti, even when the precipitation of 18 vol % of α-Ti shifts the matrix composition to a Nb-rich composition of theoretically lower H c2

  6. Conceptual design of a coal-fired MHD retrofit. Final technical report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1994-06-01

    Coal-fired magnetohydrodynamics (MHD) technology is ready for its next level of development - an integrated demonstration at a commercial scale. The development and testing of MHD has shown its potential to be the most efficient, least costly, and cleanest way to burn coal. Test results have verified a greater than 99% removal of sulphur with a potential for greater than 60% efficiency. This development and testing, primarily funded by the U.S. Department of Energy (DOE), has progressed through the completion of its proof-of-concept (POC) phase at the 50 MWt Component Development and Integration Facility (CDIF) and 28 MWt Coal Fired Flow Facility (CFFF), thereby, providing the basis for demonstration and further commercial development and application of the technology. The conceptual design of a retrofit coal-fired MHD generating plant was originally completed by the MHD Development Corporation (MDC) under this Contract, DE-AC22-87PC79669. Thereafter, this concept was updated and changed to a stand-alone MHD demonstration facility and submitted by MDC to DOE in response to the fifth round of solicitations for Clean Coal Technology. Although not selected, that activity represents the major interest in commercialization by the developing industry and the type of demonstration that would be eventually necessary. This report updates the original executive summary of the conceptual design by incorporating the results of the POC program as well as MDC`s proposed Billings MHD Demonstration Project (BMDP) and outlines the steps necessary for commercialization.

  7. Introduction to the second international workshop on the design and construction of final repositories

    International Nuclear Information System (INIS)

    Simmons, G.R.

    1995-01-01

    Canadian repository design studies are reviewed. Two conceptual designs are described. The first is a single-level spent-fuel repository using the in-floor borehole emplacement configuration. The disposal container for 72 bundles is made of titanium. The depth will probably be 1000 m. Maximum temperature must not exceed 100 deg C. The near-surface extension zone must not exceed 100 m in depth. The cost for disposal of 10.1 million bundles over 89 years is estimated to be about C$13 billion. The second concept, a single level spent-fuel repository using the in-room emplacement configuration, may be more suitable for the stress conditions that may be encountered in the plutonic rocks of the Canadian shield at a depth greater than 500 m. In this case, the container is made of copper, and the capacity of the repository will be determined by maintaining the emplacement area at about 2 km square, and the required container to container and room to room spacing to satisfy the temperature criterion. A concrete floor will be provided.The buffer material will be formed in pre-compacted blocks. 10 refs., 1 tab., 4 figs

  8. Stirling engine electric hybrid vehicle propulsion system conceptual design study. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Dochat, G; Artiles, A; Killough, J; Ray, A; Chen, H S

    1978-08-01

    Results of a six-month study to characterize a series Stirling engine electric hybrid vehicle propulsion system are presented. The Stirling engine was selected as the heat conversion element to exploit the high efficiency (> .36), low pollution, multi-fuel and quiet operation of this machine. A free-piston Stirling engine driving a linear alternator in a hermatically sealed enclosure was chosen to gain the reliability, long life, and maintenance free characteristics of a sealed unit. The study performs trade off evaluations, selection of engine, battery, motor and inverter size, optimization of components, and develops a conceptual design and characterization of the total propulsion system. The conclusion of the study is that a Stirling engine electric hybrid propulsion system can be used successfully to augment the battery storage of a passenger vehicle and will result in significant savings of petroleum energy over present passenger vehicles. The performance and range augmentation of the hybrid design results in significant improvements over an all electric vehicle. The hybrid will be capable of performing 99% of the passenger vehicle annual trip distribution requirements with extremely low fuel usage. (TFD)

  9. Molecular Design of Doped Polymers for Thermoelectric Systems-Final Technical Report

    Energy Technology Data Exchange (ETDEWEB)

    Chabinyc, Michael L. [University of California, Santa Barbara; Hawker, Craig J. [University of California, Santa Barbara

    2013-10-09

    The self-assembly of organic semiconducting molecules and polymers is critical for their electrical properties. This project addressed the design of organic semiconductors with novel synthetic building blocks for proton-dopable conducting materials and the molecular order and microstructure of high performance semiconducting polymers blended with charge transfer dopants. Novel azulene donor-acceptor materials were designed and synthesized with unique electronic effects upon protonation to generate charged species in solution. The microstructure and optical properties of these derivatives were examined to develop structure-property relationships. Studies of the microstructure of blends of charge transfer doped semiconducting polymers revealed highly ordered conductive phases in blends. The molecular packing of one blend was studied in detail using a combination of solid-state NMR and x-ray scattering revealing that dopant incorporation is unlikely to be random as assumed in transport models. Studies of the electrical properties of these highly ordered blends revealed a universal trend between the thermopower and electrical conductivity of semiconducting polymers that is independent of the doping mechanism.

  10. Final Report: Conceptual Design of an Electron Accelerator for Bio-Solid Waste Treatment

    Energy Technology Data Exchange (ETDEWEB)

    Cooper, Charles [Fermi National Accelerator Lab. (FNAL), Batavia, IL (United States)

    2017-09-20

    Several studies have identified electron beam (EB) irradiation of municipal wastewater and bio-solids as an effective and promising approach to the environmental remediation of the enormous quantities of human waste created by a growing world-wide population and increased urbanization. However, despite the technical success of experimental and pilot programs over the last several decades, the technique is still not in commercial use anywhere in the world. In addition, the report also identifies the need for “Financial and infrastructure participation from a utility for demonstration project” and “Education and awareness of safety of utilizing electron beam technology” as two additional roadblocks preventing technology adoption of EB treatment for bio-solids. In this concept design, we begin to address these barriers by working with Metropolitan Water Reclamation District of Greater Chicago (MWRD) and by the applying the latest accelerator technologies developed at Fermilab and within the DOE Office of Science laboratory complex.

  11. Conceptual design and systems analysis of photovoltaic systems. Volume II. Study results. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Kirpich, A.

    1977-03-19

    This investigation of terrestrial PV systems considered the technical and economic feasibility for systems in three size categories: a small system of about 12 kW peak output for on-site residential use; a large 1500 MW central power plant contributing to the bulk energy of a utility system power grid; and an intermediate size system of about 250 kW for use on public or commercial buildings. In each category, conceptual designs were developed, performance was analyzed for a range of climatic regions, economic analyses were performed, and assessments were made of pertinent institutional issues. The report consists of three volumes. Volume I contains a Study Summary of the major study results. This volume contains the detailed results pertaining to on-site residential photovoltaic systems, central power plant photovoltaic systems, and intermediate size systems applied to commercial and public buildings. Volume III contains supporting appendix material. (WHK)

  12. Final report: Seven-layer membrane electrode assembly - an innovative approach to PEM fuel cell design

    Energy Technology Data Exchange (ETDEWEB)

    Chapman, A.

    2005-07-01

    Costs of materials and fabrication, rather than appropriateness of technology, are the major barriers to the sales of fuel cells. With the objective of reducing costs, potential alternative component materials for (a) the fluid flow plate (FFP) and (b) the gas diffusion layers were investigated. The concept of a 7-layer membrane electrode assembly (MEA), in which components are bonded into a unitised module, was also studied. The advantages of the bonded cell, and the flow field design, are expounded. Low-cost carbon particle composites were developed for the FFPs. The modular 7-layer MEA has an order of magnitude saving over current materials. Overall, the study has led to a greater volumetric power output, lower costs and greater reliability. The work was carried out by Morgan Group Technology Limited and funded by the DTI.

  13. Army Gas-Cooled Reactor Systems program: alternator final design report

    Energy Technology Data Exchange (ETDEWEB)

    1964-06-01

    The development and testing of a demonstration brushless alternator for the ML-1 mobile nuclear power plant is described. The brushless concept was selected after it became apparent that a conventional power generator could not satisfy the ML-1 weight and size requirements. The demonstration alternator fabricated and tested under this program did not meet all performance specifications; the efficiency was low and the unit could not be operated for significant periods of time without overheating. However, a large body of useful data was accumulated during the extensive development program. Of special interest are data on the rotor and stator design, the cooling requirements and on the distribution of eddy current losses. Analysis of the data indicates that a brushless alternator, only slightly larger and heavier than was specified for the ML-1, could be developed with a modest additional effort.

  14. Interaction point feedback design and integrated simulations to stabilize the CLIC final focus

    CERN Document Server

    Balik, G; Deleglise, G; Jeremie, A; Pacquet, L; Badel, A; Caron, B; Le Breton, R; Latina, A; Pfingstner, J; Schulte, D; Snuverink, J

    2011-01-01

    The Compact Linear Collider (CLIC) accelerator has strong precision requirements on the offset position between the beams. Sensitive to ground motion (GM), the beam needs to be stabilized to unprecedented requirements. Different Beam Based Feedback (BBF) algorithms such as Orbit Feedback (OFB) and Interaction Point Feedback (IPFB) have been designed. This paper focuses on the IPFB control which could be added to the CLIC baseline. IPFB control has been tested for different GM models in presence of noises or disturbances and it uses digital linear control with an adaptive loop. The simulations demonstrate that it is possible to achieve the required performances and quantify the maximum allowed noise level. This amount of admitted noises and disturbances is given in terms of an equivalent disturbance on the position of the magnet that controls the beam offset. Due to the limited sampling frequency of the process, the control loop is in a very small bandwidth. The study shows that these disturbances have to be l...

  15. Design, Observing and Data Systems, and Final Installation of the NEPTUNE Canada Regional Cabled Ocean Observatory

    Science.gov (United States)

    Barnes, C. R.; Best, M. M.; Johnson, F. R.; Phibbs, P.; Pirenne, B.

    2009-05-01

    NEPTUNE Canada (NC; www.neptunecanada.ca) will complete most of the installation of the world's first regional cabled ocean observatory in late 2009 off Canada's west coast. It will comprise five main observatory nodes (100-2700m water depths) linked by an 800km backbone cable delivering 10kVDC power and 10Gbps communications bandwidth to hundreds of sensors, with a 25-year design life. Infrastructure (100M) and initial operational funding (20M) is secured. University of Victoria (UVic) leads a consortium of 12 Canadian universities, hosts the coastal VENUS cabled observatory, with Ocean Networks Canada (ONC) providing management oversight. Observatory architecture has a trunk and branch topology. Installed in late 2007, the backbone cable loops from/to UVic's Port Alberni shore station. The wet plant's design, manufacture and installation was contracted to Alcatel-Lucent. Each node provides six interface ports for connection of science instrument arrays or extensions. Each port provides dual optical Ethernet links and up to 9kW of electrical power at 400VDC. Junction boxes, designed and built by OceanWorks support up to 10 instruments each and can be daisy- chained. They accommodate both serial and 10/100 Ethernet instruments, and provide a variety of voltages (400V, 48V, 24V, 15V). Backbone equipment has all been qualified and installed; shore station re-equipping is complete; junction boxes are manufactured. A major marine program will deploy nodes and instruments in July-September 2009; instruments to one node will probably be deferred until 2010. Observatory instruments will be deployed in subsurface (boreholes), on seabed, and buoyed through the water column. Over 130 instruments (over 40 different types) will host several hundred sensors; mobile assets include a tethered crawler and a 400m vertical profiler. Experiments will address: earthquake dynamics and tsunami hazards; fluid fluxes in both ocean crust and sediments, including gas hydrates; ocean

  16. Innovative grinding wheel design for cost-effective machining of advanced ceramics. Phase I, final report

    Energy Technology Data Exchange (ETDEWEB)

    Licht, R.H.; Ramanath, S.; Simpson, M.; Lilley, E.

    1996-02-01

    Norton Company successfully completed the 16-month Phase I technical effort to define requirements, design, develop, and evaluate a next-generation grinding wheel for cost-effective cylindrical grinding of advanced ceramics. This program was a cooperative effort involving three Norton groups representing a superabrasive grinding wheel manufacturer, a diamond film manufacturing division and a ceramic research center. The program was divided into two technical tasks, Task 1, Analysis of Required Grinding Wheel Characteristics, and Task 2, Design and Prototype Development. In Task 1 we performed a parallel path approach with Superabrasive metal-bond development and the higher technical risk, CVD diamond wheel development. For the Superabrasive approach, Task 1 included bond wear and strength tests to engineer bond-wear characteristics. This task culminated in a small-wheel screening test plunge grinding sialon disks. In Task 2, an improved Superabrasive metal-bond specification for low-cost machining of ceramics in external cylindrical grinding mode was identified. The experimental wheel successfully ground three types of advanced ceramics without the need for wheel dressing. The spindle power consumed by this wheel during test grinding of NC-520 sialon is as much as to 30% lower compared to a standard resin bonded wheel with 100 diamond concentration. The wheel wear with this improved metal bond was an order of magnitude lower than the resin-bonded wheel, which would significantly reduce ceramic grinding costs through fewer wheel changes for retruing and replacements. Evaluation of ceramic specimens from both Tasks 1 and 2 tests for all three ceramic materials did not show evidence of unusual grinding damage. The novel CVD-diamond-wheel approach was incorporated in this program as part of Task 1. The important factors affecting the grinding performance of diamond wheels made by CVD coating preforms were determined.

  17. Foundation Heat Exchanger Final Report: Demonstration, Measured Performance, and Validated Model and Design Tool

    Energy Technology Data Exchange (ETDEWEB)

    Hughes, Patrick [Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States); Im, Piljae [Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)

    2012-01-01

    (FHX) has been coined to refer exclusively to ground heat exchangers installed in the overcut around the basement walls. The primary technical challenge undertaken by this project was the development and validation of energy performance models and design tools for FHX. In terms of performance modeling and design, ground heat exchangers in other construction excavations (e.g., utility trenches) are no different from conventional HGHX, and models and design tools for HGHX already exist. This project successfully developed and validated energy performance models and design tools so that FHX or hybrid FHX/HGHX systems can be engineered with confidence, enabling this technology to be applied in residential and light commercial buildings. The validated energy performance model also addresses and solves another problem, the longstanding inadequacy in the way ground-building thermal interaction is represented in building energy models, whether or not there is a ground heat exchanger nearby. Two side-by-side, three-level, unoccupied research houses with walkout basements, identical 3,700 ft{sup 2} floor plans, and hybrid FHX/HGHX systems were constructed to provide validation data sets for the energy performance model and design tool. The envelopes of both houses are very energy efficient and airtight, and the HERS ratings of the homes are 44 and 45 respectively. Both houses are mechanically ventilated with energy recovery ventilators, with space conditioning provided by water-to-air heat pumps with 2 ton nominal capacities. Separate water-to-water heat pumps with 1.5 ton nominal capacities were used for water heating. In these unoccupied research houses, human impact on energy use (hot water draw, etc.) is simulated to match the national average. At House 1 the hybrid FHX/HGHX system was installed in 300 linear feet of excavation, and 60% of that was construction excavation (needed to construct the home). At House 2 the hybrid FHX/HGHX system was installed in 360 feet of

  18. Foundation Heat Exchanger Final Report: Demonstration, Measured Performance, and Validated Model and Design Tool

    Energy Technology Data Exchange (ETDEWEB)

    Hughes, Patrick [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Im, Piljae [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

    2012-04-01

    (FHX) has been coined to refer exclusively to ground heat exchangers installed in the overcut around the basement walls. The primary technical challenge undertaken by this project was the development and validation of energy performance models and design tools for FHX. In terms of performance modeling and design, ground heat exchangers in other construction excavations (e.g., utility trenches) are no different from conventional HGHX, and models and design tools for HGHX already exist. This project successfully developed and validated energy performance models and design tools so that FHX or hybrid FHX/HGHX systems can be engineered with confidence, enabling this technology to be applied in residential and light commercial buildings. The validated energy performance model also addresses and solves another problem, the longstanding inadequacy in the way ground-building thermal interaction is represented in building energy models, whether or not there is a ground heat exchanger nearby. Two side-by-side, three-level, unoccupied research houses with walkout basements, identical 3,700 ft{sup 2} floor plans, and hybrid FHX/HGHX systems were constructed to provide validation data sets for the energy performance model and design tool. The envelopes of both houses are very energy efficient and airtight, and the HERS ratings of the homes are 44 and 45 respectively. Both houses are mechanically ventilated with energy recovery ventilators, with space conditioning provided by water-to-air heat pumps with 2 ton nominal capacities. Separate water-to-water heat pumps with 1.5 ton nominal capacities were used for water heating. In these unoccupied research houses, human impact on energy use (hot water draw, etc.) is simulated to match the national average. At House 1 the hybrid FHX/HGHX system was installed in 300 linear feet of excavation, and 60% of that was construction excavation (needed to construct the home). At House 2 the hybrid FHX/HGHX system was installed in 360 feet of

  19. Energy independent scaling of the ridge and final state description of high multiplicity p +p collisions at √{s }=7 and 13 TeV

    Science.gov (United States)

    Sarkar, Debojit

    2018-02-01

    An energy independent scaling of the near-side ridge yield at a given multiplicity has been observed by the ATLAS and the CMS collaborations in p +p collisions at √{s }=7 and 13 TeV. Such a striking feature of the data can be successfully explained by approaches based on initial state momentum space correlation generated due to gluon saturation. In this paper, we try to examine if such a scaling is also an inherent feature of the approaches that employ strong final state interaction in p +p collisions. We find that hydrodynamical modeling of p +p collisions using EPOS 3 shows a violation of such scaling. The current study can, therefore, provide important new insights on the origin of long-range azimuthal correlations in high multiplicity p +p collisions at the LHC energies.

  20. Safety assessment in plant layout design using indexing approach: implementing inherent safety perspective. Part 1 - guideword applicability and method description.

    Science.gov (United States)

    Tugnoli, Alessandro; Khan, Faisal; Amyotte, Paul; Cozzani, Valerio

    2008-12-15

    Layout planning plays a key role in the inherent safety performance of process plants since this design feature controls the possibility of accidental chain-events and the magnitude of possible consequences. A lack of suitable methods to promote the effective implementation of inherent safety in layout design calls for the development of new techniques and methods. In the present paper, a safety assessment approach suitable for layout design in the critical early phase is proposed. The concept of inherent safety is implemented within this safety assessment; the approach is based on an integrated assessment of inherent safety guideword applicability within the constraints typically present in layout design. Application of these guidewords is evaluated along with unit hazards and control devices to quantitatively map the safety performance of different layout options. Moreover, the economic aspects related to safety and inherent safety are evaluated by the method. Specific sub-indices are developed within the integrated safety assessment system to analyze and quantify the hazard related to domino effects. The proposed approach is quick in application, auditable and shares a common framework applicable in other phases of the design lifecycle (e.g. process design). The present work is divided in two parts: Part 1 (current paper) presents the application of inherent safety guidelines in layout design and the index method for safety assessment; Part 2 (accompanying paper) describes the domino hazard sub-index and demonstrates the proposed approach with a case study, thus evidencing the introduction of inherent safety features in layout design.

  1. A Summary Description of a Computer Program Concept for the Design and Simulation of Solar Pond Electric Power Generation Systems

    Science.gov (United States)

    1984-01-01

    A solar pond electric power generation subsystem, an electric power transformer and switch yard, a large solar pond, a water treatment plant, and numerous storage and evaporation ponds. Because a solar pond stores thermal energy over a long period of time, plant operation at any point in time is dependent upon past operation and future perceived generation plans. This time or past history factor introduces a new dimension in the design process. The design optimization of a plant must go beyond examination of operational state points and consider the seasonal variations in solar, solar pond energy storage, and desired plant annual duty-cycle profile. Models or design tools will be required to optimize a plant design. These models should be developed in order to include a proper but not excessive level of detail. The model should be targeted to a specific objective and not conceived as a do everything analysis tool, i.e., system design and not gradient-zone stability.

  2. [Final clinical indications and etiology in 1,023 enucleations. Descriptive databank evaluation with SPSS software in variable response mode with dummy variables].

    Science.gov (United States)

    Becker, H; Bialasiewicz, A A; Schaudig, U; Schäfer, H; von Domarus, D

    2002-05-01

    A new data bank developed for ophthalmopathology using a computer-generated, multidigital data code is expected to be able to accomplish complex clinicopathologic correlations of diagnoses and signs, as provided by (multiple) clinical events and histopathologically proven etiologies, and to facilitate the documentation of new data. In the ophthalmopathology laboratory 2890 eyes were examined between January 20, 1975 and December 12, 1996. The main diagnoses and patient data from this 22-year period were recorded. To facilitate the presentation of data, a 10-year period with eyes of 976 patients enucleated from December, 1986 to December, 1996 was chosen. Principal and secondary diagnoses served for establishing the data bank. The frequencies of successive histologic and clinical diagnoses were evaluated by a descriptive computing program using an SPSS-multi-response mode with dummy variables and a categorical variable listing of the software (SPSS version 10.0) classified as (a) non-filtered random, (b) filtered by multiple etiologies, and (c) filtered by multiple events. The principal groups (e.g., histologic diagnoses concerning etiology) and subgroups (e.g., trauma, neoplasia, surgery, systemic diseases, and inflammations) were defined and correlated with 798 separate diagnoses. From 11 diagnoses/events ascribed to the clinical cases, 11,198 namings resulted. Thus, a comparative study of complex etiologies and events leading to enucleation in different hospitals of a specific area may be performed using this electronic ophthalmopathologic data bank system. The complexity of rare disease and integration into a superimposed structure can be managed with this custom-made data bank. A chronologically and demographically oriented consideration of reasons for enucleation is thus feasible.

  3. Final Scientific/Technical Report for "Enabling Exascale Hardware and Software Design through Scalable System Virtualization"

    Energy Technology Data Exchange (ETDEWEB)

    Dinda, Peter August [Northwestern Univ., Evanston, IL (United States)

    2015-03-17

    This report describes the activities, findings, and products of the Northwestern University component of the "Enabling Exascale Hardware and Software Design through Scalable System Virtualization" project. The purpose of this project has been to extend the state of the art of systems software for high-end computing (HEC) platforms, and to use systems software to better enable the evaluation of potential future HEC platforms, for example exascale platforms. Such platforms, and their systems software, have the goal of providing scientific computation at new scales, thus enabling new research in the physical sciences and engineering. Over time, the innovations in systems software for such platforms also become applicable to more widely used computing clusters, data centers, and clouds. This was a five-institution project, centered on the Palacios virtual machine monitor (VMM) systems software, a project begun at Northwestern, and originally developed in a previous collaboration between Northwestern University and the University of New Mexico. In this project, Northwestern (including via our subcontract to the University of Pittsburgh) contributed to the continued development of Palacios, along with other team members. We took the leadership role in (1) continued extension of support for emerging Intel and AMD hardware, (2) integration and performance enhancement of overlay networking, (3) connectivity with architectural simulation, (4) binary translation, and (5) support for modern Non-Uniform Memory Access (NUMA) hosts and guests. We also took a supporting role in support for specialized hardware for I/O virtualization, profiling, configurability, and integration with configuration tools. The efforts we led (1-5) were largely successful and executed as expected, with code and papers resulting from them. The project demonstrated the feasibility of a virtualization layer for HEC computing, similar to such layers for cloud or datacenter computing. For effort (3

  4. Projet BIOTRYTIS : Description du site expérimental, des équipements et de la métrologie. Rapport final Irstea-Onema

    OpenAIRE

    Petitjean, A.; Bouyer, M.; Forquet, N.; Cretollier, C.; Bourgeois, V.; Clement, R.; Gregoire, J.C.; Ahyerre, M.; Coquery, M.; Boutin, C.; Choubert, J.M.

    2016-01-01

    Buffer zones between wastewater treatment plants and receiving water bodies have recently gained interest in France. These planted discharge areas (PDA) receive treated wastewater and may have various designs aiming to mimic 'natural' wetlands. Research is needed to assess the treatment efficiency of such systems: a comprehensive study co-funded by ONEMA (French National Agency for Water and Aquatic Environments) is carried out to understand the fate of water, conventional pollutants and micr...

  5. 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.

  6. Design and manufacture of radar absorbing wind turbine blades - final report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-02-15

    This report describes the results of a collaborative project between QinetiQ Ltd and NOI (Scotland) Ltd to design and manufacture radar absorbent wind turbine blades. The main objectives were to: use predictive modelling to understand the contribution made by the blade to radar cross section (RCS) of the complete turbine; confirm that the turbine RCS could feasibility be reduced to appropriate levels through the use of radar absorbent material (RAM); and to demonstrate that introduction of stealth technology within current composite sections would allow RAM variants of the blade materials to be manufactured with minimal impact on the structure. The RCS of a turbine was predicted at frequencies at which representative air traffic control (ATC), weather and marine navigation radar systems operate. The material compositions that exist on the blades produced by NOI were studied and methods by which RAM could be introduced to each region were identified. RCS predictions for a blade having RAM over its surface were then repeated. The study showed that it was possible to modify all material regions of the NOI blades to create RAM with little or no degradation in structural properties, thus reducing detection by non-Doppler radar and ATC radars. A full practical demonstration of a stealthy turbine is recommended to allow the benefits of RCS reduction through the use of RAM to be quantified by all stakeholders.

  7. Kelly Hot Spring Geothermal Project: Kelly Hot Spring Agricultural Center preliminary design. Final technical report

    Energy Technology Data Exchange (ETDEWEB)

    Longyear, A.B. (ed.)

    1980-08-01

    A Phase 1 Preliminary Design, Construction Planning and Economic Analysis has been conducted for the Kelly Hot Spring Agricultural Center in Modoc County, California. The core activity is a 1360 breeding sow, swine raising complex that utilizes direct heat energy from the Kelly Hot Spring geothermal resource. The swine is to be a totally confined operation for producing premium pork in controlled-environment facilities. The complex contains a feed mill, swine raising buildings and a complete waste management facility that produces methane gas to be delivered to a utility company for the production of electricity. The complex produces 6.7 million pounds of live pork (29,353 animals) shipped to slaughter per year; 105,000 cu. ft. of scrubbed methane per day; and fertilizer. Total effluent is less than 200 gpm of agricultural quality-water with full odor control. The methane production rate made possible with geothermal direct heat is equivalent to at least 400 kw continuous. Sale of the methane on a co-generation basis is being discussed with the utility company. The use of geothermal direct heat energy in the complex displaces nearly 350,000 gallons of fuel oil per year. Generation of the biogas displaces an additional 300,000 gallons of fuel oil per year.

  8. PULSE COMBUSTOR DESIGN QUALIFICATION TEST AND CLEAN COAL FEEDSTOCK TEST - VOLUME I AND VOLUME II; FINAL

    International Nuclear Information System (INIS)

    Unknown

    2002-01-01

    For this Cooperative Agreement, the pulse heater module is the technology envelope for an indirectly heated steam reformer. The field of use of the steam reformer pursuant to this Cooperative Agreement with DOE is for the processing of sub-bituminous coals and lignite. The main focus is the mild gasification of such coals for the generation of both fuel gas and char-for the steel industry is the main focus. An alternate market application for the substitution of metallurgical coke is also presented. This project was devoted to qualification of a 253-tube pulse heater module. This module was designed, fabricated, installed, instrumented and tested in a fluidized bed test facility. Several test campaigns were conducted. This larger heater is a 3.5 times scale-up of the previous pulse heaters that had 72 tubes each. The smaller heater has been part of previous pilot field testing of the steam reformer at New Bern, North Carolina. The project also included collection and reduction of mild gasification process data from operation of the process development unit (PDU). The operation of the PDU was aimed at conditions required to produce char (and gas) for the Northshore Steel Operations. Northshore Steel supplied the coal for the process unit tests

  9. Brayton power conversion system parametric design modelling for nuclear electric propulsion. Final report

    International Nuclear Information System (INIS)

    Ashe, T.L.; Otting, W.D.

    1993-11-01

    The parametrically based closed Brayton cycle (CBC) computer design model was developed for inclusion into the NASA LeRC overall Nuclear Electric Propulsion (NEP) end-to-end systems model. The code is intended to provide greater depth to the NEP system modeling which is required to more accurately predict the impact of specific technology on system performance. The CBC model is parametrically based to allow for conducting detailed optimization studies and to provide for easy integration into an overall optimizer driver routine. The power conversion model includes the modeling of the turbines, alternators, compressors, ducting, and heat exchangers (hot-side heat exchanger and recuperator). The code predicts performance to significant detail. The system characteristics determined include estimates of mass, efficiency, and the characteristic dimensions of the major power conversion system components. These characteristics are parametrically modeled as a function of input parameters such as the aerodynamic configuration (axial or radial), turbine inlet temperature, cycle temperature ratio, power level, lifetime, materials, and redundancy

  10. Final Report for 'Gyrotron Design and Evaluation using New Particle-in-Cell Capability'

    International Nuclear Information System (INIS)

    Smithe, David N.

    2008-01-01

    ITER will depend on high power CW gyrotrons to deliver power to the plasma at ECR frequencies. However, gyrotrons can suffer from undesirable low frequency oscillations (LFO's) which are known to interfere with the gun-region diagnostics and data collection, and are also expected to produce undesirable energy and velocity spread in the beam. The origins and processes leading to these oscillations are poorly understood, and existing gyrotron R and D tools, such as static gun solvers and interaction region models, are not designed to look at time-dependant oscillatory behavior. We have applied a time-domain particle-in-cell method to investigate the LFO phenomenon. Our company is at the forefront of smooth-curved-boundary treatment of the electromagnetic fields and particle emission surfaces, and such methods are necessary to simulate the adiabatically trapped and reflected electrons thought to be driving the oscillations. This approach provides the means for understanding, in microscopic detail, the underlying physical processes driving the low-frequency oscillations. In the Phase I project, an electron gun region from an existing gyrotron, known to observe LFO's, was selected as a proof-of-principle geometry, and was modeled with the curved-geometry time-domain simulation tool, in order to establish the feasibility of simulating LFO physics with this tool on office-scale, and larger, parallel cluster computers. Generally, it was found to be feasible to model the simulation geometry, emission, and magnetic features of the electron gun. Ultimately, the tool will be used to investigate the origins and life cycle within the trapped particle population. This tool also provides the foundations and validation for potential application of the software to numerous other time-dependant beam and rf source problems in the commercial arena.

  11. Design basis for the copper/steel canister. Stage four. Final report

    International Nuclear Information System (INIS)

    Bowyer, W.H.

    1998-06-01

    The development of the copper/iron canister which has been proposed by SKB for the containment of high level nuclear waste has been studied from the points of view of choice of materials, manufacturing technology and quality assurance. Cast steel has been rejected in favour of cast iron as a candidate material for the load bearing liner. Nodular (or ductile) iron is selected and this is capable of providing mechanical properties which are equally suitable as those of the originally selected high strength low alloy steel. The material specified for the overpack is Oxygen free copper with 50 ppm of phosphorus added. Corrosion studies supported by SKB indicate that in the absence of mechanical failure or accelerated localised corrosion the overpack should provide corrosion shielding of the canister for its full design life. Published work claiming that the nodular iron liner would have corrosion characteristics similar to the carbon steel which had been examined in depth is flawed since the microstructures of the iron and carbon steel specimens used were not investigated. It is highly unlikely that nodular irons in the form used for the experiments would have similar structures to nodular iron in the canisters by chance. If the overpack were breached during the aerobic period of the repository life then very rapid penetration of the inner liner could occur. It has been recognised that the roll forming method is not suitable for serial production and alternatives are being sought. The electron beam welding process has been explored with tenacity but has so far failed to produce a satisfactory lid weld. A new welder is being developed for supply to the SKB pilot plant where development will be continued. An alternative welding process, friction stir welding, is being examined as a candidate for attaching lids. Surface breaking defects may be detected using eddy current methods but there is currently no reliable way of detecting small sub surface defects in the overpack

  12. Computer software design description for the Treated Effluent Disposal Facility (TEDF), Project L-045H, Operator Training Station (OTS)

    International Nuclear Information System (INIS)

    Carter, R.L. Jr.

    1994-01-01

    The Treated Effluent Disposal Facility (TEDF) Operator Training Station (OTS) is a computer-based training tool designed to aid plant operations and engineering staff in familiarizing themselves with the TEDF Central Control System (CCS)

  13. CALIOP: a multichannel design code for gas-cooled fast reactors. Code description and user's guide

    Energy Technology Data Exchange (ETDEWEB)

    Thompson, W.I.

    1980-10-01

    CALIOP is a design code for fluid-cooled reactors composed of parallel fuel tubes in hexagonal or cylindrical ducts. It may be used with gaseous or liquid coolants. It has been used chiefly for design of a helium-cooled fast breeder reactor and has built-in cross section information to permit calculations of fuel loading, breeding ratio, and doubling time. Optional cross-section input allows the code to be used with moderated cores and with other fuels.

  14. Design basis for the copper/steel canister. Stage five. Final report

    International Nuclear Information System (INIS)

    Bowyer, W.H.

    1999-05-01

    The development of the copper/iron canister which has been proposed by SKB for the containment of high level nuclear waste in the Swedish Program, has been studied by the present author from the points of view of choice of materials, manufacturing technology and quality assurance. This report describes the observations on progress that has been made between May-1-1998 and April-30-1999 and the result of further literature studies. Cast steel has been rejected in favour of cast iron as a candidate material for the load bearing liner. The nodular iron that was selected has been the subject of casting trials at several foundries. Early trials, using uphill feeding, met with limited success owing to difficulties feeding during solidification. Lessons from this trial led to a modification to the casting design to include extra cores that have the effect of reducing the need for feeding in the heaviest sections. Results using the new design and direct (downhill) casting are very promising. Castings appear to be sound and mechanical test results cast-on bars are within specification. Tensile test results from specimens cut from the casting have reduced ductility compared with the cast-on bars and this may be evidence of microstructural variations within the casting. The material specified for the overpack is OF (Oxygen Free) copper with 50 ppm of phosphorus added. Concentration limits have now been placed on impurity elements which are below those allowed in the OF specification. All current trials are using material from Outokompu produced from cathode on their OF(E) line, which delivers total impurity levels of less than 30 ppm excluding silver and phosphorus. The phosphorus addition is made using a master alloy added to the launder and this does not give good control of phosphorus level either within or between castings. Phosphorus is added to improve creep rates and creep strain to failure. The level is limited to 50 ppm in order to avoid difficulties, which it might

  15. Descriptive Research

    DEFF Research Database (Denmark)

    Wigram, Anthony Lewis

    2003-01-01

    Descriptive research is described by Lathom-Radocy and Radocy (1995) to include Survey research, ex post facto research, case studies and developmental studies. Descriptive research also includes a review of the literature in order to provide both quantitative and qualitative evidence of the effect...... starts will allow effect size calculations to be made in order to evaluate effect over time. Given the difficulties in undertaking controlled experimental studies in the creative arts therapies, descriptive research methods offer a way of quantifying effect through descriptive statistical analysis...

  16. Multiple Descriptions Using Sparse Decompositions

    DEFF Research Database (Denmark)

    Jensen, Tobias Lindstrøm; Østergaard, Jan; Dahl, Joachim

    2010-01-01

    In this paper, we consider the design of multiple descriptions (MDs) using sparse decompositions. In a description erasure channel only a subset of the transmitted descriptions is received. The MD problem concerns the design of the descriptions such that they individually approximate the source...... first-order method to the proposed convex problem such that we can solve large-scale instances for image sequences....

  17. Description of the Design and Implementation of a School-Based Obesity Prevention Program Addressing Needs of Middle School Students

    Science.gov (United States)

    Ward-Begnoche, Wendy L.; Gance-Cleveland, Bonnie; Harris, Margaret M.; Dean, Janice

    2008-01-01

    This article describes the design and implementation of a school-based obesity prevention program, the successes associated with its implementation, and challenges with development and application of the program's curriculum base. The program is described, including purpose and goals, content and structure of the curriculum, type and training of…

  18. [Design an educational intervention to prevent falls of older people in social housing: description of a research method].

    Science.gov (United States)

    Trevidy, Frédérique; Wolfrom, Jacques; Sebbane, Georges; Brugidou, Guillaume; Bonnetin, Denis; Gagnayre, Rémi

    2017-12-05

    In a social environment in which prevention of falls in older people has become a public health issue, adaptation of housing for older people is particularly important. Based on the home-identity concept, the objective of this research was to design an educational model specifically adapted to the context of a Social Housing Company (SHC), focussing on elderly tenants who have experienced a fall in order to allow them to adapt their lodgings and avoid subsequent falls. This article describes design-based research (DBR), which enabled the research committee (composed of professionals, tenants, and researchers) to construct the educational intervention based on analysis of the SHC context. The creation of a common approach within the research committee and the production of design-linked intentions enabled the creation of a formal intervention composed of four educational sessions, involving a private occupational therapist, an SHC social worker and a caretaker. The use of DBR can be justified by the research goal, i.e. validation of an educational model (based on the theoretical home-identity model) that can be transposed to a SHC. As this research is still underway, its quality criteria will only be partially described and will be completed by field experimentation. This exploratory study could eventually result in interventional research designed to assess this model in a multifactorial therapeutic patient education programme for older people at high risk of falls (e.g.: Personnes Âgées En Risque de Perte d'Autonomie device).

  19. A descriptive study of the barriers to study abroad in engineering undergraduate education and recommendations for program design

    Science.gov (United States)

    Klahr, Sabine Christine

    This study analyzed and compared the program designs of international exchange and internship programs for engineering students in the United States and the European Union (E.U.) as well as the extent to which these programs have removed barriers to study abroad. The purpose of this study was to provide recommendations for the design of international programs in the U.S. that would increase the proportion of engineering students who choose to study or intern abroad. Coordinators of international programs in engineering were surveyed about their perceptions of program success and a number of variables related to program design. A Chi-Square Test of Independence of (A) program success and (B) European and U.S. programs (i.e. institution location) cross-tabulated with all other variables and each other indicated those variables that contribute to the success of programs and those variables that are associated with either U.S. or European programs. In addition, all programs were described and the answers to open-ended survey questions were analyzed quantitatively. The analyses indicated that European programs tend to be more successful in implementing study/intern abroad programs for engineering students than U.S. programs. The elements of program design contributing to the greater success of European programs and the success of specific U.S. programs were described. In addition, the characteristics of overall successful programs (U.S. and E.U. data combined) were explained. The results indicated that successful programs tend to: (1) be promoted by the college and/or departments of engineering, (2) offer study/intern abroad opportunities in English-speaking settings, (3) award full credit at the home institution for required engineering courses completed at the host institution, (4) offer scholarships and financial aid for participation in the program, (5) require participating students to have completed their second year of university course work prior to applying to

  20. System design description of forced-convection molten-salt corrosion loops MSR-FCL-3 and MSR-FCL-4

    Energy Technology Data Exchange (ETDEWEB)

    Huntley, W.R.; Silverman, M.D.

    1976-11-01

    Molten-salt corrosion loops MSR-FCL-3 and MSR-FCL-4 are high-temperature test facilities designed to evaluate corrosion and mass transfer of modified Hastelloy N alloys for future use in Molten-Salt Breeder Reactors. Salt is circulated by a centrifugal sump pump to evaluate material compatibility with LiF-BeF/sub 2/-ThF/sub 4/-UF/sub 4/ fuel salt at velocities up to 6 m/s (20 fps) and at salt temperatures from 566 to 705/sup 0/C (1050 to 1300/sup 0/F). The report presents the design description of the various components and systems that make up each corrosion facility, such as the salt pump, corrosion specimens, salt piping, main heaters, salt coolers, salt sampling equipment, and helium cover-gas system, etc. The electrical systems and instrumentation and controls are described, and operational procedures, system limitations, and maintenance philosophy are discussed.

  1. System design description of forced-convection molten-salt corrosion loops MSR-FCL-3 and MSR-FCL-4

    International Nuclear Information System (INIS)

    Huntley, W.R.; Silverman, M.D.

    1976-11-01

    Molten-salt corrosion loops MSR-FCL-3 and MSR-FCL-4 are high-temperature test facilities designed to evaluate corrosion and mass transfer of modified Hastelloy N alloys for future use in Molten-Salt Breeder Reactors. Salt is circulated by a centrifugal sump pump to evaluate material compatibility with LiF-BeF 2 -ThF 4 -UF 4 fuel salt at velocities up to 6 m/s (20 fps) and at salt temperatures from 566 to 705 0 C (1050 to 1300 0 F). The report presents the design description of the various components and systems that make up each corrosion facility, such as the salt pump, corrosion specimens, salt piping, main heaters, salt coolers, salt sampling equipment, and helium cover-gas system, etc. The electrical systems and instrumentation and controls are described, and operational procedures, system limitations, and maintenance philosophy are discussed

  2. School-based peer-related social competence interventions for children with autism spectrum disorder: a meta-analysis and descriptive review of single case research design studies.

    Science.gov (United States)

    Whalon, Kelly J; Conroy, Maureen A; Martinez, Jose R; Werch, Brittany L

    2015-06-01

    The purpose of this review was to critically examine and summarize the impact of school-based interventions designed to facilitate the peer-related social competence of children with autism spectrum disorder (ASD). Reviewed studies employed a single-case experimental design, targeted peer-related social competence, included children 3-12 years old with an ASD, and took place in school settings. Articles were analyzed descriptively and using the evaluative method to determine study quality. Additionally, effect size estimates were calculated using nonoverlap of all pairs method and Tau-U. A total of 37 studies including 105 children were reviewed. Overall, ES estimates ranged from weak to strong, but on average, the reviewed interventions produced a moderate to strong effect, and quality ratings were generally in the acceptable to high range. Findings suggest that children with ASD can benefit from social skill interventions implemented with peers in school settings.

  3. System Design Description for the SY-101 Hydrogen Mitigation Test Project Data Acquisition and Control System (DACS-1)

    Energy Technology Data Exchange (ETDEWEB)

    ERMI, A.M.

    1999-08-25

    This document describes the hardware and software of the computer subsystems for the Data Acquisition and Control System (DACS) used in mitigation tests conducted on waste tank 241-SY-101 at the Hanford Nuclear Reservation, The original system was designed and implemented by LANL, supplied to WHC, and turned over to LMHC for operation. In 1999, the hardware and software were upgraded to provide a state-of-the-art, Year-2000 compliant system.

  4. Elements of power plant design for inertial fusion energy. Final report of a coordinated research project 2000-2004

    International Nuclear Information System (INIS)

    2005-06-01

    There are two major approaches in fusion energy research: magnetic fusion energy (MFE) and inertial fusion energy (IFE). The basic physics of IFE (compression and ignition of small fuel pellets containing deuterium and tritium) is being increasingly understood. Based on recent advances by individual countries, IFE has reached a stage at which benefits could be obtained from a coordinated approach in the form of an IAEA Coordinated Research Project (CRP) on Elements of Power Plant Design for Inertial Fusion Energy. This CRP helped Member States to promote the development of plasma/fusion technology transfer and to emphasize safety and environmental advantages of fusion energy. The CRP was focused on interface issues including those related to, - the driver/target interface (e.g. focusing and beam uniformity required by the target), - the driver/chamber interface (e.g. final optics and magnets protection and shielding), - and the target/chamber interface (e.g. target survival during injection, target positioning and tracking in the chamber). The final report includes an assessment of the state of the art of the technologies required for an IFE power plant (drivers, chambers, targets) and systems integration as presented and evaluated by members of the CRP. Additional contributions by cost free invited experts to the final RCM are included. The overall objective of this CRP was to foster the inertial fusion energy development by improving international cooperation. The variety of contributions compiled in this TECDOC reflects, that the goal of stimulating the exchange of knowledge was well achieved. Further the CRP led to the creation of a network, which not only exchanged their scientific results, but also developed healthy professional relations and strong mutual interest in the work of the group members

  5. Final system design document.

    Science.gov (United States)

    2009-02-01

    The Next Generation 9-1-1 (NG9-1-1) Initiative is a research and development project funded by the US Department of Transportation (USDOT) to define the framework and plan to deploy Internet Protocol (IP)-based emergency communications across the nat...

  6. A comprehensive quadratic assignment problem for an integrated layout design of final assembly line and manufacturing feeder cells

    Directory of Open Access Journals (Sweden)

    Masoud Rabbani

    2017-04-01

    Full Text Available Assembly lines and cellular manufacturing systems (CMSs design have been widely used in the literature. However the integration of these manufacturing concepts is neglected in an environment where parts need to be assembled after production in different shops. In this paper, a comprehensive quadratic assignment problem is developed for the assignment of machines of each part manufacturing cell, sub-assembly tasks of each sub-assembly cell as well as the assignment of different cells and final assembly tasks within the shop floor in their relevant predetermined locations. A genetic algorithm (GA as well as a memetic algorithm (MA consisting of the proposed GA and Tabu search (TS algorithm are proposed and implemented on different size numerical examples. The obtained results show the efficiency of both algorithms to reach near optimal solutions compared to the optimal solution of small-sized problems.

  7. A Brief Description of High Temperature Solid Oxide Fuel Cell’s Operation, Materials, Design, Fabrication Technologies and Performance

    Directory of Open Access Journals (Sweden)

    Muneeb Irshad

    2016-03-01

    Full Text Available Today’s world needs highly efficient systems that can fulfill the growing demand for energy. One of the promising solutions is the fuel cell. Solid oxide fuel cell (SOFC is considered by many developed countries as an alternative solution of energy in near future. A lot of efforts have been made during last decade to make it commercial by reducing its cost and increasing its durability. Different materials, designs and fabrication technologies have been developed and tested to make it more cost effective and stable. This article is focused on the advancements made in the field of high temperature SOFC. High temperature SOFC does not need any precious catalyst for its operation, unlike in other types of fuel cell. Different conventional and innovative materials have been discussed along with properties and effects on the performance of SOFC’s components (electrolyte anode, cathode, interconnect and sealing materials. Advancements made in the field of cell and stack design are also explored along with hurdles coming in their fabrication and performance. This article also gives an overview of methods required for the fabrication of different components of SOFC. The flexibility of SOFC in terms fuel has also been discussed. Performance of the SOFC with varying combination of electrolyte, anode, cathode and fuel is also described in this article.

  8. LIFAC demonstration at Richmond Power and Light Whitewater Valley Unit No. 2. Final report, Volume 1 - public design

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-02-01

    This report discusses the demonstration of LIFAC sorbent injection technology at Richmond Power and Light`s (RP&L) Whitewater Valley Unit No. 2 under the auspices of the U.S. Department of Energy`s (DOE) Clean Coal Technology Program. LIFAC is a sorbent injection technology capable of removing 75 to 85 percent of a power plant`s SO{sub 2} emissions using limestone at calcium to sulfur molar ratios of between 2 and 2.5. The site of the demonstration is a coal-fired electric utility power plant located in Richmond, Indiana. The project is being conducted by LIFAC North American (LIFAC NA), a joint venture partnership of Tampella Power Corporation and ICF Kaiser Engineers, in cooperation with DOE, RP&L, and several other organizations including the Electric Power Research Institute (EPRI), the State of Indiana, and Black Beauty Coal Company. The purpose of Final Report Volume 1: Public Design is to consolidate, for public use, all design and cost information regarding the LIFAC Desulfurization Facility at the completion of construction and startup.

  9. Final design, fluid dynamic and structural mechanical analysis of a liquid hydrogen Moderator for the European Spallation Source

    Science.gov (United States)

    Bessler, Y.; Henkes, C.; Hanusch, F.; Schumacher, P.; Natour, G.; Butzek, M.; Klaus, M.; Lyngh, D.; Kickulies, M.

    2017-02-01

    The European Spallation Source (ESS) is currently in the construction phase and should have first beam on Target in 2019. ESS, located in Sweden, will be the most powerful spallation neutron source worldwide, with the goal to produce neutrons for research. As an in-kind partner the Forschungszentrum Juelich will among others, design and manufacture the four liquid hydrogen Moderators, which are located above and below the Target. Those vessels are confining the cold hydrogen used to reduce the energy level of the fast neutrons, produced by spallation in the Target, in order to make the neutrons usable for neutron scattering instruments. Due to the requirements [1], a fluid dynamic analysis with pressure and temperature depended hydrogen data, taking into account the pseudo critical phenomena and the pulsed neutronic heating (pressure waves) is necessary. With the fluid dynamic results, a structure mechanical analysis including radiation damage investigation (RCC-MRx code [5]), low temperature properties as well as strength reduction by welding can be realized. Finally, the manufacturing and welding completes the design process.

  10. IER-297 CED-2: Final Design for Thermal/Epithermal eXperiments with Jemima Plates with Polyethylene and Hafnium

    Energy Technology Data Exchange (ETDEWEB)

    Nelson, A. J. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Percher, C. M. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Zywiec, W. J. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Heinrichs, D. P. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

    2018-01-11

    This report presents the final design (CED-2) for IER-297, and focuses on 15 critical configurations using highly enriched uranium (HEU) Jemima plates moderated by polyethylene with and without hafnium diluent. The goal of the U.S. Nuclear Criticality Safety Program’s Thermal/Epithermal eXperiments (TEX) is to design and conduct new critical experiments to address high priority nuclear data needs from the nuclear criticality safety and nuclear data communities, with special emphasis on intermediate energy (0.625 eV – 100 keV) assemblies that can be easily modified to include various high priority diluent materials. The TEX (IER 184) CED-1 Report [1], completed in 2012, demonstrated the feasibility of meeting the TEX goals with two existing NCSP fissile assets, plutonium Zero Power Physics Reactor (ZPPR) plates and highly enriched uranium (HEU) Jemima plates. The first set of TEX experiments will focus on using the plutonium ZPPR plates with polyethylene moderator and tantalum diluents.

  11. A descriptive, cross-sectional study of medical student preferences for vodcast design, format and pedagogical approach.

    Science.gov (United States)

    Pettit, Robin K; Kinney, Marjorie; McCoy, Lise

    2017-05-19

    Vodcasts (video podcasts) are becoming increasingly popular in medical education. At A.T. Still University School of Osteopathic Medicine in Arizona (ATSU SOMA), vodcasts are an essential component of our blended learning environment, where year 2-4 students train in a contextual setting at community health centers across the U.S. Vodcasts are used far less frequently in our year 1 residential learning environment at the main campus in Arizona, but we are considering moving to significantly more interactive educational experiences with on-demand videos followed by in-class activities. The aim of this study was to determine stakeholder (i.e. medical student) preferences for vodcast design, format, and pedagogical strategies. The overall goal was to increase opportunities for students to learn with this modality. An interactive Qualtrics™ survey was administered to three cohorts of medical students. The survey generated quantitative and open-ended response data that addressed principles of vodcast instructional design and learning. Responses to survey items were analyzed for statistical significance using the independent samples t-test for interval data, the chi-square test for categorical data, and the Kruskal-Wallis test for ordinal data, using the post-hoc Bonferroni procedure to determine the appropriate α level. Responses to open-ended prompts were categorized using open- and axial-coding. The most highly valued vodcast attributes, considered essential by all three cohorts, were clear explanations, organization, conciseness, high-yield for medical board exams, and the ability to speed vodcasts up. The least helpful vodcast attributes for all three cohorts were music and objects moving on screen. The average preferred vodcast length for each cohort was 27-28 min. There were significant differences between the less experienced learners in the residential setting and the more mature learners in the blended learning environment regarding certain vodcast

  12. Uranium Mill Tailings Remedial Action Project (UMTRAP), Slick Rock, Colorado, Revision 1. Volume 2, Calculations, Final design for construction

    International Nuclear Information System (INIS)

    1995-09-01

    Volume two contains calculations for: embankment design--slope stability analysis; embankment design--excavation stability; embankment design--settlement and cover cracking analysis; radon barrier design--statistical analysis of ra-226 concentrations for North Continent and Union Carbide sites; radon barrier design--RAECOM input data; radon barrier design--design thickness; and cover design--frost penetration depth

  13. System design description for SY-101 hydrogen mitigation test project data acquisition and control system (DACS-1)

    International Nuclear Information System (INIS)

    Truitt, R.W.; Pounds, T.S.; Smith, S.O.

    1994-01-01

    This document describes the hardware subsystems of the data acquisition and control system (DACS) used in mitigation tests conducted on waste tank SY-101 at the Hanford Nuclear Reservation. The system was designed and implemented by Los Alamos National Laboratory (LANL) and supplied to Westinghouse Hanford Company (WHC). The mitigation testing uses a pump immersed in the waste tank, directed at certain angles and operated at different speeds and time durations. The SY-101 tank has experienced recurrent periodic gas releases of hydrogen, nitrous oxide, ammonia, and (recently discovered) methane. The hydrogen gas represents a danger, as some of the releases are in amounts above the lower flammability limit (LFL). These large gas releases must be mitigated. Several instruments have been added to the tank to monitor the gas compositions, the tank level, the tank temperature, and other parameters. A mixer pump has been developed to stir the tank waste to cause the gases to be released at a slow rate. It is the function of the DACS to monitor those instruments and to control the mixer pump in a safe manner. During FY93 and FY94 the mixer pump was installed with associated testing operations support equipment and a mitigation test project plan was implemented. These activities successfully demonstrated the mixer pump's ability to mitigate the SY-101 tank hydrogen gas hazard

  14. Field test facility for monitoring water/radionuclide transport through partially saturated geologic media: design, construction, and preliminary description

    International Nuclear Information System (INIS)

    Phillips, S.J.; Campbell, A.C.; Campbell, M.D.; Gee, G.W.; Hoober, H.H.; Schwarzmiller, K.O.

    1979-11-01

    Shallow land burial has been a common practice for disposing radioactive waste materials since the beginning of plutonium production operations. Accurate monitoring of radionuclide transport and factors causing transport within the burial sites is essential to minimizing risks associated with disposal. However, monitoring has not always been adequate. Consequently, the Department of Energy (DOE) has begun a program aimed at better assuring and evaluating containment of radioactive wastes at shallow land burial sites. This program includes a technological base for monitoring transport. As part of the DOE program, Pacific Northwest Laboratory (PNL) is developing geohydrologic monitoring systems to evaluate burial sites located in arid regions. For this project, a field test facility was designed and constructed to assess monitoring systems for near-surface disposal of radioactive waste and to provide information for evaluating site containment performance. The facility is an integrated network of monitoring devices and data collection instruments. This facility is used to measure water and radionuclide migration under field conditions typical of arid regions. Monitoring systems were developed to allow for measurement of both mass and energy balance. Work on the facility is ongoing. Continuing work includes emplacement of prototype monitoring instruments, data collection, and data synthesis. At least 2 years of field data are needed to fully evaluate monitoring information

  15. Descriptive analysis of the type and design of contact lenses fitted according to keratoconus severity and morphology

    Directory of Open Access Journals (Sweden)

    Letícia Helena Lunardi

    2016-04-01

    Full Text Available ABSTRACT Purpose: Keratoconus is characterized by bilateral asymmetrical corneal ectasia that leads to inferior stromal thinning and corneal protrusion. There is currently a lack of consensus regarding the most efficacious method for fitting contact lenses in patients with keratoconus, given the various topographical patterns and evolution grades observed in affected populations. The purpose of the present study was to evaluate the association between keratoconus evolution grade and topography pattern and the type and design of fitted contact lens. Methods: We performed a retrospective analysis of contact lenses fitted in a total of 185 patients with keratoconus (325 eyes. Keratoconus was classified as either grade I, II, III, or IV based on keratometry and cone morphology (nipple, oval, globus, or indeterminate results. Results: A total of 325 eyes were evaluated in the present study. Of the 62 eyes classified as grade I, 66.1% were fitted with monocurve contact lenses. Of the 162 eyes classified as grade I and II, 51%, 30%, and 19% were fitted with adapted monocurve rigid gas-permeable contact lenses (RGPCL, bicurve lenses, and others lens types, respectively. Bicurve lenses were fitted in 52.1% and 62.2% of eyes classified as grade III and IV, respectively. Of the eyes classified as grade III and IV, monocurve and bicurve RGPCL were fitted in 26% and 55%, respectively. In eyes with oval keratoconus, 45%, 35%, and 20% were fitted with monocurve lenses, bicurve lenses, and other lens types, respectively. In eyes with round cones (nipple morphology, 55%, 30%, and 15% were fitted with bicurve lenses, monocurve lenses, and other lens types, respectively. Conclusion: Monocurve RGPCL were most frequently fitted in patients with mild to moderate keratoconus and oval cones morphology, while bicurve lenses were more frequently fitted in patients with severe and advanced keratoconus. This was probably because bicurve lenses are more appropriate for

  16. Design

    DEFF Research Database (Denmark)

    Jensen, Ole B.; Pettiway, Keon

    2017-01-01

    by designers, planners, etc. (staging from above) and mobile subjects (staging from below). A research agenda for studying situated practices of mobility and mobilities design is outlined in three directions: foci of studies, methods and approaches, and epistemologies and frames of thinking. Jensen begins......In this chapter, Ole B. Jensen takes a situational approach to mobilities to examine how ordinary life activities are structured by technology and design. Using “staging mobilities” as a theoretical approach, Jensen considers mobilities as overlapping, actions, interactions and decisions...... with a brief description of how movement is studied within social sciences after the “mobilities turn” versus the idea of physical movement in transport geography and engineering. He then explains how “mobilities design” was derived from connections between traffic and architecture. Jensen concludes...

  17. A near-peer teaching program designed, developed and delivered exclusively by recent medical graduates for final year medical students sitting the final objective structured clinical examination (OSCE

    Directory of Open Access Journals (Sweden)

    Sobowale Oluwaseun

    2011-03-01

    Full Text Available Abstract Background The General Medical Council states that teaching doctors and students is important for the care of patients. Our aim was to deliver a structured teaching program to final year medical students, evaluate the efficacy of teaching given by junior doctors and review the pertinent literature. Methods We developed a revision package for final year medical students sitting the Objective Structured Clinical Examination (OSCE. The package was created and delivered exclusively by recent medical graduates and consisted of lectures and small group seminars covering the core areas of medicine and surgery, with a focus on specific OSCE station examples. Students were asked to complete a feedback questionnaire during and immediately after the program. Results One hundred and eighteen completed feedback questionnaires were analysed. All participants stated that the content covered was relevant to their revision. 73.2% stated that junior doctors delivered teaching that is comparable to that of consultant - led teaching. 97.9% stated the revision course had a positive influence on their learning. Conclusions Our study showed that recent medical graduates are able to create and deliver a structured, formal revision program and provide a unique perspective to exam preparation that was very well received by our student cohort. The role of junior doctors teaching medical students in a formal structured environment is very valuable and should be encouraged.

  18. W.A. Parish Post Combustion CO2 Capture and Sequestration Project Final Public Design Report

    Energy Technology Data Exchange (ETDEWEB)

    Armpriester, Anthony [Petra Nova Parish Holdings, Washington, DC (United States)

    2017-02-17

    The Petra Nova Project is a commercial scale post-combustion carbon dioxide capture project that is being developed by a joint venture between NRG Energy (NRG) and JX Nippon Oil and Gas Exploration (JX). The project is designed to separate and capture carbon dioxide from an existing coal-fired unit's flue gas slipstream at NRG's W.A. Parish Generation Station located southwest of Houston, Texas. The captured carbon dioxide will be transported by pipeline and injected into the West Ranch oil field to boost oil production. The project, which is partially funded by financial assistance from the U.S. Department of Energy will use Mitsubishi Heavy Industries of America, Inc.'s Kansai Mitsubishi Carbon Dioxide Recovery (KM-CDR(R)) advanced amine-based carbon dioxide absorption technology to treat and capture at least 90% of the carbon dioxide from a 240 megawatt equivalent flue gas slipstream off of Unit 8 at W.A. Parish. The project will capture approximately 5,000 tons of carbon dioxide per day or 1.5 million tons per year that Unit 8 would otherwise emit, representing the largest commercial scale deployment of post-combustion carbon dioxide capture at a coal power plant to date. The joint venture issued full notice to proceed in July 2014 and when complete, the project is expected to be the world's largest post-combustion carbon dioxide capture facility on an existing coal plant. The detailed engineering is sufficiently complete to prepare and issue the Final Public Design Report.

  19. 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.

  20. Design and Evaluation of a Clock Multiplexing Circuit for the SSRL Booster Accelerator Timing System - Final Paper

    Energy Technology Data Exchange (ETDEWEB)

    Araya, Million

    2015-08-21

    SPEAR3 is a 234 m circular storage ring at SLAC’s synchrotron radiation facility (SSRL) in which a 3 GeV electron beam is stored for user access. Typically the electron beam decays with a time constant of approximately 10hr due to electron lose. In order to replenish the lost electrons, a booster synchrotron is used to accelerate fresh electrons up to 3GeV for injection into SPEAR3. In order to maintain a constant electron beam current of 500mA, the injection process occurs at 5 minute intervals. At these times the booster synchrotron accelerates electrons for injection at a 10Hz rate. A 10Hz 'injection ready' clock pulse train is generated when the booster synchrotron is operating. Between injection intervals-where the booster is not running and hence the 10 Hz ‘injection ready’ signal is not present-a 10Hz clock is derived from the power line supplied by Pacific Gas and Electric (PG&E) to keep track of the injection timing. For this project I constructed a multiplexing circuit to 'switch' between the booster synchrotron 'injection ready' clock signal and PG&E based clock signal. The circuit uses digital IC components and is capable of making glitch-free transitions between the two clocks. This report details construction of a prototype multiplexing circuit including test results and suggests improvement opportunities for the final design.

  1. CANISTER HANDLING FACILITY DESCRIPTION DOCUMENT

    International Nuclear Information System (INIS)

    Beesley. J.F.

    2005-01-01

    The purpose of this facility description document (FDD) is to establish requirements and associated bases that drive the design of the Canister Handling Facility (CHF), which will allow the design effort to proceed to license application. This FDD will be revised at strategic points as the design matures. This FDD identifies the requirements and describes the facility design, as it currently exists, with emphasis on attributes of the design provided to meet the requirements. This FDD is an engineering tool for design control; accordingly, the primary audience and users are design engineers. This FDD is part of an iterative design process. It leads the design process with regard to the flowdown of upper tier requirements onto the facility. Knowledge of these requirements is essential in performing the design process. The FDD follows the design with regard to the description of the facility. The description provided in this FDD reflects the current results of the design process

  2. CANISTER HANDLING FACILITY DESCRIPTION DOCUMENT

    Energy Technology Data Exchange (ETDEWEB)

    J.F. Beesley

    2005-04-21

    The purpose of this facility description document (FDD) is to establish requirements and associated bases that drive the design of the Canister Handling Facility (CHF), which will allow the design effort to proceed to license application. This FDD will be revised at strategic points as the design matures. This FDD identifies the requirements and describes the facility design, as it currently exists, with emphasis on attributes of the design provided to meet the requirements. This FDD is an engineering tool for design control; accordingly, the primary audience and users are design engineers. This FDD is part of an iterative design process. It leads the design process with regard to the flowdown of upper tier requirements onto the facility. Knowledge of these requirements is essential in performing the design process. The FDD follows the design with regard to the description of the facility. The description provided in this FDD reflects the current results of the design process.

  3. Fuel Handling Facility Description Document

    International Nuclear Information System (INIS)

    M.A. LaFountain

    2005-01-01

    The purpose of the facility description document (FDD) is to establish the requirements and their bases that drive the design of the Fuel Handling Facility (FHF) to allow the design effort to proceed to license application. This FDD is a living document that will be revised at strategic points as the design matures. It identifies the requirements and describes the facility design as it currently exists, with emphasis on design attributes provided to meet the requirements. This FDD was developed as an engineering tool for design control. Accordingly, the primary audience and users are design engineers. It leads the design process with regard to the flow down of upper tier requirements onto the facility. Knowledge of these requirements is essential to performing the design process. It trails the design with regard to the description of the facility. This description is a reflection of the results of the design process to date

  4. Solar production of intermediate temperature process heat. Phase I design. Final report. [For sugarcane processing plant in Hawaii

    Energy Technology Data Exchange (ETDEWEB)

    None

    1980-08-01

    This report is the final effort in the Phase I design of a solar industrial process heat system for the Hilo Coast Processing Company (HCPC) in Pepeekeo, Hawaii. The facility is used to wash, grind and extract sugar from the locally grown sugarcane and it operates 24 hours a day, 305 days per year. The major steam requirements in the industrial process are for the prime movers (mill turbines) in the milling process and heat for evaporating water from the extracted juices. Bagasse (the fibrous residue of milled sugarcane) supplied 84% of the fuel requirement for steam generation in 1979, while 65,000 barrels of No. 6 industrial fuel oil made up the remaining 16%. These fuels are burned in the power plant complex which produces 825/sup 0/F, 1,250 psi superheated steam to power a turbogenerator set which, in addition to serving the factory, generates from 7 to 16 megawatts of electricity that is exported to the local utility company. Extracted steam from the turbo-generator set supplies the plant's process steam needs. The system consists of 42,420 ft./sup 2/ of parabolic trough, single axis tracking, concentrating solar collectors. The collectors will be oriented in a North-South configuration and will track East-West. A heat transfer fluid (Gulf Synfluid 4cs) will be circulated in a closed loop fashion through the solar collectors and a series of heat exchangers. The inlet and outlet fluid temperatures for the collectors are 370/sup 0/F and 450/sup 0/F respectively. It is estimated that the net useable energy delivered to the industrial process will be 7.2 x 10/sup 9/ Btu's per year. With an HCPC boiler efficiency of 78% and 6.2 x 10/sup 6/ Btu's per barrel of oil, the solar energy system will displace 1489 barrels of oil per year. (WHK)

  5. SNAP-21 program, Phase II. Deep sea radioisotope-fueled thermoelectric generator power supply system. Final design description, 10-watt system

    Energy Technology Data Exchange (ETDEWEB)

    Wickenberg, R.F.; Harris, W.W.

    1969-10-01

    The SNAP-21 10-W system provides electrical power for use under the surface of the sea. It functions by converting the heat from a decaying radioisotope fuel into useful electrical energy. This heat energy is converted into electrical energy by a thermoelectric generator. Semiconductor-type thermoelectric materials, maintained in a temperature gradient, accomplish the conversion. The isotopic fuel supplies heat to the thermoelectric materials and sea water acts as the heat sink to maintain the temperature gradient. Other components are employed to increase efficiency and condition the electrical output to the desired form. The components performing these functions are enclosed in a pressure vessel which protects them from sea water pressure and exposure. No external inputs are required to maintain operation of the system. With this type of mechanically-static, unsupported operation, long life with no maintenance is achieved.

  6. Resource Description Framework (RDF)

    OpenAIRE

    Gibbins, Nicholas; Shadbolt, Nigel

    2009-01-01

    The Resource Description Framework (RDF) is the standard knowledge representation language for the Semantic Web, an evolution of the World Wide Web that aims to provide a well-founded infrastructure for publishing, sharing and querying structured data. This article provides an introduction to RDF and its related vocabulary definition language RDF Schema, and explains its relationship with the OWL Web Ontology Language. Finally, it provides an overview of the historical development of RDF and ...

  7. MCFire model technical description

    Science.gov (United States)

    David R. Conklin; James M. Lenihan; Dominique Bachelet; Ronald P. Neilson; John B. Kim

    2016-01-01

    MCFire is a computer program that simulates the occurrence and effects of wildfire on natural vegetation, as a submodel within the MC1 dynamic global vegetation model. This report is a technical description of the algorithms and parameter values used in MCFire, intended to encapsulate its design and features a higher level that is more conceptual than the level...

  8. Design

    DEFF Research Database (Denmark)

    Jensen, Ole B.; Pettiway, Keon

    2017-01-01

    In this chapter, Ole B. Jensen takes a situational approach to mobilities to examine how ordinary life activities are structured by technology and design. Using “staging mobilities” as a theoretical approach, Jensen considers mobilities as overlapping, actions, interactions and decisions by desig......In this chapter, Ole B. Jensen takes a situational approach to mobilities to examine how ordinary life activities are structured by technology and design. Using “staging mobilities” as a theoretical approach, Jensen considers mobilities as overlapping, actions, interactions and decisions...... by designers, planners, etc. (staging from above) and mobile subjects (staging from below). A research agenda for studying situated practices of mobility and mobilities design is outlined in three directions: foci of studies, methods and approaches, and epistemologies and frames of thinking. Jensen begins...... with a brief description of how movement is studied within social sciences after the “mobilities turn” versus the idea of physical movement in transport geography and engineering. He then explains how “mobilities design” was derived from connections between traffic and architecture. Jensen concludes...

  9. Analytical functions used for description of the plastic deformation process in Zirconium alloys WWER type fuel rod cladding under designed accident conditions

    International Nuclear Information System (INIS)

    Fedotov, A.

    2003-01-01

    The aim of this work was to improve the RAPTA-5 code as applied to the analysis of the thermomechanical behavior of the fuel rod cladding under designed accident conditions. The irreversible process thermodynamics methods were proposed to be used for the description of the plastic deformation process in zirconium alloys under accident conditions. Functions, which describe yielding stress dependence on plastic strain, strain rate and temperature may be successfully used in calculations. On the basis of the experiments made and the existent experimental data the dependence of yielding stress on plastic strain, strain rate, temperature and heating rate for E110 alloy was determined. In future the following research work shall be made: research of dynamic strain ageing in E635 alloy under different strain rates; research of strain rate influence on plastic strain in E635 alloy under test temperature higher than 873 K; research of deformation strengthening of E635 alloy under high temperatures; research of heating rate influence n phase transformation in E110 and E635 alloys

  10. Pharmacogenetic study of second-generation antipsychotic long-term treatment metabolic side effects (the SLiM Study): rationale, objectives, design and sample description.

    Science.gov (United States)

    Pina-Camacho, Laura; Díaz-Caneja, Covadonga M; Saiz, Pilar A; Bobes, Julio; Corripio, Iluminada; Grasa, Eva; Rodriguez-Jimenez, Roberto; Fernández, Miryam; Sanjuán, Julio; García-López, Aurelio; Tapia-Casellas, Cecilia; Álvarez-Blázquez, María; Fraguas, David; Mitjans, Marina; Arias, Bárbara; Arango, Celso

    2014-01-01

    Weight gain is an important and common side effect of second generation antipsychotics (SGAs). Furthermore, these drugs can induce other side effects associated with higher cardiovascular morbidity and mortality, such as insulin resistance, diabetes or metabolic syndrome. Preliminary studies show that inter-individual genetic differences produce varying degrees of vulnerability to the different SGA-induced side effects. The Second-generation antipsychotic Long-term treatment Metabolic side effects (SLiM) study aims to identify clinical, environmental and genetic factors that explain inter-individual differences in weight gain and metabolic changes in drug-naïve patients after six months of treatment with SGAs. The SLIM study is a multicenter, observational, six-month pharmacogenetic study where a cohort of 307 drug-naïve paediatric and adult patients (age range 8.8-90.1 years) and a cohort of 150 age- and sex- matched healthy controls (7.8-73.2 years) were recruited. This paper describes the rationale, objectives and design of the study and provides a description of the sample at baseline. Results from the SLiM study will provide a better understanding of the clinical, environmental, and genetic factors involved in weight gain and metabolic disturbances associated with SGA treatment. Copyright © 2014 SEP y SEPB. Published by Elsevier España. All rights reserved.

  11. Nursing students' evaluation of a new feedback and reflection tool for use in high-fidelity simulation - Formative assessment of clinical skills. A descriptive quantitative research design.

    Science.gov (United States)

    Solheim, Elisabeth; Plathe, Hilde Syvertsen; Eide, Hilde

    2017-11-01

    Clinical skills training is an important part of nurses' education programmes. Clinical skills are complex. A common understanding of what characterizes clinical skills and learning outcomes needs to be established. The aim of the study was to develop and evaluate a new reflection and feedback tool for formative assessment. The study has a descriptive quantitative design. 129 students participated who were at the end of the first year of a Bachelor degree in nursing. After highfidelity simulation, data were collected using a questionnaire with 19 closed-ended and 2 open-ended questions. The tool stimulated peer assessment, and enabled students to be more thorough in what to assess as an observer in clinical skills. The tool provided a structure for selfassessment and made visible items that are important to be aware of in clinical skills. This article adds to simulation literature and provides a tool that is useful in enhancing peer learning, which is essential for nurses in practice. The tool has potential for enabling students to learn about reflection and developing skills for guiding others in practice after they have graduated. Copyright © 2017 Elsevier Ltd. All rights reserved.

  12. Programmable Logic Device (PLD) Design Description for the Integrated Power, Avionics, and Software (iPAS) Space Telecommunications Radio System (STRS) Radio

    Science.gov (United States)

    Shalkhauser, Mary Jo W.

    2017-01-01

    The Space Telecommunications Radio System (STRS) provides a common, consistent framework for software defined radios (SDRs) to abstract the application software from the radio platform hardware. The STRS standard aims to reduce the cost and risk of using complex, configurable and reprogrammable radio systems across NASA missions. To promote the use of the STRS architecture for future NASA advanced exploration missions, NASA Glenn Research Center (GRC) developed an STRS compliant SDR on a radio platform used by the Advance Exploration System program at the Johnson Space Center (JSC) in their Integrated Power, Avionics, and Software (iPAS) laboratory. At the conclusion of the development, the software and hardware description language (HDL) code was delivered to JSC for their use in their iPAS test bed to get hands-on experience with the STRS standard, and for development of their own STRS Waveforms on the now STRS compliant platform.The iPAS STRS Radio was implemented on the Reconfigurable, Intelligently-Adaptive Communication System (RIACS) platform, currently being used for radio development at JSC. The platform consists of a Xilinx ML605 Virtex-6 FPGA board, an Analog Devices FMCOMMS1-EBZ RF transceiver board, and an Embedded PC (Axiomtek eBox 620-110-FL) running the Ubuntu 12.4 operating system. Figure 1 shows the RIACS platform hardware. The result of this development is a very low cost STRS compliant platform that can be used for waveform developments for multiple applications.The purpose of this document is to describe the design of the HDL code for the FPGA portion of the iPAS STRS Radio particularly the design of the FPGA wrapper and the test waveform.

  13. Conceptual design of advanced central receiver power systems sodium-cooled receiver concept. Volume 2, Book 2. Appendices. Final report

    Energy Technology Data Exchange (ETDEWEB)

    1979-03-01

    The appendices include: (A) design data sheets and P and I drawing for 100-MWe commercial plant design, for all-sodium storage concept; (B) design data sheets and P and I drawing for 100-MWe commercial plant design, for air-rock bed storage concept; (C) electric power generating water-steam system P and I drawing and equipment list, 100-MWe commercial plant design; (D) design data sheets and P and I drawing for 281-MWe commercial plant design; (E) steam generator system conceptual design; (F) heat losses from solar receiver surface; (G) heat transfer and pressure drop for rock bed thermal storage; (H) a comparison of alternative ways of recovering the hydraulic head from the advanced solar receiver tower; (I) central receiver tower study; (J) a comparison of mechanical and electromagnetic sodium pumps; (K) pipe routing study of sodium downcomer; and (L) sodium-cooled advanced central receiver system simulation model. (WHK)

  14. Human factors methods for nuclear control room design. Volume I. Human factors enhancement of existing nuclear control rooms. Final report

    International Nuclear Information System (INIS)

    Seminara, J.L.; Seidenstein, S.; Eckert, S.K.; Smith, D.L.

    1979-11-01

    Human factors engineering is an interdisciplinary specialty concerned with influencing the design of equipment systems, facilities, and operational environments to promote safe, efficient, and reliable operator performance. Human factors approaches were applied in the design of representative nuclear power plant control panels. First, methods for upgrading existing operational control panels were examined. Then, based on detailed human factors analyses of operator information and control requirements, designs of reactor, feedwater, and turbine-generator control panels were developed to improve the operator-control board interface, thereby reducing the potential for operator errors. In addition to examining present-generation concepts, human factors aspects of advanced systems and of hybrid combinations of advanced and conventional designs were investigated. Special attention was given to warning system designs. Also, a survey was conducted among control board designers to (1) develop an overview of design practices in the industry, and (2) establish appropriate measures leading to a more systematic concern for human factors in control board design

  15. Review and assessment of research relevant to design aspects of nuclear power plant piping systems. Final report

    International Nuclear Information System (INIS)

    Rodabaugh, E.C.; Maxey, W.A.; Eiber, R.J.

    1977-06-01

    Significant research on piping systems is evaluated, and the correlation of that research with design practices is presented. The objective is to quantify the research/design practices in terms of the reliability of piping used in nuclear power plants

  16. A static analysis method for barge-impact design of bridges with consideration of dynamic amplification : final report, November 2009.

    Science.gov (United States)

    2009-11-01

    Current practice with regard to designing bridge structures to resist impact loads associated with barge collisions relies upon the : use of the American Association of State Highway and Transportation Officials (AASHTO) bridge design specifications....

  17. 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

  18. 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.

  19. Dental devices: classification of dental amalgam, reclassification of dental mercury, designation of special controls for dental amalgam, mercury, and amalgam alloy; technical amendment. Final rule; technical amendment.

    Science.gov (United States)

    2010-06-11

    The Food and Drug Administration (FDA) published a final rule in the Federal Register of August 4, 2009 (74 FR 38686) which classified dental amalgam as a class II device, reclassified dental mercury from class I to class II, and designated special controls for dental amalgam, mercury, and amalgam alloy. The effective date of the rule was November 2, 2009. The final rule was published with an inadvertent error in the codified section. This document corrects that error. This action is being taken to ensure the accuracy of the agency's regulations.

  20. Olkiluoto site description 2004

    International Nuclear Information System (INIS)

    2005-05-01

    This Olkiluoto Site Description 2004 is a description of the Olkiluoto site, in which the various disciplines have been integrated to produce a coherent picture, and is based on the data available prior to the start of the underground excavation of the ONKALO facility. This report is the first version of such a Site Report and supplements the site syntheses that have already been published. Further Site Reports will be produced on a regular basis and it is planned that the Site Report should form the geoscientific basis of the Safety Case in a future licence application. The report updates the Baseline report published in 2003 and is designed to produce an integrated site model, by focusing on interdisciplinary interactions, and also by including new data obtained during 2003 and 2004. The report has been produced by the OMTF (Olkiluoto Modelling Task Force), which covers the areas of geology, rock mechanics, hydrogeology and hydrogeochemistry. In addition to discussing the input from these four disciplines, the Site Report also includes a description of the surface conditions. Formally, the surface conditions are not within the remit of the OMTF, which is concentrating on modelling the bedrock around the ONKALO and the future repository. The influence of the surface conditions to the overall system and to the conditions at depth is recognised, however, and thus a summary of climate, ecosystems and overburden properties is also included in this report. Chapter 1 sets out the methodology to be used in the modelling, describes the various discipline-specific models which are developed and the modelled areas which are used, and also describes two important processes - the prediction/outcome studies and the uncertainty and confidence assessment. The difference between the estimate (the prediction) and the result (the outcome) indicates the level of knowledge and the prevailing uncertainties in the models. Chapter 2 presents the applied investigation data, which are

  1. New Concepts in Fish Ladder Design, Part I of IV, Summary Report, 1982-1984 Final Project Report.

    Energy Technology Data Exchange (ETDEWEB)

    Orsborn, John F.

    1985-08-01

    The report looks at the most active periods of fishway research since 1938 as background for a project to apply fundamental fluid and bio-mechanics to fishway design, and develop more cost effective fish passage facilities with primary application to small scale hydropower facilities. Also discussed are new concepts in fishway design, an assessment of fishway development and design, and an analysis of barriers to upstream migration. (ACR)

  2. 77 FR 24451 - Direct Final Approval of Hospital/Medical/Infectious Waste Incinerators State Plan for Designated...

    Science.gov (United States)

    2012-04-24

    ... FURTHER INFORMATION CONTACT: Margaret Sieffert, Environmental Engineer, Environmental Protection Agency... ENVIRONMENTAL PROTECTION AGENCY 40 CFR Part 62 [EPA-R05-OAR-2012-0087; FRL-9663-5] Direct Final... Pollutants: Illinois AGENCY: Environmental Protection Agency (EPA). ACTION: Proposed rule. SUMMARY: EPA is...

  3. Final safety evaluation report related to the certification of the advanced boiling water reactor design. Volume 1: Main report

    Energy Technology Data Exchange (ETDEWEB)

    1994-07-01

    This safety evaluation report (SER) documents the technical review of the US Advanced Boiling Water Reactor (ABWR) standard design by the US Nuclear Regulatory Commission (NRC) staff. The application for the ABWR design was initially submitted by the General Electric Company, now GE Nuclear Energy (GE), in accordance with the procedures of Appendix O of Part 50 of Title 10 of the Code of Federal Regulations (10 CFR Part 50). Later GE requested that its application be considered as an application for design approval and subsequent design certification pursuant to 10 CFR {section} 52.45. The ABWR is a single-cycle, forced-circulation, boiling water reactor (BWR) with a rated power of 3,926 megawatts thermal (MWt) and a design power of 4,005 MWt. To the extent feasible and appropriate, the staff relied on earlier reviews for those ABWR design features that are substantially the same as those previously considered. Unique features of the ABWR design include internal recirculation pumps, fine-motion control rod drives, microprocessor-based digital logic and control systems, and digital safety systems. On the basis of its evaluation and independent analyses, the NRC staff concludes that, subject to satisfactory resolution of the confirmatory items identified in Section 1.8 of this SER, GE`s application for design certification meets the requirements of Subpart B of 10 CFR Part 52 that are applicable and technically relevant to the US ABWR standard design.

  4. Final safety evaluation report related to the certification of the advanced boiling water reactor design. Volume 2: Appendices

    Energy Technology Data Exchange (ETDEWEB)

    1994-07-01

    This safety evaluation report (SER) documents the technical review of the US Advanced Boiling Water Reactor (ABWR) standard design by the US Nuclear Regulatory Commission (NRC) staff. The application for the ABWR design was initially submitted by the General Electric Company, now GE Nuclear Energy (GE), in accordance with the procedures of Appendix O of Part 50 of Title 10 of the code of Federal Regulations (10 CFR Part 50). Later GE requested that its application be considered as an application for design approval and subsequent design certification pursuant to 10 CFR {section} 52.45. The ABWR is a single-cycle, forced-circulation, boiling water reactor (BWR) with a rated power of 3,926 megawatts thermal (MWt) and a design power of 4,005 MWt. To the extent feasible and appropriate, the staff relied on earlier reviews for those ABWR design features that are substantially the same as those previously considered. Unique features of the ABWR design include internal recirculation pumps, fine-motion control rod drives, microprocessor-based digital logic and control systems, and digital safety systems. On the basis of its evaluation and independent analyses, the NRC staff concludes that, subject to satisfactory resolution of the confirmatory items identified in Section 1.8 of this SER, GE`s application for design certification meets the requirements of Subpart B of 10 CFR Part 52 that are applicable and technically relevant to the US ABWR standard design.

  5. Final safety evaluation report related to the certification of the advanced boiling water reactor design. Volume 2: Appendices

    International Nuclear Information System (INIS)

    1994-07-01

    This safety evaluation report (SER) documents the technical review of the US Advanced Boiling Water Reactor (ABWR) standard design by the US Nuclear Regulatory Commission (NRC) staff. The application for the ABWR design was initially submitted by the General Electric Company, now GE Nuclear Energy (GE), in accordance with the procedures of Appendix O of Part 50 of Title 10 of the code of Federal Regulations (10 CFR Part 50). Later GE requested that its application be considered as an application for design approval and subsequent design certification pursuant to 10 CFR section 52.45. The ABWR is a single-cycle, forced-circulation, boiling water reactor (BWR) with a rated power of 3,926 megawatts thermal (MWt) and a design power of 4,005 MWt. To the extent feasible and appropriate, the staff relied on earlier reviews for those ABWR design features that are substantially the same as those previously considered. Unique features of the ABWR design include internal recirculation pumps, fine-motion control rod drives, microprocessor-based digital logic and control systems, and digital safety systems. On the basis of its evaluation and independent analyses, the NRC staff concludes that, subject to satisfactory resolution of the confirmatory items identified in Section 1.8 of this SER, GE's application for design certification meets the requirements of Subpart B of 10 CFR Part 52 that are applicable and technically relevant to the US ABWR standard design

  6. Final safety evaluation report related to the certification of the advanced boiling water reactor design. Volume 1: Main report

    International Nuclear Information System (INIS)

    1994-07-01

    This safety evaluation report (SER) documents the technical review of the US Advanced Boiling Water Reactor (ABWR) standard design by the US Nuclear Regulatory Commission (NRC) staff. The application for the ABWR design was initially submitted by the General Electric Company, now GE Nuclear Energy (GE), in accordance with the procedures of Appendix O of Part 50 of Title 10 of the Code of Federal Regulations (10 CFR Part 50). Later GE requested that its application be considered as an application for design approval and subsequent design certification pursuant to 10 CFR section 52.45. The ABWR is a single-cycle, forced-circulation, boiling water reactor (BWR) with a rated power of 3,926 megawatts thermal (MWt) and a design power of 4,005 MWt. To the extent feasible and appropriate, the staff relied on earlier reviews for those ABWR design features that are substantially the same as those previously considered. Unique features of the ABWR design include internal recirculation pumps, fine-motion control rod drives, microprocessor-based digital logic and control systems, and digital safety systems. On the basis of its evaluation and independent analyses, the NRC staff concludes that, subject to satisfactory resolution of the confirmatory items identified in Section 1.8 of this SER, GE's application for design certification meets the requirements of Subpart B of 10 CFR Part 52 that are applicable and technically relevant to the US ABWR standard design

  7. Multidimensional nonlinear descriptive analysis

    CERN Document Server

    Nishisato, Shizuhiko

    2006-01-01

    Quantification of categorical, or non-numerical, data is a problem that scientists face across a wide range of disciplines. Exploring data analysis in various areas of research, such as the social sciences and biology, Multidimensional Nonlinear Descriptive Analysis presents methods for analyzing categorical data that are not necessarily sampled randomly from a normal population and often involve nonlinear relations. This reference not only provides an overview of multidimensional nonlinear descriptive analysis (MUNDA) of discrete data, it also offers new results in a variety of fields. The first part of the book covers conceptual and technical preliminaries needed to understand the data analysis in subsequent chapters. The next two parts contain applications of MUNDA to diverse data types, with each chapter devoted to one type of categorical data, a brief historical comment, and basic skills peculiar to the data types. The final part examines several problems and then concludes with suggestions for futu...

  8. Human-system interface design review guideline -- Reviewer`s checklist: Final report. Revision 1, Volume 2

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-06-01

    NUREG-0700, Revision 1, provides human factors engineering (HFE) guidance to the US Nuclear Regulatory Commission staff for its: (1) review of the human system interface (HSI) design submittals prepared by licensees or applications for a license or design certification of commercial nuclear power plants, and (2) performance of HSI reviews that could be undertaken as part of an inspection or other type of regulatory review involving HSI design or incidents involving human performance. The guidance consists of a review process and HFE guidelines. The document describes those aspects of the HSI design review process that are important to the identification and resolution of human engineering discrepancies that could adversely affect plant safety. Guidance is provided that could be used by the staff to review an applicant`s HSI design review process or to guide the development of an HSI design review plan, e.g., as part of an inspection activity. The document also provides detailed HFE guidelines for the assessment of HSI design implementations. NUREG-0700, Revision 1, consists of three stand-alone volumes. Volume 2 is a complete set of the guidelines contained in Volume 1, Part 2, but in a checklist format that can be used by reviewers to assemble sets of individual guidelines for use in specific design reviews. The checklist provides space for reviewers to enter guidelines evaluations and comments.

  9. Ocean thermal energy conversion power system development-I. Phase I. Preliminary design report. Volume 1. Final report

    Energy Technology Data Exchange (ETDEWEB)

    1978-12-18

    The results of a conceptual and preliminary design study of Ocean Thermal Energy Conversion (OTEC) closed loop ammonia power system modules performed by Lockheed Missiles and Space Company, Inc. (LMSC) are presented. This design study is the second of 3 tasks in Phase I of the Power System Development-I Project. The Task 2 objectives were to develop: 1) conceptual designs for a 40 to 50-MW(e) closed cycle ammonia commercial plant size power module whose heat exchangers are immersed in seawater and whose ancillary equipments are in a shirt sleeve environment; preliminary designs for a modular application power system sized at 10-MW(e) whose design, construction and material selection is analogous to the 50 MW(e) module, except that titanium tubes are to be used in the heat exchangers; and 3) preliminary designs for heat exchanger test articles (evaporator and condenser) representative of the 50-MW(e) heat exchangers using aluminum alloy, suitable for seawater service, for testing on OTEC-1. The reference ocean platform was specified by DOE as a surface vessel with the heat exchanger immersed in seawater to a design depth of 0 to 20 ft measured from the top of the heat exchanger. For the 50-MW(e) module, the OTEC 400-MW(e) Plant Ship, defined in the Platform Configuration and Integration study, was used as the reference platform. System design, performance, and cost are presented. (WHK)

  10. SOLERAS - Solar Controlled Environment Agriculture Project. Final report, Volume 4. Saudi Engineering Solar Energy Applications System Design Study

    Energy Technology Data Exchange (ETDEWEB)

    1985-01-01

    Literature summarizing a study on the Saudi Arabian solar controlled environment agriculture system is presented. Specifications and performance requirements for the system components are revealed. Detailed performance and cost analyses are used to determine the optimum design. A preliminary design of an engineering field test is included. Some weather data are provided for Riyadh, Saudi Arabia. (BCS)

  11. Human-system interface design review guideline -- Review software and user's guide: Final report. Revision 1, Volume 3

    International Nuclear Information System (INIS)

    1996-06-01

    NUREG-0700, Revision 1, provides human factors engineering (HFE) guidance to the US Nuclear Regulatory Commission staff for its: (1) review of the human system interface (HSI) design submittals prepared by licensees or applications for a license or design certification of commercial nuclear power plants, and (2) performance of HSI reviews that could be undertaken as part of an inspection or other type of regulatory review involving HSI design or incidents involving human performance. The guidance consists of a review process and HFE guidelines. The document describes those aspects of the HSI design review process that are important to the identification and resolution of human engineering discrepancies that could adversely affect plant safety. Guidance is provided that could be used by the staff to review an applicant's HSI design review process or to guide the development of an HSI design review plan, e.g., as part of an inspection activity. The document also provides detailed HFE guidelines for the assessment of HSI design implementations. NUREG-0700, Revision 1, consists of three stand-alone volumes. Volume 3 contains an interactive software application of the NUREG-0700, Revision 1 guidance and a user's guide for this software. The software supports reviewers during review preparation, evaluation design using the human factors engineering guidelines, and in report preparation. The user's guide provides system requirements and installation instructions, detailed explanations of the software's functions and features, and a tutorial on using the software

  12. The Standard for Clinicians’ Interview in Psychiatry (SCIP): A Clinician-administered Tool with Categorical, Dimensional, and Numeric Output—Conceptual Development, Design, and Description of the SCIP

    Science.gov (United States)

    Nasrallah, Henry; Muvvala, Srinivas; El-Missiry, Ahmed; Mansour, Hader; Hill, Cheryl; Elswick, Daniel; Price, Elizabeth C.

    2016-01-01

    Existing standardized diagnostic interviews (SDIs) were designed for researchers and produce mainly categorical diagnoses. There is an urgent need for a clinician-administered tool that produces dimensional measures, in addition to categorical diagnoses. The Standard for Clinicians’ Interview in Psychiatry (SCIP) is a method of assessment of psychopathology for adults. It is designed to be administered by clinicians and includes the SCIP manual and the SCIP interview. Clinicians use the SCIP questions and rate the responses according to the SCIP manual rules. Clinicians use the patient’s responses to questions, observe the patient’s behaviors and make the final rating of the various signs and symptoms assessed. The SCIP method of psychiatric assessment has three components: 1) the SCIP interview (dimensional) component, 2) the etiological component, and 3) the disorder classification component. The SCIP produces three main categories of clinical data: 1) a diagnostic classification of psychiatric disorders, 2) dimensional scores, and 3) numeric data. The SCIP provides diagnoses consistent with criteria from editions of the Diagnostic and Statistical Manual (DSM) and International Classification of Disease (ICD). The SCIP produces 18 dimensional measures for key psychiatric signs or symptoms: anxiety, posttraumatic stress, obsessions, compulsions, depression, mania, suicidality, suicidal behavior, delusions, hallucinations, agitation, disorganized behavior, negativity, catatonia, alcohol addiction, drug addiction, attention, and hyperactivity. The SCIP produces numeric severity data for use in either clinical care or research. The SCIP was shown to be a valid and reliable assessment tool, and the validity and reliability results were published in 2014 and 2015. The SCIP is compatible with personalized psychiatry research and is in line with the Research Domain Criteria framework. PMID:27800284

  13. Final safety evaluation report related to the certification of the System 80{sup +} design (Docket No. 52-002). Volume 2, Chapters 15--22 and appendices

    Energy Technology Data Exchange (ETDEWEB)

    1994-08-01

    This final safety evaluation report (FSER) documents the technical review of the System 80+ standard design by the US Nuclear Regulatory Commission (NRC) staff. The application for the system 80+ design was submitted by Combustion Engineering, Inc., now Asea Brown Boveri-Combustion Engineering (ABB-CE) as an application for design approval and subsequent design certification pursuant to 10 CFR {section} 52.45. System 80+ is a pressurized water reactor with a rated power of 3914 megawatts thermal (MWt) and a design power of 3992 MWt at which accidents are analyzed. Many features of the System 80+ are similar to those of ABB-CE`s System 80 design from which it evolved. Unique features of the System 80+ design include: a large spherical, steel containment; an in-containment refueling water storage tank; a reactor cavity flooding system, hydrogen ignitors and a safety depressurization system for severe accident mitigation; a combustion gas turbine for an alternate ac source; and an advanced digitally based control room. On the basis of its evaluation and independent analyses, the NRC staff concludes that ABB-CE`s application for design certification meets the requirements of Subpart B of 10 CFR Part 52 that are applicable and technically relevant to the System 80+ standard design. This document, Volume 2, contains Chapters 15 through 22 and Appendices A through E.

  14. Final safety evaluation report related to the certification of the System 80{sup +} design (Docket No. 52-002). Volume 1, Chapters 1--14

    Energy Technology Data Exchange (ETDEWEB)

    1994-08-01

    This final safety evaluation report (FSER) documents the technical review of the System 80+ standard design by the US Nuclear Regulatory Commission (NRC) staff. The application for the System 80+ design was submitted by Combustion Engineering, Inc., now Asea Brown Boveri-Combustion Engineering (ABB-CE) as an application for design approval and subsequent design certification pursuant to 10 CFR {section} 52.45. System 80+ is a pressurized water reactor with a rated power of 3914 megawatts thermal (MWt) and a design power of 3992 MWt at which accidents are analyzed. Many features of the System 80+ are similar to those of Abb-CE`s System 80 design from which it evolved. Unique features of the System 80+ design included: a large spherical, steel containment; an in-containment refueling water storage tank; a reactor cavity flooding system, hydrogen ignitors, and a safety depressurization system for severe accident mitigation; a combustion gas turbine for an alternate ac source; and an advanced digitally based control room. On the basis of its evaluation and independent analyses, the NRC staff concludes that ABB-CE`s application for design certification meets the requirements of Subpart B of 10 CFR Part 52 that are applicable and technically relevant to the System 80+ standard design. This document, Volume 1, contains Chapters 1 through 14 of this report.

  15. Final safety evaluation report related to the certification of the System 80+ design (Docket No. 52-002). Volume 1, Chapters 1--14

    International Nuclear Information System (INIS)

    1994-08-01

    This final safety evaluation report (FSER) documents the technical review of the System 80+ standard design by the US Nuclear Regulatory Commission (NRC) staff. The application for the System 80+ design was submitted by Combustion Engineering, Inc., now Asea Brown Boveri-Combustion Engineering (ABB-CE) as an application for design approval and subsequent design certification pursuant to 10 CFR section 52.45. System 80+ is a pressurized water reactor with a rated power of 3914 megawatts thermal (MWt) and a design power of 3992 MWt at which accidents are analyzed. Many features of the System 80+ are similar to those of Abb-CE's System 80 design from which it evolved. Unique features of the System 80+ design included: a large spherical, steel containment; an in-containment refueling water storage tank; a reactor cavity flooding system, hydrogen ignitors, and a safety depressurization system for severe accident mitigation; a combustion gas turbine for an alternate ac source; and an advanced digitally based control room. On the basis of its evaluation and independent analyses, the NRC staff concludes that ABB-CE's application for design certification meets the requirements of Subpart B of 10 CFR Part 52 that are applicable and technically relevant to the System 80+ standard design. This document, Volume 1, contains Chapters 1 through 14 of this report

  16. Final safety evaluation report related to the certification of the System 80+ design (Docket No. 52-002). Volume 2, Chapters 15--22 and appendices

    International Nuclear Information System (INIS)

    1994-08-01

    This final safety evaluation report (FSER) documents the technical review of the System 80+ standard design by the US Nuclear Regulatory Commission (NRC) staff. The application for the system 80+ design was submitted by Combustion Engineering, Inc., now Asea Brown Boveri-Combustion Engineering (ABB-CE) as an application for design approval and subsequent design certification pursuant to 10 CFR section 52.45. System 80+ is a pressurized water reactor with a rated power of 3914 megawatts thermal (MWt) and a design power of 3992 MWt at which accidents are analyzed. Many features of the System 80+ are similar to those of ABB-CE's System 80 design from which it evolved. Unique features of the System 80+ design include: a large spherical, steel containment; an in-containment refueling water storage tank; a reactor cavity flooding system, hydrogen ignitors and a safety depressurization system for severe accident mitigation; a combustion gas turbine for an alternate ac source; and an advanced digitally based control room. On the basis of its evaluation and independent analyses, the NRC staff concludes that ABB-CE's application for design certification meets the requirements of Subpart B of 10 CFR Part 52 that are applicable and technically relevant to the System 80+ standard design. This document, Volume 2, contains Chapters 15 through 22 and Appendices A through E

  17. Descriptive research

    NARCIS (Netherlands)

    Lans, W; van der Voordt, Theo; de Jong, T.M.; van der Voordt, D.J.M.

    2002-01-01

    A lot of knowledge is needed for a good design; one that is functional, affordable, with architectonic interest etc. The same applies to a wealth of other activities within the architectural discipline; as there are policy development, spatial planning, formulating programmes of requirement,

  18. Transmission final lenses in the HiPER laser fusion power plant: system design for temperature control

    Science.gov (United States)

    Páramo, A. R.; Sordo, F.; Garoz, D.; Le Garrec, B.; Perlado, J. M.; Rivera, A.

    2014-12-01

    The European laser fusion project HiPER is developing technologically feasible components for a laser fusion power plant with an evacuated dry wall chamber which is likely to operate with a shock ignition scheme and direct targets. One of the key components is the final optics. In this work, we consider silica transmission final lenses and address the major issues regarding the unavoidable neutron irradiation they must withstand. For pre-commercial power plants (150 MJ target yield at 10 Hz) a distance of 16 m between the final lenses and target leads to maximum lens temperatures within tolerable limits. However, a non-uniform steady-state temperature profile is a major concern because it is the origin of unacceptable aberrations that severely affect the target spots. We have devised an active intervention system based on a heat-transfer fluid to keep the temperature profile as smooth as possible. The main characteristics of the temperature control system are defined throughout this work and enable the operation of the plant, both for the start-up procedure and for normal operation.

  19. 150 kWe solar-powered deep-well irrigation facility. Phase I. Preliminary design study. Final report

    Energy Technology Data Exchange (ETDEWEB)

    1977-08-08

    Results of a preliminary design study for a solar-powered irrigation facility to be located on a farm between Phoenix and Tucson, Arizona, are presented. The ERDA-specified generic design criteria are detailed. A detailed systems analysis is presented, and preliminary designs of the thermal storage system, organic Rankine cycle power system, cooling water system, power distribution system, and collector foundation are given. Site layout and improvements are described, and a cost analysis of prototype and production units is included. Engineering drawings are included. (WHK)

  20. Factors Influencing Student Nurses' Performance in the Final ...

    African Journals Online (AJOL)

    The purpose of this study was to identify leads to factors influencing student nurses' performance in the final year practical examination at Gweru School of Nursing. A descriptive survey was used to collect data from a census of 16 assessors and cluster sample of 35 student nurses. A questionnaire designed for the research ...

  1. Economic impact of multi-span, prestressed concrete girder bridges designed as simple span versus continuous span : final report.

    Science.gov (United States)

    2016-10-01

    The objective of this study was to determine the economic impact of designing pre-tensioned prestressed concrete beam (PPCB) : bridges utilizing the continuity developed in the bridge deck as opposed to the current Iowa Department of Transportation (...

  2. Conceptual design of retrieval systems for emplaced transuranic waste containers in a salt bed depository. Final report

    International Nuclear Information System (INIS)

    Fogleman, S.F.

    1980-04-01

    The US Department of Energy and the Nuclear Regulatory Commission have jurisdiction over the nuclear waste management program. Design studies were previously made of proposed repository site configurations for the receiving, processing, and storage of nuclear wastes. However, these studies did not provide operational designs that were suitable for highly reliable TRU retrieval in the deep geologic salt environment for the required 60-year period. The purpose of this report is to develop a conceptual design of a baseline retrieval system for emplaced transuranic waste containers in a salt bed depository. The conceptual design is to serve as a working model for the analysis of the performance available from the current state-of-the-art equipment and systems. Suggested regulations would be based upon the results of the performance analyses

  3. Conceptual design of retrieval systems for emplaced transuranic waste containers in a salt bed depository. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Fogleman, S.F.

    1980-04-01

    The US Department of Energy and the Nuclear Regulatory Commission have jurisdiction over the nuclear waste management program. Design studies were previously made of proposed repository site configurations for the receiving, processing, and storage of nuclear wastes. However, these studies did not provide operational designs that were suitable for highly reliable TRU retrieval in the deep geologic salt environment for the required 60-year period. The purpose of this report is to develop a conceptual design of a baseline retrieval system for emplaced transuranic waste containers in a salt bed depository. The conceptual design is to serve as a working model for the analysis of the performance available from the current state-of-the-art equipment and systems. Suggested regulations would be based upon the results of the performance analyses.

  4. Dynamic Isotope Power System (DIPS) Applications Study. Volume II. Nuclear Integrated Multimission Spacecraft (NIMS) design definition. Final report

    International Nuclear Information System (INIS)

    1979-11-01

    The design requirements for the Nuclear Integrated Multimission Spacecraft. (NIMS) are discussed in detail. The requirements are a function of mission specifications, payload, control system requirements, electric system specifications, and cost limitations

  5. Joint application of AI techniques, PRA and disturbance analysis methodology to problems in the maintenance and design of nuclear power plants. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Okrent, D.

    1989-03-01

    This final report summarizes the accomplishments of a two year research project entitled ``Joint Application of Artificial Intelligence Techniques, Probabilistic Risk Analysis, and Disturbance Analysis Methodology to Problems in the Maintenance and Design of Nuclear Power Plants. The objective of this project is to develop and apply appropriate combinations of techniques from artificial intelligence, (AI), reliability and risk analysis and disturbance analysis to well-defined programmatic problems of nuclear power plants. Reactor operations issues were added to those of design and maintenance as the project progressed.

  6. TMACS system description

    International Nuclear Information System (INIS)

    Scaief, C.C.

    1995-01-01

    This document provides a description of the Tank Monitor and Control System (TMACS). It is intended as an introduction for those persons unfamiliar with the system as well as a reference document for the users, maintenance personnel, and system designers. In addition to describing the system, the document outlines the associated drawing documentation, provides maintenance and spare parts information, and discusses other TMACS documents that provide additional detail

  7. Design of 3x3 Focusing Array for Heavy Ion Driver Final Report on CRADA TC-02082-04

    Energy Technology Data Exchange (ETDEWEB)

    Martovetsky, N. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

    2017-09-28

    This memo presents a design of a 3x3 quadrupole array for HIF. It contains 3 D magnetic field computations of the array build with racetrack coils with and without different shields. It is shown that it is possible to have a low error magnetic field in the cells and shield the stray fields to acceptable levels. The array design seems to be a practical solution to any size array for future multi-beam heavy ion fusion drivers.

  8. Near Term Hybrid Passenger Vehicle Development Program. Phase I, Final report. Appendix C: preliminary design data package. Volume I

    Energy Technology Data Exchange (ETDEWEB)

    Piccolo, R.

    1979-07-31

    The assumptions made, analysis methods used, and preliminary results of research to determine the design specifications for a hybrid electric-powered and internal combustion engine-powered vehicle that would optimize the fuel economy of passenger automobiles are described. Information is included on body and component design, selection of spark-ignition engine and Ni-Zn batteries, life-cycle costs and life-cycle fuel consumption. (LCL)

  9. Safety Evalution Report related to the final design approval of the GESSAR II BWR/6 nuclear island design (Docket No. 50-447)

    International Nuclear Information System (INIS)

    1984-11-01

    This report supplements the GESSAR II SER (NUREG-0979), issued in April 1983, summarizing the results of the staff's safety review of the GESSAR II BWR/6 nuclear island design. The review is carried out in accordance with the procedures for demonstrating the acceptability of the design for the severe-accident concerns described in draft NUREG-1070, NRC Policy on Future Reactor Designs: Decisions on Severe Accident Issues in Nuclear Power Plant Regulation. Supplement 2 also provides more recent information regarding resolution or update of the confirmatory items and FDA-1 conditions identified in SSER 1. Subject to favorable resolution of the items discussed in this supplement, the staff concludes that the GESSAR II design satisfactorily addresses the severe-accident concerns described in draft NUREG-1070

  10. Updating action domain descriptions.

    Science.gov (United States)

    Eiter, Thomas; Erdem, Esra; Fink, Michael; Senko, Ján

    2010-10-01

    constraints. We finally discuss methods to compute solutions and approximate solutions (which disregard preference). Our results provide a semantic and computational basis for developing systems that incorporate new information into action domain descriptions in an action language, in the presence of additional constraints.

  11. Fort Hood Solar Total Energy Project. Volume II. Preliminary design. Part 2. System performance and supporting studies. Final report

    Energy Technology Data Exchange (ETDEWEB)

    None,

    1979-01-01

    The preliminary design developed for the Solar Total Energy System to be installed at Fort Hood, Texas, is presented. System performance analysis and evaluation are described. Feedback of completed performance analyses on current system design and operating philosophy is discussed. The basic computer simulation techniques and assumptions are described and the resulting energy displacement analysis is presented. Supporting technical studies are presented. These include health and safety and reliability assessments; solar collector component evaluation; weather analysis; and a review of selected trade studies which address significant design alternatives. Additional supporting studies which are generally specific to the installation site are reported. These include solar availability analysis; energy load measurements; environmental impact assessment; life cycle cost and economic analysis; heat transfer fluid testing; meteorological/solar station planning; and information dissemination. (WHK)

  12. Georgetown University Integrated Community Energy System (GU-ICES). Phase III, Stage II. Preliminary design. Final report

    Energy Technology Data Exchange (ETDEWEB)

    None

    1980-11-01

    Results are presented for two elements in the Georgetown University ICES program - the installation of a 2500-kW backpressure steam-turbine generator within a new extension to the heating and cooling plant (cogeneration) and the provision of four additional ash silos for the university's atmospheric fluidized-bed boiler plant (added storage scheme). The preliminary design and supporting documentation for the work items and architectural drawings are presented. Section 1 discusses the basis for the report, followed by sections on: feasibility analysis update; preliminary design documents; instrumentation and testing; revised work management plan; and appendices including outline constructions, turbine-generator prepurchase specification, design calculations, cost estimates, and Potomac Electric Company data. (MCW)

  13. Application analysis of solar total energy systems to the residential sector. Volume III, conceptual design. Final report

    Energy Technology Data Exchange (ETDEWEB)

    1979-07-01

    The objective of the work described in this volume was to conceptualize suitable designs for solar total energy systems for the following residential market segments: single-family detached homes, single-family attached units (townhouses), low-rise apartments, and high-rise apartments. Conceptual designs for the total energy systems are based on parabolic trough collectors in conjunction with a 100 kWe organic Rankine cycle heat engine or a flat-plate, water-cooled photovoltaic array. The ORC-based systems are designed to operate as either independent (stand alone) systems that burn fossil fuel for backup electricity or as systems that purchase electricity from a utility grid for electrical backup. The ORC designs are classified as (1) a high temperature system designed to operate at 600/sup 0/F and (2) a low temperature system designed to operate at 300/sup 0/F. The 600/sup 0/F ORC system that purchases grid electricity as backup utilizes the thermal tracking principle and the 300/sup 0/F ORC system tracks the combined thermal and electrical loads. Reject heat from the condenser supplies thermal energy for heating and cooling. All of the ORC systems utilize fossil fuel boilers to supply backup thermal energy to both the primary (electrical generating) cycle and the secondary (thermal) cycle. Space heating is supplied by a central hot water (hydronic) system and a central absorption chiller supplies the space cooling loads. A central hot water system supplies domestic hot water. The photovoltaic system uses a central electrical vapor compression air conditioning system for space cooling, with space heating and domestic hot water provided by reject heat from the water-cooled array. All of the systems incorporate low temperature thermal storage (based on water as the storage medium) and lead--acid battery storage for electricity; in addition, the 600/sup 0/F ORC system uses a therminol-rock high temperature storage for the primary cycle. (WHK)

  14. Design and development of an automotive propulsion system utilizing a Rankine cycle engine (water based fluid). Final report

    Energy Technology Data Exchange (ETDEWEB)

    Demler, R.L.

    1977-09-01

    Under EPA and ERDA sponsorship, SES successfully designed, fabricated and tested the first federally sponsored steam powered automobile. The automobile - referred to as the simulator - is a 1975 Dodge Monaco standard size passenger car with the SES preprototype Rankine cycle automotive propulsion system mounted in the engine compartment. In the latter half of 1975, the simulator successfully underwent test operations at the facilities of SES in Watertown, Massachusetts and demonstrated emission levels below those of the stringent federally established automotive requirements originally set for implementation by 1976. The demonstration was accomplished during testing over the Federal Driving Cycle on a Clayton chassis dynamometer. The design and performance of the vehicle are described.

  15. STANFORD-OHWAKI-KOHS TACTILE BLOCK DESIGN INTELLIGENCE TEST FOR THE BLIND. PART ONE-FINAL REPORT.

    Science.gov (United States)

    DAUTERMAN, WILLIAM L.; SUINN, RICHARD M.

    THIS TEST WAS DEVELOPED TO MEASURE THE INTELLIGENCE OF BLIND ADOLESCENTS AND ADULTS. SIX HUNDRED AND THIRTY BLIND SUBJECTS 14 YEARS OF AGE AND OLDER WERE USED IN REFINING AND STANDARDIZING THE NONVERBAL, PERFORMANCE OHWAKI-KOHS BLOCK DESIGN TEST FOR USE BY BLIND INDIVIDUALS IN THE UNITED STATES. RESULTS INDICATED STATISTICALLY SIGNIFICANT…

  16. 77 FR 4169 - Endangered and Threatened Species: Final Rule To Revise the Critical Habitat Designation for the...

    Science.gov (United States)

    2012-01-26

    ... of foraging is expected to support leatherback individual and population growth, reproduction, and..., or distinct population segments (DPS) are threatened or endangered and for designating critical..., westward to the Sulawasi and Sulu and South China Seas, or northward to the Sea of Japan (Benson et al...

  17. 75 FR 51817 - Final Effect of Designation of a Class of Employees for Addition to the Special Exposure Cohort

    Science.gov (United States)

    2010-08-23

    ... decision to designate a class of employees from the Bethlehem Steel Corporation facility in Lackawanna, New... Employer employees who worked at the Bethlehem Steel Corporation facility in Lackawanna, New York from January 1, 1949 to December 31, 1952, for a number of work days aggregating at least 250 work days...

  18. Grid connected integrated community energy system. Phase II: final stage 2 report. Preliminary design of cogeneration plant

    Energy Technology Data Exchange (ETDEWEB)

    1978-03-22

    The preliminary design of a dual-purpose power plant to be located on the University of Minnesota is described. This coal-fired plant will produce steam and electric power for a grid-connected Integrated Community Energy System. (LCL)

  19. TIBER II/ETR final design report: Volume 1, 1.0 Introduction; 2.0 plasma engineering

    International Nuclear Information System (INIS)

    Lee, J.D.

    1987-09-01

    This paper discusses the design of the TIBER II tokamak test reactor. Specific topics discussed are the physics objectives for Tiber, magnetics, baseline operating point, pulsed inductive operation, edge physics and impurity control, fueling, disruption control, vertical stability and impurity flow reversal

  20. Paducah-Louisville Consortium. Project VIII: Focus on Dropouts... A New Design. Final Evaluation Report, 1971-72.

    Science.gov (United States)

    Lyne, Evelyn

    Project VIII is an innovative behavioral science-oriented educational program for potential dropouts. It is designed to reduce the dropout rate in grades 9 through 12, increase attendance in grades 7 through 12, decrease discipline referrals and suspensions, increase reading and math achievement in grades 3 through 11, and improve the student's…

  1. Revision of Electro-Mechanical Drafting Program to Include CAD/D (Computer-Aided Drafting/Design). Final Report.

    Science.gov (United States)

    Snyder, Nancy V.

    North Seattle Community College decided to integrate computer-aided design/drafting (CAD/D) into its Electro-Mechanical Drafting Program. This choice necessitated a redefinition of the program through new curriculum and course development. To initiate the project, a new industrial advisory council was formed. Major electronic and recruiting firms…

  2. Consultancy on Large-Scale Submerged Aerobic Cultivation Process Design - Final Technical Report: February 1, 2016 -- June 30, 2016

    Energy Technology Data Exchange (ETDEWEB)

    Crater, Jason [Gemomatica, Inc., San Diego, CA (United States); Galleher, Connor [Gemomatica, Inc., San Diego, CA (United States); Lievense, Jeff [Gemomatica, Inc., San Diego, CA (United States)

    2017-05-12

    NREL is developing an advanced aerobic bubble column model using Aspen Custom Modeler (ACM). The objective of this work is to integrate the new fermentor model with existing techno-economic models in Aspen Plus and Excel to establish a new methodology for guiding process design. To assist this effort, NREL has contracted Genomatica to critique and make recommendations for improving NREL's bioreactor model and large scale aerobic bioreactor design for biologically producing lipids at commercial scale. Genomatica has highlighted a few areas for improving the functionality and effectiveness of the model. Genomatica recommends using a compartment model approach with an integrated black-box kinetic model of the production microbe. We also suggest including calculations for stirred tank reactors to extend the models functionality and adaptability for future process designs. Genomatica also suggests making several modifications to NREL's large-scale lipid production process design. The recommended process modifications are based on Genomatica's internal techno-economic assessment experience and are focused primarily on minimizing capital and operating costs. These recommendations include selecting/engineering a thermotolerant yeast strain with lipid excretion; using bubble column fermentors; increasing the size of production fermentors; reducing the number of vessels; employing semi-continuous operation; and recycling cell mass.

  3. Report on the design and operation of a full-scale anaerobic dairy manure digester. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Coppinger, E.; Brautigam, J.; Lenart, J.; Baylon, D.

    1979-12-01

    A full-scale anaerobic digester on the Monroe State Dairy Farm was operated and monitored for 24 months with funding provided by the United States Department of Energy, Fuels from Biomass Systems Branch. During the period of operation, operating parameters were varied and the impact of those changes is described. Operational experiences and system component performance are discussed. Internal digester mixing equipment was found to be unnecessary, and data supporting this conclusion are given. An influent/effluent heat exchanger was installed and tested, and results of the tests are included. Recommendations for digester design and operation are presented. Biological stability was monitored, and test results are given. Gas production rates and system net energy are analyzed. The economics of anaerobic digestion are evaluated based on various financing options, design scales, and expected benefits. Under many circumstances digesters are feasible today, and a means of analysis is given.

  4. Design, Fabrication, and Operation of Innovative Microalgae Culture Experiments for the Purpose of Producing Fuels: Final Report, Phase I

    Energy Technology Data Exchange (ETDEWEB)

    1985-01-01

    A conceptual design was developed for a 1000-acre (water surface) algae culture facility for the production of fuels. The system is modeled after the shallow raceway system with mixing foils that is now being operated at the University of Hawaii. A computer economic model was created to calculate the discounted breakeven price of algae or fuels produced by the culture facility. A sensitivity analysis was done to estimate the impact of changes in important biological, engineering, and financial parameters on product price.

  5. Time-Dependent Deformation Modelling for a Chopped-Glass Fiber Composite for Automotive Durability Design Criteria; FINAL

    International Nuclear Information System (INIS)

    Ren, W

    2001-01-01

    Time-dependent deformation behavior of a polymeric composite with chopped-glass-fiber reinforcement was investigated for automotive applications, The material under stress was exposed to representative automobile service environments. Results show that environment has substantial effects on time-dependent deformation behavior of the material. The data were analyzed and experimentally-based models developed for the time-dependent deformation behavior as a basis for automotive structural durability design criteria

  6. Solar central receiver hybrid power system, Phase I. Volume 2. Conceptual design. Final technical report, October 1978-August 1979

    Energy Technology Data Exchange (ETDEWEB)

    None

    1979-09-01

    The objectives of this study were to develop a hybrid power system design that (1) produces minimum cost electric power, (2) minimizes the capital investment and operating cost, (3) permits capacity displacement, (4) and achieves utility acceptance for market penetration. We have met the first three of these objectives and therefore believe that the fourth, utility acceptance, will become a reality. These objectives have been met by utilizing the Martin Marietta concept that combines the alternate central receiver power system design and a high-temperature salt primary heat transfer fluid and thermal storage media system with a fossil-fired nonsolar energy source. Task 1 reviewed the requirements definition document and comments and recommendations were provided to DOE/San Francisco. Task 2 consisted of a market analysis to evaluate the potential market of solar hybrid power plants. Twenty-two utilities were selected within nine regions of the country. Both written and verbal correspondence was used to assess solar hybrid power plants with respect to the utilities' future requirements and plans. The parametric analysis of Task 3 evaluated a wide range of subsystem configurations and sizes. These analyses included subsystems from the solar standalone alternate central receiver power system using high-temperature molten salt and from fossil fuel nonsolar subsystems. Task 4, selection of the preferred commerical system configuration, utilized the parametric analyses developed in Task 3 to select system and subsystem configurations for the commercial plant design. Task 5 developed a conceptual design of the selected commercial plant configuration and assessed the related cost and performance. Task 6 assessed the economics and performance of the selected configuration as well as future potential improvements or limitations of the hybrid power plants.

  7. Investigation on Stress-Rupture Behavior of a Chopped-Glass-Fiber Composite for Automotive Durability Design Criteria; FINAL

    International Nuclear Information System (INIS)

    Ren, W

    2001-01-01

    Practical and inexpensive testing methods were developed to investigate stress-rupture properties of a polymeric composite with chopped glass fiber reinforcement for automotive applications. The material was tested in representative automotive environments to generate experimental data. The results indicate that environments have substantial effects on the stress-rupture behavior. The data were analyzed and developed into stress-rupture design criteria to address one of the durability aspects of the material for automotive structural applications

  8. Open-Source Integrated Design-Analysis Environment for Nuclear Energy Advanced Modeling & Simulation Phase I Final Report

    Energy Technology Data Exchange (ETDEWEB)

    O' Leary, Patrick [Kitware, Inc., Clifton Park, NY (United States)

    2014-03-18

    Our proposal described an approach for addressing the barriers of advanced modeling and simulation (M&S) adoption by the nuclear energy industry. This will be achieved by developing a state-of-the-art, open-source integrated design-analysis environment (IDAE) to work on a range of nuclear energy applications, while leveraging best-in-class software created through millions of investment dollars from the Department of Energy (DOE) Office for Nuclear Energy (NE) and from several other funding agencies.

  9. Integrated Design for Marketing and Manufacturing team: An examination of LA-ICP-AES in a mobile configuration. Final report

    International Nuclear Information System (INIS)

    1994-05-01

    The Department of Energy (DOE) has identified the need for field-deployable elemental analysis devices that are safer, faster, and less expensive than the fixed laboratory procedures now used to screen hazardous waste sites. As a response to this need, the Technology Integration Program (TIP) created a mobile, field-deployable laser ablation-inductively coupled plasma-atomic emission spectrometry (LA-ICP-AES) sampling and analysis prototype. Although the elemental. screening prototype has been successfully field-tested, continued marketing and technical development efforts are required to transfer LA-ICP-AES technology to the commercial sector. TIP established and supported a student research and design group called the Integrated Design for Marketing and Manufacturing (IDMM) team to advance the technology transfer of mobile, field-deployable LA-ICP-AES. The IDMM team developed a conceptual design (which is detailed in this report) for a mobile, field-deployable LA-ICP-AES sampling and analysis system, and reports the following findings: Mobile, field-deployable LA-ICP-AES is commercially viable. Eventual regulatory acceptance of field-deployable LA-ICP-AES, while not a simple process, is likely. Further refinement of certain processes and components of LA-ICP-AES will enhance the device's sensitivity and accuracy

  10. Phase 1: conceptual design. Ocean thermal energy conversion power system development. Volume 2 of 3. Technical details. Final report

    Energy Technology Data Exchange (ETDEWEB)

    1978-01-30

    Westinghouse has completed the conceptual design of the Power System for the Ocean Thermal Energy Conversion (OTEC) Demonstration Plant project. This study included the development of a conceptual design for the following three items: first, a full-size power system module for the 100 MWe Demonstration Plant; second, a scaled proof of concept power system; and third, a heat exchanger test article. The study was limited to a closed cycle ammonia power system module, using a water temperature difference of 40/sup 0/F., and a surface platform/ship reference hull. Two power module of 50 MWe each are recommended for the demonstration plant. The 50 MWe module was selected since it has the lowest cost, and since it is of a size which convincingly demonstrates that future economically viable commercial plants, having reliable operation with credible anticipated costs, are possible. A modular, tube bundle approach to heat exchanger design makes large heat exchangers practical and economical. Other power module elements are considered to be within state-of-practice. Technological assessments of all subsystems indicate requirements for verification only, rather than continued research. A complete test program, which will verify the mechanical reliability as well as thermal performance, is recommended.

  11. PV Inverter Products Manufacturing and Design Improvements for Cost Reduction and Performance Enhancements: Final Subcontract Report, November 2003 (Revised)

    Energy Technology Data Exchange (ETDEWEB)

    West, R.

    2004-04-01

    The specific objectives of this subcontracted development work by Xantrex Technology Inc. were to: (1) Capture the newest digital signal processor (DSP) technology to create high-impact,''next generation'' power conversion equipment for the PV industry; (2) Create a common resource base for three PV product lines. This standardized approach to both hardware and software control platforms will provide significant market advantage over foreign competition; (3) Achieve cost reductions through increased volume of common components, reduced assembly labor, and the higher efficiency of producing more products with fewer design, manufacturing, and production test variations; (4) Increase PV inverter product reliability. Reduce inverter size, weight and conversion losses. The contract goals were to achieve an overall cost reduction of 10% to 20% for the three inverters and with no compromise in performance. The cost of the 10-kW inverter was reduced by 56%, and the cost of the 25-kW inverter was reduced by 53%. The 2.5-kW inverter has no basis for comparison, but should benefit equally from this design approach. Not only were the contract cost reduction goals exceeded by a wide margin, but the performance and reliability of the products were also enhanced. The conversion efficiency improvement, as reflected in the 50% conversion loss reduction, adds significant value in renewable energy applications. The size and weight reductions also add value by providing less cumbersome product solutions for system designers.

  12. New Concepts in Fish Ladder Design, Volume III of IV, Assessment of Fishway Development and Design, 1982-1983 Final Report.

    Energy Technology Data Exchange (ETDEWEB)

    Powers, Patrick D.; Orsborn, John F.

    1985-08-01

    This volume covers the broad, though relatively short, historical basis for this project. The historical developments of certain design features, criteria and research activities are traced. Current design practices are summarized based on the results of an international survey and interviews with agency personnel and consultants. The fluid mechanics and hydraulics of fishway systems are discussed. Fishways (or fishpasses) can be classified in two ways: (1) on the basis of the method of water control (chutes, steps (ladders), or slots); and (2) on the basis of the degree and type of water control. This degree of control ranges from a natural waterfall to a totally artificial environment at a hatchery. Systematic procedures for analyzing fishways based on their configuration, species, and hydraulics are presented. Discussions of fish capabilities, energy expenditure, attraction flow, stress and other factors are included.

  13. Compressed air energy storage: preliminary design and site development program in an aquifer. Final draft, Task 1: establish facility design criteria and utility benefits

    Energy Technology Data Exchange (ETDEWEB)

    None

    1980-10-01

    Compressed air energy storage (CAES) has been identified as one of the principal new energy storage technologies worthy of further research and development. The CAES system stores mechanical energy in the form of compressed air during off-peak hours, using power supplied by a large, high-efficiency baseload power plant. At times of high electrical demand, the compressed air is drawn from storage and is heated in a combustor by the burning of fuel oil, after which the air is expanded in a turbine. In this manner, essentially all of the turbine output can be applied to the generation of electricity, unlike a conventional gas turbine which expends approximately two-thirds of the turbine shaft power in driving the air compressor. The separation of the compression and generation modes in the CAES system results in increased net generation and greater premium fuel economy. The use of CAES systems to meet the utilities' high electrical demand requirements is particularly attractive in view of the reduced availability of premium fuels such as oil and natural gas. This volume documents the Task 1 work performed in establishing facility design criteria for a CAES system with aquifer storage. Information is included on: determination of initial design bases; preliminary analysis of the CAES system; development of data for site-specific analysis of the CAES system; detailed analysis of the CAES system for three selected heat cycles; CAES power plant design; and an economic analysis of CAES.

  14. Final Report

    Energy Technology Data Exchange (ETDEWEB)

    R Paul Drake

    2004-01-12

    OAK-B135 This is the final report from the project Hydrodynamics by High-Energy-Density Plasma Flow and Hydrodynamics and Radiation Hydrodynamics with Astrophysical Applications. This project supported a group at the University of Michigan in the invention, design, performance, and analysis of experiments using high-energy-density research facilities. The experiments explored compressible nonlinear hydrodynamics, in particular at decelerating interfaces, and the radiation hydrodynamics of strong shock waves. It has application to supernovae, astrophysical jets, shock-cloud interactions, and radiative shock waves.

  15. The project to design and develop an energy-related program for public housing residents: Final report

    Energy Technology Data Exchange (ETDEWEB)

    1986-12-01

    This demonstration project studied how to minimize the costs associated with public housing tenants in standard public housing as well as under homeownership transfers. A related problem was how to graduate the tenants to another level of responsibility and self-sufficiency through resident business developments and training in energy-related fields. The goal that emanated was the design and development of an energy-related demonstration program that educates public housing residents, facilities indigenous business development where appropriate, and trains residents to provide needed services.

  16. Uranium Mill Tailings Remedial Action Project (UMTRAP), Slick Rock, Colorado, Revision 1, Volume 3. Calculations, Final design for construction

    International Nuclear Information System (INIS)

    1995-09-01

    Volume three contains calculations for: site hydrology--rainfall intensity, duration, and frequency relations; site hydrology-- probable maximum precipitation; erosion protection--rock quality evaluation; erosion protection--embankment top and side slope; erosion protection--embankment toe apron; erosion protection-- gradations and layer thicknesses; Union Carbide site--temporary drainage ditch design; Union Carbide site--retention basin sediment volume; Union Carbide site--retention basin sizing; Burro Canyon site temporary drainage--temporary drainage facilities; and Union Carbide site temporary drainage--water balance

  17. Conceptual design analysis of an MHD power conversion system for droplet-vapor core reactors. Final report

    International Nuclear Information System (INIS)

    Anghaie, S.; Saraph, G.

    1995-01-01

    A nuclear driven magnetohydrodynamic (MHD) generator system is proposed for the space nuclear applications of few hundreds of megawatts. The MHD generator is coupled to a vapor-droplet core reactor that delivers partially ionized fissioning plasma at temperatures in range of 3,000 to 4,000 K. A detailed MHD model is developed to analyze the basic electrodynamics phenomena and to perform the design analysis of the nuclear driven MHD generator. An incompressible quasi one dimensional model is also developed to perform parametric analyses

  18. European contribution to heat exchanger design/performance: HTFS research and computer programs. Final report. [SCON4 and CEMP1

    Energy Technology Data Exchange (ETDEWEB)

    Lang, C.; Skrovanek, T.

    1979-01-01

    The performance of selected HTFS computer program in solving example heat exchanger design/performance situations is evaluated. In addition, the specific inputs required by the program are presented to give an idea of the amount of detail the user must supply concerning the heat transfer system. Comments on the versatility of each program and technical details necessary for running each program are also provided. The computer programs examined rate the performance of shell-and-tube type condensers and plate-fin heat exchangers.

  19. CRADA Final Report: Thermal Design and Analysis Tools for Dense-Wavelength-Division-Multiplexed (DWDM) Optical Networks

    Energy Technology Data Exchange (ETDEWEB)

    Hopkins, Deborah

    2005-01-31

    The current project originated from discussions with designers and engineers in the opto-electronics industry who sought help from LBNL in identifying effective thermal-management strategies for optical-network components and systems. Miniaturization of opto-electronic components exacerbates the thermal management problem because it allows a greater number of temperature-sensitive components to be fit into less space. Measurement techniques are required to evaluate emerging technologies, test prototype designs, and provide data that can be used to calibrate and validate models. To address these needs, LBNL and project partners developed a test station that allows experiments to be performed under tightly controlled conditions. The central component of the testing device is a "guarded" hot plate that enables high-precision temperature measurements, allowing forced-convection cooling devices to be evaluated. The device is so named because guard plates are used to eliminate heat flow and ensure that heat is not dissipated through the cooling device under investigation. This tool not only allows characterization of emerging technologies and materials, but also allows collection of high-resolution data that can be used to validate and improve simulation tools used to develop next-generation cooling devices for telecommunication systems. The ability to measure and analyze thermal performance benefits the photonics and optical-network industry by reducing development costs and time to market.

  20. Grid-connected integrated community energy system. Phase II, Stage 1, final report. Conceptual design: pyrolysis and waste management systems

    Energy Technology Data Exchange (ETDEWEB)

    1978-03-08

    The University of Minnesota is studying and planning a grid-connected integrated community energy system to include disposal of wastes from health centers and utilizing the heat generated. Following initial definition of the 7-county metropolitan region for which the solid waste management system is to be planned, information is then necessary about the nature of the waste generated within this region. Estimates of the quantities generated, generation rates, and properties of the waste to be collected and disposed of are required in order to determine the appropriate size and capacity of the system. These estimates are designated and subsequently referred to as ''system input''. Institutional information is also necessary in designing the planned system, to be compatible with existing institutional operations and procedures, or to offer a minimum amount of problems to the participating institution in the region. Initial considerations of health care institutions generating solid waste within the defined region are made on a comprehensive basis without any attempt to select out or include feasible candidate institutions, or institutional categories. As the study progresses, various criteria are used in selecting potential candidate institutional categories and institutions within the 7-county region as offering the most feasible solid waste system input to be successfully developed into a centralized program; however, it is hoped that such a system if developed could be maintained for the entire 7-county region, and remain comprehensive to the entire health care industry. (MCW)