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

System Design Description for the TMAD Code

International Nuclear Information System (INIS)

Finfrock, S.H.

1995-01-01

This document serves as the System Design Description (SDD) for the TMAD Code System, which includes the TMAD code and the LIBMAKR code. The SDD provides a detailed description of the theory behind the code, and the implementation of that theory. It is essential for anyone who is attempting to review or modify the code or who otherwise needs to understand the internal workings of the code. In addition, this document includes, in Appendix A, the System Requirements Specification for the TMAD System

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....

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

Cold Vacuum Drying (CVD) Electrical System Design Description

International Nuclear Information System (INIS)

SINGH, G.

2000-01-01

This system design description (SDD) provides a technical explanation of the design and operation of the electrical system for the Cold Vacuum Drying Facility (CVDF). This SDD also identifies the requirements, and the basis for the requirements and details on how the requirements have been implemented in the design and construction of the facility. This SDD also provides general guidance for the surveillance, testing, and maintenance of this system

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

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

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

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

Final amplifier design and mercury

International Nuclear Information System (INIS)

Rose, E.A.; Hanson, D.E.

1991-01-01

The final amplifier for the Mercury KrF excimer facility is being designed. The design exercise involves extensive modeling to predict amplifier performance. Models of the pulsed-power system, including a Child-Langmuir diode with closure, electron-beam energy deposition, KrF laser kinetics, amplified spontaneous emission (ASE), a time-dependent laser extraction in the presence of ASE are presented as a design package. The design exercise indicates that the energy objective of Phase I -- 100 joules -- will be met

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)

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

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

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.

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

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

Spent Nuclear Fuel (SNF) Cold Vacuum Drying (CVD) Facility Operations Manual; FINAL

International Nuclear Information System (INIS)

IRWIN, J.J.

1999-01-01

This document provides the Operations Manual for the Cold Vacuum Drying Facility (CVDF). The Manual was developed in conjunction with HNF-553, Spent Nuclear Fuel Project Final Safety Analysis Report Annex B-Cold Vacuum Drying Facility. The HNF-SD-SNF-DRD-002, 1999, Cold Vacuum Drying Facility Design Requirements, Rev. 4, and the CVDF Final Design Report. The Operations Manual contains general descriptions of all the process, safety and facility systems in the CVDF, a general CVD operations sequence and references to the CVDF System Design Descriptions (SDDs). This manual 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

Design review report for the MCO loading system

Energy Technology Data Exchange (ETDEWEB)

Brisbin, S.A.

1997-06-23

This design report presents the 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 review report for the MCO loading system

International Nuclear Information System (INIS)

Brisbin, S.A.

1997-01-01

This design report presents the 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

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

COG Software Architecture Design Description Document

International Nuclear Information System (INIS)

Buck, R.M.; Lent, E.M.

2009-01-01

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.

Final Exam Weighting as Part of Course Design

Science.gov (United States)

Franke, Matthew

2018-01-01

The weighting of a final exam or a final assignment is an essential part of course design that is rarely discussed in pedagogical literature. Depending on the weighting, a final exam or assignment may provide unequal benefits to students depending on their prior performance in the class. Consequently, uncritical grade weighting can discount…

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.

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

Reference Design Description for a Geologic Repository, Rev. 03, ICN 02

International Nuclear Information System (INIS)

Gerald Shideler

2001-01-01

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

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)

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...... management tools and methods for description and modelling of production systems supporting the decisions. In this article a structural framework to describe and model production systems will be introduced, and it is shown how the production system of a minor Danish manufacturer of electromechanical...

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.

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.

Facility Description 2012. Summary report of the encapsulation plant and disposal facility designs

International Nuclear Information System (INIS)

Palomaeki, J.; Ristimaeki, L.

2013-10-01

The purpose of the facility description is to be a specific summary report of the scope of Posiva's nuclear facilities (encapsulation plant and disposal facility) in Olkiluoto. This facility description is based on the 2012 designs and completing Posiva working reports. The facility description depicts the nuclear facilities and their operation as the disposal of spent nuclear fuel starts in Olkiluoto in about 2020. According to the decisions-in-principle of the government, the spent nuclear fuel from Loviisa and Olkiluoto nuclear power plants in operation and in future cumulative spent nuclear fuel from Loviisa 1 and 2, Olkiluoto 1, 2, 3 and 4 nuclear power plants, is permitted to be disposed of in Olkiluoto bedrock. The design of the disposal facility is based on the KBS-3V concept (vertical disposal). Long-term safety concept is based on the multi-barrier principle i.e. several release barriers, which ensure one another so that insufficiency in the performance of one barrier doesn't jeopardize long-term safety of the disposal. The release barriers are the following: canister, bentonite buffer and deposition tunnel backfill, and the host rock around the repository. The canisters are installed into the deposition holes, which are bored to the floor of the deposition tunnels. The canisters are enveloped with compacted bentonite blocks, which swell after absorbing water. The surrounding bedrock and the central and access tunnel backfill provide additional retardation, retention, and dilution. The nuclear facilities consist of an encapsulation plant and of underground final disposal facility including other aboveground buildings and surface structures serving the facility. The access tunnel and ventilation shafts to the underground disposal facility and some auxiliary rooms are constructed as a part of ONKALO underground rock characterization facility during years 2004-2014. The construction works needed for the repository start after obtaining the construction

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

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

Design description of the Tangaye Village photovoltaic power system

Science.gov (United States)

Martz, J. E.; Ratajczak, A. F.

1982-01-01

The engineering design of a stand alone photovoltaic (PV) powered grain mill and water pump for the village of Tangaye, Upper Volta is described. The socioeconomic effects of reducing the time required by women in rural areas for drawing water and grinding grain were studied. The suitability of photovoltaic technology for use in rural areas by people of limited technical training was demonstrated. The PV system consists of a 1.8-kW (peak) solar cell array, 540 ampere hours of battery storage, instrumentation, automatic controls, and a data collection and storage system. The PV system is situated near an improved village well and supplies d.c. power to a grain mill and a water pump. The array is located in a fenced area and the mill, battery, instruments, controls, and data system are in a mill building. A water storage tank is located near the well. The system employs automatic controls which provide battery charge regulation and system over and under voltage protection. This report includes descriptions of the engineering design of the system and of the load that it serves; a discussion of PV array and battery sizing methodology; descriptions of the mechanical and electrical designs including the array, battery, controls, and instrumentation; and a discussion of the safety features. The system became operational on March 1, 1979.

UMTRA project: Canonsburg final design

International Nuclear Information System (INIS)

Thiers, G.R.; Guros, F.B.; Smith, E.S.

1984-01-01

Final design for on-site stabilization of over 300,000 cubic yards of abandoned mill tailings in Canonsburg, Pennsylvania, is being completed this Fall. This paper describes design criteria, design procedures, and difficulties encountered for the following required elements: 1. Encapsulation cell; 2. Durability of erosion protection material; 3. Flood control berm; 4. Sedimentation pond; 5. Wastewater treatment plant. The 70,000 cubic yards of the tailings for which radiation levels exceed 100 picocuries per gram will be placed on a 2-ft-thick compacted clay liner and encased by a 3-ft-thick compacted clay cover. The remaining tailings will be covered with at least two feet of clay to prevent radon escape and to reduce rainfall infiltration. Erosion protection will be provided for the encapsulation cell, the drainage swales, and from potential meandering of nearby Chartiers Creek

Spacecraft System Integration and Test: SSTI Lewis critical design audit

Science.gov (United States)

Brooks, R. P.; Cha, K. K.

1995-01-01

The Critical Design Audit package is the final detailed design package which provides a comprehensive description of the SSTI mission. This package includes the program overview, the system requirements, the science and applications activities, the ground segment development, the assembly, integration and test description, the payload and technology demonstrations, and the spacecraft bus subsystems. Publication and presentation of this document marks the final requirements and design freeze for SSTI.

Reference design description for a geologic repository: Revision 01

International Nuclear Information System (INIS)

1997-09-01

This document describes the current design expectations for a potential geologic repository that could be located at Yucca Mountain in Nevada. This Reference Design Description (RDD) looks at the surface and subsurface repository and disposal container design. Additionally, it reviews the expected long-term performance of the potential repository. In accordance with current legislation, the reference design for the potential repository does not include an interim storage option. The reference design presented allows the disposal of highly radioactive material received from government-owned spent fuel custodian sites; produces high-level waste sites, and commercial spent fuel sites. All design elements meet current federal, state, and local regulations governing the disposal of high-level radioactive waste and protection of the public and the environment. Due to the complex nature of developing a repository, the design will be created in three phases to support Viability Assessment, License Application, and construction. This document presents the current reference design. It will be updated periodically as the design progresses. Some of the details presented here may change significantly as more cost-effective solutions, technical advancements, or changes to requirements are identified

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

Sewage Solids Irradiator Transportation System (SSITS) cask: preliminary design description

International Nuclear Information System (INIS)

Eakes, R.G.; Kempka, S.N.; Lamoreaux, G.H.; Sutherland, S.H.

1983-02-01

The preliminary design of the Sewage Solids Irradiator Transportation System (SSITS) Cask is presented in this document. The SSITS cask is to be used for the transport of radioactive cesium chloride and strontium fluoride capsules which are of use in irradiators or as heat sources. The SSITS cask is approximately 1.4 m in diameter, 1.3 m high, weighs roughly 9 t, provides 33 cm of steel shielding, and can dissipate up to 5.2 kW of decay heat. The cask design criteria are identified and a description of the cask design and operation is provided. Detailed analyses of the design were performed to demonstrate licensability of the cask by the Nuclear Regulatory Commission (NRC). Results of the analyses indicate that the preliminary design is in compliance with the pertinent regulatory requirements for licensing of a radioactive material transportation container

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

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

Final Exam Weighting as Part of Course Design

Directory of Open Access Journals (Sweden)

Matthew Franke

2018-03-01

Full Text Available The weighting of a final exam or a final assignment is an essential part of course design that is rarely discussed in pedagogical literature. Depending on the weighting, a final exam or assignment may provide unequal benefits to students depending on their prior performance in the class. Consequently, uncritical grade weighting can discount student learning, by ensuring that improved mastery of material at the semester’s end is not reflected in the course grade. Problems related to several common final exam weights are explored, as are potential solutions to unequal student outcomes made possible by uncritical grade weighting. Ultimately, this essay argues that choosing a weight for a final exam or a final assignment determines what types of student success ought to be possible in the class; therefore, instructors should assign exam weights intentionally, being fully aware of the potential benefits and problems of the weights that they choose.

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.

Automatic control system generation for robot design validation

Science.gov (United States)

Bacon, James A. (Inventor); English, James D. (Inventor)

2012-01-01

The specification and drawings present a new method, system and software product for and apparatus for generating a robotic validation system for a robot design. The robotic validation system for the robot design of a robotic system is automatically generated by converting a robot design into a generic robotic description using a predetermined format, then generating a control system from the generic robotic description and finally updating robot design parameters of the robotic system with an analysis tool using both the generic robot description and the control system.

A Description Logic Based Knowledge Representation Model for Concept Understanding

DEFF Research Database (Denmark)

Badie, Farshad

2017-01-01

This research employs Description Logics in order to focus on logical description and analysis of the phenomenon of ‘concept understanding’. The article will deal with a formal-semantic model for figuring out the underlying logical assumptions of ‘concept understanding’ in knowledge representation...... systems. In other words, it attempts to describe a theoretical model for concept understanding and to reflect the phenomenon of ‘concept understanding’ in terminological knowledge representation systems. Finally, it will design an ontology that schemes the structure of concept understanding based...

Hardware description languages

Science.gov (United States)

Tucker, Jerry H.

1994-01-01

Hardware description languages are special purpose programming languages. They are primarily used to specify the behavior of digital systems and are rapidly replacing traditional digital system design techniques. This is because they allow the designer to concentrate on how the system should operate rather than on implementation details. Hardware description languages allow a digital system to be described with a wide range of abstraction, and they support top down design techniques. A key feature of any hardware description language environment is its ability to simulate the modeled system. The two most important hardware description languages are Verilog and VHDL. Verilog has been the dominant language for the design of application specific integrated circuits (ASIC's). However, VHDL is rapidly gaining in popularity.

High Luminosity LHC Project Description

CERN Document Server

Apollinari, Giorgio; Rossi, Lucio

2014-01-01

The High Luminosity LHC (HL-LHC) is a novel configuration of the Large Hadron Collider, aiming at increasing the luminosity by a factor five or more above the nominal LHC design, to allow increasing the integrated luminosity, in the high luminosity experiments ATLAS and CMS, from the 300 fb-1 of the LHC original design up to 3000 fb-1 or more. This paper contains a short description of the main machine parameters and of the main equipment that need to be developed and installed. The preliminary cost evaluation and the time plan are presented, too. Finally, the international collaboration that is supporting the project, the governance and the project structure are discussed, too.

Design description of the European pressurized water reactor

International Nuclear Information System (INIS)

Leverenz, R.

1999-01-01

The EPR (the European Pressurized Water Reactor) is an evolutionary PWR developed by Nuclear Power International and its parent companies, Framatome and Siemens, in co-operation with Electricite de France and German Utilities. NPI can rely on the huge experience gained by its parent companies; they have constructed more than 100 nuclear power plants throughout the world. The total installed capacity exceeds 100,000 MW - about 25% of the total world-wide figure. Following the conceptual design phase of the so-called Common Product conducted by NPI, Framatome and Siemens, from 1989 through 1991, Electricite de France (EDF) and several major German utilities decided to merge their own development programmes, - the N4 Plus and REP 2000 projects on the French side and the further development of the KONVOI technology on the German side, - with the NPI project. From that time on, the NPI project became one single common development line for both countries. In parallel, EDF and the German utilities decided to establish, together with other European utilities, specifications that would represent common utility views on the design and performance of future nuclear power plants. These are documented in the European Utility Requirements (EURs). The basic design has been completed in 1997, and in 1998 a design optimization is being carried out with the goal to even increase the economic competitiveness of nuclear power. This paper provides a brief design description of the EPR. (author)

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

Final Design Report for the RH LLW Disposal Facility (RDF) Project, Revision 3

International Nuclear Information System (INIS)

Austad, Stephanie Lee

2015-01-01

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.

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

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

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.

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

ITER Conceptual design: Interim report

International Nuclear Information System (INIS)

1990-01-01

This interim report describes the results of the International Thermonuclear Experimental Reactor (ITER) Conceptual Design Activities after the first year of design following the selection of the ITER concept in the autumn of 1988. Using the concept definition as the basis for conceptual design, the Design Phase has been underway since October 1988, and will be completed at the end of 1990, at which time a final report will be issued. This interim report includes an executive summary of ITER activities, a description of the ITER device and facility, an operation and research program summary, and a description of the physics and engineering design bases. Included are preliminary cost estimates and schedule for completion of the project

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...

Handling final storage of unreprocessed spent nuclear fuel

International Nuclear Information System (INIS)

1978-01-01

The present second report from KBS describes how the safe final storage of spent unreprocessed nuclear fuel can be implemented. According to the Swedish Stipulation Law, the owner must specify in which form the waste is to be stored, how final storage is to be effected, how the waste is to be transported and all other aspects of fuel handling and storage which must be taken into consideration in judging whether the proposed final storage method can be considered to be absolutely safe and feasible. Thus, the description must go beyond general plans and sketches. The description is therefore relatively detailed, even concerning those parts which are less essential for evaluating the safety of the waste storage method. For those parts of the handling chain which are the same for both alternatives of the Stipulation Law, the reader is referred in some cases to the first report. Both of the alternatives of the Stipulation Law may be used in the future. Handling equipment and facilities for the two storage methods are so designed that a combination in the desired proportions is practically feasible. In this first part of the report are presented: premises and data, a description of the various steps of the handling procedure, a summary of dispersal processes and a safety analysis. (author)

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

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)

Stochastic final-state dynamics of widening entanglement-a possible description of quantum measurement

International Nuclear Information System (INIS)

Eriksson, Karl-Erik

2009-01-01

The measurement process of quantum mechanics is analysed in the scattering theory of quantum field theory. A matrix of bilinear forms of the scattering amplitudes (the R-matrix) is used as the basic descriptive tool. The measurement process is viewed as a final-state interaction described through a series of linear stochastic mappings of the R-matrix, not changing the observable to be measured. The unknown details of the measurement apparatus enter through the stochasticity of the mappings. Although linear in terms of the R-matrix, the mappings are nonlinear in the density matrix, which is obtainable from the R-matrix through normalization. The eigenstates of the observable are the attractors of the mapping process. This result, known from previous generalizations of quantum mechanics, is obtained here within linear quantum mechanics. The conclusion is that the measurement process can be understood within relativistic quantum field theory itself without any generalization or metatheory.

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

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...

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.

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

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

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...... by the availability of sophisticated methods and tools alone, but does evidently also depend on the accuracy of the input information used. As existing approaches for the description of manufacturing variation focus however, almost exclusively, on monitoring and controlling production processes, there is frequently...... 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...

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

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

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

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.

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.

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

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.)

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.

Torus II. Technical description of the design proposal

International Nuclear Information System (INIS)

Aymar, R.; Deck, C.; Deschamps, P.; Lafon, D.; Leloup, C.; Pariente, M.; Renaud, C.; Sledziewski, Z.; Torossian, A.

1976-06-01

A new Tokamak device, called TORUS II, is proposed to be built inside the EURATOM-CEA Association. This is a large machine: I=1.7MA; B=30kGs; R=1.8m; a=75cm, designed to be a successor to TFR and to follow the lines of research already initiated in the present TFR programme, i.e. on plasma heating, on impurities, on energy confinement and scaling laws, providing to JET a very efficient backing. This part of the report provides a technical description of the main components of the basic machine, according to the state of design reached in June 1976. Every subsystem whose assembly forms the basic machine is the subject of one section: vacuum vessel, toroidal field coils, poloidal field system, mechanical structures, monitoring, control and data acquisition, and power supplies. The first part in each section attempts to summarize the solution that was retained, pointing out the problems to be solved and the choice made. No contribution takes into account the problems of installation and buildings and the time schedule which is given is only concerned with the simplest solution. By way, contributions are given which show the state of development of the peripheral systems envisaged for TORUS II, mainly: additional heating, control of impurities and plasma diagnostics [fr

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

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

Science.gov (United States)

2012-09-12

... NUCLEAR REGULATORY COMMISSION [NRC-2010-0131] Notice of Withdrawal of Final Design Approval; Westinghouse Electric Company; Advanced Passive 1000 By letter dated December 10, 2010, Westinghouse Electric... final design approval (FDA) for the Advanced Passive 1000 (AP1000) design upon the completion of...

Final design of the neutral beam lines for the Tokamak Fusion Test Reactor

International Nuclear Information System (INIS)

Pittenger, L.C.; Valby, L.E.; Stone, R.R.; Pedrotti, L.R.; Denhoy, B.; Yoard, R.

1979-01-01

Final design of the neutral beam lines for TFTR has been completed. A prototype has been assembled at Lawrence Berkeley Laboratory and is undergoing testing as part of the Neutral Beam System Test Facility (NBSTF). The final neutral beam line (NBL) configuration differs in several details from that previously reported upon; certain components have been added; and testing of the cryopump system has led to some design simplification. It is these developments which are reported herein

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).

"Who Doesn't?"--The Impact of Descriptive Norms on Corruption.

Science.gov (United States)

Köbis, Nils C; van Prooijen, Jan-Willem; Righetti, Francesca; Van Lange, Paul A M

2015-01-01

Corruption poses one of the major societal challenges of our time. Considerable advances have been made in understanding corruption on a macro level, yet the psychological antecedents of corrupt behavior remain largely unknown. In order to explain why some people engage in corruption while others do not, we explored the impact of descriptive social norms on corrupt behavior by using a novel behavioral measure of corruption. We conducted three studies to test whether perceived descriptive norms of corruption (i.e. the belief about the prevalence of corruption in a specific context) influence corrupt behavior. The results indicated that descriptive norms highly correlate with corrupt behavior--both when measured before (Study 1) or after (Study 2) the behavioral measure of corruption. Finally, we adopted an experimental design to investigate the causal effect of descriptive norms on corruption (Study 3). Corrupt behavior in the corruption game significantly drops when participants receive short anti-corruption descriptive norm primes prior to the game. These findings indicate that perceived descriptive norms can impact corrupt behavior and, possibly, could offer an explanation for inter-personal and inter-cultural variation in corrupt behavior in the real world. We discuss implications of these findings and draw avenues for future research.

"Who Doesn't?"--The Impact of Descriptive Norms on Corruption.

Directory of Open Access Journals (Sweden)

Nils C Köbis

Full Text Available Corruption poses one of the major societal challenges of our time. Considerable advances have been made in understanding corruption on a macro level, yet the psychological antecedents of corrupt behavior remain largely unknown. In order to explain why some people engage in corruption while others do not, we explored the impact of descriptive social norms on corrupt behavior by using a novel behavioral measure of corruption. We conducted three studies to test whether perceived descriptive norms of corruption (i.e. the belief about the prevalence of corruption in a specific context influence corrupt behavior. The results indicated that descriptive norms highly correlate with corrupt behavior--both when measured before (Study 1 or after (Study 2 the behavioral measure of corruption. Finally, we adopted an experimental design to investigate the causal effect of descriptive norms on corruption (Study 3. Corrupt behavior in the corruption game significantly drops when participants receive short anti-corruption descriptive norm primes prior to the game. These findings indicate that perceived descriptive norms can impact corrupt behavior and, possibly, could offer an explanation for inter-personal and inter-cultural variation in corrupt behavior in the real world. We discuss implications of these findings and draw avenues for future research.

Mod-1 wind turbine generator analysis and design report, volume 1

Science.gov (United States)

1979-01-01

The activities leading to the completion of detail design of the MOD-1 wind turbine generator are described. Emphasis is placed on the description of the design as it finally evolved. However, the steps through which the design progressed are also traced in order to understand the major design decisions.

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

Final analysis and design of a thermal protection system for 8-foot HTST combustor

Science.gov (United States)

Moskowitz, S.

1973-01-01

The cylindrical shell combustor with T-bar supports in the 8-foot HTST at the NASA-Langley Research Center encountered vibratory fatigue cracking over a period of 50-250 tunnel tests within a limited range of the required operating envelope. A preliminary design study provided several suitable thermal protection system designs for the combustor, one of which was a two-pass regenerative type air-cooled omega-shaped segment liner. A final design layout of the omega segment liner was prepared and analyzed for steady-state and transient conditions. The design of a support system for the fuel spray bar assembly was also included. Detail drawings suitable for fabrication purposes were also prepared. Liner design problems defined during the preliminary study included (1) the ingress of gas into the attachment bulb section of the omega segment, (2) the large thermal gradient along the leg of the omega bulb attachment section and, (3) the local peak metal temperature at the radius between the liner ID and the leg of the bulb attachment. These were resolved during the final design task. Analyses of the final design of the omega segment liner indicated that all design goals were met and the design provided the capability of operating over the required test envelope with a life expectancy substantially above the goal of 1500 cycles.

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

NFR TRIGA package design review report

International Nuclear Information System (INIS)

Clements, M.D.

1994-01-01

The purpose of this document is to compile, present and document the formal design review of the NRF TRIGA packaging. The contents of this document include: the briefing meeting presentations, package description, design calculations, package review drawings, meeting minutes, action item lists, review comment records, final resolutions, and released drawings. This design review required more than two meeting to resolve comments. Therefore, there are three meeting minutes and two action item lists

An automated approach for generating and checking control logic for reversible hardware description language-based designs

DEFF Research Database (Denmark)

Wille, Robert; Keszocze, Oliver; Othmer, Lars

2017-01-01

to significantly different design challenges to be addressed. In this work, we consider problems that occur when describing a reversible control flow using Hardware Description Languages (HDLs). Here, the commonly used conditional statements must, in addition to the established if-condition for forward computation......, be provided with an additional fi-condition for backward computation. Unfortunately, deriving correct and consistent fi-conditions is often not obvious. Moreover, HDL descriptions exist which may not be realized with a reversible control flow at all. In this work, we propose automatic solutions, which...

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

SURFACE INDUSTRIAL HVAC SYSTEM DESCRIPTION DOCUMENT

Energy Technology Data Exchange (ETDEWEB)

M.M. Ansari

2005-04-05

The purpose of this system description document (SDD) is to establish requirements that drive the design of the surface industrial heating, ventilation, and air-conditioning (HVAC) system and its bases to allow the design effort to proceed to license application. This SDD will be revised at strategic points as the design matures. This SDD identifies the requirements and describes the system design, as it currently exists, with emphasis on attributes of the design provided to meet the requirements. This SDD is an engineering tool for design control; accordingly, the primary audience and users are design engineers. This SDD is part of an iterative design process. It leads the design process with regard to the flowdown of upper tier requirements onto the system. Knowledge of these requirements is essential to performing the design process. The SDD follows the design with regard to the description of the system. The description that provided in this SDD reflects the current results of the design process.

SNF/HLW Transfer System Description Document

International Nuclear Information System (INIS)

W. Holt

2005-01-01

The purpose of this system description document (SDD) is to establish requirements that drive the design of the spent nuclear fuel (SNF)/high-level radioactive waste (HLW) transfer system and associated bases, which will allow the design effort to proceed to license application. This SDD will be revised at strategic points as the design matures. This SDD identifies the requirements and describes the system design, as it currently exists, with emphasis on attributes of the design provided to meet the requirements. This SDD is an engineering tool for design control. Accordingly, the primary audience and users are design engineers. This SDD is part of an iterative design process. It leads the design process with regard to the flowdown of upper tier requirements onto the system. Knowledge of these requirements is essential in performing the design process. The SDD follows the design with regard to the description of the system. The description provided in this SDD reflects the current results of the design process

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)

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)

Sixty-five-year old final clarifier performance rivals that of modern designs.

Science.gov (United States)

Barnard, James L; Kunetz, Thomas E; Sobanski, Joseph P

2008-01-01

The Stickney plant of the Metropolitan Wastewater Reclamation District of Greater Chicago (MWRDGC), one of the largest wastewater treatment plants in the world, treats an average dry weather flow of 22 m3/s and a sustained wet weather flow of 52 m3/s that can peak to 63 m3/s. Most of the inner city of Chicago has combined sewers, and in order to reduce pollution through combined sewer overflows (CSO), the 175 km Tunnel and Reservoir Plan (TARP) tunnels, up to 9.1 m in diameter, were constructed to receive and convey CSO to a reservoir from where it will be pumped to the Stickney treatment plant. Pumping back storm flows will result in sustained wet weather flows over periods of weeks. Much of the success of the plant will depend on the ability of 96 circular final clarifiers to produce an effluent of acceptable quality. The nitrifying activated sludge plant is arranged in a plug-flow configuration, and some denitrification takes place as a result of the high oxygen demand in the first pass of the four-pass aeration basins that have a length to width ratio of 18:1. The SVI of the mixed liquor varies between 60 and 80 ml/g. The final clarifiers, which were designed by the District's design office in 1938, have functioned for more than 65 years without major changes and are still producing very high-quality effluent. This paper will discuss the design and operation of these final clarifiers and compare the design with more modern design practices. (c) IWA Publishing 2008.

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

Employing Picture Description to Assess the Students' Descriptive Paragraph Writing

Directory of Open Access Journals (Sweden)

Ida Ayu Mega Cahyani

2018-03-01

Full Text Available Writing is considered as an important skill in learning process which is needed to be mastered by the students. However, in teaching learning process at schools or universities, the assessment of writing skill is not becoming the focus of learning process and the assessment is administered inappropriately. In this present study, the researcher undertook the study which dealt with assessing descriptive paragraph writing ability of the students through picture description by employing an ex post facto as the research design. The present study was intended to answer the research problem dealing with the extent of the students’ achievement of descriptive paragraph writing ability which is assessed through picture description. The samples under the study were 40 students determined by means of random sampling technique with lottery system. The data were collected through administering picture description as the research instrument. The obtained data were analyzed by using norm-reference measure of five standard values. The results of the data analysis showed that there were 67.50% samples of the study were successful in writing descriptive paragraph, while there were 32.50% samples were unsuccessful in writing descriptive paragraph which was assessed by administering picture description test

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

Cold Vacuum Drying Instrument Air System Design Description (SYS 12)

Energy Technology Data Exchange (ETDEWEB)

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

2000-06-05

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 & Instrument Air P&ID, and H-1.82161, Cold Vacuum Drying Facility Process Equipment Skid P&ID MCO/Cusk Interface. Figure 1-1 shows the physical location of the 1A system in the CVD Facility.

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

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......, 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......The context of the study is the very strict regulation of energy consumption for operating buildings in Denmark. It is difficult to meet the requirements by system optimisation in the final design phase, so recent research has focused on ways of meeting the target by adapting the whole design...

Final turbine and test facility design report Alden/NREC fish friendly turbine

Energy Technology Data Exchange (ETDEWEB)

Cook, Thomas C. [Alden Research Lab., Holden, MA (United States); Cain, Stuart A. [Alden Research Lab., Holden, MA (United States); Fetfatsidis, Paul [Alden Research Lab., Holden, MA (United States); Hecker, George E. [Alden Research Lab., Holden, MA (United States); Stacy, Philip S. [Alden Research Lab., Holden, MA (United States)

2000-09-01

The final report provides an overview of the Alden/NREC Fish Friendly turbine design phase, turbine test plan, preliminary test results, costs, schedule, and a hypothetical application at a real world project.

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.

Cold Vacuum Drying facility heating, ventilation, and Air Conditioning system design description

International Nuclear Information System (INIS)

SINGH, G.

2000-01-01

This System Design Description (SDD) addresses the HVAC system for the CVDF. The CVDF HVAC system consists of five subsystems: (1) Administration building HVAC system; (2) Process bay recirculation HVAC system; (3) Process bay local exhaust HVAC and process vent system; (4) Process general supply/exhaust HVAC system; and (5) Reference air system. The HVAC and reference air systems interface with the following systems: the fire protection control system, Monitoring and Control System (MCS), electrical power distribution system (including standby power), compressed air system, Chilled Water (CHW) system, drainage system, and other Cold Vacuum Drying (CVD) control systems not addressed in this SDD

Mod-5A Wind Turbine Generator Program Design Report. Volume 2: Conceptual and Preliminary Design, Book 1

Science.gov (United States)

1984-01-01

The design, development and analysis of the 7.3 MW MOD-5A wind turbine generator is documented. There are four volumes. In Volume 2, book 1 the requirements and criteria for the design are presented. The conceptual design studies, which defined a baseline configuration and determined the weights, costs and sizes of each subsystem, are described. The development and optimization of the wind turbine generator are presented through the description of the ten intermediate configurations between the conceptual and final designs. Analyses of the system's load and dynamics are presented.

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.

Phase B: Final definition and preliminary design study for the initial Atmospheric Cloud Physics Laboratory (ACPL): A spacelab mission payload. Final review (DR-MA-03)

Science.gov (United States)

Clausen, O. W.

1976-01-01

Systems design for an initial atmospheric cloud physics laboratory to study microphysical processes in zero gravity is presented. Included are descriptions of the fluid, thermal, mechanical, control and data, and electrical distribution interfaces with Spacelab. Schedule and cost analysis are discussed.

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

Pre-conceptual design requirements and system description for FED frame seal welder and cutter

International Nuclear Information System (INIS)

Masson, L.S.; Longhurst, G.R.; Watts, K.D.; Williams, S.A.

1981-03-01

The Fusion Engineering Device (FED) is being designed in a torus shape using ten removable segments to form the torus geometry. The torus consists of a frame and ten shield assemblies which fit into the frame and are held in place structurally using electrically insulated backing plates. It is then necessary to seal the shield segment to the frame for the assembly to sustain an internal vacuum of 10 -7 torr. This task is intended to be accomplished by welding a frame seal between the frame and the shield segment. An example of this concept is shown. This document covers the equipment requirements and pre-conceptual design description for installing and removing the frame seal

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)

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.

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.

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)

“Who Doesn’t?”—The Impact of Descriptive Norms on Corruption

Science.gov (United States)

Köbis, Nils C.; van Prooijen, Jan-Willem; Righetti, Francesca; Van Lange, Paul A. M.

2015-01-01

Corruption poses one of the major societal challenges of our time. Considerable advances have been made in understanding corruption on a macro level, yet the psychological antecedents of corrupt behavior remain largely unknown. In order to explain why some people engage in corruption while others do not, we explored the impact of descriptive social norms on corrupt behavior by using a novel behavioral measure of corruption. We conducted three studies to test whether perceived descriptive norms of corruption (i.e. the belief about the prevalence of corruption in a specific context) influence corrupt behavior. The results indicated that descriptive norms highly correlate with corrupt behavior—both when measured before (Study 1) or after (Study 2) the behavioral measure of corruption. Finally, we adopted an experimental design to investigate the causal effect of descriptive norms on corruption (Study 3). Corrupt behavior in the corruption game significantly drops when participants receive short anti-corruption descriptive norm primes prior to the game. These findings indicate that perceived descriptive norms can impact corrupt behavior and, possibly, could offer an explanation for inter-personal and inter-cultural variation in corrupt behavior in the real world. We discuss implications of these findings and draw avenues for future research. PMID:26121127

Experimental fusion power reactor conceptual design study. Final report. Volume III

International Nuclear Information System (INIS)

Baker, C.C.

1976-12-01

This document is the final report which describes the work carried out by General Atomic Company for the Electric Power Research Institute on a conceptual design study of a fusion experimental power reactor (EPR) and an overall EPR facility. The primary objective of the two-year program was to develop a conceptual design of an EPR that operates at ignition and produces continuous net power. A conceptual design was developed for a Doublet configuration based on indications that a noncircular tokamak offers the best potential of achieving a sufficiently high effective fuel containment to provide a viable reactor concept at reasonable cost. Other objectives included the development of a planning cost estimate and schedule for the plant and the identification of critical R and D programs required to support the physics development and engineering and construction of the EPR. This volume contains the following appendices: (1) tradeoff code analysis, (2) residual mode transport, (3) blanket/first wall design evaluations, (4) shielding design evaluation, (5) toroidal coil design evaluation, (6) E-coil design evaluation, (7) F-coil design evaluation, (8) plasma recycle system design evaluation, (9) primary coolant purification design evaluation, (10) power supply system design evaluation, (11) number of coolant loops, (12) power conversion system design evaluation, and (13) maintenance methods evaluation

ELECTRICAL SUPPORT SYSTEM DESCRIPTION DOCUMENT

International Nuclear Information System (INIS)

Roy, S.

2004-01-01

The purpose of this revision of the System Design Description (SDD) is to establish requirements that drive the design of the electrical support system and their bases to allow the design effort to proceed to License Application. This SDD is a living document that will be revised at strategic points as the design matures over time. This SDD identifies the requirements and describes the system design as they exist at this time, with emphasis on those attributes of the design provided to meet the requirements. This SDD has been developed to be an engineering tool for design control. Accordingly, the primary audience/users are design engineers. This type of SDD both ''leads'' and ''trails'' the design process. It leads the design process with regard to the flow down of upper tier requirements onto the system. Knowledge of these requirements is essential in performing the design process. The SDD trails the design with regard to the description of the system. The description provided in the SDD is a reflection of the results of the design process to date. Functional and operational requirements applicable to electrical support systems are obtained from the ''Project Functional and Operational Requirements'' (F andOR) (Siddoway 2003). Other requirements to support the design process have been taken from higher-level requirements documents such as the ''Project Design Criteria Document'' (PDC) (Doraswamy 2004), and fire hazards analyses. The above-mentioned low-level documents address ''Project Requirements Document'' (PRD) (Canon and Leitner 2003) requirements. This SDD contains several appendices that include supporting information. Appendix B lists key system charts, diagrams, drawings, and lists, and Appendix C includes a list of system procedures

Final report of the ITER EDA. Final report of the ITER Engineering Design Activities. Prepared by the ITER Council

International Nuclear Information System (INIS)

2001-01-01

This is the Final Report by the ITER Council on work carried out by ITER participating countries on cooperation in the Engineering Design Activities (EDA) for the ITER. In this report the main ITER EDA technical objectives, the scope of ITER EDA, its organization and resources, engineering design of ITER tokamak and its main parameters are presented. This Report also includes safety and environmental assessments, site requirements and proposed schedule and estimates of manpower and cost as well as proposals on approaches to joint implementation of the project

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

DEFF Research Database (Denmark)

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

, 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......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...

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

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-12-01

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. Refs, figs, tabs

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

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

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)

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

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.

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

Design of Training Systems, Phase II Report, Volume III; Model Program Descriptions and Operating Procedures. TAEG Report No. 12-2.

Science.gov (United States)

Naval Training Equipment Center, Orlando, FL. Training Analysis and Evaluation Group.

The Design of Training Systems (DOTS) project was initiated by the Department of Defense (DOD) to develop tools for the effective management of military training organizations. Volume 3 contains the model and data base program descriptions and operating procedures designed for phase 2 of the project. Flow charts and program listings for the…

ELECTRICAL SUPPORT SYSTEM DESCRIPTION DOCUMENT

Energy Technology Data Exchange (ETDEWEB)

S. Roy

2004-06-24

The purpose of this revision of the System Design Description (SDD) is to establish requirements that drive the design of the electrical support system and their bases to allow the design effort to proceed to License Application. This SDD is a living document that will be revised at strategic points as the design matures over time. This SDD identifies the requirements and describes the system design as they exist at this time, with emphasis on those attributes of the design provided to meet the requirements. This SDD has been developed to be an engineering tool for design control. Accordingly, the primary audience/users are design engineers. This type of SDD both ''leads'' and ''trails'' the design process. It leads the design process with regard to the flow down of upper tier requirements onto the system. Knowledge of these requirements is essential in performing the design process. The SDD trails the design with regard to the description of the system. The description provided in the SDD is a reflection of the results of the design process to date. Functional and operational requirements applicable to electrical support systems are obtained from the ''Project Functional and Operational Requirements'' (F&OR) (Siddoway 2003). Other requirements to support the design process have been taken from higher-level requirements documents such as the ''Project Design Criteria Document'' (PDC) (Doraswamy 2004), and fire hazards analyses. The above-mentioned low-level documents address ''Project Requirements Document'' (PRD) (Canon and Leitner 2003) requirements. This SDD contains several appendices that include supporting information. Appendix B lists key system charts, diagrams, drawings, and lists, and Appendix C includes a list of system procedures.

Final design and construction issues of the TAPIRO epithermal column

International Nuclear Information System (INIS)

Burn, K.W.; Casalini, L.; Nava, E.; Tinti, R.; Martini, S.; Mondini, D.; Rosi, G.

2006-01-01

The construction of the epithermal column for clinical trials at the 5 kW fast reactor TAPIRO (ENEA, Casaccia, Italy) has been completed, the experimental bunker in the reactor hall has been designed and the beam characterisation will shortly be underway. As has been reviewed at the last two ICNCT conferences, the low power of the neuron source and the relatively distant patient position outside the reactor shield led to a column design with certain characteristics. One consequence is the employment of a collimator containing lead of high purity with the resultant problems of mechanical construction. Another is the substantial neutron leakage from the column outside the aperture into the experimental bunker. Furthermore the absence of a gamma shield has led to an electron dose to the skin. This is resolved with an electron shield of aluminium. Here the construction and final design issues are discussed and the state of the project is presented. (author)

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...

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...

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

ELECTRICAL POWER SYSTEM DESCRIPTION DOCUMENT

Energy Technology Data Exchange (ETDEWEB)

M. Maniyar

2004-06-22

The purpose of this revision of the System Description Document (SDD) is to establish requirements that drive the design of the electrical power system and their bases to allow the design effort to proceed to License Application. This SDD is a living document that will be revised at strategic points as the design matures over time. This SDD identifies the requirements and describes the system design as they exist at this time, with emphasis on those attributes of the design provided to meet the requirements. This SDD has been developed to be an engineering tool for design control. Accordingly, the primary audience are design engineers. This type of SDD leads and follows the design process. It leads the design process with regard to the flow down of upper tier requirements onto the system. Knowledge of these requirements is essential to performing the design process. This SDD follows the design with regard to the description of the system. The description provided in the SDD is a reflection of the results of the design process to date. Functional and operational requirements applicable to this system are obtained from ''Project Functional and Operational Requirements'' (F&OR) (Siddoway, 2003). Other requirements to support the design process have been taken from higher level requirements documents such as ''Project Design Criteria Document'' (PDC) (Doraswamy 2004), the fire hazards analyses, and the preclosure safety analysis. The above mentioned low-level documents address ''Project Requirements Document'' (PRD) (Canori and Leitner 2003) requirements. This SDD includes several appendices with supporting information. Appendix B lists key system charts, diagrams, drawings, and lists; and Appendix C is a list of system procedures.

Description of Measurements on Biogas Stations

Directory of Open Access Journals (Sweden)

Ladislav Novosád

2016-08-01

Full Text Available This paper focuses mainly on performance analysis for three biogas stations situated within the territory of the Czech Republic. This paper contains basic details of the individual biogas stations as well as description of their types. It also refers to the general description of the measurement gauge involved, with specifications of its potential use. The final part of this paper deals with the analysis of course data obtained, with special regard to voltage, current, active power and reactive power data.

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

KBS-3H design description 2005

Energy Technology Data Exchange (ETDEWEB)

Autio, Jorma (Saanio and Riekkola Oy, Helsinki (Finland))

2008-05-15

SKB and Posiva are performing an RandD program over the period of 2002-2007 with the overall aim to develop the KBS-3H to an alternative to the KBS-3V concept for disposal of spent nuclear fuel. A feasibility study of the KBS-3H concept was carried out in 2002, followed by the setting up of basic design in 2003. Several problems related to the behavior of the design and scope of future research and development work were addressed. Therefore the design basis was developed further and two candidate designs were developed: 1) previous Basic Design (BD) was developed more robust and tolerable to inflows. Parallel to that a novel modified 2) DAWE design with Drainage, Air evacuation and Watering and was developed to function robustly at various inflow situations. The candidate designs presented in this report include several novel components, such as fixing rings and steel plugs which have been designed without support of applicable design guidelines, regulations or standards available. The design basis and performance of these components include uncertainties, which should be studied and verified. It is possible that a feasible site specific design can be based on using both alternatives

KBS-3H design description 2005

International Nuclear Information System (INIS)

Autio, Jorma

2008-05-01

SKB and Posiva are performing an RandD program over the period of 2002-2007 with the overall aim to develop the KBS-3H to an alternative to the KBS-3V concept for disposal of spent nuclear fuel. A feasibility study of the KBS-3H concept was carried out in 2002, followed by the setting up of basic design in 2003. Several problems related to the behavior of the design and scope of future research and development work were addressed. Therefore the design basis was developed further and two candidate designs were developed: 1) previous Basic Design (BD) was developed more robust and tolerable to inflows. Parallel to that a novel modified 2) DAWE design with Drainage, Air evacuation and Watering and was developed to function robustly at various inflow situations. The candidate designs presented in this report include several novel components, such as fixing rings and steel plugs which have been designed without support of applicable design guidelines, regulations or standards available. The design basis and performance of these components include uncertainties, which should be studied and verified. It is possible that a feasible site specific design can be based on using both alternatives

Receptive fields selection for binary feature description.

Science.gov (United States)

Fan, Bin; Kong, Qingqun; Trzcinski, Tomasz; Wang, Zhiheng; Pan, Chunhong; Fua, Pascal

2014-06-01

Feature description for local image patch is widely used in computer vision. While the conventional way to design local descriptor is based on expert experience and knowledge, learning-based methods for designing local descriptor become more and more popular because of their good performance and data-driven property. This paper proposes a novel data-driven method for designing binary feature descriptor, which we call receptive fields descriptor (RFD). Technically, RFD is constructed by thresholding responses of a set of receptive fields, which are selected from a large number of candidates according to their distinctiveness and correlations in a greedy way. Using two different kinds of receptive fields (namely rectangular pooling area and Gaussian pooling area) for selection, we obtain two binary descriptors RFDR and RFDG .accordingly. Image matching experiments on the well-known patch data set and Oxford data set demonstrate that RFD significantly outperforms the state-of-the-art binary descriptors, and is comparable with the best float-valued descriptors at a fraction of processing time. Finally, experiments on object recognition tasks confirm that both RFDR and RFDG successfully bridge the performance gap between binary descriptors and their floating-point competitors.

Experimental fusion power reactor conceptual design study. Final report. Volume II

International Nuclear Information System (INIS)

Baker, C.C.

1976-12-01

This document is the final report which describes the work carried out by General Atomic Company for the Electric Power Research Institute on a conceptual design study of a fusion experimental power reactor (EPR) and an overall EPR facility. The primary objective of the two-year program was to develop a conceptual design of an EPR that operates at ignition and produces continuous net power. A conceptual design was developed for a Doublet configuration based on indications that a noncircular tokamak offers the best potential of achieving a sufficiently high effective fuel containment to provide a viable reactor concept at reasonable cost. Other objectives included the development of a planning cost estimate and schedule for the plant and the identification of critical R and D programs required to support the physics development and engineering and construction of the EPR. This volume contains the following sections: (1) reactor components, (2) auxiliary systems, (3) operations, (4) facility design, (5) program considerations, and (6) conclusions and recommendations

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.

KBS-3H design description 2005

International Nuclear Information System (INIS)

Autio, J.

2007-03-01

SKB and Posiva are performing an R and D program over the period of 2002-2007 with the overall aim to develop the KBS-3H to an alternative to the KBS-3V concept for disposal of spent nuclear fuel. A feasibility study of the KBS-3H concept was carried out in 2002, followed by the setting up of basic design in 2003. Several problems related to the behavior of the design and scope of future research and development work were addressed. Therefore the design basis was developed further and two candidate designs were developed: (1) previous Basic Design (BD) was developed more robust and tolerable to inflows. Parallel to that a novel modified (2) DAWE design with Drainage, Air evacuation and Watering and was developed to function robustly at various inflow situations. The candidate designs presented in this report include several novel components, such as fixing rings and steel plugs which have been designed without support of applicable design guidelines, regulations or standards available. The design basis and performance of these components include uncertainties, which should be studied and verified. It is possible that a feasible site specific design can be based on using both alternatives. (orig.)

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.

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.

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)

Formal description of the OSI session layer: introduction

NARCIS (Netherlands)

Ajubi, I.; Scollo, Giuseppe; van Sinderen, Marten J.; van Eijk, P.H.J.; Vissers, C.A.; Diaz, M.

1989-01-01

The LOTOS formal description of the OSI session layer is introduced with the purpose of familiarizing the reader with the design choices that influenced the development of the formal description. Such design choices concern the adoptation of specification styles and the reflection of elements of the

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.

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

Final report. CIRP seminar on micro and nano technology. November 2003

DEFF Research Database (Denmark)

Hansen, Hans Nørgaard; Alting, Leo

This final reports contains a description of the 1st international CIRP seminar on micro and nano technology held at DTU in November 2003.......This final reports contains a description of the 1st international CIRP seminar on micro and nano technology held at DTU in November 2003....

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.

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

International Nuclear Information System (INIS)

Salo, J-P.; Reikkola, R.

1995-01-01

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

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.

Prototypical spent nuclear fuel rod consolidation equipment: Phase 2, Final design report: Volume 1, Detailed design

International Nuclear Information System (INIS)

Blissell, W.H.; Ciez, A.P.; Goedicke, F.E.; Bessko, C.

1987-01-01

This document describes the Westinghouse Final Design for the Prototypical Spent Fuel Consolidation Equipment Demonstration Project. This design represents a fully qualified, licensable, cost effective spent fuel rod consolidation system. As a result of significant concerns raised by DOE and its Technical Review Committee during the 30% Design Review, significant changes were made to the original Preliminary Design resulting from Phase I activities. These changes focused on increased automation, end fitting removal, the rod pulling process and the need to maintain the consolidation canisters as clean as possible. As a result of these changes, the new system is greatly enhanced with a much greater probability of meeting or exceeding the project functional requirements. As a result of delays in resolving cost and contractual differences, additional bench testing was not conducted during Phase II. It is however our belief that the current design exceeds the 90% confidence level required by DOE because of the confidence gained from the Phase I tests, the additional engineering detail completed and the fact that our rod pulling tool has been demonstrated in a similar application at Oconee while our ID tube cutter is a modified (mounting method only) off-the-shelf design. 7 refs., 49 figs., 36 tabs

The geometry description markup language

International Nuclear Information System (INIS)

Chytracek, R.

2001-01-01

Currently, a lot of effort is being put on designing complex detectors. A number of simulation and reconstruction frameworks and applications have been developed with the aim to make this job easier. A very important role in this activity is played by the geometry description of the detector apparatus layout and its working environment. However, no real common approach to represent geometry data is available and such data can be found in various forms starting from custom semi-structured text files, source code (C/C++/FORTRAN), to XML and database solutions. The XML (Extensible Markup Language) has proven to provide an interesting approach for describing detector geometries, with several different but incompatible XML-based solutions existing. Therefore, interoperability and geometry data exchange among different frameworks is not possible at present. The author introduces a markup language for geometry descriptions. Its aim is to define a common approach for sharing and exchanging of geometry description data. Its requirements and design have been driven by experience and user feedback from existing projects which have their geometry description in XML

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

Design descriptions of the Prometheus-L and -H inertial fusion energy drivers

Energy Technology Data Exchange (ETDEWEB)

Linford, G.J. (TRW Inc., Bld. O1/1220, Redondo Beach, CA 90278 (United States)); Driemeyer, D.E. (McDonnell Douglas Aerospace Co. (MDAC), St. Louis, MO 63166 (United States)); Fornaca, S.W. (TRW Inc., Bld. O1/1220, Redondo Beach, CA 90278 (United States)); Maschke, A.W. (TRW Inc., Bld. O1/1220, Redondo Beach, CA 90278 (United States))

1994-08-01

Two innovative drivers have been designed for a prototype 1000MW thermonuclear power plant planned for operation early in the next century. The Prometheus-L driver is a 4MJ KrF master oscillator power amplifier laser system designed to operate at a 5.6Hz repetition rate. Output pulses from the KrF master oscillator are synchronized with the pulsed-power excitation of the KrF power amplifiers and the launching of the inertial fusion energy deuterium/tritium targets. The Prometheus-L laser architecture features 960 5kJ electric discharge KrF power amplifiers pumping 60 crossed stimulated rotational Raman scattering H[sub 2] amplifiers serving as beam accumulators. Pulse compression of the 60 accumulator beams is accomplished in 60 chirped, self-seeded SF[sub 6] stimulated Brillouin scattering pulse compressors. Grazing incidence metal focusing mirrors minimize back-streaming radiation damage from the target chamber. This architecture permits the laser driver to deliver spectrally broad-band, temporally complex optical pulses in 60 beam lines to implode the direct-drive IFE targets within a 5m radius target chamber.The Prometheus-H driver is a 7.8MJ 4GeV Pb[sup ++] heavy ion (HI) inertial fusion energy system designed to operate at a 3.5He repetition rate. The HI driver design is based on a short, ramped gradient, 5MeV accelerator, followed by a longer, 2km constant gradient, single beam linear accelerator operated in a 50kHz burst mode to generate sequentially 18 4GeV beamlets. A two-sided irradiation geometry was developed for indirect-drive HI targets. Six beamlets are used for the 45ns precursor HI pulses stored in two superconducting storage rings, 12 superconducting storage rings accumulate the 12 main beamlets, with a final buncher generating the 8ns HI pulses which arrive at the target chamber simultaneously. Final focusing is accomplished with large aperture triplet focusing magnets through Pb-vapor neutralization cells to reduce the effect of space charge.

77 FR 15759 - Final Effect of Designation of a Class of Employees for Addition to the Special Exposure Cohort

Science.gov (United States)

2012-03-16

... DEPARTMENT OF HEALTH AND HUMAN SERVICES Final Effect of Designation of a Class of Employees for Addition to the Special Exposure Cohort AGENCY: National Institute for Occupational Safety and Health...). ACTION: Notice. SUMMARY: HHS gives notice concerning the final effect of the HHS decision to designate a...

78 FR 21955 - Final Effect of Designation of a Class of Employees for Addition to the Special Exposure Cohort

Science.gov (United States)

2013-04-12

... DEPARTMENT OF HEALTH AND HUMAN SERVICES Final Effect of Designation of a Class of Employees for Addition to the Special Exposure Cohort AGENCY: National Institute for Occupational Safety and Health...). ACTION: Notice. SUMMARY: HHS gives notice concerning the final effect of the HHS decision to designate a...

78 FR 70949 - Final Effect of Designation of a Class of Employees for Addition to the Special Exposure Cohort

Science.gov (United States)

2013-11-27

... DEPARTMENT OF HEALTH AND HUMAN SERVICES Final Effect of Designation of a Class of Employees for Addition to the Special Exposure Cohort AGENCY: National Institute for Occupational Safety and Health...). ACTION: Notice. SUMMARY: HHS gives notice concerning the final effect of the HHS decision to designate a...

77 FR 60438 - Final Effect of Designation of a Class of Employees for Addition to the Special Exposure Cohort

Science.gov (United States)

2012-10-03

... DEPARTMENT OF HEALTH AND HUMAN SERVICES Final Effect of Designation of a Class of Employees for Addition to the Special Exposure Cohort AGENCY: National Institute for Occupational Safety and Health...). ACTION: Notice. SUMMARY: HHS gives notice concerning the final effect of the HHS decision to designate a...

75 FR 27784 - Final Effect of Designation of a Class of Employees for Addition to the Special Exposure Cohort

Science.gov (United States)

2010-05-18

... DEPARTMENT OF HEALTH AND HUMAN SERVICES Final Effect of Designation of a Class of Employees for Addition to the Special Exposure Cohort AGENCY: National Institute for Occupational Safety and Health... concerning the final effect of the decision to designate a class of employees from Lawrence Livermore...

75 FR 37812 - Final Effect of Designation of a Class of Employees for Addition to the Special Exposure Cohort

Science.gov (United States)

2010-06-30

... DEPARTMENT OF HEALTH AND HUMAN SERVICES Final Effect of Designation of a Class of Employees for Addition to the Special Exposure Cohort AGENCY: National Institute for Occupational Safety and Health... and Human Services (HHS) gives notice concerning the final effect of the HHS decision to designate a...

77 FR 60437 - Final Effect of Designation of a Class of Employees for Addition to the Special Exposure Cohort

Science.gov (United States)

2012-10-03

... DEPARTMENT OF HEALTH AND HUMAN SERVICES Final Effect of Designation of a Class of Employees for Addition to the Special Exposure Cohort AGENCY: National Institute for Occupational Safety and Health...). ACTION: Notice. SUMMARY: HHS gives notice concerning the final effect of the HHS decision to designate a...

77 FR 69845 - Final Effect of Designation of a Class of Employees for Addition to the Special Exposure Cohort

Science.gov (United States)

2012-11-21

... DEPARTMENT OF HEALTH AND HUMAN SERVICES Final Effect of Designation of a Class of Employees for Addition to the Special Exposure Cohort AGENCY: National Institute for Occupational Safety and Health...). ACTION: Notice. SUMMARY: HHS gives notice concerning the final effect of the HHS decision to designate a...

78 FR 21954 - Final Effect of Designation of a Class of Employees for Addition to the Special Exposure Cohort

Science.gov (United States)

2013-04-12

... DEPARTMENT OF HEALTH AND HUMAN SERVICES Final Effect of Designation of a Class of Employees for Addition to the Special Exposure Cohort AGENCY: National Institute for Occupational Safety and Health...). ACTION: Notice. SUMMARY: HHS gives notice concerning the final effect of the HHS decision to designate a...

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)

1995 Baseline solid waste management system description

International Nuclear Information System (INIS)

Anderson, G.S.; Konynenbelt, H.S.

1995-09-01

This provides a detailed solid waste system description that documents the treatment, storage, and disposal (TSD) strategy for managing Hanford's solid low-level waste, low-level mixed waste, transuranic and transuranic mixed waste, and greater-than-Class III waste. This system description is intended for use by managers of the solid waste program, facility and system planners, as well as system modelers. The system description identifies the TSD facilities that constitute the solid waste system and defines these facilities' interfaces, schedules, and capacities. It also provides the strategy for treating each of the waste streams generated or received by the Hanford Site from generation or receipt through final destination

SNF AGING SYSTEM DESCRIPTION DOCUMENT

Energy Technology Data Exchange (ETDEWEB)

L.L. Swanson

2005-04-06

The purpose of this system description document (SDD) is to establish requirements that drive the design of the spent nuclear fuel (SNF) aging system and associated bases, which will allow the design effort to proceed. This SDD will be revised at strategic points as the design matures. This SDD identifies the requirements and describes the system design, as it currently exists, with emphasis on attributes of the design provided to meet the requirements. This SDD is an engineering tool for design control; accordingly, the primary audience and users are design engineers. This SDD is part of an iterative design process. It leads the design process with regard to the flow down of upper tier requirements onto the system. Knowledge of these requirements is essential in performing the design process. The SDD follows the design with regard to the description of the system. The description provided in the SDD reflects the current results of the design process. Throughout this SDD, the term aging cask applies to vertical site-specific casks and to horizontal aging modules. The term overpack is a vertical site-specific cask that contains a dual-purpose canister (DPC) or a disposable canister. Functional and operational requirements applicable to this system were obtained from ''Project Functional and Operational Requirements'' (F&OR) (Curry 2004 [DIRS 170557]). Other requirements that support the design process were taken from documents such as ''Project Design Criteria Document'' (PDC) (BSC 2004 [DES 171599]), ''Site Fire Hazards Analyses'' (BSC 2005 [DIRS 172174]), and ''Nuclear Safety Design Bases for License Application'' (BSC 2005 [DIRS 171512]). The documents address requirements in the ''Project Requirements Document'' (PRD) (Canori and Leitner 2003 [DIRS 166275]). This SDD includes several appendices. Appendix A is a Glossary; Appendix B is a list of key system charts

SNF AGING SYSTEM DESCRIPTION DOCUMENT

International Nuclear Information System (INIS)

L.L. Swanson

2005-01-01

The purpose of this system description document (SDD) is to establish requirements that drive the design of the spent nuclear fuel (SNF) aging system and associated bases, which will allow the design effort to proceed. This SDD will be revised at strategic points as the design matures. This SDD identifies the requirements and describes the system design, as it currently exists, with emphasis on attributes of the design provided to meet the requirements. This SDD is an engineering tool for design control; accordingly, the primary audience and users are design engineers. This SDD is part of an iterative design process. It leads the design process with regard to the flow down of upper tier requirements onto the system. Knowledge of these requirements is essential in performing the design process. The SDD follows the design with regard to the description of the system. The description provided in the SDD reflects the current results of the design process. Throughout this SDD, the term aging cask applies to vertical site-specific casks and to horizontal aging modules. The term overpack is a vertical site-specific cask that contains a dual-purpose canister (DPC) or a disposable canister. Functional and operational requirements applicable to this system were obtained from ''Project Functional and Operational Requirements'' (F andOR) (Curry 2004 [DIRS 170557]). Other requirements that support the design process were taken from documents such as ''Project Design Criteria Document'' (PDC) (BSC 2004 [DES 171599]), ''Site Fire Hazards Analyses'' (BSC 2005 [DIRS 172174]), and ''Nuclear Safety Design Bases for License Application'' (BSC 2005 [DIRS 171512]). The documents address requirements in the ''Project Requirements Document'' (PRD) (Canori and Leitner 2003 [DIRS 166275]). This SDD includes several appendices. Appendix A is a Glossary; Appendix B is a list of key system charts, diagrams, drawings, lists and additional supporting information; and Appendix C is a list of

76 FR 72928 - Final Effect of Designation of a Class of Employees for Addition to the Special Exposure Cohort

Science.gov (United States)

2011-11-28

... DEPARTMENT OF HEALTH AND HUMAN SERVICES Final Effect of Designation of a Class of Employees for Addition to the Special Exposure Cohort AGENCY: National Institute for Occupational Safety and Health... concerning the final effect of the HHS decision to designate a class of employees from Vitro Manufacturing in...

76 FR 7852 - Final Effect of Designation of a Class of Employees for Addition to the Special Exposure Cohort

Science.gov (United States)

2011-02-11

... DEPARTMENT OF HEALTH AND HUMAN SERVICES Final Effect of Designation of a Class of Employees for Addition to the Special Exposure Cohort AGENCY: National Institute for Occupational Safety and Health... concerning the final effect of the HHS decision to designate a class of employees from Texas City Chemicals...

76 FR 59701 - Final Effect of Designation of a Class of Employees for Addition to the Special Exposure Cohort

Science.gov (United States)

2011-09-27

... DEPARTMENT OF HEALTH AND HUMAN SERVICES Final Effect of Designation of a Class of Employees for Addition to the Special Exposure Cohort AGENCY: National Institute for Occupational Safety and Health... concerning the final effect of the HHS decision to designate a class of employees from the Sandia National...

75 FR 67364 - Final Effect of Designation of a Class of Employees for Addition to the Special Exposure Cohort

Science.gov (United States)

2010-11-02

... DEPARTMENT OF HEALTH AND HUMAN SERVICES Final Effect of Designation of a Class of Employees for Addition to the Special Exposure Cohort AGENCY: National Institute for Occupational Safety and Health... concerning the final effect of the HHS decision to designate a class of employees from the Blockson Chemical...

75 FR 51816 - Final Effect of Designation of a Class of Employees for Addition to the Special Exposure Cohort

Science.gov (United States)

2010-08-23

... Final Effect of Designation of a Class of Employees for Addition to the Special Exposure Cohort AGENCY...). ACTION: Notice. SUMMARY: HHS gives notice concerning the final effect of the HHS decision to designate a... Special Exposure Cohort (SEC) under the Energy Employees Occupational Illness Compensation Program Act of...

75 FR 27785 - Final Effect of Designation of a Class of Employees for Addition to the Special Exposure Cohort

Science.gov (United States)

2010-05-18

... DEPARTMENT OF HEALTH AND HUMAN SERVICES Final Effect of Designation of a Class of Employees for Addition to the Special Exposure Cohort AGENCY: National Institute for Occupational Safety and Health... concerning the final effect of the decision to designate a class of employees from Area IV of the Santa...

Qualitative Descriptive Methods in Health Science Research.

Science.gov (United States)

Colorafi, Karen Jiggins; Evans, Bronwynne

2016-07-01

The purpose of this methodology paper is to describe an approach to qualitative design known as qualitative descriptive that is well suited to junior health sciences researchers because it can be used with a variety of theoretical approaches, sampling techniques, and data collection strategies. It is often difficult for junior qualitative researchers to pull together the tools and resources they need to embark on a high-quality qualitative research study and to manage the volumes of data they collect during qualitative studies. This paper seeks to pull together much needed resources and provide an overview of methods. A step-by-step guide to planning a qualitative descriptive study and analyzing the data is provided, utilizing exemplars from the authors' research. This paper presents steps to conducting a qualitative descriptive study under the following headings: describing the qualitative descriptive approach, designing a qualitative descriptive study, steps to data analysis, and ensuring rigor of findings. The qualitative descriptive approach results in a summary in everyday, factual language that facilitates understanding of a selected phenomenon across disciplines of health science researchers. © The Author(s) 2016.

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.

Final design of ITER port plug test facility

Energy Technology Data Exchange (ETDEWEB)

Cerisier, Thierry, E-mail: thierry.cerisier@yahoo.fr [ITER Organization, Route de Vinon-sur-Verdon, CS 90046, St Paul-lez-Durance Cedex, 13067 (France); Levesy, Bruno [ITER Organization, Route de Vinon-sur-Verdon, CS 90046, St Paul-lez-Durance Cedex, 13067 (France); Romannikov, Alexander [Institution “Project Center ITER”, Kurchatov sq. 1, Building 3, Moscow 123182 (Russian Federation); Rumyantsev, Yuri [JSC “Cryogenmash”, Moscow reg., Balashikha 143907 (Russian Federation); Cordier, Jean-Jacques; Dammann, Alexis [ITER Organization, Route de Vinon-sur-Verdon, CS 90046, St Paul-lez-Durance Cedex, 13067 (France); Minakov, Victor; Rosales, Natalya; Mitrofanova, Elena [JSC “Cryogenmash”, Moscow reg., Balashikha 143907 (Russian Federation); Portone, Sergey; Mironova, Ekaterina [Institution “Project Center ITER”, Kurchatov sq. 1, Building 3, Moscow 123182 (Russian Federation)

2016-11-01

Highlights: • We introduce the port plug test facility (purpose and status of the design). • We present the PPTF sub-systems. • We present the environmental and functional tests. • We present the occupational and nuclear safety functions. • We conclude on the achievements and next steps. - Abstract: To achieve the overall ITER machine availability target, the availability of diagnostics and heating port plugs shall be as high as 99.5%. To fulfill this requirement, it is mandatory to test the port plugs at operating temperature before installation on the machine and after refurbishment. The ITER port plug test facility (PPTF) is composed of several test stands that can be used to test the port plugs whereas at the end of manufacturing (in a non-nuclear environment), or after refurbishment in the ITER hot cell facility. The PPTF provides the possibility to perform environmental (leak tightness, vacuum and thermo-hydraulic performances) and functional tests (radio frequency acceptance tests, behavior of the plugs’ steering mechanism and calibration of diagnostics) on upper and equatorial port plugs. The final design of the port plug test facility is described. The configuration of the standalone test stands and the integration in the hot cell facility are presented.

Final design of the generic equatorial port plug structure for ITER diagnostic systems

International Nuclear Information System (INIS)

Udintsev, V.S.; Maquet, P.; Alexandrov, E.; Casal, N.; Cuenca, D.; Drevon, J.-M.; Feder, R.; Friconneau, J.P.; Giacomin, T.; Guirao, J.; Iglesias, S.; Josseaume, F.; Levesy, B.; Loesser, D.; Ordieres, J.; Quinn, E.; Pak, S.; Penot, C.; Pitcher, C.S.; Portalès, M.

2015-01-01

The Diagnostic Generic Equatorial Port Plug (GEPP) is designed to be common to all equatorial port-based diagnostic systems. It is designed to survive throughout the lifetime of ITER for 20 years, 30,000 discharges, and 3000 disruptions. The EPP structure dimensions (without Diagnostic First Walls and Diagnostic Shield Modules) are L2.9 × W1.9 × H2.4 m"3. The length of the fully integrated EPP is 3174 mm. The weight of the EPP structure is about 15 t, whereas the total weight of the integrated EPP may be up to 45 t. The EPP structure provides a flexible platform for a variety of diagnostics. The Diagnostic Shield Module assemblies, or drawers, allow a modular approach with respect to diagnostic integration and maintenance. In the nuclear phase of ITER operations, they will be remotely inserted into the EPP structure in the Hot Cell Facility. The port plug structure must also contribute to the nuclear shielding, or plugging, of the port and further contain circulated water to allow cooling during operation and heating during bake-out. The Final Design of the GEPP has been successfully passed in late 2013 and is now heading toward manufacturing. The final design of the GEPP includes interfaces, manufacturing, R&D, operation and maintenance, load cases and analysis of failure modes.

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

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

Wind turbine blockset in Saber. General overview and description of the models

DEFF Research Database (Denmark)

Iov, Florin; Timbus, Adrian Vasile; Hansen, Anca Daniela

This report presents a new developed Saber Toolbox for wind turbine applications. This toolbox has been developed during the research project “Simulation Platform to model, optimize and design wind turbines”. The report provides a quick overview of the Saber and then explains the structure...... of this simulation package, which is different than other tools e.g. Matlab/Simulink. Then the structure of the toolbox is shown as well as the description of the developed models. The main focus here is to underline the special structure of the models, which are a mixture of Saber built-in blocks and new developed...... blocks. Since the developed models are based on Saber built-in blocks, a description of the libraries from Saber is given. Then some simulation results using the developed models are shown. Finally some general conclusions regarding this new developed Toolbox as well as some directions for future work...

Wind Turbine Blockset in Saber. General Overview and Description of the Model

DEFF Research Database (Denmark)

Iov, Florin; Timbus, Adrian Vasile; Hansen, A. D.

This report presents a new developed Saber Toolbox for wind turbine applications. This toolbox has been developed during the research project ?Simulation Platform to model, optimize and design wind turbines?. The report provides a quick overview of the Saber and then explains the structure...... of this simulation package, which is different than other tools e.g. Matlab/Simulink. Then the structure of the toolbox is shown as well as the description of the developed models. The main focus here is to underline the special structure of the models, which are a mixture of Saber built-in blocks and new developed...... blocks. Since the developed models are based on Saber built-in blocks, a description of the libraries from Saber is given. Then some simulation results using the developed models are shown. Finally some general conclusions regarding this new developed Toolbox as well as some directions for future work...

Implementing Project-Based Learning (PBL) in Final Collection to Improve the Quality of Fashion Design Student

OpenAIRE

Indarti, Indarti

2016-01-01

Fashion design education is one of education that prepares students to work in fashion design field. Students research future fashion trends, sketch designs, select colors, fabrics and patterns, and give instructions on how to make the products they designed. Fashion design education not only nurture and develop student's creative skills, it also teaches essential practical skills such as production techniques and material properties, to create a final product. According to this, new educatio...

Final design of the Korean AC/DC converters for the ITER coil power supply system

Energy Technology Data Exchange (ETDEWEB)

Oh, Jong-Seok, E-mail: jsoh@nfri.re.kr [ITER Korea, National Fusion Research Institute, Daejeon 305-806 (Korea, Republic of); Choi, Jungwan; Suh, Jae-Hak; Choi, Jihyun [ITER Korea, National Fusion Research Institute, Daejeon 305-806 (Korea, Republic of); Lee, Lacksang; Kim, Changwoo; Park, Hyungjin; Jo, Seongman; Lee, Seungyun; Hwang, Kwangcheol; Liu, Hyoyol [Dawonsys Corp., Siheung 429-450 (Korea, Republic of); Hong, Ki-Don; Sim, Dong-Joon; Lee, Jang-Soo [Hyosung Corp., Gongdeok-Dong, Seoul 121-720 (Korea, Republic of); Lee, Eui-Jae; Kwon, Yang-Hae; Lee, Dae-Yeol; Ko, Ki-Won; Kim, Jong-Min [Mobiis Corp., Yangjae-dong, Seoul 137-888 (Korea, Republic of); Song, Inho [ITER Organization, Route de Vinon sur Verdon, CS 90 046, 13067 St. Paul Lez Durance Cedex (France); and others

2015-10-15

The final design of the ITER TF, CS, CC and VS AC/DC converters has been completed to implement ITER requirements following the detailed design and refinements of the preliminary design. The number of parallel thyristors and the rating of fuses are coordinated to keep those devices within the explosion limit even under most severe fault conditions. The impedance of the converter transformer has been optimized taking into account the energization inrush current, short circuit current, reactive power consumption and the available DC voltage. To ensure system integrity, AC/DC converters are mechanically divided into transformers, AC busbars, 6-pulse bridges, DC interconnecting busbars and DC reactors, and then all subsystems are decoupled by flexible links. To provide stable real time network communication down to the converters, a one GbE link is deployed between master controllers and local controllers. IEEE 1588 is implemented to the embedded controllers for precision time synchronization. This paper describes the detailed solutions implemented in the final design for the ITER AC/DC converters with R&D results of converter prototypes.

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 ...

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).

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

Employing a Qualitative Description Approach in Health Care Research.

Science.gov (United States)

Bradshaw, Carmel; Atkinson, Sandra; Doody, Owen

2017-01-01

A qualitative description design is particularly relevant where information is required directly from those experiencing the phenomenon under investigation and where time and resources are limited. Nurses and midwives often have clinical questions suitable to a qualitative approach but little time to develop an exhaustive comprehension of qualitative methodological approaches. Qualitative description research is sometimes considered a less sophisticated approach for epistemological reasons. Another challenge when considering qualitative description design is differentiating qualitative description from other qualitative approaches. This article provides a systematic and robust journey through the philosophical, ontological, and epistemological perspectives, which evidences the purpose of qualitative description research. Methods and rigor issues underpinning qualitative description research are also appraised to provide the researcher with a systematic approach to conduct research utilizing this approach. The key attributes and value of qualitative description research in the health care professions will be highlighted with the aim of extending its usage.

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.

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.

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.

Experiences of final year nursing students in their preparedness to become registered nurses

Directory of Open Access Journals (Sweden)

S Carlson

2005-09-01

Full Text Available The objectives of this study were: firstly, to explore and describe the experiences of final year nursing students relating to how they experience their preparedness to fulfil the role of professional nurse; secondly, to explore and describe the experiences of novice professional nurses in the role of professional nurse; finally, to generate a model which will assist the final year nursing student to become a professional nurse. A theory-generative, qualitative, explorative, descriptive and contextual research design was utilized to reach the objectives of the study. Results indicated that final year nursing students experience a lack of confidence to take on the responsibilities of professional nursing. The results are displayed in table form and discussed in the article. This abstract forms part of a bigger study that addresses the professional maturity of the novice professional nurse for the practice of nursing.

Project No. 8 - Final decommissioning plan

International Nuclear Information System (INIS)

2000-01-01

Ignalina NPP should prepare the final Ignalina NPP unit 1 decommissioning plan by march 31, 2002. This plan should include the following : description of Ignalina NPP and the Ignalina NPP boundary that could be influenced by decommissioning process; decommissioning strategy selected and a logical substantiation for this selection; description of the decommissioning actions suggested and a time schedule for the actions to be performed; conceptual safety and environmental impact assessment covering ionizing radiation and other man and environment impact; description of the environmental monitoring program proposed during decommissioning process; description of the waste management proposed; assessment of decommissioning expenses including waste management, accumulated funds and other sources. Estimated project cost - 0.75 M EURO

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

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

Energy Technology Data Exchange (ETDEWEB)

Pak, Sunil, E-mail: paksunil@nfri.re.kr [National Fusion Research Institute, Daejeon (Korea, Republic of); Feder, Russell [Princeton Plasma Physics Laboratory, Princeton, NJ (United States); Giacomin, Thibaud; Guirao, Julio; Iglesias, Silvia; Josseaume, Fabien [ITER Organization, Route de Vinon sur Verdon, 13115 St Paul-lez-Durance (France); Kalish, Michael; Loesser, Douglas [Princeton Plasma Physics Laboratory, Princeton, NJ (United States); Maquet, Philippe [ITER Organization, Route de Vinon sur Verdon, 13115 St Paul-lez-Durance (France); Ordieres, Javier; Panizo, Marcos [NATEC, Ingenieros, Gijón (Spain); Pitcher, Spencer; Portalès, Mickael [ITER Organization, Route de Vinon sur Verdon, 13115 St Paul-lez-Durance (France); Proust, Maxime [CEA, Cadarache, St. Paul-lez-Durance (France); Ronden, Dennis [FOM Institute DIFFER, Nieuwegein (Netherlands); Serikov, Arkady [Karlsruhe Institute of Technology, Eggenstein-Leopoldshafen (Germany); Suarez, Alejandro [ITER Organization, Route de Vinon sur Verdon, 13115 St Paul-lez-Durance (France); Tanchuk, Victor [NIIEFA, St.-Petersburg (Russian Federation); Udintsev, Victor; Vacas, Christian [ITER Organization, Route de Vinon sur Verdon, 13115 St Paul-lez-Durance (France); and others

2016-01-15

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 in 2013, is described here. The diagnostic port plug is cantilevered to the vacuum vessel with a heavy payload at the front, so called the diagnostic first wall (DFW) and the diagnostic shield module (DSM). Most of electromagnetic (EM) load (∼80%) occurs in DFW/DSM. Therefore, the mounting design to transfer the EM load from DFW/DSM to the GUPP structure is challenging, which should also comply with thermal expansion and tolerance for assembly and manufacturing. Another key design parameter to be considered is the gap between the port plug and the vacuum vessel port. The gap should be large enough to accommodate the remote handling of the heavy port plug (max. 25 t), the structural deflection due to external loads and machine assembly tolerance. At the same time, the gap should be minimized to stop the neutron streaming according to the ALARA (as low as reasonably achievable) principle. With these design constraints, the GUPP structure should also provide space for diagnostic integration as much as possible. This requirement has led to the single wall structure having the gun-drilled water channels inside the structure. Furthermore, intensive efforts have been made on the manufacturing study including material selection, manufacturing codes and French regulation related to nuclear equipment and safety. All these main design and manufacturing aspects are discussed in this paper, including requirements, interfaces, loads and structural assessment and maintenance.

Employing a Qualitative Description Approach in Health Care Research

Science.gov (United States)

Bradshaw, Carmel; Atkinson, Sandra; Doody, Owen

2017-01-01

A qualitative description design is particularly relevant where information is required directly from those experiencing the phenomenon under investigation and where time and resources are limited. Nurses and midwives often have clinical questions suitable to a qualitative approach but little time to develop an exhaustive comprehension of qualitative methodological approaches. Qualitative description research is sometimes considered a less sophisticated approach for epistemological reasons. Another challenge when considering qualitative description design is differentiating qualitative description from other qualitative approaches. This article provides a systematic and robust journey through the philosophical, ontological, and epistemological perspectives, which evidences the purpose of qualitative description research. Methods and rigor issues underpinning qualitative description research are also appraised to provide the researcher with a systematic approach to conduct research utilizing this approach. The key attributes and value of qualitative description research in the health care professions will be highlighted with the aim of extending its usage. PMID:29204457

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

VHDL Descriptions for the FPGA Implementation of PWL-Function-Based Multi-Scroll Chaotic Oscillators.

Directory of Open Access Journals (Sweden)

Esteban Tlelo-Cuautle

Full Text Available Nowadays, chaos generators are an attractive field for research and the challenge is their realization for the development of engineering applications. From more than three decades ago, chaotic oscillators have been designed using discrete electronic devices, very few with integrated circuit technology, and in this work we propose the use of field-programmable gate arrays (FPGAs for fast prototyping. FPGA-based applications require that one be expert on programming with very-high-speed integrated circuits hardware description language (VHDL. In this manner, we detail the VHDL descriptions of chaos generators for fast prototyping from high-level programming using Python. The cases of study are three kinds of chaos generators based on piecewise-linear (PWL functions that can be systematically augmented to generate even and odd number of scrolls. We introduce new algorithms for the VHDL description of PWL functions like saturated functions series, negative slopes and sawtooth. The generated VHDL-code is portable, reusable and open source to be synthesized in an FPGA. Finally, we show experimental results for observing 2, 10 and 30-scroll attractors.

VHDL Descriptions for the FPGA Implementation of PWL-Function-Based Multi-Scroll Chaotic Oscillators.

Science.gov (United States)

Tlelo-Cuautle, Esteban; Quintas-Valles, Antonio de Jesus; de la Fraga, Luis Gerardo; Rangel-Magdaleno, Jose de Jesus

2016-01-01

Nowadays, chaos generators are an attractive field for research and the challenge is their realization for the development of engineering applications. From more than three decades ago, chaotic oscillators have been designed using discrete electronic devices, very few with integrated circuit technology, and in this work we propose the use of field-programmable gate arrays (FPGAs) for fast prototyping. FPGA-based applications require that one be expert on programming with very-high-speed integrated circuits hardware description language (VHDL). In this manner, we detail the VHDL descriptions of chaos generators for fast prototyping from high-level programming using Python. The cases of study are three kinds of chaos generators based on piecewise-linear (PWL) functions that can be systematically augmented to generate even and odd number of scrolls. We introduce new algorithms for the VHDL description of PWL functions like saturated functions series, negative slopes and sawtooth. The generated VHDL-code is portable, reusable and open source to be synthesized in an FPGA. Finally, we show experimental results for observing 2, 10 and 30-scroll attractors.

Seismic design and analysis of nuclear fuel cycle facilities in France

International Nuclear Information System (INIS)

Sollogoub, P.

2001-01-01

Methodology for seismic design of nuclear fuel facilities and power plants in France is described. After the description of regulatory and normative texts for seismic design, different elements are examined: definition of ground motion, analysis methods, new trends, reevaluation and specificity of Fuel Cycle Facilities. R/D developments are explicated in each part. Their final objective are to better quantify the margins of each step which, in relation with safety analysis,lead to balanced design, analysis and retrofit rules. (author)

Ship design methodologies of preliminary design

CERN Document Server

Papanikolaou, Apostolos

2014-01-01

This book deals with ship design and in particular with methodologies of the preliminary design of ships. The book is complemented by a basic bibliography and five appendices with useful updated charts for the selection of the main dimensions and other basic characteristics of different types of ships (Appendix A), the determination of hull form  from the data of systematic hull form series (Appendix B), the detailed description of the relational method for the preliminary estimation of ship weights (Appendix C), a brief review of the historical evolution of shipbuilding science and technology from the prehistoric era to date (Appendix D) and finally a historical review of regulatory developments of ship's damage stability to date (Appendix E).  The book can be used as textbook for ship design courses or as additional reading for university or college students of naval architecture courses and related disciplines; it may also serve as a reference book for naval architects, practicing engineers of rel...

The development of mobile computation and the related formal description

International Nuclear Information System (INIS)

Jin Yan; Yang Xiaozong

2003-01-01

The description and research for formal representation in mobile computation, which is very instructive to resolve the status transmission, domain administration, authentication. This paper presents the descriptive communicating process and computational process from the view of formal calculus, what's more, it construct a practical application used by mobile ambient. Finally, this dissertation shows the future work and direction. (authors)

CASK/MSC/WP PREPARATION SYSTEM DESCRIPTION DOCUMENT

International Nuclear Information System (INIS)

S. Drummond

2005-01-01

The purpose of this system description document (SDD) is to establish requirements that drive the design of the Cask/MSC/WP preparation system and their bases to allow the design effort to proceed to license application. This SDD is a living document that will be revised at strategic points as the design matures over time. This SDD identifies the requirements and describes the system design, as they exist at this time, with emphasis on those attributes of the design provided to meet the requirements. This SDD has been developed to be an engineering tool for design control. Accordingly, the primary audience and users are design engineers. This type of SDD both leads and trails the design process. It leads the design process with regard to the flow down of upper tier requirements onto the system. Knowledge of these requirements is essential in performing the design process. This SDD trails the design with regard to the description of the system. The description provided in the SDD is a reflection of the results of the design process to date. This SDD addresses the ''Project Requirements Document'' (PRD) (Canori and Leitner 2003 [DIRS 166275]) requirements. Additional PRD requirements may be cited, as applicable, to drive the design of specific aspects of the system, with justifications provided in the basis. Functional and operational requirements applicable to this system are obtained from the ''Project Functional and Operational Requirements'' (F and OR) (Curry 2004 [DIRS 170557]) document. Other requirements to support the design process have been taken from higher-level requirements documents such as the ''Project Design Criteria Document'' (PDC) (BSC 2004 [DIRS 171599]) and the preclosure safety analyses

Decontamination and dismantlement of the JANUS Reactor at Argonne National Laboratory-East. Project final report

International Nuclear Information System (INIS)

Fellhauer, C.R.; Clark, F.R.

1997-10-01

The decontamination and dismantlement of the JANUS Reactor at Argonne National Laboratory-East (ANL-E) was completed in October 1997. Descriptions and evaluations of the activities performed and analyses of the results obtained during the JANUS D and D Project are provided in this Final Report. The following information is included: objective of the JANUS D and D Project; history of the JANUS Reactor facility; description of the ANL-E site and the JANUS Reactor facility; overview of the D and D activities performed; description of the project planning and engineering; description of the D and D operations; summary of the final status of the JANUS Reactor facility based upon the final survey results; description of the health and safety aspects of the project, including personnel exposure and OSHA reporting; summary of the waste minimization techniques utilized and total waste generated by the project; and summary of the final cost and schedule for the JANUS D and D Project

Termination of the Special Metallurgical (SM) Building at Mound Laboratory: a final report

International Nuclear Information System (INIS)

Harris, W.R.; Kokenge, B.R.; Marsh, G.C.

1976-01-01

The report describes and highlights the more important factors associated with the termination of the Special Metallurgical (SM) Building at Mound Laboratory. As a result, a written record of the more important techniques and procedures is now available for reference by others involved in similar termination efforts. Included in this report is a description of the organizational units that were used in this effort along with a description of their responsibilities. A general description of the SM Building and a discussion of the more relevant procedures and equipment that were used are also presented. In addition, pertinent Health Physics information, such as personnel exposure, final wipe levels in the terminated facility, and assays of the structure, are provided. Based on the experience gained from this project, recommendations were made regarding the design of future radioactive material handling facilities so that when they are ultimately terminated the effort can be accomplished more efficiently

National Ignition Facility subsystem design requirements final optics assembly subsystem SSDR 1.8.7

International Nuclear Information System (INIS)

Adams, C.

1996-01-01

This SSDR establishes the performance, design, development and test requirements for the Final Optic Assembly (FOA). The FOA (WBS 1.8.7) as part of the Target Experimental System (1.8) includes vacuum windows, frequency conversion crystals, focus lens, debris shields and supporting mechanical equipment

Design and test of the final ALICE SDD CARLOS end ladder board

CERN Document Server

Antinori, S; Falchieri, D; Gabrielli, A; Gandolfi, E; Masetti, M; Tosellob, F

2007-01-01

The paper presents the design and test of the final prototype of the CARLOS (Compression And Run Length Encoding Subsystem) end ladder board that is going to be used in the ALICE experiment at CERN. This board is able to compress data coming from one Silicon Drift Detector (SDD) front-end electronics and to send them towards the data concentrator card CARLOSrx in counting room via a 800 Mb/s optical link. The board design faces several constraints, mainly size (54x49 mm) and radiation tolerance: for this reason the board contains several CERN developed ASICs. A test setup has been realized for selecting the good devices among the 500 cards already produced.

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

Four ignition TNS tokamak reactor systems: design summary

International Nuclear Information System (INIS)

Flanagan, C.A.

1977-10-01

Principal TNS objectives assumed included: (1) demonstration of ignition and burning dynamics; and (2) reactor technology forcing. The selection of an overall design approach for TNS required an early quantitative assessment of the most important design issues; namely, choice of ignition plasma design conditions (principally size and confining field of axis), and choice of toroidal field coil technology (resistive or superconducting windings). The design space investigated in this study ranged from ignited plasmas (elongated) with minor radii varying between 0.8 m (TFTR-like) and approximately 2.0 m (EPR-like). Four TF coil types were examined; these included copper, NbTi, Nb 3 Sn, and a hybrid design employing nested coils of copper and NbTi. A final step involved a further comparison of the four reference concepts using decision modeling techniques as a mechanism for selecting a preferred design approach for the TNS mission. Section 3.0 describes the TNS study process. Section 4.0 presents a summary of the parameters for the four reference point designs. Finally, Section 5.0 presents a brief description of the design features of many of the systems comprising the TNS design

Operational Experiences Tuning the ATF2 Final Focus Optics Towards Obtaining a 37nm Electron Beam IP Spot Size

CERN Document Server

White, Glen; Woodley, Mark; Bai, Sha; Bambade, Philip; Renier, Yves; Bolzon, Benoit; Kamiya, Yoshio; Komamiya, Sachio; Oroku, Masahiro; Yamaguchi, Yohei; Yamanaka, Takashi; Kubo, Kiyoshi; Kuroda, Shigeru; Okugi, Toshiyuki; Tauchi, Toshiaki; Marin, Eduardo

2010-01-01

The primary aim of the ATF2 research accelerator is to test a scaled version of the final focus optics planned for use in next-generation linear lepton colliders. ATF2 consists of a 1.3 GeV linac, damping ring providing lowemittance electron beams (<12pm in the vertical plane), extraction line and final focus optics. The design details of the final focus optics and implementation at ATF2 are presented elsewhere. The ATF2 accelerator is currently being commissioned, with a staged approach to achieving the design IP spot size. It is expected that as we implement more demanding optics and reduce the vertical beta function at the IP, the tuning becomes more difficult and takes longer. We present here a description of the implementation of the tuning procedures and describe operational experiences and performances

Final design and status of the NSLS vacuum system

International Nuclear Information System (INIS)

Schuchman, J.C.

1982-01-01

We describe the final system, as built, reasons for changes and the general status of the NSLS. The NSLS is a dedicated facility for the purpose of producing synchrotron radiation. It consists of an electron linac-booster injector system, and two storage rings, one for uv research and the other for x-ray research. (Synchrotron radiation is produced by accelerating electrons in the storage rings.) The design current and energies are 1000 ma at 700 MeV for the vuv ring and 500 ma at 2.5 GeV for the x-ray ring. A total of 44 experimental beam ports are available for use. Since each beam port may be divided into two or more experimentall beam lines, it is quite plausible to have upward of 100 simultaneously operating beam lines

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

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 ...

Final report.

Science.gov (United States)

2017-02-14

This project report provides a descriptive overview of the architecture and design of wireless underground radio frequency smart sensors, data collection and Internet of Things (IOT) [8] transmission system and an SLR decision support system. The roa...

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 ...

CASK/MSC/WP PREPARATION SYSTEM DESCRIPTION DOCUMENT

Energy Technology Data Exchange (ETDEWEB)

S. Drummond

2005-04-12

The purpose of this system description document (SDD) is to establish requirements that drive the design of the Cask/MSC/WP preparation system and their bases to allow the design effort to proceed to license application. This SDD is a living document that will be revised at strategic points as the design matures over time. This SDD identifies the requirements and describes the system design, as they exist at this time, with emphasis on those attributes of the design provided to meet the requirements. This SDD has been developed to be an engineering tool for design control. Accordingly, the primary audience and users are design engineers. This type of SDD both leads and trails the design process. It leads the design process with regard to the flow down of upper tier requirements onto the system. Knowledge of these requirements is essential in performing the design process. This SDD trails the design with regard to the description of the system. The description provided in the SDD is a reflection of the results of the design process to date. This SDD addresses the ''Project Requirements Document'' (PRD) (Canori and Leitner 2003 [DIRS 166275]) requirements. Additional PRD requirements may be cited, as applicable, to drive the design of specific aspects of the system, with justifications provided in the basis. Functional and operational requirements applicable to this system are obtained from the ''Project Functional and Operational Requirements'' (F&OR) (Curry 2004 [DIRS 170557]) document. Other requirements to support the design process have been taken from higher-level requirements documents such as the ''Project Design Criteria Document'' (PDC) (BSC 2004 [DIRS 171599]) and the preclosure safety analyses.

Mining skeletal phenotype descriptions from scientific literature.

Directory of Open Access Journals (Sweden)

Tudor Groza

Full Text Available Phenotype descriptions are important for our understanding of genetics, as they enable the computation and analysis of a varied range of issues related to the genetic and developmental bases of correlated characters. The literature contains a wealth of such phenotype descriptions, usually reported as free-text entries, similar to typical clinical summaries. In this paper, we focus on creating and making available an annotated corpus of skeletal phenotype descriptions. In addition, we present and evaluate a hybrid Machine Learning approach for mining phenotype descriptions from free text. Our hybrid approach uses an ensemble of four classifiers and experiments with several aggregation techniques. The best scoring technique achieves an F-1 score of 71.52%, which is close to the state-of-the-art in other domains, where training data exists in abundance. Finally, we discuss the influence of the features chosen for the model on the overall performance of the method.

Fixation, description and DNA barcode of a neotype for Botryllus schlosseri (Pallas, 1766) (Tunicata, Ascidiacea).

Science.gov (United States)

Brunetti, Riccardo; Manni, Lucia; Mastrototaro, Francesco; Gissi, Carmela; Gasparini, Fabio

2017-11-22

Botryllus schlosseri is a widespread colonial ascidian commonly considered cosmopolitan and amply used as model for researches ranging from developmental biology to immunobiology. Recently, molecular data lead to hypothesize that the species named B. schlosseri may consist of more than a single taxon. Indeed, five highly divergent clades, named A-E, have been genetically identified and are referred as cryptic species. In this context, and lacking both a type and a detailed morphological description, we believe that it is necessary, as a taxonomic reference point, to designate a neotype and re-describe the species. Therefore, a sample from the Lagoon of Venice (Adriatic Sea, Italy) was deposited as neotype in the Natural History Museum of Venice (Italy), preserved both in formalin and in 90% ethanol. Here we provide a morphological description of the suggested neotype of B. schlosseri that takes into account several developmental stages (oozooid, zooid of first blastogenic generations, and mature zooid) and is carefully compared with the previous descriptions of samples coming from other European and non-European localities. Finally, we associate our morphological description to a "DNA barcode", consisting in a long fragment of the mitochondrial COI gene. Our description is associated to clade A, although at now we cannot guarantee that this association is univocal.

Summary description of the Fast Flux Test Facility

International Nuclear Information System (INIS)

Cabell, C.P.

1980-12-01

This document has been compiled and issued to provide an illustrated engineering summary description of the FFTF. The document is limited to a description of the plant and its functions, and does not cover the extensive associated programs that have been carried out in the fields of design, design analysis, safety analysis, fuels development, equipment development and testing, quality assurance, equipment fabrication, plant construction, acceptance testing, operations planning and training, and the like

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.

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

A systems approach to the design of personal armour for explosive ordnance disposal

OpenAIRE

Couldrick, C A

2004-01-01

A qualitative description of the personal armour design system is elicited by comparing armour throughout the ages. Inputs that 'shape' designs are the materials technology, threat, wearer, task and environment. The emergent properties of protection, ergonomic effectiveness and financial cost form the basis of trade-offs to select final solutions. Work on the protection subsystem refines the key positive emergent property of personal armour. Existing quantifications of protection effective...

Computerized Italian criticality guide, description and validation

International Nuclear Information System (INIS)

Carotenuto, M.; Landeyro, P.A.

1988-10-01

Our group is developing an 'expert system' for collecting engineering know-how on back-end nuclear plant design. An expert system is the most suitable software tool for our problem. During the analysis, the design process was divided into different branches. At each branch of the design process the Expert System relates a computerized design procedure. Any design procedure is composed of a set of design methods, together with their condition of application and reliability limits. In the framework of this expert system, the nuclear criticality safety analysis procedure was developed, in the form of a computerized criticality guide, attempting to reproduce the designer's normal 'reasoning' process. The criticality guide is composed of two parts: A computerized text, including theory, a description of the accidents occurred in the past and a description of the italian design experience; An interactive computer aided calculation module, containing a graphical facility for critical parameter curves. In the present report are presented the criticality guide (computerized Italian Criticality Guide) and its validation test. (author)

Computerized Italian criticality guide, description and validation

Energy Technology Data Exchange (ETDEWEB)

Carotenuto, M; Landeyro, P A [ENEA - Dipartimento Ciclo del Combustibile, Centro Ricerche Energia, Casaccia (Italy)

1988-10-15

Our group is developing an 'expert system' for collecting engineering know-how on back-end nuclear plant design. An expert system is the most suitable software tool for our problem. During the analysis, the design process was divided into different branches. At each branch of the design process the Expert System relates a computerized design procedure. Any design procedure is composed of a set of design methods, together with their condition of application and reliability limits. In the framework of this expert system, the nuclear criticality safety analysis procedure was developed, in the form of a computerized criticality guide, attempting to reproduce the designer's normal 'reasoning' process. The criticality guide is composed of two parts: A computerized text, including theory, a description of the accidents occurred in the past and a description of the italian design experience; An interactive computer aided calculation module, containing a graphical facility for critical parameter curves. In the present report are presented the criticality guide (computerized Italian Criticality Guide) and its validation test. (author)

Test results of pre-production prototype distributed ion pump design for the PEP-II Asymmetric B-Factory collider

Energy Technology Data Exchange (ETDEWEB)

Holdener, F.R.; Behne, D.; Hathaway, D. [and others

1995-04-24

We have built and tested a plate-type pre-production distributed Ion Pump (DIP) for the PEP-II B-Factory High Energy Ring (HER). The design has been an earlier design to use less materials and to costs. Penning cell hole sizes of 15, 18, and 21 mm have been tested in a uniform magnetic field of 0.18 T to optimize pumping speed. The resulting final DIP design consisting of a 7-plate, 15 mm basic cell size anode was magnetic field of the HER dipole. A description of the final optimized DIP design will be presented along with the test results of the pumping speed measurements.

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.

DEVELOPING FINAL COURSE MONOGRAPHS USING A TEAM-BASED LEARNING METHODOLOGY

Directory of Open Access Journals (Sweden)

Ani Mari Hartz

2016-04-01

Full Text Available This article describes an experience with the Team-Based Learning (TBL methodology in courses designed to support the planning and execution of final course monographs. It contains both professors’ and students’ perceptions, through observation and assessment. A qualitative approach using observation techniques and desk research was used in conjunction with a quantitative approach based on a questionnaire. The sample consisted of 49 students from a higher education institution, 27 of them in a Communication Course and the remaining 22 in a Business Administration course. Qualitative data analysis was performed through simple categorization with back-defined categories, while the quantitative data analysis employed descriptive statistics and cluster analysis using Minitab 17.1 software. The main findings include the identification of: three student profiles (designated as traditional, collaborative and practical; a preference for guidance and feedback from the professor rather than other students; and a need for a professor-led closing discussion when applying the TBL method. As regards the main benefits to students, they recognized that discussion in groups allowed them to realize how much they really know about the subject studied. Finally, most students seemed to like the TBL approach.

Rock quality designation of the hydraulic properties in the near field of a final repository for spent nuclear fuel

International Nuclear Information System (INIS)

Carlsson, Hans; Carlsson, Leif; Pusch, Roland

1989-06-01

Quality assurance of a final repository for spent nuclear fuel requires detailed information on the characteristics of the rock, backfill, canisters and the waste itself. Furthermore, and of fundamental importance, is the knowledge of the behaviour of the integrated system of the waste and the different barriers. The in-situ characteristics of the rock must therefore be assessed and their influence on and interactions with the remaining barriers must be predicted and verified. A rock quality designation process of the hydraulic properties in the near-field is out-lined both for the KBS-3 system as well as for the WP-cave system. The process, once updated and approved, will be included in a Quality Assurance Program for the final repository for spent nuclear fuel. Some of the available methods for the near-field designation process are presented as well as techniques that need further development or are not developed at all. Finally, a presentation is given of a generic designation process of the KBS-3 and WP-cave repository systems in the previously investigated area in Central Sweden, where the final repository for reactor waste, SFR, is located. Geological and hydrogeological data are here at hand and it is therefore possible to carry out a simulation of how the designation process would be accomplished. (authors) (72 figs., 12 tabs., 43 refs.)

Hadron final states in deep inelastic processes

International Nuclear Information System (INIS)

Bjorken, J.D.

1976-05-01

Lectures are presented dealing mainly with the description and discussion of hadron final states in electroproduction, colliding beams, and neutrino reactions from the point of view of the simple parton model. Also the space-time evolution of final states in the parton model is considered. It is found that the picture of space-time evolution of hadron final states in deep inelastic processes isn't totally trivial and that it can be made consistent with the hypotheses of the parton model. 39 references

System description of the Repository-Only System for the FY 1990 systems integration program studies

International Nuclear Information System (INIS)

McKee, R.W.; Young, J.R.; Konzek, G.J.

1991-07-01

This document provides both functional and physical descriptions of a conceptual high-level waste management system defined as a Repository-Only System. Its purpose is to provide a basis for required system computer modeling and system studies initiated in FY 1990 under the Systems Integration Program of the US Department of Energy's (DOE) Office of Civilian Radioactive Waste Management (OCRWM). The Repository-Only System is designed to accept 3000 MTU per year of spent fuel and 400 equivalent MTU per year of high-level wastes disposal in the geologic repository. This document contains both functional descriptions of the processes in the waste management system and physical descriptions of the equipment and facilities necessary for performance of those processes. These descriptions contain the level of detail needed for the projected systems analysis studies. The Repository-Only System contains all system components, from the waste storage facilities of the waste generators to the underground facilities for final disposal of the wastes. The major facilities in the system are the waste generator waste storage facilities, a repository facility that packages the wastes and than emplaces them in the geologic repository, and the transportation equipment and facilities for transporting the wastes between these major facilities. 18 refs., 39 figs

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...

Northeast Oregon Hatchery Project, Conceptual Design Report, Final Report.

Energy Technology Data Exchange (ETDEWEB)

Watson, Montgomery (Montgomery Watson, Bellevue, WA)

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.

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

Systematic logging utilizing a log sheet designed for drill core descriptions. An example in uranium exploration activities

International Nuclear Information System (INIS)

Sasao, Eiji; Tsuruta, Tadahiko; Iida, Yoshimasa

2000-01-01

We describe the log sheets used during uranium exploration activities for unconformity-related uranium deposits by JNC. The purpose of using the logging sheets is to standardize the objects which all geologists must observe and for data quality assurance. The log sheets are a three-part set describing basement lithology, sandstone lithology and geotechnics. We devised our own log sheets to describe both the sandstone and the underlying basement rock when we started exploration in Athabasca Basin, Canada. We modified the sheets to gain a better understanding of the geological features related to uranium mineralization, and made final improvements to satisfy required quality based on the criteria of descriptive objects and accuracy. Use of the log sheets resulted in effective performance of core logging and improvement in the display of data. (author)

The 168/E at CERN and the MARK 2. An improved processor design

International Nuclear Information System (INIS)

Kunz, P.; Botterill, D.R.; Lord, D.; Edwards, A.; Fucci, A.; Lee, G.; Martin, B.; Mornacchi, G.; Scharff-Hansen, P.; Storr, M.

1981-01-01

In the first part of this paper the history of the 168/E work at CERN is reviewed, this is followed by a short description of the hardware and software in use and finally some examples of future applications are given. In the second part of the paper the limitations of the present 168/E design are discussed and the ways that a new design, Mark 2, could overcome them are presented. (orig.)

Technical description of the Swedish natural gas distribution system

Energy Technology Data Exchange (ETDEWEB)

Nilsson, Ronny [KM Miljoeteknik AB (Sweden)

1997-06-01

This description of the Swedish distribution network has been produced to provide information for distribution companies, trade organisations, etc., who have an interest in getting a clear understanding of the technical design and standards, technical directives, etc., which have served as guidance in the development. The technical description covers the piping system from a measuring and regulating station (MR station) up to the consumer`s substation, however, only sections with a maximum operating pressure of 4 bar. By way of introduction, the description contains introductory information on supply channels, consumption patterns and the principal design of the high pressure network in Sweden 10 refs, 10 figs, 1 tab

Preliminary design report: Babcock and Wilcox BR-100 100-ton rail/barge spent fuel shipping cask

International Nuclear Information System (INIS)

1990-02-01

The purpose of this document is to provide information on burnup credit as applied to the preliminary design of the BR-100 shipping cask. There is a brief description of the preliminary basket design and the features used to maintain a critically safe system. Following the basket description is a discussion of various criticality analyses used to evaluate burnup credit. The results from these analyses are then reviewed in the perspective of fuel burnups expected to be shipped to either the final repository or a Monitored Retrievable Storage (MRS) facility. The hurdles to employing burnup credit in the certification of any cask are then outlines and reviewed. the last section gives conclusions reached as to burnup credit for the BR-100 cask, based on our analyses and experience. All information in this study refers to the cask configured to transport PWR fuel. Boiling Water Reactor (BWR) fuel satisfies the criticality requirements so that burnup credit is not needed. All calculations generated in the preparation of this report were based upon the preliminary design which will be optimized during the final design. 8 refs., 19 figs., 16 tabs

Respiratory protective device design using control system techniques

Science.gov (United States)

Burgess, W. A.; Yankovich, D.

1972-01-01

The feasibility of a control system analysis approach to provide a design base for respiratory protective devices is considered. A system design approach requires that all functions and components of the system be mathematically identified in a model of the RPD. The mathematical notations describe the operation of the components as closely as possible. The individual component mathematical descriptions are then combined to describe the complete RPD. Finally, analysis of the mathematical notation by control system theory is used to derive compensating component values that force the system to operate in a stable and predictable manner.

Conceptual design of bend, compression, and final focus components of ILSE [Induction Linac System Experiment

International Nuclear Information System (INIS)

Lee, E.P.; Fong, C.; Mukherjee, S.; Thur, W.

1989-03-01

The Induction Linac System Experiment (ILSE) includes a 180/degree/ bend system, drift compression line and a final focus, which test the analogous features of a heavy ion driver for inertial fusion. These components are novel in their transport of a space-charge-dominated ion beam with large head-to-tail velocity tilt. Their conceptual design is presented, including calculations of the beam envelope, momentum dispersion, and engineering design of magnets, vacuum system, diagnostics, alignment, and support. 3 refs., 5 figs

Characteristics of Qualitative Descriptive Studies: A Systematic Review.

Science.gov (United States)

Kim, Hyejin; Sefcik, Justine S; Bradway, Christine

2017-02-01

Qualitative description (QD) is a term that is widely used to describe qualitative studies of health care and nursing-related phenomena. However, limited discussions regarding QD are found in the existing literature. In this systematic review, we identified characteristics of methods and findings reported in research articles published in 2014 whose authors identified the work as QD. After searching and screening, data were extracted from the sample of 55 QD articles and examined to characterize research objectives, design justification, theoretical/philosophical frameworks, sampling and sample size, data collection and sources, data analysis, and presentation of findings. In this review, three primary findings were identified. First, although there were some inconsistencies, most articles included characteristics consistent with the limited available QD definitions and descriptions. Next, flexibility or variability of methods was common and effective for obtaining rich data and achieving understanding of a phenomenon. Finally, justification for how a QD approach was chosen and why it would be an appropriate fit for a particular study was limited in the sample and, therefore, in need of increased attention. Based on these findings, recommendations include encouragement to researchers to provide as many details as possible regarding the methods of their QD studies so that readers can determine whether the methods used were reasonable and effective in producing useful findings. © 2016 Wiley Periodicals, Inc. © 2016 Wiley Periodicals, Inc.

Final safety and hazards analysis for the Battelle LOCA simulation tests in the NRU reactor

International Nuclear Information System (INIS)

Axford, D.J.; Martin, I.C.; McAuley, S.J.

1981-04-01

This is the final safety and hazards report for the proposed Battelle LOCA simulation tests in NRU. A brief description of equipment test design and operating procedure precedes a safety analysis and hazards review of the project. The hazards review addresses potential equipment failures as well as potential for a metal/water reaction and evaluates the consequences. The operation of the tests as proposed does not present an unacceptable risk to the NRU Reactor, CRNL personnel or members of the public. (author)

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

Software architecture design patterns in Java

CERN Document Server

Kuchana, Partha

2004-01-01

AN INTRODUCTION TO DESIGN PATTERNSDesign Patterns: Origin and HistoryArchitectural to Software Design PatternsWhat is a Design Pattern?More about Design PatternsAbout This BookUNIFIED MODELING LANGUAGE (UML)UML: A Quick ReferenceClass DiagramsSequence diagramsBASIC PATTERNSInterfaceDescriptionExamplePractice QuestionsAbstract Parent ClassDescriptionExamplePractice QuestionsPrivate MethodsDescriptionExamplePractice QuestionsAccessor MethodsDescriptionAccessor Method NomenclatureExampleDirect Reference versus Accessor MethodsPractice QuestionsConstant Data ManagerDescriptionExamplePractice Quest

Desenvolvimento e aplicação de modelo descritivo-normativo para análise de websites Development and application of a descriptive/ normative framework for website analysis

Directory of Open Access Journals (Sweden)

Stephania Padovani

2009-01-01

Full Text Available Este estudo tem como objetivo desenvolver um modelo descritivo-normativo para análise de websites. Inicialmente, explicamos no que consiste a análise de similares, quais os objetivos e benefícios desse estágio no processo de design. Em seguida, descrevemos alguns modelos descritivos e normativos voltados à análise de sistemas de informação e representações gráficas, encontrados na literatura das áreas de design da informação e ergonomia. Por fim, apresentamos uma proposta de modelo descritivo-normativo a ser utilizado na fase de análise de similares em projetos de websites, exemplificando sua aplicação em um website do gênero informativo.In this study, we propose a descriptive and normative framework for website analysis. To begin with, we explain competitor analysis, outlining the aims and benefits of this stage within the design process. After that, we describe a range of descriptive and normative frameworks aimed at analyzing information systems and graphic representations found in Ergonomics and Information Design literature. Finally, we propose a new descriptive and normative framework to be used during the competitor analysis phase in website design, illustrating its application with an informative website.

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

International Nuclear Information System (INIS)

Brantberger, Martin; Zetterqvist, Anders; Arnbjerg-Nielsen, Torben; Olsson, Tommy; Outters, Nils; Syrjaenen, Pauli

2006-04-01

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 to the applied

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

Biotrans functional and technical description. Report of VIEWLS WP5, modelling studies

International Nuclear Information System (INIS)

Van Tilburg, X.; Egging, R.; Londo, H.M.

2006-01-01

The overall objectives of this project are to provide structured and clear data on the availability and performance of biofuels and to identify the possibilities and strategies towards large scale sustainable production, use and trading of biofuels for the transport sector in Europe, including Central and Eastern European Countries (CEEC). The report supplements the two other reports in the work package: 'Biofuel and Bio-energy implementation scenarios - final report of VIEWLS WP5' (2005) and 'VIEWLS modelling and analysis, technical data for biofuel production chains' (2005). This document contains a functional and technical description of the BioTrans model, accompanied by a description of the system. Section 2 contains a conceptual and functional description of the biofuel model. Section 3 describes the optimisation method in technical terms, discussing aspects like the target function and constraints used. Finally, section 4 discusses the input and output requirements for the BioTrans system

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

Energy Technology Data Exchange (ETDEWEB)

Saurwein, John

2011-07-15

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

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

International Nuclear Information System (INIS)

Saurwein, J.

2011-01-01

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

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.

A design method for process design kit based on an SMIC 65 nm process

International Nuclear Information System (INIS)

Luo Haiyan; Chen Lan; Yin Minghui

2010-01-01

The frame structure of a process design kit (PDK) is described in detail, and a practical design method for PDK is presented. Based on this method, a useful SMIC 65 nm PDK has been successfully designed and realized, which is applicable to native EDA software of Zeni. The design process and difficulties of PDK are introduced by developing and analyzing these parameterized cell (Pcell) devices (MOS, resistor, etc.). A structured design method was proposed to implement Pcell, which makes thousands upon thousands of source codes of Pcell concise, readable, easy-to-upkeep and transplantable. Moreover, a Pcase library for each Pcell is designed to verify the Pcell in batches. By this approach, the Pcell can be verified efficiently and the PDK will be more reliable and steady. In addition, the component description format parameters and layouts of the Pcell are optimized by adding flexibility and improving performance, which benefits analog and custom IC designers to satisfy the demand of design. Finally, the SMIC 65 nm PDK was applied to IC design. The results indicate that the SMIC 65 nm PDK is competent to support IC design. (semiconductor integrated circuits)

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

Reservoir characterization of Pennsylvanian sandstone reservoirs. Final report

Energy Technology Data Exchange (ETDEWEB)

Kelkar, M.

1995-02-01

This final report summarizes the progress during the three years of a project on Reservoir Characterization of Pennsylvanian Sandstone Reservoirs. The report is divided into three sections: (i) reservoir description; (ii) scale-up procedures; (iii) outcrop investigation. The first section describes the methods by which a reservoir can be described in three dimensions. The next step in reservoir description is to scale up reservoir properties for flow simulation. The second section addresses the issue of scale-up of reservoir properties once the spatial descriptions of properties are created. The last section describes the investigation of an outcrop.

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)

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)

Description of disintegration in a three-body system

CERN Document Server

Takibaev, N Z

2000-01-01

In the frame of approach based on the effective potential of interaction between constituents, description of inelastic transition, in particularly, the processes of system disintegration. Relationship is shown between the approach results and those of the theory of final state interaction where coefficients of reaction gaining factor are determined. (author)

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

Design & Implementation of Company Database for MME Subcontracting Unit

CERN Document Server

Horvath, Benedek

2016-01-01

The purpose of this document is to introduce the software stack designed and implemented by me, during my student project. The report includes both the project description, the requirements set against the solution, the already existing alternatives for solving the problem, and the final solution that has been implemented. Reading this document you may have a better understanding of what I was working on for eleven weeks in the summer of 2016.

Design of a Flywheel Storage System

International Nuclear Information System (INIS)

Cavia Santos, S.; Garcia-Tabares Rodriguez, L.

1998-01-01

Storing mechanical kinetic energy for short time with flywheels has been known for centuries. However the applications of flywheels for longer storage times like electrochemical batteries is recent. Advanced flywheels have been possible thanks to the development from materials science with high tensile strength composite materials, and bearing technology with magnetic bearing, which suspend rotating shaft or rotor by magnetic forces. This summary report provides a study of the mechanics of flywheel, design considerations, material for advance flywheels, and magnetic bearing. Finally a brief description of a conventional flywheel prototype is given. (Author)

BWR [boiling-water reactor] and PWR [pressurized-water reactor] off-normal event descriptions

International Nuclear Information System (INIS)

1987-11-01

This document chronicles a total of 87 reactor event descriptions for use by operator licensing examiners in the construction of simulator scenarios. Events are organized into four categories: (1) boiling-water reactor abnormal events; (2) boiling-water reactor emergency events; (3) pressurized-water reactor abnormal events; and (4) pressurized-water reactor emergency events. Each event described includes a cover sheet and a progression of operator actions flow chart. The cover sheet contains the following general information: initial plant state, sequence initiator, important plant parameters, major plant systems affected, tolerance ranges, final plant state, and competencies tested. The progression of operator actions flow chart depicts, in a flow chart manner, the representative sequence(s) of expected immediate and subsequent candidate actions, including communications, that can be observed during the event. These descriptions are intended to provide examiners with a reliable, performance-based source of information from which to design simulator scenarios that will provide a valid test of the candidates' ability to safely and competently perform all licensed duties and responsibilities

Fast Flux Test Facility final safety analysis report. Amendment 72

Energy Technology Data Exchange (ETDEWEB)

Gantt, D. A.

1992-08-01

This document provides the Final Safety Analysis Report (FSAR) Amendment 72 for incorporation into the Fast Flux Test Facility (FFTF) FSAR set. This amendment change incorporates Engineering Change Notices issued subsequent to Amendment 71 and approved for incorporation before June 24, 1992. These include changes in: Chapter 2, Site Characteristics; Chapter 3, Design Criteria Structures, Equipment, and Systems; Chapter 5B, Reactor Coolant System; Chapter 7, Instrumentation and Control Systems; Chapter 8, Electrical Systems - The description of the Class 1E, 125 Vdc systems is updated for the higher capacity of the newly installed, replacement batteries; Chapter 9, Auxiliary Systems - The description of the inert cell NASA systems is corrected to list the correct number of spare sample points; Chapter 11, Reactor Refueling System; Chapter 12, Radiation Protection and Waste Management; Chapter 13, Conduct of Operations; Chapter 16, Quality Assurance; Chapter 17, Technical Specifications; Chapter 19, FFTF Fire Specifications for Fire Detection, Alarm, and Protection Systems; Chapter 20, FFTF Criticality Specifications; and Appendix B, Primary Piping Integrity Evaluation.

Conceptual models in man-machine design verification

International Nuclear Information System (INIS)

Rasmussen, J.

1985-01-01

The need for systematic methods for evaluation of design concepts for new man-machine systems has been rapidly increasing in consequence of the introduction of modern information technology. Direct empirical methods are difficult to apply when functions during rare conditions and support of operator decisions during emergencies are to be evaluated. In this paper, the problems of analytical evaluations based on conceptual models of the man-machine interaction are discussed, and the relations to system design and analytical risk assessment are considered. Finally, a conceptual framework for analytical evaluation is proposed, including several domains of description: 1. The problem space, in the form of a means-end hierarchy; 2. The structure of the decision process; 3. The mental strategies and heuristics used by operators; 4. The levels of cognitive control and the mechanisms related to human errors. Finally, the need for models representing operators' subjective criteria for choosing among available mental strategies and for accepting advice from intelligent interfaces is discussed

Horticulture Therapy Curriculum Development. Final Report.

Science.gov (United States)

Taylor, Sally; And Others

This final report includes two major components: a narrative describing a project at Edmonds Community College, Washington, to develop a horticultural therapy curriculum and descriptions of six courses developed or revised during the project. The narrative reports the development of a supplementary interdisciplinary certification program to train…

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.

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

Descriptive catalogue of radioactive waste families

International Nuclear Information System (INIS)

2004-01-01

This document describes the different types of radioactive wastes produced in France or which are expected to be produced in the future. The wastes have been shared into different families having similar characteristics. A description is made for each family: general presentation, photos, position of the family in the French classification, industrial origin, status of production. Some informations about the raw waste and its conditioning process are also given. The qualitative description is completed by some numerical data like: the quantity produced in the past and to be produced in the future, the evaluation of the radioactivity in 2002 and 2020, and the evaluation of the thermal power when it exists. Finally, some informations are given about the risk of toxicity of some chemical species or compounds. (J.S.)

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)

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.

Fused Silica Final Optics for Inertial Fusion Energy: Radiation Studies and System-Level Analysis

International Nuclear Information System (INIS)

Latkowski, Jeffery F.; Kubota, Alison; Caturla, Maria J.; Dixit, Sham N.; Speth, Joel A.; Payne, Stephen A.

2003-01-01

The survivability of the final optic, which must sit in the line of sight of high-energy neutrons and gamma rays, is a key issue for any laser-driven inertial fusion energy (IFE) concept. Previous work has concentrated on the use of reflective optics. Here, we introduce and analyze the use of a transmissive final optic for the IFE application. Our experimental work has been conducted at a range of doses and dose rates, including those comparable to the conditions at the IFE final optic. The experimental work, in conjunction with detailed analysis, suggests that a thin, fused silica Fresnel lens may be an attractive option when used at a wavelength of 351 nm. Our measurements and molecular dynamics simulations provide convincing evidence that the radiation damage, which leads to optical absorption, not only saturates but that a 'radiation annealing' effect is observed. A system-level description is provided, including Fresnel lens and phase plate designs

Retrievable storage concept designs. Final report

International Nuclear Information System (INIS)

Nickell, R.E.

1979-01-01

Three tasks related to the reference design of retrievable storage canisters for radioactive waste have been completed. The three tasks consist of the reference design itself, the definition of failure modes most appropriate for structural integrity determinations for the reference canister, and the development of a failure methodology for the structural integrity of the containers. The reference design is a sealed storage canister concept based upon the waste isolation pilot plant (WIPP) design, with slight modifications. The modifications consist of an alternate lifting yoke arrangement for the top head and a revised bottom head design for absorption of impact energy. Welded closures provide the seal at each end. Overpacking is considered as a possibility, but is not included in the preliminary reference design. The four failure modes that are deemed the most appropriate for the design of the reference canister are: (i) a loss of functional capability; (ii) ductile rupture of the canister; (iii) buckling of the structural members; and (iv) stress corrosion cracking. Failure scenarios are provided for each of the relevant failure modes. In addition, a failure methodology based upon the distribution of demand and the distribution of capacity for the structural members, with respect to each failure mode, is proffered

Minding the Gap: Narrative Descriptions about Mental States Attenuate Parochial Empathy

Science.gov (United States)

Bruneau, Emile G.; Cikara, Mina; Saxe, Rebecca

2015-01-01

In three experiments, we examine parochial empathy (feeling more empathy for in-group than out-group members) across novel group boundaries, and test whether we can mitigate parochial empathy with brief narrative descriptions. In the absence of individuating information, participants consistently report more empathy for members of their own assigned group than a competitive out-group. However, individualized descriptions of in-group and out-group targets significantly reduce parochial empathy by interfering with encoding of targets’ group membership. Finally, the descriptions that most effectively decrease parochial empathy are those that describe targets’ mental states. These results support the role of individuating information in ameliorating parochial empathy, suggest a mechanism for their action, and show that descriptions emphasizing targets’ mental states are particularly effective. PMID:26505194

30 CFR 1.2 - Description.

Science.gov (United States)

2010-07-01

... MINE SAFETY AND HEALTH ADMINISTRATION, DEPARTMENT OF LABOR OFFICIAL EMBLEM AND OMB CONTROL NUMBERS FOR RECORDKEEPING AND REPORTING MINE SAFETY AND HEALTH ADMINISTRATION; ESTABLISHMENT AND USE OF OFFICIAL EMBLEM § 1.2 Description. The emblem of the Mine Safety and Health Administration is of contemporary design...

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.

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

Management control system description

Energy Technology Data Exchange (ETDEWEB)

Bence, P. J.

1990-10-01

This Management Control System (MCS) description describes the processes used to manage the cost and schedule of work performed by Westinghouse Hanford Company (Westinghouse Hanford) for the US Department of Energy, Richland Operations Office (DOE-RL), Richland, Washington. Westinghouse Hanford will maintain and use formal cost and schedule management control systems, as presented in this document, in performing work for the DOE-RL. This MCS description is a controlled document and will be modified or updated as required. This document must be approved by the DOE-RL; thereafter, any significant change will require DOE-RL concurrence. Westinghouse Hanford is the DOE-RL operations and engineering contractor at the Hanford Site. Activities associated with this contract (DE-AC06-87RL10930) include operating existing plant facilities, managing defined projects and programs, and planning future enhancements. This document is designed to comply with Section I-13 of the contract by providing a description of Westinghouse Hanford's cost and schedule control systems used in managing the above activities. 5 refs., 22 figs., 1 tab.

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)

Monitored Geologic Repository Project Description Document

International Nuclear Information System (INIS)

Curry, P.

2000-01-01

The primary objective of the Monitored Geologic Repository Project Description Document (PDD) is to allocate the functions, requirements, and assumptions to the systems at Level 5 of the Civilian Radioactive Waste Management System (CRWMS) architecture identified in Section 4. It provides traceability of the requirements to those contained in Section 3 of the ''Monitored Geologic Repository Requirements Document'' (MGR RD) (CRWMS M and O 2000b) and other higher-level requirements documents. In addition, the PDD allocates design related assumptions to work products of non-design organizations. The document provides Monitored Geologic Repository (MGR) engineering design basis in support of design and performance assessment in preparing for the Site Recommendation (SR) and License Application (LA) milestones. The engineering design basis documented in the PDD is to be captured in the System Description Documents (SDDs) which address each of the systems at Level 5 of the CRWMS architecture. The design engineers obtain the engineering design basis from the SDDs and by reference from the SDDs to the PDD. The design organizations and other organizations will obtain design related assumptions directly from the PDD. These organizations may establish additional assumptions for their individual activities, but such assumptions are not to conflict with the assumptions in the PDD. The PDD will serve as the primary link between the engineering design basis captured in the SDDs and the design requirements captured in U.S. Department of Energy (DOE) documents. The approved PDD is placed under Level 3 baseline control by the CRWMS Management and Operating Contractor (M and O) and the following portions of the PDD constitute the Technical Design Baseline for the MGR: the design characteristics listed in Table 2-1, the MGR Architecture (Section 4.1),the Engineering Design Bases (Section 5), and the Controlled Project Assumptions (Section 6)

76 FR 17160 - Office of New Reactors; Final Interim Staff Guidance on the Review of Nuclear Power Plant Designs...

Science.gov (United States)

2011-03-28

... design certification (DC) application for new nuclear power reactors under Title 10 of the Code of... NUCLEAR REGULATORY COMMISSION [NRC-2010-0033; DC/COL-ISG-021] Office of New Reactors; Final Interim Staff Guidance on the Review of Nuclear Power Plant Designs Using a Gas Turbine Driven Standby...

Epsilon. A System Description Language

DEFF Research Database (Denmark)

Jensen, Kurt; Kyng, Morten

This paper discusses the use of Petri nets as a semantic tool in the design of languages and in the construction and analysis of system descriptions. The topics treated are: -- Languages based on nets. -- The problem of time in nets. -- Nets and related models. -- Nets and formal semantics...

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

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

International Nuclear Information System (INIS)

1984-11-01

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

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.

Final design of thermal diagnostic system in SPIDER ion source

International Nuclear Information System (INIS)

Brombin, M.; Dalla Palma, M.; Pasqualotto, R.; Pomaro, N.

2016-01-01

The prototype radio frequency source of the ITER heating neutral beams will be first tested in SPIDER test facility to optimize H"− 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.

Development of the biosphere code BIOMOD: final report

International Nuclear Information System (INIS)

Kane, P.

1983-05-01

Final report to DoE on the development of the biosphere code BIOMOD. The work carried out under the contract is itemised. Reference is made to the six documents issued along with the final report. These consist of two technical notes issued as interim consultative documents, a user's guide and a programmer's guide to BIOMOD, a database description, program test document and a technical note entitled ''BIOMOD - preliminary findings''. (author)

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

Technical baseline description for in situ vitrification laboratory test equipment

International Nuclear Information System (INIS)

Beard, K.V.; Bonnenberg, R.W.; Watson, L.R.

1991-09-01

IN situ vitrification (ISV) has been identified as possible waste treatment technology. ISV was developed by Pacific Northwest Laboratory (PNL), Richland, Washington, as a thermal treatment process to treat contaminated soils in place. The process, which electrically melts and dissolves soils and associated inorganic materials, simultaneously destroys and/or removes organic contaminants while incorporating inorganic contaminants into a stable, glass-like residual product. This Technical Baseline Description has been prepared to provide high level descriptions of the design of the Laboratory Test model, including all design modifications and safety improvements made to data. Furthermore, the Technical Baseline Description provides a basic overview of the interface documents for configuration management, program management interfaces, safety, quality, and security requirements. 8 figs

Identification of characteristics which influence repository design domal salt, Task 1. Final report

International Nuclear Information System (INIS)

Rawlings, G.; Antonnen, G.; Chamness, M.

1984-04-01

The purpose of the complete project is to provide NRC with technical assistance to enable the focused, adequate review by NRC of the aspects related to design and construction of an underground test facility and final geologic repository as presented by the Department of Energy (DOE). The study presented in this report covers the identification of characteristics which influence design and construction of a geologic repository in domal salt. This report has identified five key issues, i.e., constructibility, thermal response, mechanical response, hydrologic response, and geochemical response. This report involves both short-term (up to closure) and long-term (post closure) effects. The characteristics of domal salt and its environment are described under the headings of stratigraphic/structural, tectonic, mechanical, thermal and hydrologic. Characteristics are separated into parameters (quantified and measured) and factors (qualitative). The characteristics are then subjectively ranked by their influence on the key issues. This takes into account the availability and suitability of conservative design/construction techniques, uncertainty in model and model sensitivity to the characteristic

Towards the final MRPC design. Performance test with heavy ion beam

Energy Technology Data Exchange (ETDEWEB)

Deppner, Ingo; Herrmann, Norbert [Physikalisches Institut Uni. Heidelberg, Heidelberg (Germany)

2015-07-01

The Compressed Baryonic Matter spectrometer (CBM) is a future heavy ion experiment located at the Facility for Anti-proton and Ion Research (FAIR) in Darmstadt, Germany. The key element in CBM providing hadron identification at incident energies between 2 and 35 AGeV will be a 120 m{sup 2} large Time-of-Flight (ToF) wall composed of Multi-gap Resistive Plate Chambers (MRPC) with a system time resolution better than 80 ps. Aiming for an interaction rate of 10 MHz for Au+Au collisions the MRPCs have to cope with an incident particle flux between 0.1 kHz/cm{sup 2} and 25 kHz/cm{sup 2} depending on their location. Characterized by granularity and rate capability the actual conceptual design of the ToF-wall foresees 4 different counter types called MRPC1 - MRPC4. In order to elaborate the final MRPC design of these counters a heavy ion test beam time was performed at GSI. In this contribution we present performance test results of 2 different MRPC3 full size prototypes developed at Heidelberg University and Tsinghua University, Beijing.

Design and test of box girder for a large wind turbine blade

DEFF Research Database (Denmark)

Nielsen, Per Hørlyk; Tesauro, Angelo; Bitsche, Robert

This report is covering the structural design and full scale test of a box girder as a part of the project “Demonstration of new blade design using manufacturing process simulations” supported by the EUDP program. A box girder with a predetermined outer geometry was designed using new inventions...... that the manufacturing process could include the new inventions. Subsequently the box girder was transported to the blade test facility at DTU Wind Energy. A series of test was performed with the blade to investigate the behaviour during loading, and finally the girder was loaded to ultimate failure. The report includes...... the description of the test setup, the test and an overview over the results from the test performed on the box girder. During the final test the box girder failed at 58 % of the expected ultimate load. Unfortunately, no definite conclusion could be made concerning the failure mechanism....

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

Wind Turbine Blockset in Matlab/Simulink - General overview and description of the models

Energy Technology Data Exchange (ETDEWEB)

Iov, F.; Hansen, A.D.; Soerensen, P.; Blaabjerg, F.

2004-03-01

This report presents a new developed Matlab/Simulink Toolbox for wind turbine applications. This toolbox has been developed during the research project 'Simulation Platform to model, optimize and design wind turbines' and it has been used as a general developer tool for other three simulation tools: Saber, DIgSILENT, HAWC. The report provides first a quick overview over Matlab issues and then explains the structure of the developed toolbox. The attention in the report is mainly drawn to the description of the most important mathematical models, which have been developed in the Toolbox. Then, some simulation results using the developed models are shown. Finally, some general conclusions regarding this new developed Toolbox as well as some directions for future work are made. (au)

Wind turbine blockset in Matlab/Simulink. General overview and description of the models

Energy Technology Data Exchange (ETDEWEB)

Iov, F.; Timbus, A.V.; Hansen, A.D.; Soerensen, P.; Blaabjerg, F.

2004-03-01

This report presents a new developed Matlab/Simulink Toolbox for wind turbine applications. This toolbox has been developed during the research project 'Simulation Platform to model, optimize and design wind turbines' and it has been used as a general developer tool for other three simulation tools: Saber, DIgSILENT, HAWC. The report provides first a quick overview over Matlab issues and then explains the structure of the developed toolbox. The attention in the report is mainly drawn to the description of the most important mathematical models, which have been developed in the Toolbox. Then, some simulation results using the developed models are shown. Finally, some general conclusions regarding this new developed Toolbox as well as some directions for future work are made. (au)

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

Cold Vacuum Drying facility condensate collection system design description (SYS 19); FINAL

International Nuclear Information System (INIS)

PITKOFF, C.C.

1999-01-01

This document describes the Cold Vacuum Drying Facility (CVDF) condensate collection system (CCS). The function of the CCS is to collect cooling coil condensate from air-handling units in the CVDF and to isolate the condensate in collection tanks until the condensate is determined to be acceptable to drain to the effluent drain collection basin

Ontology-Based Device Descriptions and Device Repository for Building Automation Devices

Directory of Open Access Journals (Sweden)

Dibowski Henrik

2011-01-01

Full Text Available Device descriptions play an important role in the design and commissioning of modern building automation systems and help reducing the design time and costs. However, all established device descriptions are specialized for certain purposes and suffer from several weaknesses. This hinders a further design automation, which is strongly needed for the more and more complex building automation systems. To overcome these problems, this paper presents novel Ontology-based Device Descriptions (ODDs along with a layered ontology architecture, a specific ontology view approach with virtual properties, a generic access interface, a triple store-based database backend, and a generic search mask GUI with underlying query generation algorithm. It enables a formal, unified, and extensible specification of building automation devices, ensures their comparability, and facilitates a computer-enabled retrieval, selection, and interoperability evaluation, which is essential for an automated design. The scalability of the approach to several ten thousand devices is demonstrated.

RETRIEVAL EQUIPMENT DESCRIPTIONS

International Nuclear Information System (INIS)

J. Steinhoff

1997-01-01

The objective and the scope of this document are to list and briefly describe the major mobile equipment necessary for waste package (WP) retrieval from the proposed subsurface nuclear waste repository at Yucca Mountain. Primary performance characteristics and some specialized design features of the equipment are explained and summarized in the individual subsections of this document. There are no quality assurance requirements or QA controls in this document. Retrieval under normal conditions is accomplished with the same fleet of equipment as is used for emplacement. Descriptions of equipment used for retrieval under normal conditions is found in Emplacement Equipment Descriptions, DI: BCAF00000-01717-5705-00002 (a document in progress). Equipment used for retrieval under abnormal conditions is addressed in this document and consists of the following: (1) Inclined Plane Hauler; (2) Bottom Lift Transporter; (3) Load Haul Dump (LHD) Loader; (4) Heavy Duty Forklift for Emplacement Drifts; (5) Covered Shuttle Car; (6) Multipurpose Vehicle; and (7) Scaler

Evaluating Pragmatic Competence in Nigerian Undergraduates' Language Errors within Descriptive ESL Writing

Science.gov (United States)

Muhammad, Anas Sa'idu; Nair, Subadrah Madhawa

2017-01-01

This study investigates the level of pragmatic competence for ESL writing skills among Nigerian undergraduates. Methodologically, it adopts descriptive research design within the explanatory framework of the QUAN-Qual model. The instruments used are descriptive essay text and focus group interview questions. In writing the descriptive essays, a…

A sectionwise defined model for the material description of 100Cr6 in the thixotropic state

Science.gov (United States)

Behrens, B.-A.; Chugreev, A.; Hootak, M.

2018-05-01

A sectionwise defined material model has been developed for the numerical description of thixoforming processes. It consists of two sections. The first one describes the material behaviour below the solidus temperature and comprises an approach from structure mechanics, whereas the second section model describes the thixotropic behaviour above the solidus temperature based on the Ostwald-de Waele power law. The material model has been implemented in a commercial FE software Simufact Forming by means of user-defined subroutines. Numerical and experimental investigations of special upsetting tests have been designed and carried out with Armco iron-coated specimens. Finally, the model parameters were fitted by reverse engineering.

Chipless RFID design procedure and detection techniques

CERN Document Server

Rezaiesarlak, Reza

2015-01-01

This book examines the design of chipless RFID systems. The authors begin with the historical development of wireless identification systems and finally arrive at a representation of the chipless RFID system as a block diagram illustration. Chapter 2 is devoted to the theoretical bases for the design of chipless RFID tags and detection techniques in the reader. A rigorous mathematical formulation is presented based on the singularity expansion method (SEM) and characteristic mode theory (CMT) in order to study the scattered fields from an object in a general form. Th e authors attempt to explain some physical concepts behind the mathematical descriptions of the theories in this chapter. In Chapter 3, two design procedures based on complex natural resonance and CMT are presented for the design of the chipless RFID tag. By studying the effects of structural parameters on radiation and resonant behaviors of the tag, some design conclusions are presented in this chapter. Chapter 4 is dedicated to the time-frequen...

Final focus nomenclature

International Nuclear Information System (INIS)

Erickson, R.

1986-01-01

The formal names and common names for all devices in the final focus system of the SLC are listed. The formal names consist of a device type designator, microprocessor designator, and a four-digit unit number

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.)

Smart farming technologies - description, taxonomy and economic impact

DEFF Research Database (Denmark)

Balafoutis, Athanasios T.; Beck, Bert; Tsiropoulos, Zisis

2017-01-01

Precision Agriculture is a cyclic optimization process where data have to be collected from the field, analysed and evaluated and finally used for decision making for site-specific management of the field. Smart farming technologies (SFT ) cover all these aspects of precision agriculture and can...... comprise the delineation of management zones, decision support systems and farm management information system s. Finally, precision application technologies embrace variable-rate application technologies, precision irrigation and weeding and machine guidance. In this chapter, the reader can find...... a technical description of the technologies included in each category accompanied by a taxonomy of all SFT in terms of farming system type, cropping system, availability, level of investment and farmers’ motives to adopt them. Finally, the economic impact that each SFT has compared to conventional...

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.

WASTE PACKAGE TRANSPORTER DESIGN

International Nuclear Information System (INIS)

Weddle, D.C.; Novotny, R.; Cron, J.

1998-01-01

The purpose of this Design Analysis is to develop preliminary design of the waste package transporter used for waste package (WP) transport and related functions in the subsurface repository. This analysis refines the conceptual design that was started in Phase I of the Viability Assessment. This analysis supports the development of a reliable emplacement concept and a retrieval concept for license application design. The scope of this analysis includes the following activities: (1) Assess features of the transporter design and evaluate alternative design solutions for mechanical components. (2) Develop mechanical equipment details for the transporter. (3) Prepare a preliminary structural evaluation for the transporter. (4) Identify and recommend the equipment design for waste package transport and related functions. (5) Investigate transport equipment interface tolerances. This analysis supports the development of the waste package transporter for the transport, emplacement, and retrieval of packaged radioactive waste forms in the subsurface repository. Once the waste containers are closed and accepted, the packaged radioactive waste forms are termed waste packages (WP). This terminology was finalized as this analysis neared completion; therefore, the term disposal container is used in several references (i.e., the System Description Document (SDD)) (Ref. 5.6). In this analysis and the applicable reference documents, the term ''disposal container'' is synonymous with ''waste package''

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

Final focus nomenclature

Energy Technology Data Exchange (ETDEWEB)

Erickson, R.

1986-08-08

The formal names and common names for all devices in the final focus system of the SLC are listed. The formal names consist of a device type designator, microprocessor designator, and a four-digit unit number. (LEW)

Transuranic-contaminated solid waste Treatment Development Facility. Final safety analysis report

International Nuclear Information System (INIS)

Warner, C.L.

1979-07-01

The Final Safety Analysis Report (FSAR) for the Transuranic-Contaminated Solid-Waste Treatment Facility has been prepared in compliance with the Department of Energy (DOE) Manual Chapter 0531, Safety of Nonreactor Nuclear Facilities. The Treatment Development Facility (TDF) at the Los Alamos Scientific Laboratory is a research and development facility dedicated to the study of radioactive-waste-management processes. This analysis addresses site assessment, facility design and construction, and the design and operating characteristics of the first study process, controlled air incineration and aqueous scrub off-gas treatment with respect to both normal and accident conditions. The credible accidents having potentially serious consequences relative to the operation of the facility and the first process have been analyzed and the consequences of each postulated credible accident are presented. Descriptions of the control systems, engineered safeguards, and administrative and operational features designed to prevent or mitigate the consequences of such accidents are presented. The essential features of the operating and emergency procedures, environmental protection and monitoring programs, as well as the health and safety, quality assurance, and employee training programs are described

Transuranic-contaminated solid waste Treatment Development Facility. Final safety analysis report

Energy Technology Data Exchange (ETDEWEB)

Warner, C.L. (comp.)

1979-07-01

The Final Safety Analysis Report (FSAR) for the Transuranic-Contaminated Solid-Waste Treatment Facility has been prepared in compliance with the Department of Energy (DOE) Manual Chapter 0531, Safety of Nonreactor Nuclear Facilities. The Treatment Development Facility (TDF) at the Los Alamos Scientific Laboratory is a research and development facility dedicated to the study of radioactive-waste-management processes. This analysis addresses site assessment, facility design and construction, and the design and operating characteristics of the first study process, controlled air incineration and aqueous scrub off-gas treatment with respect to both normal and accident conditions. The credible accidents having potentially serious consequences relative to the operation of the facility and the first process have been analyzed and the consequences of each postulated credible accident are presented. Descriptions of the control systems, engineered safeguards, and administrative and operational features designed to prevent or mitigate the consequences of such accidents are presented. The essential features of the operating and emergency procedures, environmental protection and monitoring programs, as well as the health and safety, quality assurance, and employee training programs are described.

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)

On the description of electronic final states in the K-shell ionization by protons

International Nuclear Information System (INIS)

Aashamar, O.; Kocbach, L.

1976-06-01

The choice of free electronic wave functions in the description of K-shell ionization by protons is discussed. The previously known discrepancies between PWBA and SCA results are shown to be entirely due to two different choices of electronic wave functions. Calculations in the SCA framework with Hartree-Fock-Slater wave functions are reported. Some general features of the SCA calculations are discussed. (Auth.)

Study of an analog/logic processor for the design of an auto patch hybrid computer

International Nuclear Information System (INIS)

Koched, Hassen

1976-01-01

This paper presents the experimental study of an analog multiprocessor designed at SES/CEN-Saclay. An application of such a device as a basic component of an auto-patch hybrid computer is presented. First, the description of the processor, and a presentation of the theoretical concepts which governed the design of the processor are given. Experiments on an hybrid computer are then presented. Finally, different systems of automatic patching are presented, and conveniently modified, for the use of such a processor. (author) [fr

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.

Thermodynamical description of excited nuclei

International Nuclear Information System (INIS)

Bonche, P.

1989-01-01

In heavy ion collisions it has been possible to obtain composite systems at rather high excitation energies corresponding to temperatures of several MeV. The theoretical studies of these systems are based on concepts borrowed from thermodynamics or statistical physics, such as the temperature. In these lectures, we present the concepts of statistical physics which are involved in the physics of heavy ion as they are produced nowadays in the laboratory and also during the final stage of a supernova collapse. We do not attempt to describe the reaction mechanisms which yield such nuclear systems nor their decay by evaporation or fragmentation. We shall only study their static properties. The content of these lectures is organized in four main sections. The first one gives the basic features of statistical physics and thermodynamics necessary to understand quantum mechanics at finite temperature. In the second one, we present a study of the liquid-gas phase transition in nuclear physics. A phenomenological approach of the stability of hot nuclei follows. The microscopic point of view is proposed in the third part. Starting from the basic concepts derived in the first part, it provides a description of excited or hot nuclei which confirms the qualitative results of the second part. Furthermore it gives a full description of most properties of these nuclei as a function of temperature. Finally in the last part, a microscopic derivation of the equation of state of nuclear matter is proposed to study the collapse of a supernova core

Conceptual Design Report for Remote-Handled Low-Level Waste Disposal Facility

Energy Technology Data Exchange (ETDEWEB)

Lisa Harvego; David Duncan; Joan Connolly; Margaret Hinman; Charles Marcinkiewicz; Gary Mecham

2010-10-01

This conceptual design report addresses development of replacement remote-handled low-level waste disposal capability for the Idaho National Laboratory. Current disposal capability at the Radioactive Waste Management Complex is planned until the facility is full or until it must be closed in preparation for final remediation (approximately at the end of Fiscal Year 2017). This conceptual design report includes key project assumptions; design options considered in development of the proposed onsite disposal facility (the highest ranked alternative for providing continued uninterrupted remote-handled low level waste disposal capability); process and facility descriptions; safety and environmental requirements that would apply to the proposed facility; and the proposed cost and schedule for funding, design, construction, and operation of the proposed onsite disposal facility.

Over facility design description for the CPDF [Centrifuge Plant Demonstration Facility]: SDD-1 [System Design Description

International Nuclear Information System (INIS)

1987-04-01

The Centrifuge Plant Demonstration Facility (CPDF) is an essential part of the continuing development of first-production-plant centrifuge technology that will integrate centrifuge machines into a process and enrichment plant design. The CPDF will provide facilities for testing and continued development of a unit cascade in direct support of the commercial Gas Centrifuge Enrichment Plant (GCEP). The basic cascade-oriented equipment, feed, withdrawal, drive system, process piping, utility piping, and other auxiliary and support equipment will be tested in an operating configuration that represents, to the extent possible, GCEP arrangement and operating conditions. The objective will be to demonstrate procedures for production cascade installation, start-up, operation, and maintenance, and to provide proof of overall cascade and associated system design, construction, and operating and maintenance concepts. To the maximum possible extent, all equipment for the CPDF will be procured from commercial sources. Centrifuges will be procured from industry using government-supplied specifications and drawings. The existing Component Preparation Laboratory (CPL) located near the CPDF site will be used for centrifuge component receiving, inspection, assembly, and qualification testing of pre-production test machines. Later in the test program, samples of production machines planned for use in the GCEP will be tested in the CPDF

The role of XML in the CMS detector description

International Nuclear Information System (INIS)

Liendl, M.; Lingen, F.van; Todorov, T.; Arce, P.; Furtjes, A.; Innocente, V.; Roeck, A. de; Case, M.

2001-01-01

Offline Software such as Simulation, Reconstruction, Analysis, and Visualisation are all in need of a detector description. These applications have several common but also many specific requirements for the detector description in order to build up their internal representations. To achieve this in a consistent and coherent manner a common source of information, the detector description database, will be consulted by each of the applications. The role and suitability of XML in the design of the detector description database in the scope of the CMS detector at the LHC is discussed. Different aspects such as data modelling capabilities of XML, tool support, integration to C++ representations of data models are treated and recent results of prototype implementations are presented

Quantum logical description of microsystems

International Nuclear Information System (INIS)

Stachow, E.-W.

1984-01-01

An abstract object language with respect to single microsystems and its pragmatic foundation are considered in a systematic way. The quantum physical restrictions of local operations of a speaker lead to a propositional language which, under certain conditions, can be referred to an individual microsystem. The time dependence of the propositions according to the measuring process is discussed. Finally the language is extended to a space-time description of microsystems. Hereby relativity imposes certain constraints on the validi ty regions of propositions in space-time. Via realization, the language establishes the essential features of quantum physics in Hilbert space. (author)

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.)

Monitored Geologic Repository Project Description Document

International Nuclear Information System (INIS)

Curry, P. M.

2001-01-01

The primary objective of the Monitored Geologic Repository Project Description Document (PDD) is to allocate the functions, requirements, and assumptions to the systems at Level 5 of the Civilian Radioactive Waste Management System (CRWMS) architecture identified in Section 4. It provides traceability of the requirements to those contained in Section 3 of the ''Monitored Geologic Repository Requirements Document'' (MGR RD) (YMP 2000a) and other higher-level requirements documents. In addition, the PDD allocates design related assumptions to work products of non-design organizations. The document provides Monitored Geologic Repository (MGR) technical requirements in support of design and performance assessment in preparing for the Site Recommendation (SR) and License Application (LA) milestones. The technical requirements documented in the PDD are to be captured in the System Description Documents (SDDs) which address each of the systems at Level 5 of the CRWMS architecture. The design engineers obtain the technical requirements from the SDDs and by reference from the SDDs to the PDD. The design organizations and other organizations will obtain design related assumptions directly from the PDD. These organizations may establish additional assumptions for their individual activities, but such assumptions are not to conflict with the assumptions in the PDD. The PDD will serve as the primary link between the technical requirements captured in the SDDs and the design requirements captured in US Department of Energy (DOE) documents. The approved PDD is placed under Level 3 baseline control by the CRWMS Management and Operating Contractor (M and O) and the following portions of the PDD constitute the Technical Design Baseline for the MGR: the design characteristics listed in Table 1-1, the MGR Architecture (Section 4.1), the Technical Requirements (Section 5), and the Controlled Project Assumptions (Section 6)

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

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

Nursing students' perceptions of a collaborative clinical placement model: A qualitative descriptive study.

Science.gov (United States)

van der Riet, Pamela; Levett-Jones, Tracy; Courtney-Pratt, Helen

2018-03-01

Clinical placements are specifically designed to facilitate authentic learning opportunities and are an integral component of undergraduate nursing programs. However, as academics and clinicians frequently point out, clinical placements are fraught with problems that are long-standing and multidimensional in nature. Collaborative placement models, grounded in a tripartite relationship between students, university staff and clinical partners, and designed to foster students' sense of belonging, have recently been implemented to address many of the challenges associated with clinical placements. In this study a qualitative descriptive design was undertaken with the aim of exploring 14 third year third year nursing students' perceptions of a collaborative clinical placement model undertaken in an Australian university. Students participated in audio recorded focus groups following their final clinical placement. Thematic analysis of the interview data resulted in identification of six main themes: Convenience and Camaraderie, Familiarity and Confidence, Welcomed and Wanted, Belongingness and Support, Employment, and The Need for Broader Clinical Experiences. The clinical collaborative model fostered a sense of familiarity for many of the participants and this led to belongingness, acceptance, confidence and meaningful learning experiences. Copyright © 2018 Elsevier Ltd. All rights reserved.

Final Focus Systems in Linear Colliders

International Nuclear Information System (INIS)

Raubenheimer, Tor

1998-01-01

In colliding beam facilities, the ''final focus system'' must demagnify the beams to attain the very small spot sizes required at the interaction points. The first final focus system with local chromatic correction was developed for the Stanford Linear Collider where very large demagnifications were desired. This same conceptual design has been adopted by all the future linear collider designs as well as the SuperConducting Supercollider, the Stanford and KEK B-Factories, and the proposed Muon Collider. In this paper, the over-all layout, physics constraints, and optimization techniques relevant to the design of final focus systems for high-energy electron-positron linear colliders are reviewed. Finally, advanced concepts to avoid some of the limitations of these systems are discussed

Accelerator design of the KEK B-Factory

International Nuclear Information System (INIS)

Kurokawa, Shin-ichi; Satoh, Kotaro; Kikutani, Eiji

1991-03-01

A design study has been made for the KEK B-Factory, an accelerator complex dedicated to the detection of the CP-violation effect of B-mesons. It is an asymmetric two-ring electron-positron collider of 3.5x8 GeV within a new tunnel measuring 1273 m circumference. The design peak luminosity is to be 10 34 cm -2 s -1 , which will be realized in two steps. The luminosity is to be 2 x 10 33 cm -2 s -1 with a head-on collision scheme in the first step; it is then increased to a final value of 10 34 cm -2 s -1 with a finite-angle crossing scheme. This document comprises two parts; the first part presents an overview of the design; the second part is a collection of papers giving detailed descriptions of various subjects. Stress is put on the design of the first step; the second step is mentioned when necessary. (author)

78 FR 21617 - Notice of Proposed Information Collection: Comment Request; Final Endorsement of Credit Instrument

Science.gov (United States)

2013-04-11

... Information Collection: Comment Request; Final Endorsement of Credit Instrument AGENCY: Office of the... Proposal: Final Endorsement of Credit Instrument. OMB Control Number, if applicable: 2502-0016. Description... Endorsement of Credit Instrument'' form is used to request to request final endorsement by HUD of the credit...

Final design proposal: Theta Group-The Hotbox. A proposal in response to a commercial air transportation study

Science.gov (United States)

1991-01-01

The Hotbox is a 40 passenger commercial aircraft designed to have a minimum range of 5500 ft and cruise at a velocity of 30 ft/sec. The aircraft is designed to serve the longer range overseas market in Aeroworld. In order to serve all the airports in the overseas market, the Hotbox was required to be able to use a five foot gate. A weight requirement was set a 4.5 lbs in order to maximize aircraft efficiency. Finally, a single engine system was chosen because it minimized system weight, complexity and cost. The Hotbox is estimated to cost $152,000 Aeroworld dollars and will sell for $200.000. The propulsion system for the Hotbox consists of a nose mounted Astro 15 electric powered motor and a Top Flight 12-6 propeller. A Spica airfoil was selected for the Hotbox based on the ease of construction of its flat bottom and its positive lift and drag characteristics. A fuselage of rectangular cross section will internally contain the propulsion system, control system, and a passenger bay with 2x20 seating. A combination of directional and longitudinal control will enable the Hotbox to maneuver. The final design of the Hotbox provides for takeoff distance in 26.5 ft and normal cruise range of 17,000 ft.

Preliminary design of an osmotic-type salinity gradient energy converter. Phase I, design effort

Energy Technology Data Exchange (ETDEWEB)

1979-04-30

The base case that was studied for this Phase I Interim Report is a 50 kWe design with 3.5% salt water (seawater) on one side and saturated salt water on the other side of the semi-permeable membrane. This case included a solar evaporation pond. The report includes system descriptions, system component descriptions, siting restrictions, environmental considerations, pretreatment, membrane characteristics, preliminary system capital costs, and recommendations for further work. During the course of the study and investigations, it was decided to extend the review to develop an additional basic flow sheet using brackish water instead of seawater with a solar pond. This option requires reduced flow rates and therefore can utilize smaller and less expensive components as compared to the seawater base case. Based on data for reverse osmosis water purification systems, the operating costs for pretreatment and labor would also be expected to be less for the brackish water system than for the seawater system. Finally, the use of brackish water systems greatly increases the potential number of sites available for a practical Osmo-Hydro Power System.

Hydrogen electrode reaction: A complete kinetic description

International Nuclear Information System (INIS)

Quaino, P.M.; Gennero de Chialvo, M.R.; Chialvo, A.C.

2007-01-01

The kinetic description of the hydrogen electrode reaction (HER) in the whole range of overpotentials (-0.2 < η (V) < 0.40) is presented. The Volmer-Heyrovsky-Tafel mechanism was solved considering simultaneously the following items: (i) the diffusional contribution of the molecular hydrogen from and towards the electrode surface, (ii) the forward and backward reaction rates of each elementary step and (iii) a Frumkin type adsorption for the reaction intermediate. In order to verify the descriptive capability of the kinetic expressions derived, an experimental study of the HER was carried out on a rotating platinum disc electrode in acid solution. From the correlation of these results the elementary kinetic parameters were evaluated and several aspects related to the kinetic mechanism were discussed. Finally, the use of these kinetic expressions to interpret results obtained on microelectrodes is also analysed

Towards a Pattern Language Approach to Document Description

Directory of Open Access Journals (Sweden)

Robert Waller

2012-07-01

Full Text Available Pattern libraries, originating in architecture, are a common way to share design solutions in interaction design and software engineering. Our aim in this paper is to consider patterns as a way of describing commonly-occurring document design solutions to particular problems, from two points of view. First, we are interested in their use as exemplars for designers to follow, and second, we suggest them as a means of understanding linguistic and graphical data for their organization into corpora that will facilitate descriptive work. We discuss the use of patterns across a range of disciplines before suggesting the need to place patterns in the context of genres, with each potentially belonging to a “home genre” in which it originates and to which it makes an implicit intertextual reference intended to produce a particular reader response in the form of a reading strategy or interpretative stance. We consider some conceptual and technical issues involved in the descriptive study of patterns in naturally-occurring documents, including the challenges involved in building a document corpus.

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…

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)

Innovation in Deep Space Habitat Interior Design: Lessons Learned From Small Space Design in Terrestrial Architecture

Science.gov (United States)

Simon, Matthew A.; Toups, Larry

2014-01-01

Increased public awareness of carbon footprints, crowding in urban areas, and rising housing costs have spawned a 'small house movement' in the housing industry. Members of this movement desire small, yet highly functional residences which are both affordable and sensitive to consumer comfort standards. In order to create comfortable, minimum-volume interiors, recent advances have been made in furniture design and approaches to interior layout that improve both space utilization and encourage multi-functional design for small homes, apartments, naval, and recreational vehicles. Design efforts in this evolving niche of terrestrial architecture can provide useful insights leading to innovation and efficiency in the design of space habitats for future human space exploration missions. This paper highlights many of the cross-cutting architectural solutions used in small space design which are applicable to the spacecraft interior design problem. Specific solutions discussed include reconfigurable, multi-purpose spaces; collapsible or transformable furniture; multi-purpose accommodations; efficient, space saving appliances; stowable and mobile workstations; and the miniaturization of electronics and computing hardware. For each of these design features, descriptions of how they save interior volume or mitigate other small space issues such as confinement stress or crowding are discussed. Finally, recommendations are provided to provide guidance for future designs and identify potential collaborations with the small spaces design community.

Conceptual Design Report for the Remote-Handled Low-Level Waste Disposal Project

Energy Technology Data Exchange (ETDEWEB)

David Duncan

2011-05-01

This conceptual design report addresses development of replacement remote-handled low-level waste disposal capability for the Idaho National Laboratory. Current disposal capability at the Radioactive Waste Management Complex is planned until the facility is full or until it must be closed in preparation for final remediation (approximately at the end of Fiscal Year 2017). This conceptual design report includes key project assumptions; design options considered in development of the proposed onsite disposal facility (the highest ranked alternative for providing continued uninterrupted remote-handled low level waste disposal capability); process and facility descriptions; safety and environmental requirements that would apply to the proposed facility; and the proposed cost and schedule for funding, design, construction, and operation of the proposed onsite disposal facility.

Conceptual Design Report for the Remote-Handled Low-Level Waste Disposal Project

Energy Technology Data Exchange (ETDEWEB)

Lisa Harvego; David Duncan; Joan Connolly; Margaret Hinman; Charles Marcinkiewicz; Gary Mecham

2011-03-01

This conceptual design report addresses development of replacement remote-handled low-level waste disposal capability for the Idaho National Laboratory. Current disposal capability at the Radioactive Waste Management Complex is planned until the facility is full or until it must be closed in preparation for final remediation (approximately at the end of Fiscal Year 2017). This conceptual design report includes key project assumptions; design options considered in development of the proposed onsite disposal facility (the highest ranked alternative for providing continued uninterrupted remote-handled low level waste disposal capability); process and facility descriptions; safety and environmental requirements that would apply to the proposed facility; and the proposed cost and schedule for funding, design, construction, and operation of the proposed onsite disposal facility.

Computer hardware description languages - A tutorial

Science.gov (United States)

Shiva, S. G.

1979-01-01

The paper introduces hardware description languages (HDL) as useful tools for hardware design and documentation. The capabilities and limitations of HDLs are discussed along with the guidelines needed in selecting an appropriate HDL. The directions for future work are provided and attention is given to the implementation of HDLs in microcomputers.

Waste disposal technologies: designs and evaluations

International Nuclear Information System (INIS)

Shaw, R.A.

1987-01-01

Many states and compacts are presently in the throes of considering what technology to select for their low level waste disposal site. Both the technical and economic aspects of disposal technology are important considerations in these decisions. It is also important that they be considered in the context of the entire system. In the case of a nuclear power plant, that system encompasses the various individual waste streams that contain radioactivity, the processing equipment which reduces the volume and/or alters the form in which the radioisotopes are contained, the packaging of the processed wastes in shipment, and finally its disposal. One further part of this is the monitoring that takes place in all stages of this operation. This paper discusses the results of some research that has been sponsored by EPRI with the principal contractor being Rogers and Associates Engineering Corporation. Included is a description of the distinguishing features found in disposal technologies developed in a generic framework, designs for a selected set of these disposal technologies and the costs which have been derived from these designs. In addition, a description of the early efforts towards defining the performance of these various disposal technologies is described. 5 figures, 1 table

Analyzing and modeling interdisciplinary product development a framework for the analysis of knowledge characteristics and design support

CERN Document Server

Neumann, Frank

2015-01-01

Frank Neumann focuses on establishing a theoretical basis that allows a description of the interplay between individual and collective processes in product development. For this purpose, he introduces the integrated descriptive model of knowledge creation as the first constituent of his research framework. As a second part of the research framework, an analysis and modeling method is proposed that captures the various knowledge conversion activities described by the integrated descriptive model of knowledge creation. Subsequently, this research framework is applied to the analysis of knowledge characteristics of mechatronic product development (MPD). Finally, the results gained from the previous steps are used within a design support system that aims at federating the information and knowledge resources contained in the models published in the various development activities of MPD. Contents Descriptive Model of Knowledge Creation in Interdisciplinary Product Development Research Framework for the Analysis of ...

Using Self-Description to Handle Change in Systems

CERN Document Server

Estrella, Florida; Le Goff, Jean-Marie; McClatchey, Richard; Murray, Steven

2002-01-01

In the web age systems must be flexible, reconfigurable and adaptable in addition to being quick to develop. As a consequence, designing systems to cater for change is becoming not only desirable but required by industry. Allowing systems to be self-describing or description-driven is one way to enable these characteristics. To address the issue of evolvability in designing self-describing systems, this paper proposes a pattern-based, object-oriented, description-driven 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 fiv...

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

Energy Technology Data Exchange (ETDEWEB)

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).

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)

European Helium Cooled Pebble Bed (HCPB) test blanket. ITER design description document. Status 1.12.1996

International Nuclear Information System (INIS)

Albrecht, H.; Boccaccini, L.V.; Dalle Donne, M.; Fischer, U.; Gordeev, S.; Hutter, E.; Kleefeldt, K.; Norajitra, P.; Reimann, G.; Ruatto, P.; Schleisiek, K.; Schnauder, H.

1997-04-01

The Helium Cooled Pebble Bed (HCPB) blanket is based on the use of separate small lithium orthosilicate and beryllium pebble beds placed between radial toroidal cooling plates. The cooling is provided by helium at 8 MPa. The tritium produced in the pebble beds is purged by the flow of helium at 0.1 MPa. The structural material is martensitic steel. It is foreseen, after an extended R and D work, to test in ITER a blanket module based on the HCPB design, which is one of the two European proposals for the ITER Test Blanket Programme. To facilitate the handling operation the Blanket Test Module (BTM) is bolted to a surrounding water cooled frame fixed to the ITER shield blanket back plate. For the design of the test module, three-dimensional Monte Carlo neutronic calculations and thermohydraulic and stress analyses for the operation during the Basic Performance Phase (BPP) and during the Extended Performance Phase (EPP) of ITER have been performed. The behaviour of the test module during LOCA and LOFA has been investigated. Conceptual designs of the required ancillary loops have been performed. The present report is the updated version of the Design Description Document (DDD) for the HCPB Test Module. It has been written in accordance with a scheme given by the ITER Joint Central Team (JCT) and accounts for the comments made by the JCT to the previous version of this report. This work has been performed in the framework of the Nuclear Fusion Project of the Forschungszentrum Karlsruhne and it is supported by the European Union within the European Fusion Technology Program. (orig.) [de

Deep-Inelastic Final States in a Space-Time Description of Shower Development and Hadronization

OpenAIRE

Ellis, John; Geiger, Klaus; Kowalski, Henryk

1996-01-01

We extend a quantum kinetic approach to the description of hadronic showers in space, time and momentum space to deep-inelastic $ep$ collisions, with particular reference to experiments at HERA. We follow the history of hard scattering events back to the initial hadronic state and forward to the formation of colour-singlet pre-hadronic clusters and their decays into hadrons. The time evolution of the space-like initial-state shower and the time-like secondary partons are treated similarly, an...

Ecosystem description of a drainage area - a strategy in biosphere descriptions during site investigations for a repository of spent nuclear fuel

International Nuclear Information System (INIS)

Lindborg, T.; Lofgren, A.

2004-01-01

During the next few years the Swedish Nuclear Fuel and Waste Management Co. (SKB) performs site investigations at two sites in Sweden for a future repository of spent nuclear fuel. Novel methods based on systems and landscape ecology are developed to understand and model the radionuclide flow in the biosphere using site specific data for a safety assessment. This work describes the strategy for development of a descriptive ecosystem model for the surface ecosystem. The site description is needed to: a) perform a safety assessment that describes and analyzes different scenarios for radionuclide releases into the ecosystem and possible pathways for dispersal or accumulation radionuclides in the ecosystem, b) detect changes caused by the construction of a repository, c) establish a baseline for detecting long-term effects of the repository. The description adopts a site-specific approach focusing on the quantification of the properties that will constitute the descriptive model. The aim is also to present the methodology for determining the properties, to describe the development of the framework for the descriptive ecosystem models by integrating use of different properties, and finally, to present vital data from other site descriptive models such as those for geology or hydrogeology. The safety assessment will use an approach, among other methods, where transport and accumulation of radionuclides will be modelled by quantifying biogeochemical pathways of matter. The descriptive ecosystem model applied to the site was therefore built to describe and quantify processes affecting i.e. turnover of matter in a drainage area. The conclusions from applying this approach was that by have estimating the flow of matter the ecological and physical constrains on the system reduces the potential variations in outcome of future states of the ecosystem and thus also reduces the uncertainties in estimating radionuclide flow and consequences to humans and the environment. (author)

WASTE PACKAGE TRANSPORTER DESIGN

Energy Technology Data Exchange (ETDEWEB)

D.C. Weddle; R. Novotny; J. Cron

1998-09-23

The purpose of this Design Analysis is to develop preliminary design of the waste package transporter used for waste package (WP) transport and related functions in the subsurface repository. This analysis refines the conceptual design that was started in Phase I of the Viability Assessment. This analysis supports the development of a reliable emplacement concept and a retrieval concept for license application design. The scope of this analysis includes the following activities: (1) Assess features of the transporter design and evaluate alternative design solutions for mechanical components. (2) Develop mechanical equipment details for the transporter. (3) Prepare a preliminary structural evaluation for the transporter. (4) Identify and recommend the equipment design for waste package transport and related functions. (5) Investigate transport equipment interface tolerances. This analysis supports the development of the waste package transporter for the transport, emplacement, and retrieval of packaged radioactive waste forms in the subsurface repository. Once the waste containers are closed and accepted, the packaged radioactive waste forms are termed waste packages (WP). This terminology was finalized as this analysis neared completion; therefore, the term disposal container is used in several references (i.e., the System Description Document (SDD)) (Ref. 5.6). In this analysis and the applicable reference documents, the term ''disposal container'' is synonymous with ''waste package''.

Reactor analysis support package (RASP). Volume 7. PWR set-point methodology. Final report

International Nuclear Information System (INIS)

Temple, S.M.; Robbins, T.R.

1986-09-01

This report provides an overview of the basis and methodology requirements for determining Pressurized Water Reactor (PWR) technical specifications related setpoints and focuses on development of the methodology for a reload core. Additionally, the report documents the implementation and typical methods of analysis used by PWR vendors during the 1970's to develop Protection System Trip Limits (or Limiting Safety System Settings) and Limiting Conditions for Operation. The descriptions of the typical setpoint methodologies are provided for Nuclear Steam Supply Systems as designed and supplied by Babcock and Wilcox, Combustion Engineering, and Westinghouse. The description of the methods of analysis includes the discussion of the computer codes used in the setpoint methodology. Next, the report addresses the treatment of calculational and measurement uncertainties based on the extent to which such information was available for each of the three types of PWR. Finally, the major features of the setpoint methodologies are compared, and the principal effects of each particular methodology on plant operation are summarized for each of the three types of PWR

Semantic based cluster content discovery in description first clustering algorithm

International Nuclear Information System (INIS)

Khan, M.W.; Asif, H.M.S.

2017-01-01

In the field of data analytics grouping of like documents in textual data is a serious problem. A lot of work has been done in this field and many algorithms have purposed. One of them is a category of algorithms which firstly group the documents on the basis of similarity and then assign the meaningful labels to those groups. Description first clustering algorithm belong to the category in which the meaningful description is deduced first and then relevant documents are assigned to that description. LINGO (Label Induction Grouping Algorithm) is the algorithm of description first clustering category which is used for the automatic grouping of documents obtained from search results. It uses LSI (Latent Semantic Indexing); an IR (Information Retrieval) technique for induction of meaningful labels for clusters and VSM (Vector Space Model) for cluster content discovery. In this paper we present the LINGO while it is using LSI during cluster label induction and cluster content discovery phase. Finally, we compare results obtained from the said algorithm while it uses VSM and Latent semantic analysis during cluster content discovery phase. (author)

Final safety evaluation report related to the certification of the Advanced Boiling Water Reactor design. Supplement 1

International Nuclear Information System (INIS)

1997-05-01

This report supplements the final safety evaluation report (FSER) for the US Advanced Boiling Water Reactor (ABWR) standard design. The FSER was issued by the US Nuclear Regulatory Commission (NRC) staff as NUREG-1503 in July 1994 to document the NRC staff's review of the US ABWR design. The US ABWR design was submitted by GE Nuclear Energy (GE) 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 US ABWR design documentation since the issuance of the FSER. GE made these changes primarily as a result of first-of-a-kind-engineering (FOAKE) and as a result of the design certification rulemaking for the ABWR design. On the basis of its evaluations, the NRC staff concludes that the confirmatory issues in NUREG-1503 are resolved, that the changes to the ABWR design documentation are acceptable, and that GE's application for design certification meets the requirements of Subpart B to 10 CFR Part 52 that are applicable and technically relevant to the US ABWR design

Final safety evaluation report related to the certification of the Advanced Boiling Water Reactor design. Supplement 1

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-05-01

This report supplements the final safety evaluation report (FSER) for the US Advanced Boiling Water Reactor (ABWR) standard design. The FSER was issued by the US Nuclear Regulatory Commission (NRC) staff as NUREG-1503 in July 1994 to document the NRC staff`s review of the US ABWR design. The US ABWR design was submitted by GE Nuclear Energy (GE) 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 US ABWR design documentation since the issuance of the FSER. GE made these changes primarily as a result of first-of-a-kind-engineering (FOAKE) and as a result of the design certification rulemaking for the ABWR design. On the basis of its evaluations, the NRC staff concludes that the confirmatory issues in NUREG-1503 are resolved, that the changes to the ABWR design documentation are acceptable, and that GE`s application for design certification meets the requirements of Subpart B to 10 CFR Part 52 that are applicable and technically relevant to the US ABWR design.

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

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

The System 80+ Standard Plant design control document. Volume 2

International Nuclear Information System (INIS)

1997-01-01

This Design Control Document (DCD) is a repository of information comprising the System 80+trademark Standard Plant Design. The DCD also provides that design-related information to be incorporated by reference in the design certification rule for the System 80+ Standard Plant Design. Applicants for a combined license pursuant to 10 CFR 52 must ensure that the final Design Certification Rule and the associated Statements of Consideration are used when making all licensing decisions relevant to the System 80+ Standard Plant Design. The Design Control Document contains the DCD introduction, The Certified Design Material (CDM) [i.e., ''Tier 1''] and the Approved Design Material (ADM) [i.e., ''Tier 2''] for the System 80+ Standard Plant Design. The CDM includes the following sections: (1) Introductory material; (2) Certified Design Material for System 80+ systems and structures; (3) Certified Design Material for non-system-based aspects of the System 80+ Certified design; (4) Interface requirements; and (5) Site parameters. The ADM, to the extent applicable for the System 80+ Standard Plant Design, includes: (1) the information required for the final safety analysis report under 20 CFR 50.34; (2) other relevant information required by 10 CFR 52.47; and (3) emergency operations guidelines. This volume covers the following information of the CDM: (2.8) Steam and power conversion; (2.9) Radioactive waste management; (2.10) Tech Support Center; (2.11) Initial test program; (2.12) Human factors; and sections 3, 4, and 5. Also covered in this volume are parts 1--6 of section 1 (General Plant Description) of the ADM Design and Analysis

Computer-Aided Authoring of Programmed Instruction for Teaching Symbol Recognition. Final Report.

Science.gov (United States)

Braby, Richard; And Others

This description of AUTHOR, a computer program for the automated authoring of programmed texts designed to teach symbol recognition, includes discussions of the learning strategies incorporated in the design of the instructional materials, hardware description and the algorithm for the software, and current and future developments. Appendices…

Preliminary safety analysis for key design features of KALIMER

Energy Technology Data Exchange (ETDEWEB)

Hahn, D. H.; Kwon, Y. M.; Chang, W. P.; Suk, S. D.; Lee, S. O.; Lee, Y. B.; Jeong, K. S

2000-07-01

KAERI is currently developing the conceptual design of a liquid metal reactor, KALIMER(Korea Advanced Liquid Metal Reactor) under the long-term nuclear R and D program. In this report, descriptions of the KALIMER safety design features and safety analyses results for selected ATWS accidents are presented. First, the basic approach to achieve the safety goal is introduced in chapter 1, and the safety evaluation procedure for the KALIMER design is described in chapter 2. It includes event selection, event categorization, description of design basis events, and beyond design basis events. In chapter 3, results of inherent safety evaluations for the KALIMER conceptual design are presented. The KALIMER core and plant system are designed to assure design performance during a selected set of events without either reactor control or protection system intervention. Safety analyses for the postulated anticipated transient without scram(ATWS) have been performed to investigate the KALIMER system response to the events. They are categorized as bounding events(BEs) because of their low probability of occurrence. In chapter 4, the design of the KALIMER containment dome and the results of its performance analysis are presented. The designs of the existing LMR containment and the KALIMER containment dome have been compared in this chapter. Procedure of the containment performance analysis and the analysis results are described along with the accident scenario and source terms. Finally, a simple methodology is introduced to investigate the core kinetics and hydraulic behavior during HCDA in chapter 5. Mathematical formulations have been developed in the framework of the modified bethe-tait method, and scoping analyses have been performed for the KALIMER core behavior during super-prompt critical excursions.

Advisory Committee on human radiation experiments. Final report, Supplemental Volume 2. Sources and documentation

International Nuclear Information System (INIS)

1995-01-01

This volume and its appendixes supplement the Advisory Committee's final report by reporting how we went about looking for information concerning human radiation experiments and intentional releases, a description of what we found and where we found it, and a finding aid for the information that we collected. This volume begins with an overview of federal records, including general descriptions of the types of records that have been useful and how the federal government handles these records. This is followed by an agency-by-agency account of the discovery process and descriptions of the records reviewed, together with instructions on how to obtain further information from those agencies. There is also a description of other sources of information that have been important, including institutional records, print resources, and nonprint media and interviews. The third part contains brief accounts of ACHRE's two major contemporary survey projects (these are described in greater detail in the final report and another supplemental volume) and other research activities. The final section describes how the ACHRE information-nation collections were managed and the records that ACHRE created in the course of its work; this constitutes a general finding aid for the materials deposited with the National Archives. The appendices provide brief references to federal records reviewed, descriptions of the accessions that comprise the ACHRE Research Document Collection, and descriptions of the documents selected for individual treatment. Also included are an account of the documentation available for ACHRE meetings, brief abstracts of the almost 4,000 experiments individually described by ACHRE staff, a full bibliography of secondary sources used, and other information

Advisory Committee on human radiation experiments. Final report, Supplemental Volume 2. Sources and documentation

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-01-01

This volume and its appendixes supplement the Advisory Committee`s final report by reporting how we went about looking for information concerning human radiation experiments and intentional releases, a description of what we found and where we found it, and a finding aid for the information that we collected. This volume begins with an overview of federal records, including general descriptions of the types of records that have been useful and how the federal government handles these records. This is followed by an agency-by-agency account of the discovery process and descriptions of the records reviewed, together with instructions on how to obtain further information from those agencies. There is also a description of other sources of information that have been important, including institutional records, print resources, and nonprint media and interviews. The third part contains brief accounts of ACHRE`s two major contemporary survey projects (these are described in greater detail in the final report and another supplemental volume) and other research activities. The final section describes how the ACHRE information-nation collections were managed and the records that ACHRE created in the course of its work; this constitutes a general finding aid for the materials deposited with the National Archives. The appendices provide brief references to federal records reviewed, descriptions of the accessions that comprise the ACHRE Research Document Collection, and descriptions of the documents selected for individual treatment. Also included are an account of the documentation available for ACHRE meetings, brief abstracts of the almost 4,000 experiments individually described by ACHRE staff, a full bibliography of secondary sources used, and other information.

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

Tokamak blanket design study, final report

Energy Technology Data Exchange (ETDEWEB)

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/sup 2/ and a particle heat flux of 1 MW/m/sup 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.

A novel binary shape context for 3D local surface description

Science.gov (United States)

Dong, Zhen; Yang, Bisheng; Liu, Yuan; Liang, Fuxun; Li, Bijun; Zang, Yufu

2017-08-01

3D local surface description is now at the core of many computer vision technologies, such as 3D object recognition, intelligent driving, and 3D model reconstruction. However, most of the existing 3D feature descriptors still suffer from low descriptiveness, weak robustness, and inefficiency in both time and memory. To overcome these challenges, this paper presents a robust and descriptive 3D Binary Shape Context (BSC) descriptor with high efficiency in both time and memory. First, a novel BSC descriptor is generated for 3D local surface description, and the performance of the BSC descriptor under different settings of its parameters is analyzed. Next, the descriptiveness, robustness, and efficiency in both time and memory of the BSC descriptor are evaluated and compared to those of several state-of-the-art 3D feature descriptors. Finally, the performance of the BSC descriptor for 3D object recognition is also evaluated on a number of popular benchmark datasets, and an urban-scene dataset is collected by a terrestrial laser scanner system. Comprehensive experiments demonstrate that the proposed BSC descriptor obtained high descriptiveness, strong robustness, and high efficiency in both time and memory and achieved high recognition rates of 94.8%, 94.1% and 82.1% on the considered UWA, Queen, and WHU datasets, respectively.

Logical Characterisation of Ontology Construction using Fuzzy Description Logics

DEFF Research Database (Denmark)

Badie, Farshad; Götzsche, Hans

had the extension of ontologies with Fuzzy Logic capabilities which plan to make proper backgrounds for ontology driven reasoning and argumentation on vague and imprecise domains. This presentation conceptualises learning from fuzzy classes using the Inductive Logic Programming framework. Then......, employs Description Logics in characterising and analysing fuzzy statements. And finally, provides a conceptual framework describing fuzzy concept learning in ontologies using the Inductive Logic Programming....

Water Resources Research Grant Program project descriptions, fiscal year 1987

Science.gov (United States)

,

1987-01-01

This report contains information on the 34 new projects funded by the United States Geological Survey 's Water Resources Research Grant Program in fiscal year 1987 and on 3 projects completed during the year. For the new projects, the report gives the grant number, project title, performing organization, principal investigator(s), and a project description that includes: (1) identification of water related problems and problem-solution approach (2) contribution to problem solution, (3) objectives, and (4) approach. The 34 projects include 12 in the area of groundwater quality problems, 12 in the science and technology of water quality management, 1 in climate variability and the hydrologic cycle, 4 in institutional change in water resources management, and 5 in surface water management. For the three completed projects, the report furnishes the grant number; project title; performing organization; principal investor(s); starting data; data of receipt of final report; and an abstract of the final report. Each project description provides the information needed to obtain a copy of the final report. The report contains tables showing: (1) proposals received according to area of research interest, (2) grant awards and funding according to area of research interest, (3) proposals received according to type of submitting organization, and (4) awards and funding according to type of organization. (Author 's abstract)

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

Decontamination and decommissioning of the Experimental Boiling Water Reactor (EBWR): Project final report, Argonne National Laboratory

International Nuclear Information System (INIS)

Fellhauer, C.R.; Boing, L.E.; Aldana, J.

1997-03-01

The Final Report for the Decontamination and Decommissioning (D ampersand D) of the Argonne National Laboratory - East (ANL-E) Experimental Boiling Water Reactor (EBWR) facility contains the descriptions and evaluations of the activities and the results of the EBWR D ampersand D project. It provides the following information: (1) An overall description of the ANL-E site and EBWR facility. (2) The history of the EBWR facility. (3) A description of the D ampersand D activities conducted during the EBWR project. (4) A summary of the final status of the facility, including the final and confirmation surveys. (5) A summary of the final cost, schedule, and personnel exposure associated with the project, including a summary of the total waste generated. This project report covers the entire EBWR D ampersand D project, from the initiation of Phase I activities to final project closeout. After the confirmation survey, the EBWR facility was released as a open-quotes Radiologically Controlled Area,close quotes noting residual elevated activity remains in inaccessible areas. However, exposure levels in accessible areas are at background levels. Personnel working in accessible areas do not need Radiation Work Permits, radiation monitors, or other radiological controls. Planned use for the containment structure is as an interim transuranic waste storage facility (after conversion)

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.

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...

Cold Vacuum Drying (CVD) Electrical System Design Description

International Nuclear Information System (INIS)

BRISBIN, S.A.

1999-01-01

This document provides a technical explanation of the design and operation of the electrical system for the Cold Vacuum Drying Facility. This document identifies the requirements, and the basis for the requirements and details on how the requirements have been implemented in the design and construction of the facility. This document also provides general guidance for the surveillance, testing, and maintenance of this system

Status of Preliminary Design on the Assembly Tools for ITER Tokamak Machine

International Nuclear Information System (INIS)

Nam, Kyoung O; Park, Hyun Ki; Kim, Dong Jin; Moon, Jae Hwan; Kim, Byung Seok; Lee, Jae Hyuk; Shaw, Robert

2012-01-01

The ITER Tokamak device is principally composed of nine 40 .deg. sectors. Each 40 .deg. sector is made up of one 40 .deg. vacuum vessel (VV), two 20 .deg. toroidal filed coils (TFC) and associated vacuum vessel thermal shield (VVTS) segments which consist of one inboard and two outboard vacuum vessel thermal shields. Based on the design description document and final report prepared by the ITER organization (IO) and conceptual design, Korea has carried out the preliminary design of these assembly tools. The assembly strategy and relevant tools for the 40 .deg. sector sub-assembly and sector assembly at in-pit should be developed to satisfy the basic assembly requirements of the ITER Tokamak machine. Assembly strategy, preliminary design of the sector sub-assembly and assembly tools are described in this paper

A theoretical description of inhomogeneous turbulence

International Nuclear Information System (INIS)

Turner, L.

2000-01-01

This is the final report of a three-year, Laboratory-Directed Research and Development (LDRD) project at the Los Alamos National Laboratory (LANL). In this LDRD, we have developed a highly compact and descriptive formalism that allows us to broach the theoretically formidable morass of inhomogeneous turbulence. Our formalism has two novel aspects: (a) an adaptation of helicity basis functions to represent an arbitrary incompressible channel flow and (b) the invocation of a hypothesis of random phase. A result of this compact formalism is that the mathematical description of inhomogeneous turbulence looks much like that of homogeneous turbulence--at the moment, the most rigorously explored terrain in turbulence research. As a result, we can explore the effect of boundaries on such important quantities as the gradients of mean flow, mean pressure, triple-velocity correlations and pressure velocity correlations, all of which vanish under the conventional, but artificial, assumption that the turbulence is statistically spatially uniform. Under suitable conditions, we have predicted that a mean flow gradient can develop even when none is initially present

Development and Implementation of a Model Training Program to Assist Special Educators, Parks and Resource Management Personnel and Parents to Cooperatively Plan and Conduct Outdoor/Environmental Education Programs for Handicapped Children and Youth. Final Report.

Science.gov (United States)

Vinton, Dennis A.; Zachmeyer, Richard F.

This final report presents a description of a 3-year project to develop and implement a model training program (for special education personnel, park and resource management personnel, and parents of disabled children) designed to promote outdoor environmental education for disabled children. The project conducted 22 training workshops (2-5 days)…

Improved motion description for action classification

Directory of Open Access Journals (Sweden)

Mihir eJain

2016-01-01

Full Text Available Even though the importance of explicitly integrating motion characteristics in video descriptions has been demonstrated by several recent papers on action classification, our current work concludes that adequately decomposing visual motion into dominant and residual motions, i.e.: camera and scene motion, significantly improves action recognition algorithms. This holds true both for the extraction of the space-time trajectories and for computation of descriptors.We designed a new motion descriptor – the DCS descriptor – that captures additional information on local motion patterns enhancing results based on differential motion scalar quantities, divergence, curl and shear features. Finally, applying the recent VLAD coding technique proposed in image retrieval provides a substantial improvement for action recognition. These findings are complementary to each other and they outperformed all previously reported results by a significant margin on three challenging datasets: Hollywood 2, HMDB51 and Olympic Sports as reported in (Jain et al. (2013. These results were further improved by (Oneata et al. (2013; Wang and Schmid (2013; Zhu et al. (2013 through the use of the Fisher vector encoding. We therefore also employ Fisher vector in this paper and we further enhance our approach by combining trajectories from both optical flow and compensated flow. We as well provide additional details of DCS descriptors, including visualization. For extending the evaluation, a novel dataset with 101 action classes, UCF101, was added.

The design, construction and commissioning of the CERN Large Electron-Positron collider

International Nuclear Information System (INIS)

Myers, S.; Picasso, E.

1990-01-01

A description is given of the most important parameters considered in the design of the CERN Large Electron-Positron collider. It is shown how these parameters affect the collider performance and how they have been optimised with respect to the cost of the project. The functioning of each major subsystem is described with respect to its role as part of the collider. Finally, the planning, testing and initial commissioning of LEP is described and possible future developments are outlined. (author)

Alpha Group: The Behemoth Apteryx. Final design proposal

Science.gov (United States)

1991-01-01

The participation of the University of Notre Dame's Alpha Design Group in the NASA/Universities Space Research Association (USRA) University Advanced Design Program for the 1990 to 1991 academic year is presented. Alpha Design Group presented a design for an aircraft called The Behemoth Apteryx.

The arbitrary order design code Tlie 1.0

International Nuclear Information System (INIS)

Zeijts, J. van; Neri, Filippo

1993-01-01

We describe the arbitrary order charged particle transfer map code TLIE. This code is a general 6D relativistic design code with a MAD compatible input language and among others implements user defined functions and subroutines and nested fitting and optimization. First we describe the mathematics and physics in the code. Aside from generating maps for all the standard accelerator elements we describe an efficient method for generating nonlinear transfer maps for realistic magnet models. We have implemented the method to arbitrary order in our accelerator design code for cylindrical current sheet magnets. We also have implemented a self-consistent space-charge approach as in CHARLIE. Subsequently we give a description of the input language and finally, we give several examples from productions run, such as cases with stacked multipoles with overlapping fringe fields. (Author)

SP-100 coated-particle fuel development. Phase I. Final report

International Nuclear Information System (INIS)

1983-03-01

This document is the final report of Phase I of the SP-100 Coated-Particle Fuel Development Program conducted by GA Technologies Inc. for the US Department of Energy under contract DE-AT03-82SF11690. The general objective of the study conducted between September and December 1982 was to evaluate coated-particle type fuel as an alternate or backup fuel to the UO 2 tile-and-fin arrangement currently incorporated into the reference design of the SP-100 reactor core. This report presents and discusses the following topics in the order listed: the need for an alternative fuel for the SP-100 nuclear reactor; an abbreviated description of the reference and coated-particle fuel module concepts; the bases and results of the study and analysis leading to the preliminary design of a coated particle suitable for the SP-100 space power reactor; incorporation of the fuel particles into compacts and heat-pipe-cooled modules; initial efforts and plans to fabricate coated-particle fuel and fuel compacts; the design and performance of the proposed alternative core relative that of the reference fuel; and a summary of critical issues and conclusions consistent with the level of effort and duration of the study

System 80+trademark Standard Design: CESSAR design certification

International Nuclear Information System (INIS)

1990-01-01

This report, entitled Combustion Engineering Standard Safety Analysis Report -- Design Certification (CESSAR-DC), has been prepared in support of the industry effort to standardize nuclear plant designs. These volumes describe the Combustion Engineering, Inc. System 80 + trademark Standard Design. This volume 8 provides a description of instrumentation and controls

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.

Software Design Level Security Vulnerabilities

OpenAIRE

S. Rehman; K. Mustafa

2011-01-01

Several thousand software design vulnerabilities have been reported through established databases. But they need to be structured and classified to be optimally usable in the pursuit of minimal and effective mitigation mechanism. In order we developed a criterion set for a communicative description of the same to serve the purpose as a taxonomic description of security vulnerabilities, arising in the design phase of Software development lifecycle. This description is a part of an effort to id...

Graphic Description: The Mystery of Ibn Khafaja\\'s Success in Description

Directory of Open Access Journals (Sweden)

جواد رنجبر

2009-12-01

Full Text Available Graphic Description:   The Mystery of Ibn Khafaja's Success in Description    Ali Bagher Taheriniya *  Javad Ranjbar **      Abstract Ibn Khafaja is one of the poets and men of letters in Spain. He is titled to Sanobari of Spain. He is one of the masters of description. Hence, the analysis of successful techniques he has used in the descriptive art could illuminate the way for others. Al-Taswir al-harfi (graphic description is a term which denotes the highest and most detailed poems. On this basis, the best descriptive poem is one which is closer to a painting. He has used some elements called conforming elements of description which contain: imagination, feeling, faculty, and dialogue as well as three other elements: to be inborn in description, enchanting nature and convenient life. This article is going to give an analysis of the reasons for Ibn Khafaja’s success in description and portrait making.   Key words: Ibn Khafaja, poetry, description, portrait   * Associate Professor, Bu Ali Sina University of Hamadan E-mail: bTaheriniya@yahoo.com  ** M.A. in Arabic Language and Literature

Expanded studies of linear collider final focus systems at the Final Focus Test Beam

International Nuclear Information System (INIS)

Tenenbaum, P.G.

1995-12-01

In order to meet their luminosity goals, linear colliders operating in the center-of-mass energy range from 3,50 to 1,500 GeV will need to deliver beams which are as small as a few Manometers tall, with x:y aspect ratios as large as 100. The Final Focus Test Beam (FFTB) is a prototype for the final focus demanded by these colliders: its purpose is to provide demagnification equivalent to those in the future linear collider, which corresponds to a focused spot size in the FFTB of 1.7 microns (horizontal) by 60 manometers (vertical). In order to achieve the desired spot sizes, the FFTB beam optics must be tuned to eliminate aberrations and other errors, and to ensure that the optics conform to the desired final conditions and the measured initial conditions of the beam. Using a combination of incoming-beam diagnostics. beam-based local diagnostics, and global tuning algorithms, the FFTB beam size has been reduced to a stable final size of 1.7 microns by 70 manometers. In addition, the chromatic properties of the FFTB have been studied using two techniques and found to be acceptable. Descriptions of the hardware and techniques used in these studies are presented, along with results and suggestions for future research

Expanded studies of linear collider final focus systems at the Final Focus Test Beam

Energy Technology Data Exchange (ETDEWEB)

Tenenbaum, Peter Gregory [Stanford Univ., CA (United States)

1995-12-01

In order to meet their luminosity goals, linear colliders operating in the center-of-mass energy range from 3,50 to 1,500 GeV will need to deliver beams which are as small as a few Manometers tall, with x:y aspect ratios as large as 100. The Final Focus Test Beam (FFTB) is a prototype for the final focus demanded by these colliders: its purpose is to provide demagnification equivalent to those in the future linear collider, which corresponds to a focused spot size in the FFTB of 1.7 microns (horizontal) by 60 manometers (vertical). In order to achieve the desired spot sizes, the FFTB beam optics must be tuned to eliminate aberrations and other errors, and to ensure that the optics conform to the desired final conditions and the measured initial conditions of the beam. Using a combination of incoming-beam diagnostics. beam-based local diagnostics, and global tuning algorithms, the FFTB beam size has been reduced to a stable final size of 1.7 microns by 70 manometers. In addition, the chromatic properties of the FFTB have been studied using two techniques and found to be acceptable. Descriptions of the hardware and techniques used in these studies are presented, along with results and suggestions for future research.

Status of the HTR 500 design program

International Nuclear Information System (INIS)

Baust, E.; Arndt, E.

1987-01-01

Since 1982 BBC/HRB have offered the HTR 500 as the follow-on project of the THTR 300, the first large pebble bed reactor. The technical concept of the HTR-500 largely corresponds to the THTR 300 which has been in operation for almost 2 years now. In developing the design concept of the HTR 500 the ideas and demands of the reactor users in the FRG interested in the HTR have been taken into consideration to a large extent. In 1982 these potential users formed a working group 'Arbeitsgemeinschaft Hochtemperaturreaktor' (AHR), representing 16 power indusry companies and in early 1983, awarded a contract to HRB to perform a conceptual design study on the HTR 500. Within this conceptual design study BBC/HRB developed the safety concept of the HTR 500, prepared a detailed description of the overall power plant, and performed a cost calculation. These activities were completed in 1984. Based on the positive results of this conceptual design study, BBC/HRB are expecting to be granted a design contract by the users company Hochtemperaturreaktor GmbH (HRG) to establish the final complete design plans and documents for the HTR 500. (author)

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

Descriptive and mechanistic models of crop–weed competition

NARCIS (Netherlands)

Bastiaans, L.; Storkey, J.

2017-01-01

Crop-weed competitive relations are an important element of agroecosystems. Quantifying and understanding them helps to design appropriate weed management at operational, tactical and strategic level. This chapter presents and discusses simple descriptive and more mechanistic models for crop-weed

Descriptive data of JENDL-3.2

Energy Technology Data Exchange (ETDEWEB)

Shibata, Keiichi; Narita, Tsutomu [eds.; Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

1998-02-01

The second revision of JENDL-3 (JENDL-3.2) was released in 1994. The library contains evaluated neutron nuclear data for 340 nuclides which are needed for the design of fission and fusion reactors and for shielding calculation. This report presents a brief description of the evaluation method which is given in the File-1 part of JENDL-3.2. (author)

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)

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)

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

Energy Technology Data Exchange (ETDEWEB)

Bruschi, H.J. [Westinghouse Electric Corp., Pittsburgh, PA (United States)

1996-10-01

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)

78 FR 3897 - Final Effect of Designation of a Class of Employees for Addition to the Special Exposure Cohort

Science.gov (United States)

2013-01-17

... DEPARTMENT OF HEALTH AND HUMAN SERVICES Final Effect of Designation of a Class of Employees for Addition to the Special Exposure Cohort AGENCY: National Institute for Occupational Safety and Health... number of work days aggregating at least 250 work days, occurring either solely under this employment or...

78 FR 3898 - Final Effect of Designation of a Class of Employees for Addition to the Special Exposure Cohort

Science.gov (United States)

2013-01-17

... DEPARTMENT OF HEALTH AND HUMAN SERVICES Final Effect of Designation of a Class of Employees for Addition to the Special Exposure Cohort AGENCY: National Institute for Occupational Safety and Health... number of work days aggregating at least 250 work days, occurring either solely under this employment or...

Making the case for evidence-based design in healthcare: a descriptive case study of organizational decision making.

Science.gov (United States)

Shoemaker, Lorie K; Kazley, Abby Swanson; White, Andrea

2010-01-01

The aim of this study was to describe the organizational decision-making process used in the selection of evidence-based design (EBD) concepts, the criteria used to make these decisions, and the extent to which leadership style may have influenced the decision-making process. Five research questions were formulated to frame the direction of this study, including: (1) How did healthcare leaders learn of innovations in design? (2) How did healthcare leaders make decisions in the selection of healthcare design concepts? (3) What criteria did healthcare leaders use in the decision-making process? (4) How did healthcare leaders consider input from the staff in design decisions? and (5) To what extent did the leadership style of administrators affect the outcomes of the decision-making process? Current issues affecting healthcare in the community led the principal investigator's organization to undertake an ambitious facilities expansion project. As part of its planning process, the organization learned of EBD principles that seemingly had a positive impact on patient care and safety and staff working conditions. Although promising, a paucity of empirical research addressed the cost/benefit of incorporating many EBD concepts into one hospital setting, and there was no research that articulated the organizational decision-making process used by healthcare administrators when considering the use of EBD in expansion projects. A mixed-method, descriptive, qualitative, single-case study and quantitative design were used to address the five research questions. The Systems Research Organizing Model provided the theoretical framework. A variety of data collection methods was used, including interviews of key respondents, the review of documentary evidence, and the Multifactor Leadership Questionnaire. A participatory process was used throughout the design decision phases, involving staff at all levels of the organization. The Internet and architects facilitated learning about

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

JEM-X ISSW architectural design document

DEFF Research Database (Denmark)

Maisala, S.; Huovelin, J.; Westergaard, Niels Jørgen Stenfeldt

Detailed description of the architectural design of the JEM-X instrument specific software, to be delivered by SDAST to ISDC.......Detailed description of the architectural design of the JEM-X instrument specific software, to be delivered by SDAST to ISDC....

Design of an integrated I and C system

International Nuclear Information System (INIS)

Lee, C. K.; Oh, I. S.; Kim, D. H.

2004-08-01

The final goal of this project is to develop an integrated I and C systems, and through this project the localized equipment and systems being developed should secure the safety, the reliability, their applicability and technical competitiveness. As well, the technical interfaces among sub-projects should be maintained for integration. The results of this project are as following ; 1. Development of an integrated I and C system architecture: Development of the design concepts for KNICS and the design requirements for each I and C system, Development of the design requirements of control systems based on DCS, Design of the communication systems, Design of the interface signals among systems and analysis of traffic load for networks, Conceptual design of measuring and monitoring systems, Review of the structure of computer systems for information processing, Development of architectures for each system and KOICS 2. Technological integration and management of projects: Development of evaluation criteria for DCS and network systems, Evaluation of the DCS prototype, Design review of KNICS protection system, Review of the functions and design requirements of I and C systems in NPP, Analysis of the I and C system H/W in NPP and the APR1400 I and C system design, Review of the technology criteria and the regulatory trend for licensing issues, Extracting items for preparing the technical description of I and C systems, a part of proposal to invitation to bid (ITB), Planning for KNICS to be of practical use The results of this project will be applied as design bases during the development of 2nd phase KNICS. As well it is expected that the results of this project will be finally applied for the technical self-reliance of component design and manufacturing of NPP I and C systems

Nuclear Electric flask design and safety case development during the last ten years

International Nuclear Information System (INIS)

Dougall, I.; Jones, D.K.

1994-01-01

The scope of Nuclear Electric's (NE) requirements for irradiated fuel transport and the relevant safety and regulatory compliance standards are outlined. To illustrate NE's approach to demonstrating package design compliance the basis of the safety case for unbottled Magnox fuel transport in the Mk M2 Magnox flask is described. The considerations which lay behind the development of the Mk A2 AGR Flask are indicated and a description is given of the main design features of this flask. Finally there is a summary of progress in obtaining Type B(M) approvals, based on the 1985 IAEA Regulations, for the requisite range of flask contents. (author)

Final Report Package_Winnebago

Energy Technology Data Exchange (ETDEWEB)

Carolyn Stewart, Director, Red Mountain Energy Partners

2006-10-31

The Winnebago Tribe of Nebraska energy options study results will be used to advance the Tribe’s near term energy management objectives. The array of energy options identified allows the Tribe to select those activities that best fit its energy strategies, goals and objectives. During the course of the study, Red Mountain analyzed both energy options and energy organizational alternatives suitable for the Tribe, presented findings to the Tribal Council, and made recommendations regarding each. Work products delivered to the Tribe, and provided in the Final Report included: • A matrix of energy management options applicable to the Tribe, which provided descriptions of particular conservation, efficiency, weatherization, and demand management alternatives. The matrix also provided insight about relative costs of the alternatives, cost/benefit efficacy, ease of implementation, resources for implementing, and observations about each. • A matrix of utility service options applicable to the Tribe, describing each of the four alternatives described above. The matrix also provided insight about key benefits of each option, required resources, costs and timeframe for implementation, funding sources and analysis, and key issues for consideration. • Discussion guides prepared for each meeting between the Energy Committee and Council, and the Tribe’s contractor, Red Mountain Energy Partners, which included preliminary analysis and findings. • A Position Description for the Energy Manager position, which was reviewed by the Tribal HR Department, and used by the Tribe to develop a position posting. • A Utility Code designed for Winnebago to use in establishing its Utility Board, and, ultimately, to provide guidance for the Board’s further development. • A project summary book developed to include all key information, deliverables and utility provider data for the project. Winnebago’s growth trends and expansion plans require the Tribe to play a more active

Design of a fuel-efficient guidance system for a STOL aircraft

Science.gov (United States)

Mclean, J. D.; Erzberger, H.

1981-01-01

In the predictive mode, the system synthesizes a horizontal path from an initial aircraft position and heading to a desired final position and heading and then synthesizes a fuel-efficient speed-altitude profile along the path. In the track mode, the synthesized trajectory is reconstructed and tracked automatically. An analytical basis for the design of the system is presented and a description of the airborne computer implementation is given. A detailed discussion of the software, which should be helpful to those who use the actual software developed for these tests, is also provided.

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)

Hardware synthesis from DDL. [Digital Design Language for computer aided design and test of LSI

Science.gov (United States)

Shah, A. M.; Shiva, S. G.

1981-01-01

The details of the digital systems can be conveniently input into the design automation system by means of Hardware Description Languages (HDL). The Computer Aided Design and Test (CADAT) system at NASA MSFC is used for the LSI design. The Digital Design Language (DDL) has been selected as HDL for the CADAT System. DDL translator output can be used for the hardware implementation of the digital design. This paper addresses problems of selecting the standard cells from the CADAT standard cell library to realize the logic implied by the DDL description of the system.

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

Irreducible descriptive sets of attributes for information systems

KAUST Repository

Moshkov, Mikhail

2010-01-01

The maximal consistent extension Ext(S) of a given information system S consists of all objects corresponding to attribute values from S which are consistent with all true and realizable rules extracted from the original information system S. An irreducible descriptive set for the considered information system S is a minimal (relative to the inclusion) set B of attributes which defines exactly the set Ext(S) by means of true and realizable rules constructed over attributes from the considered set B. We show that there exists only one irreducible descriptive set of attributes. We present a polynomial algorithm for this set construction. We also study relationships between the cardinality of irreducible descriptive set of attributes and the number of attributes in S. The obtained results will be useful for the design of concurrent data models from experimental data. © 2010 Springer-Verlag.

Qualitative description - the poor cousin of health research?

DEFF Research Database (Denmark)

Neergaard, Mette Asbjørn; Olesen, Frede; Andersen, Rikke Sand

2009-01-01

', relatives' or professionals' experiences with a particular topic. Another great advantage of the method is that it is suitable if time or resources are limited. SUMMARY: As a consequence of the growth in qualitative research in the health sciences, researchers sometimes feel obliged to designate their work......BACKGROUND: The knowledge and use of qualitative description as a qualitative research approach in health services research is limited.The aim of this article is to discuss the potential benefits of a qualitative descriptive approach, to identify its strengths and weaknesses and to provide examples...... of use. DISCUSSION: Qualitative description is a useful qualitative method in much medical research if you keep the limitations of the approach in mind. It is especially relevant in mixed method research, in questionnaire development and in research projects aiming to gain firsthand knowledge of patients...

Distinguishing Features and Similarities Between Descriptive Phenomenological and Qualitative Description Research.

Science.gov (United States)

Willis, Danny G; Sullivan-Bolyai, Susan; Knafl, Kathleen; Cohen, Marlene Z

2016-09-01

Scholars who research phenomena of concern to the discipline of nursing are challenged with making wise choices about different qualitative research approaches. Ultimately, they want to choose an approach that is best suited to answer their research questions. Such choices are predicated on having made distinctions between qualitative methodology, methods, and analytic frames. In this article, we distinguish two qualitative research approaches widely used for descriptive studies: descriptive phenomenological and qualitative description. Providing a clear basis that highlights the distinguishing features and similarities between descriptive phenomenological and qualitative description research will help students and researchers make more informed choices in deciding upon the most appropriate methodology in qualitative research. We orient the reader to distinguishing features and similarities associated with each approach and the kinds of research questions descriptive phenomenological and qualitative description research address. © The Author(s) 2016.

Optical design of high power excimer laser system

International Nuclear Information System (INIS)

Zhang Yongsheng; Zhao Jun; Ma Lianying; Yi Aiping; Liu Jingru

2011-01-01

Image relay and angular multiplexing,which should be considered together in the design of high power excimer laser system, is reviewed. It's important to select proper illumination setup and laser beam shaping techniques. Given the complex and special angular multiplexing scheme in high power excimer laser systems, some detailed conceptual layout schemes are given in the paper. After a brief description of lens array and reflective telescope objective, which combine the incoming beams to a common focus, a new schematic layout which uses the final targeting optics and one optical delay line array, to realize multiplexing and de-multiplexing simultaneously is first proposed in the paper. (authors)

Conceptual Design for Consolidation TCAP

International Nuclear Information System (INIS)

Klein, J.E.

1999-01-01

Two alternate Thermal Cycling Absorption Process (TCAP) designs have been developed for the Tritium Facility Modernization and Consolidation (TFM and C) Project. The alternate designs were developed to improve upon the existing Replacement Tritium Facility (RTF) TCAP design and to eliminate the use of building distributed hot and cold nitrogen system.A brief description of TCAP theory and modeling is presented, followed by an overview of the design criteria for the Isotope Separation System (ISS). Both designs are described in detail, along with a generic description of the complete TCAP system. A design is recommend for the Consolidation Project, and a development plan for both designs is proposed

Analytic transfer maps for Lie algebraic design codes

International Nuclear Information System (INIS)

van Zeijts, J.; Neri, F.; Dragt, A.J.

1990-01-01

Lie algebraic methods provide a powerful tool for modeling particle transport through Hamiltonian systems. Briefly summarized, Lie algebraic design codes work as follows: first the time t flow generated by a Hamiltonian system is represented by a Lie algebraic map acting on the initial conditions. Maps are generated for each element in the lattice or beamline under study. Next all these maps are concatenated into a one-turn or one-pass map that represents the complete dynamics of the system. Finally, the resulting map is analyzed and design decisions are made based on the linear and nonlinear entries in the map. The authors give a short description of how to find Lie algebraic transfer maps in analytic form, for inclusion in accelerator design codes. As an example they find the transfer map, through third order, for the combined-function quadrupole magnet, and use such magnets to correct detrimental third-order aberrations in a spot forming system

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…

Anti-foam System design description

International Nuclear Information System (INIS)

White, M.A.

1994-01-01

The Anti-foam System is a sub-system of the 242-A Evaporator facility. The Anti-foam is used within the C-A-1 Vapor-Liquid Separator, to reduce the effect of foaming and reduce fluid bumping while the vapor and liquid are separated within the C-A-1 Vapor-Liquid Separator. Excessive foaming within the vessel may possibly cause the liquid slurry mixture in the evaporator vessel to foul the de-entrainment pads and cause plant shutdown. The Anti-foam System consists of the following primary elements: the Anti-foam Tank and the Metering Pump. The upgrades to Anti-foam System include the following: installation of a new pump, instruments, and valves; and connection of the instruments, pump and agitator associated with the Anti-foam System to the Monitoring and Control System (MCS). The 242-A Evaporator is a waste treatment facility designed to reduce liquid waste volumes currently stored in the Hanford Area double shell Waste Storage Tanks. The evaporator uses evaporative concentration to achieve this volume reduction, returning the concentrated slurry to the double-shell tanks for storage and, at the same time, releasing the process effluent to a retention facilities for eventual treatment and release to the environment

Technical description of the test section SUCOT to investigate a water/steam two-phase flow

International Nuclear Information System (INIS)

Daubner, M.; Janssens-Maenhout, G.; Knebel, J.U.

2002-02-01

Within the POOLTHY Project of the European Union (Euratom Fourth Framework Programme contract FJ4J-CT95-0003) an active/passive concept (SUCO-Programme) was investigated which controls the heat removal after a potential core melt-down accident in an evolutionary light water reactor by spreading and stabilising the core melt in the reactor sump and flooding the melt with sump water from above. The experiments were performed in the test facility SUCOT which was designed and erected at the Institute for Nuclear and Energy Technologies (IKET). The report gives an overview on the SUCO-Programme and the scaling analysis, which was applied to design the test facility SUCOT. A detailed technical description of the test facility SUCOT is given, in which the natural circulation driven two-phase flow within the reactor sump and relevant phenomena such as flow boiling, disperse bubbly flow with and without mass transfer, and geysering are investigated. The major components of the test facility, the three-loop system and the instrumentation are described. Finally, a perspective for future application of the gained knowledge is given. (orig.) [de

The electrical power subsystem design for the high energy solar physics spacecraft concepts

Science.gov (United States)

Kulkarni, Milind

1993-01-01

This paper discusses the Electrical Power Subsystem (EPS) requirements, architecture, design description, performance analysis, and heritage of the components for two spacecraft concepts for the High Energy Solar Physics (HESP) Mission. It summarizes the mission requirements and the spacecraft subsystems and instrument power requirements, and it describes the EPS architecture for both options. A trade study performed on the selection of the solar cells - body mounted versus deployed panels - and the optimum number of panels is also presented. Solar cell manufacturing losses, array manufacturing losses, and the radiation and temperature effects on the GaAs/Ge and Si solar cells were considered part of the trade study and are included in this paper. Solar cell characteristics, cell circuit description, and the solar array area design are presented, as is battery sizing analysis performed based on the power requirements during launch and initial spacecraft operations. This paper discusses Earth occultation periods and the battery power requirements during this period as well as shunt control, battery conditioning, and bus regulation schemes. Design margins, redundancy philosophy, and predicted on-orbit battery and solar cell performance are summarized. Finally, the heritage of the components and technology risk assessment are provided.

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

Qualitative description – the poor cousin of health research?

Science.gov (United States)

2009-01-01

Background The knowledge and use of qualitative description as a qualitative research approach in health services research is limited. The aim of this article is to discuss the potential benefits of a qualitative descriptive approach, to identify its strengths and weaknesses and to provide examples of use. Discussion Qualitative description is a useful qualitative method in much medical research if you keep the limitations of the approach in mind. It is especially relevant in mixed method research, in questionnaire development and in research projects aiming to gain firsthand knowledge of patients', relatives' or professionals' experiences with a particular topic. Another great advantage of the method is that it is suitable if time or resources are limited. Summary As a consequence of the growth in qualitative research in the health sciences, researchers sometimes feel obliged to designate their work as phenomenology, grounded theory, ethnography or a narrative study when in fact it is not. Qualitative description might be a useful alternative approach to consider. PMID:19607668

The effect of increasing levels of embedded generation on the distribution network. Final report

Energy Technology Data Exchange (ETDEWEB)

Collinson, A; Earp, G K; Howson, D; Owen, R D; Wright, A J

1999-10-01

This report was commissioned as part of the EA Technology Strategic Technology Programme under guidance of the Module 5 (Embedded Generation) Steering Group. This report aims to provide information related to the distribution and supply of electricity in the context of increasing levels of embedded generation. There is a brief description of the operating environment within which electricity companies in the UK must operate. Technical issues related to the connection of generation to the existing distribution infrastructure are highlighted and the design philosophy adopted by network designers in accommodating applications for the connection of embedded generation to the network is discussed. The effects embedded generation has on the network and the issues raised are presented as many of them present barriers to the connection of embedded generators. The final chapters cover the forecast of required connection to 2010 and solutions to restrictions preventing the connection of more embedded generation to the network. (author)

Feasibility and Basic Design of Solar Integrated Absorption Refrigeration for an Industry

KAUST Repository

Akhtar, Saad

2015-08-28

This paper presents a review of existing solar cooling technologies and a feasibility study of a solar absorption cooling system for a packaging facility at Tetrapak Lahore, Pakistan. The review includes brief description of existing chiller technologies and solar collectors. The case study includes analysis of the solar potential and design of the cooling system at considered site. The design calculations upon which the feasibility analysis is carried out are solar collector area and type, cooling capacity, cooling area. A comparison is made between solar cooling potential of Pakistan and existing sites all across the globe. Finally an economic analysis is carried out to demonstrate the financial viability of the new cooling system.

Blind Decoding of Multiple Description Codes over OFDM Systems via Sequential Monte Carlo

Directory of Open Access Journals (Sweden)

Guo Dong

2005-01-01

Full Text Available We consider the problem of transmitting a continuous source through an OFDM system. Multiple description scalar quantization (MDSQ is applied to the source signal, resulting in two correlated source descriptions. The two descriptions are then OFDM modulated and transmitted through two parallel frequency-selective fading channels. At the receiver, a blind turbo receiver is developed for joint OFDM demodulation and MDSQ decoding. Transformation of the extrinsic information of the two descriptions are exchanged between each other to improve system performance. A blind soft-input soft-output OFDM detector is developed, which is based on the techniques of importance sampling and resampling. Such a detector is capable of exchanging the so-called extrinsic information with the other component in the above turbo receiver, and successively improving the overall receiver performance. Finally, we also treat channel-coded systems, and a novel blind turbo receiver is developed for joint demodulation, channel decoding, and MDSQ source decoding.

Qualitative Description of Spatial Quality in Inclusive Architecture.

Science.gov (United States)

Ryhl, Camilla; Kajita, Masashi; Sørensen, René

2016-01-01

Universal design (UD) has gained global significance and is in the process of institutionalisation in the Nordic Region. This is despite an urgent necessity for developing the theoretical basis and practical applicability of UD. Reflecting this need for furthering the comprehensive understanding of spatial implication of UD, this paper aims to contribute for articulating a means to assess the quality of UD in architecture. Drawing upon numerous cases from research conducted at the Danish Building Research Institute, the paper focuses on sensory aspects of spatial quality, and discusses as well as reflects an applied method for producing the qualitative description of selected buildings that embody UD through creative solutions. The qualitative description of collected examples appears to be effective in delineating sensory aspects of spatial experience; however the systematic development of assessment criteria is essential in order to support students and designers to make responsible decisions in shaping built environments that are accessible and inclusive but also enjoyable.

Exploratory shaft facility preliminary designs - Permian Basin

International Nuclear Information System (INIS)

1983-09-01

The purpose of the Preliminary Design Report, Permian Basin, is to provide a description of the preliminary design for an Exploratory Shaft Facility in the Permian Basin, Texas. This issue of the report describes the preliminary design for constructing the exploratory shaft using the Large Hole Drilling method of construction and outlines the preliminary design and estimates of probable construction cost. The Preliminary Design Report is prepared to complement and summarize other documents that comprise the design at the preliminary stage of completion, December 1982. Other design documents include drawings, cost estimates and schedules. The preliminary design drawing package, which includes the construction schedule drawing, depicts the descriptions in this report. For reference, a list of the drawing titles and corresponding numbers are included in the Appendix. The report is divided into three principal sections: Design Basis, Facility Description, and Construction Cost Estimate. 30 references, 13 tables

Final design report, September 11, 1986

International Nuclear Information System (INIS)

1988-11-01

The task is to design the quasi-optical microwave components for each of five different optical paths within the MFTF-B machine. Each path contains two reflectors. The function of the two reflectors in each path is to modify the output field of a waveguide to a desired pattern within the plasma. For all five beam paths, the waveguide output is assumed to be a TE 01 mode as decided at the July 18, design review. Each optical train consists of two reflectors. The first reflector is an off axis paraboloid which focuses the beam. The first reflector also contains the groove pattern of the twist polarizer. The second reflector receives the polarized beam from the first reflector. The function of the second reflector is to modify the phase of the polarized wavefront received from the first reflector. This modification shapes the wavefront profile in the plasma

From particle to kinetic and hydrodynamic descriptions of flocking

OpenAIRE

Ha, Seung-Yeal; Tadmor, Eitan

2008-01-01

We discuss the Cucker-Smale's (C-S) particle model for flocking, deriving precise conditions for flocking to occur when pairwise interactions are sufficiently strong long range. We then derive a Vlasov-type kinetic model for the C-S particle model and prove it exhibits time-asymptotic flocking behavior for arbitrary compactly supported initial data. Finally, we introduce a hydrodynamic description of flocking based on the C-S Vlasov-type kinetic model and prove flocking behavior \\emph{without...

Difficulties Encountered by Final-Year Male Nursing Students in Their Internship Programmes

Science.gov (United States)

Al-Momani, Mohammed Mahmoud

2017-01-01

Background The cultural norms of the Kingdom of Saudi Arabia do not encourage men to choose nursing as a career. Understanding male nursing students’ experiences of their clinical exposure to the nursing profession throughout their internship might increase their retention. This study explored the experiences of final-year male nursing students as they transitioned to the role of registered nurse. Methods A qualitative descriptive research design with an inductive content-analysis approach was used. The experiences of 22 final-year male nursing students from three public hospitals in a major city of Saudi Arabia were explored. The data were collected using focus-group interviews and documentary analysis in March 2015 and May 2015. Results Content analysis revealed three major themes: the societal and cultural image of male nurses, male students’ engagement in nursing practice, and restructuring the internship programmes’ policies to suit male students’ needs. Conclusion The findings reveal issues that mainly stem from negative social views of nursing as a male profession. Considering the students’ social and cultural needs during their internship programme will facilitate their transition into the role of registered nurse and their retention in the nursing profession. PMID:28951687

Support vector data description for fusion of multiple health indicators for enhancing gearbox fault diagnosis and prognosis

International Nuclear Information System (INIS)

Wang, Dong; Tse, Peter W; Guo, Wei; Miao, Qiang

2011-01-01

A novel method for enhancing gearbox fault diagnosis and prognosis is developed by fusion of multiple health indicators through support vector data description. First, the Comblet transform is used to identify gear residual error signals from the raw signal. Second, based on the observation of gear residual error signals, a total of 11 gear health indicators are identified, and are categorized into two types of indicators. The first and second types of indicators are for fault diagnosis and prognosis, respectively. The first type has six indicators, which are sensitive to impulsive signals triggered by anomalous impacts. The second type has five indicators, which are suitable for tracking degradation of faults. Third, through the support vector data description, the first six health indicators are fused into type one indicators for fault diagnosis. The remaining five indicators are fused into type two indicators for fault prognosis. Finally, a Gaussian kernel is designed to enhance the performance of type one and two indicators by optimal range of width size. The effectiveness of the proposed method is validated through experiments. The new method has been proven to be superior to methods that use unfused indicators individually

A feasibility study for the design of a simulated radioactive waste repository facility

International Nuclear Information System (INIS)

1986-10-01

The paper contains the text and references of a feasibility study for the design of a simulated radioactive waste repository facility (final report). The work was commissioned by the Department of the Environment, United Kingdom, as part of its radioactive waste management research programme. The nature of the candidate buffer materials, the factors defining their behaviour, and the nature of a buffer material selection and testing programme, are examined. A description is given of the properties and modelling of host materials. The complex interactions between host materials, and between buffer and host materials, are discussed, along with the instrumentation requirements for measuring the interactions. Finally, the temperature field around a waste package, and modelling a host continuum with a segmental block, are both investigated. (U.K.)

A prospective descriptive study of the management of miscarriages ...

African Journals Online (AJOL)

Objective: To assess the current management of incomplete miscarriage at Harare and Parirenyatwa Hospitals and to determine the proportion of patients with incomplete miscarriage managed with Manual Vacuum Aspiration (MVA), sharp curettage or medical evacuation. Design: A prospective descriptive study.

Prototypical spent nuclear nuclear fuel rod consolidation equipment, Phase 2: Final design report: Volume 2, Appendices: Part 1

International Nuclear Information System (INIS)

Ciez, A.P.

1987-01-01

The purpose of this specification is to establish functional and design requirements for the Prototypical Spent Nuclear Fuel Rod Consolidation System. The Department of Energy-Idaho Operations Office (DOE-ID) is responsible for the implementation of the Prototypic Dry Rod Consolidation Demonstration Project. This program is to develop and demonstrate a fully qualified, licensable, cost-effective, dry spent fuel rod consolidation system by July 1989. The work is divided into four phases as follows: Phase I--Preliminary Design, Phase II--Final Design Option, Phase III--Fabrication and System Checkout Option, and Phase IV--Installation and Hot Demonstration Option. This specification is part of the Phase II effort. The objectives of this specification are to provide functional and design requirements for the Prototypical Spent Nuclear Fuel Rod Consolidation equipment; establish specific tool and subsystem requirements such that the integrated and overall system requirements are satisfied; and establish positioning, envelope and size interface control requirements for each tool or subsystem such that the individual components will interface properly with the overall system design

System description of the Basic MRS System for the FY 1990 Systems Integration Program studies

International Nuclear Information System (INIS)

McKee, R.W.; Young, J.R.; Konzek, G.J.

1991-07-01

This document provides both functional and physical descriptions of a conceptual high-level waste management system defined as a Basic MRS System. Its purpose is to provide a basis for required system computer modeling and system studies initiated in FY 1990 under the Systems Integration Program of the Office of Civilian Radioactive Waste Management Office (OCRWM). Two specific systems studies initiated in FY 1990, the Reference System Performance Evaluation and the Aggregate Receipt Rate Study, utilize the information in this document. The Basic MRS System is the current OCRWM reference high-level radioactive wastes repository system concept. It is designed to accept 3000 MTU per year of spent fuel and 400 equivalent MTU per year of high-level wastes. The Basic MRS System includes a storage-only MRS that provides for a limited amount of commercial spent fuel storage capacity prior to acceptance by the geologic repository for disposal. This document contains both functional descriptions of the processes in the waste management system and physical descriptions of the equipment and facilities necessary for performance of those processes. The basic MRS system contains all system components, from the waste storage facilities of the waste generators to the underground facilities for final disposal of the wastes. The major facilities in the system are the waste generator waste storage facilities, an MRS facility that provides interim storage wastes accepted from the waste generators, a repository facility that packages the wastes and then emplaces them in the geologic repository, and the transportation equipment and facilities for transporting the waste between these major facilities

Final focus systems for linear colliders

International Nuclear Information System (INIS)

Erickson, R.A.

1987-11-01

The final focus system of a linear collider must perform two primary functions, it must focus the two opposing beams so that their transverse dimensions at the interaction point are small enough to yield acceptable luminosity, and it must steer the beams together to maintain collisions. In addition, the final focus system must transport the outgoing beams to a location where they can be recycled or safely dumped. Elementary optical considerations for linear collider final focus systems are discussed, followed by chromatic aberrations. The design of the final focus system of the SLAC Linear Collider (SLC) is described. Tuning and diagnostics and steering to collision are discussed. Most of the examples illustrating the concepts covered are drawn from the SLC, but the principles and conclusions are said to be generally applicable to other linear collider designs as well. 26 refs., 17 figs

On the description of fault-tolerant systems

International Nuclear Information System (INIS)

Syrbe, M.

1980-01-01

Various demands by increasing complexity and the disposability of new technologies, like the One-chip-microcomputer and fiber optics, lead to control systems, which are built as decentralized distributed multi-microcomputersystems. They realize not only new control functions but they also open possibilities to increase availability by fault-tolerance. The design or the selection and lay-out of such systems require a quantitative description of these systems. This is possible on the bases of the set of hardware and software moduls of the system by the use of queuing models, reliability nets and diagnostic graphs. This is shown by an example of a practically applied Really Distributed Computer Control System (RDC-System). Computer aided methods for these system descriptions are emphasized. (orig.) [de

On the pedagogy of pharmacological communication: a study of final semester health science students.

Science.gov (United States)

Zetterqvist, Ann; Aronsson, Patrik; Hägg, Staffan; Kjellgren, Karin; Reis, Margareta; Tobin, Gunnar; Booth, Shirley

2015-10-26

There is a need to improve design in educational programmes for the health sciences in general and in pharmacology specifically. The objective of this study was to investigate and problematize pharmacological communication in educational programmes for the health sciences. An interview study was carried out where final semester students from programmes for the medical, nursing and specialist nursing in primary health care professions were asked to discuss the pharmacological aspects of two written case descriptions of the kind they would meet in their everyday work. The study focused on the communication they envisaged taking place on the concerns the patients were voicing, in terms of two features: how communication would take place and what would be the content of the communication. A phenomenographic research approach was used. The results are presented as outcome spaces, sets of categories that describe the variation of ways in which the students voiced their understanding of communication in the two case descriptions and showed the qualitatively distinct ways in which the features of communication were experienced. The results offer a base of understanding the students' perspectives on communication that they will take with them into their professional lives. We indicate that there is room for strengthening communication skills in the field of pharmacology, integrating them into programmes of education, by more widely implementing a problem-based, a case-oriented or role-playing pedagogy where final year students work across specialisations and there is a deliberate effort to evoke and assess advanced conceptions and skills.

Design and test of box girder for a large wind turbine blade

Energy Technology Data Exchange (ETDEWEB)

Nielsen, Per H.; Tesauro, A.; Bitsche, R. [Technical Univ. of Denmark. DTU Wind Energy, DTU Risoe Campus, Roskilde (Denmark)] [and others

2012-09-15

This report is covering the structural design and full scale test of a box girder as a part of the project ''Demonstration of new blade design using manufacturing process simulations'' supported by the EUDP program. A box girder with a predetermined outer geometry was designed using new inventions, which create an inner structure in the box girder. With a combination of advanced FEM analysis and the inventions it was possible to reduce the material thickness of the cap by up to 40%. The new design of the box girder was manufactured at SSP Technology A/S, where it was demonstrated that the manufacturing process could include the new inventions. Subsequently the box girder was transported to the blade test facility at DTU Wind Energy. A series of test was performed with the blade to investigate the behaviour during loading, and finally the girder was loaded to ultimate failure. The report includes the description of the test setup, the test and an overview over the results from the test performed on the box girder. During the final test the box girder failed at 58 % of the expected ultimate load. Unfortunately, no definite conclusion could be made concerning the failure mechanism. (Author)

Application of high temperature superconductivity to electric motor design

International Nuclear Information System (INIS)

Edmonds, J.S.; Sharma, D.K.; Jordan, H.E.; Edick, J.D.; Schiferl, R.F.

1992-01-01

This paper reports on progress made in a joint project conducted by the Electric Power Research Institute and Reliance Electric Company to study the possible application of High Temperature Super Conductors (HTSC), materials to electric motors. Specific applications are identified which can be beneficially served by motors constructed with HTSC materials. A summary is presented of the components and design issues related to HTSC motors designed for these applications. During the course of this development program, a three tier HTSC wire performance specification has evolved. The three specifications and the rationale behind these three levels of performance are explained. A description of a test motor that has been constructed to verify the electromagnetic analytical techniques of HTSC motor design is given. Finally, a DC motor with an HTSC field coil is described. Measured data with the motor running is presented showing that the motor is operating with the field winding in the superconducting state

Waste Package Component Design Methodology Report

International Nuclear Information System (INIS)

D.C. Mecham

2004-01-01

This Executive Summary provides an overview of the methodology being used by the Yucca Mountain Project (YMP) to design waste packages and ancillary components. This summary information is intended for readers with general interest, but also provides technical readers a general framework surrounding a variety of technical details provided in the main body of the report. The purpose of this report is to document and ensure appropriate design methods are used in the design of waste packages and ancillary components (the drip shields and emplacement pallets). The methodology includes identification of necessary design inputs, justification of design assumptions, and use of appropriate analysis methods, and computational tools. This design work is subject to ''Quality Assurance Requirements and Description''. The document is primarily intended for internal use and technical guidance for a variety of design activities. It is recognized that a wide audience including project management, the U.S. Department of Energy (DOE), the U.S. Nuclear Regulatory Commission, and others are interested to various levels of detail in the design methods and therefore covers a wide range of topics at varying levels of detail. Due to the preliminary nature of the design, readers can expect to encounter varied levels of detail in the body of the report. It is expected that technical information used as input to design documents will be verified and taken from the latest versions of reference sources given herein. This revision of the methodology report has evolved with changes in the waste package, drip shield, and emplacement pallet designs over many years and may be further revised as the design is finalized. Different components and analyses are at different stages of development. Some parts of the report are detailed, while other less detailed parts are likely to undergo further refinement. The design methodology is intended to provide designs that satisfy the safety and operational

Waste Package Component Design Methodology Report

Energy Technology Data Exchange (ETDEWEB)

D.C. Mecham

2004-07-12

This Executive Summary provides an overview of the methodology being used by the Yucca Mountain Project (YMP) to design waste packages and ancillary components. This summary information is intended for readers with general interest, but also provides technical readers a general framework surrounding a variety of technical details provided in the main body of the report. The purpose of this report is to document and ensure appropriate design methods are used in the design of waste packages and ancillary components (the drip shields and emplacement pallets). The methodology includes identification of necessary design inputs, justification of design assumptions, and use of appropriate analysis methods, and computational tools. This design work is subject to ''Quality Assurance Requirements and Description''. The document is primarily intended for internal use and technical guidance for a variety of design activities. It is recognized that a wide audience including project management, the U.S. Department of Energy (DOE), the U.S. Nuclear Regulatory Commission, and others are interested to various levels of detail in the design methods and therefore covers a wide range of topics at varying levels of detail. Due to the preliminary nature of the design, readers can expect to encounter varied levels of detail in the body of the report. It is expected that technical information used as input to design documents will be verified and taken from the latest versions of reference sources given herein. This revision of the methodology report has evolved with changes in the waste package, drip shield, and emplacement pallet designs over many years and may be further revised as the design is finalized. Different components and analyses are at different stages of development. Some parts of the report are detailed, while other less detailed parts are likely to undergo further refinement. The design methodology is intended to provide designs that satisfy the safety

The introduction of Service Design within Industrial Design Curricula

DEFF Research Database (Denmark)

Maffei, Stefano; Morelli, Nicola; Pacenti, Elena

2005-01-01

This paper describes and reflects upon an emerging phenomena, which is the introduction of service design courses in traditional industrial design schools. Through the description of three examples of educational experiences, the authors stressed the existence of complementary approaches to service...... design that could be integrated for the development of a common methodology and educational platform....

The final management of nuclear fuel. Legal and economic aspects; La gestion final del combustible nuclear. Aspectos legales y economicos

Energy Technology Data Exchange (ETDEWEB)