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Sample records for system description document

  1. 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.

  2. 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

  3. 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.

  4. Waste Management System Description Document (WMSD)

    International Nuclear Information System (INIS)

    1992-02-01

    This report is an appendix of the ''Waste Management Description Project, Revision 1''. This appendix is about the interim approach for the technical baseline of the waste management system. It describes the documentation and regulations of the waste management system requirements and description. (MB)

  5. 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

  6. 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

  7. 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

  8. 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.

  9. 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.

  10. 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

  11. 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

  12. 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)

  13. 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)

  14. 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)

  15. 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

  16. Transportation System Requirements Document

    International Nuclear Information System (INIS)

    1993-09-01

    This Transportation System Requirements Document (Trans-SRD) describes the functions to be performed by and the technical requirements for the Transportation System to transport spent nuclear fuel (SNF) and high-level radioactive waste (HLW) from Purchaser and Producer sites to a Civilian Radioactive Waste Management System (CRWMS) site, and between CRWMS sites. The purpose of this document is to define the system-level requirements for Transportation consistent with the CRWMS Requirement Document (CRD). These requirements include design and operations requirements to the extent they impact on the development of the physical segments of Transportation. The document also presents an overall description of Transportation, its functions, its segments, and the requirements allocated to the segments and the system-level interfaces with Transportation. The interface identification and description are published in the CRWMS Interface Specification

  17. Pairwise Trajectory Management (PTM): Concept Description and Documentation

    Science.gov (United States)

    Jones, Kenneth M.; Graff, Thomas J.; Carreno, Victor; Chartrand, Ryan C.; Kibler, Jennifer L.

    2018-01-01

    Pairwise Trajectory Management (PTM) is an Interval Management (IM) concept that utilizes airborne and ground-based capabilities to enable the implementation of airborne pairwise spacing capabilities in oceanic regions. The goal of PTM is to use airborne surveillance and tools to manage an "at or greater than" inter-aircraft spacing. Due to the accuracy of Automatic Dependent Surveillance-Broadcast (ADS-B) information and the use of airborne spacing guidance, the minimum PTM spacing distance will be less than distances a controller can support with current automation systems that support oceanic operations. Ground tools assist the controller in evaluating the traffic picture and determining appropriate PTM clearances to be issued. Avionics systems provide guidance information that allows the flight crew to conform to the PTM clearance issued by the controller. The combination of a reduced minimum distance and airborne spacing management will increase the capacity and efficiency of aircraft operations at a given altitude or volume of airspace. This document provides an overview of the proposed application, a description of several key scenarios, a high level discussion of expected air and ground equipment and procedure changes, a description of a NASA human-machine interface (HMI) prototype for the flight crew that would support PTM operations, and initial benefits analysis results. Additionally, included as appendices, are the following documents: the PTM Operational Services and Environment Definition (OSED) document and a companion "Future Considerations for the Pairwise Trajectory Management (PTM) Concept: Potential Future Updates for the PTM OSED" paper, a detailed description of the PTM algorithm and PTM Limit Mach rules, initial PTM safety requirements and safety assessment documents, a detailed description of the design, development, and initial evaluations of the proposed flight crew HMI, an overview of the methodology and results of PTM pilot training

  18. IDC System Specification Document.

    Energy Technology Data Exchange (ETDEWEB)

    Clifford, David J.

    2014-12-01

    This document contains the system specifications derived to satisfy the system requirements found in the IDC System Requirements Document for the IDC Reengineering Phase 2 project. Revisions Version Date Author/Team Revision Description Authorized by V1.0 12/2014 IDC Reengineering Project Team Initial delivery M. Harris

  19. 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

  20. 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.

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

    Energy Technology Data Exchange (ETDEWEB)

    LANE, M.P.

    1999-02-24

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

  2. 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

  3. 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.

  4. Waste Management Systems Requirements and Descriptions (SRD)

    International Nuclear Information System (INIS)

    Conner, C.W.

    1986-01-01

    The Department of Energy (DOE), Office of Civilian Radioactive Waste Management (OCRWM) is responsible for the development of a system for the management of high-level radioactive waste and spent fuel in accordance with the Nuclear Waste Policy Act of 1982. The Waste Management system requirements and description document is the program-level technical baseline document. The requirements include the functions that must be performed in order to achieve the system mission and performance criteria for those functions. This document covers only the functional requirements of the system; it does not cover programmatic or procedural requirements pertaining to the processes of designing, siting and licensing. The requirements are largely based on the Nuclear Waste Policy Act of 1982, Environmental Protection Agency standards, Nuclear Regulatory Commission regulations, and DOE orders and guidance. However, nothing in this document should be construed as to relieve the DOE or its contractors from their responsibilities to comply with applicable statutes, regulations, and standards. This document also provides a brief description of the system being developed to meet the requirements. In addition to the described ''authorized system,'' a system description is provided for an ''improved-performance system'' which would include a monitored retrievable storage (MRS) facility. In the event that an MRS facility is approved by Congress, the improved-performance system will become the reference system. Neither system description includes Federal Interim Storage (FIS) capabilities. Should the need for FIS be identified, it will be included as an additional system element. The descriptions are focused on the interfaces between the system elements, rather than on the detail of the system elements themselves

  5. UO3 plant turnover - facility description document

    International Nuclear Information System (INIS)

    Clapp, D.A.

    1995-01-01

    This document was developed to provide a facility description for those portions of the UO 3 Facility being transferred to Bechtel Hanford Company, Inc. (BHI) following completion of facility deactivation. The facility and deactivated state condition description is intended only to serve as an overview of the plant as it is being transferred to BHI

  6. 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

  7. 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.

  8. 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

  9. System Description for the Double Shell Tank (DST) Confinement System

    International Nuclear Information System (INIS)

    ROSSI, H.

    2000-01-01

    This document provides a description of the Double-Shell Tank (DST) Confinement System. This description will provide a basis for developing functional, performance and test requirements (i.e., subsystem specification), as necessary, for the DST Confinement System

  10. System Design Description PFP Thermal Stabilization

    International Nuclear Information System (INIS)

    RISENMAY, H.R.

    2000-01-01

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

  11. 1993 baseline solid waste management system description

    International Nuclear Information System (INIS)

    Armacost, L.L.; Fowler, R.A.; Konynenbelt, H.S.

    1994-02-01

    Pacific Northwest Laboratory has prepared this report under the direction of Westinghouse Hanford Company. The report provides an integrated description of the system planned for managing Hanford's solid low-level waste, low-level mixed waste, transuranic waste, and transuranic mixed waste. The primary purpose of this document is to illustrate a collective view of the key functions planned at the Hanford Site to handle existing waste inventories, as well as solid wastes that will be generated in the future. By viewing this system as a whole rather than as individual projects, key facility interactions and requirements are identified and a better understanding of the overall system may be gained. The system is described so as to form a basis for modeling the system at various levels of detail. Model results provide insight into issues such as facility capacity requirements, alternative system operating strategies, and impacts of system changes (ie., startup dates). This description of the planned Hanford solid waste processing system: defines a baseline system configuration; identifies the entering waste streams to be managed within the system; identifies basic system functions and waste flows; and highlights system constraints. This system description will evolve and be revised as issues are resolved, planning decisions are made, additional data are collected, and assumptions are tested and changed. Out of necessity, this document will also be revised and updated so that a documented system description, which reflects current system planning, is always available for use by engineers and managers. It does not provide any results generated from the many alternatives that will be modeled in the course of analyzing solid waste disposal options; such results will be provided in separate documents

  12. GEODOC: the GRID document file, record structure and data element description

    Energy Technology Data Exchange (ETDEWEB)

    Trippe, T.; White, V.; Henderson, F.; Phillips, S.

    1975-11-06

    The purpose of this report is to describe the information structure of the GEODOC file. GEODOC is a computer based file which contains the descriptive cataloging and indexing information for all documents processed by the National Geothermal Information Resource Group. This file (along with other GRID files) is managed by DBMS, the Berkeley Data Base Management System. Input for the system is prepared using the IRATE Text Editing System with its extended (12 bit) character set, or punched cards.

  13. IDC System Specification Document Version 1.1.

    Energy Technology Data Exchange (ETDEWEB)

    Harris, James M. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Lober, Randall R. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2015-02-01

    This document contains the system specifications derived to satisfy the system requirements found in the IDC System Requirements Document for the IDC Reengineering Phase 2 project. Revisions Version Date Author/Team Revision Description Authorized by V1.0 12/2014 IDC Reengineering Project Team Initial delivery M. Harris V1.1 2/2015 IDC Reengineering Project Team Iteration I2 Review Comments M. Harris

  14. Waste management system requirements document

    International Nuclear Information System (INIS)

    1991-02-01

    This volume defines the top level requirements for the Mined Geologic Disposal System (MGDS). It is designed to be used in conjunction with Volume 1 of the WMSR, General System Requirements. It provides a functional description expanding the requirements allocated to the MGDS in Volume 1 and elaborates on each requirement by providing associated performance criteria as appropriate. Volumes 1 and 4 of the WMSR provide a minimum set of requirements that must be satisfied by the final MGDS design. This document sets forth specific requirements that must be fulfilled. It is not the intent or purpose of this top level document to describe how each requirement is to be satisfied in the final MGDS design. Each subsequent level of the technical document hierarchy must provide further guidance and definition as to how each of these requirements is to be implemented in the design. It is expected that each subsequent level of requirements will be significantly more detailed. Section 2 of this volume provides a functional description of the MGDS. Each function is addressed in terms of requirements, and performance criteria. Section 3 provides a list of controlling documents. Each document cited in a requirement of Chapter 2 is included in this list and is incorporated into this document as a requirement on the final system. The WMSR addresses only federal requirements (i.e., laws, regulations and DOE orders). State and local requirements are not addressed. However, it will be specifically noted at the potentially affected WMSR requirements that there could be additional or more stringent regulations imposed by a state or local requirements or administering agency over the cited federal requirements

  15. Testing System Encryption-Decryption Method to RSA Security Documents

    International Nuclear Information System (INIS)

    Supriyono

    2008-01-01

    A model of document protection which was tested as one of the instruments, especially text document. The principle of the document protection was how the system was able to protect the document storage and transfer processes. Firstly, the text-formed document was encrypted; therefore, the document cannot be read for the text was transformed into random letters. The letter-randomized text was then unfolded by the description in order that the document owner was able to read it. In the recent research, the method adopted was RSA method, in which it used complicated mathematics calculation and equipped with initial protection key (with either private key or public key), thus, it was more difficult to be attacked by hackers. The system was developed by using the software of Borland Delphi 7. The results indicated that the system was capable to save and transfer the document, both via internet and intranet in the form of encrypted letter and put it back to the initial form of document by way of description. The research also tested for encrypted and decrypted process for various memory size documents. (author)

  16. 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.

  17. Description and Documentation of the Dental School Dental Delivery System.

    Science.gov (United States)

    Chase, Rosen and Wallace, Inc., Alexandria, VA.

    A study was undertaken to describe and document the dental school dental delivery system using an integrated systems approach. In late 1976 and early 1977, a team of systems analysts and dental consultants visited three dental schools to observe the delivery of dental services and patient flow and to interview administrative staff and faculty.…

  18. Advanced Transport Operating System (ATOPS) color displays software description microprocessor system

    Science.gov (United States)

    Slominski, Christopher J.; Plyler, Valerie E.; Dickson, Richard W.

    1992-01-01

    This document describes the software created for the Sperry Microprocessor Color Display System used for the Advanced Transport Operating Systems (ATOPS) project on the Transport Systems Research Vehicle (TSRV). The software delivery known as the 'baseline display system', is the one described in this document. Throughout this publication, module descriptions are presented in a standardized format which contains module purpose, calling sequence, detailed description, and global references. The global reference section includes procedures and common variables referenced by a particular module. The system described supports the Research Flight Deck (RFD) of the TSRV. The RFD contains eight cathode ray tubes (CRTs) which depict a Primary Flight Display, Navigation Display, System Warning Display, Takeoff Performance Monitoring System Display, and Engine Display.

  19. 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

  20. 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

  1. 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

  2. System description: Isabelle/jEdit in 2014

    Directory of Open Access Journals (Sweden)

    Makarius Wenzel

    2014-10-01

    Full Text Available This is an updated system description for Isabelle/jEdit, according to the official release Isabelle2014 (August 2014. The following new PIDE concepts are explained: asynchronous print functions and document overlays, syntactic and semantic completion, editor navigation, management of auxiliary files within the document-model.

  3. A document preparation system in a large network environment

    Energy Technology Data Exchange (ETDEWEB)

    Vigil, M.; Bouchier, S.; Sanders, C.; Sydoriak, S.; Wheeler, K.

    1988-01-01

    At Los Alamos National Laboratory, we have developed an integrated document preparation system that produces publication-quality documents. This system combines text formatters and computer graphics capabilities that have been adapted to meet the needs of users in a large scientific research laboratory. This paper describes the integration of document processing technology to develop a system architecture, based on a page description language, to provide network-wide capabilities in a distributed computing environment. We describe the Laboratory requirements, the integration and implementation issues, and the challenges we faced developing this system.

  4. Mined Geologic Disposal System Requirements Document

    International Nuclear Information System (INIS)

    1994-03-01

    This Mined Geologic Disposal System Requirements Document (MGDS-RD) describes the functions to be performed by, and the requirements for, a Mined Geologic Disposal System (MGDS) for the permanent disposal of spent nuclear fuel (SNF) (including SNF loaded in multi-purpose canisters (MPCs)) and commercial and defense high-level radioactive waste (HLW) in support of the Civilian Radioactive Waste Management System (CRWMS). The purpose of the MGDS-RD is to define the program-level requirements for the design of the Repository, the Exploratory Studies Facility (ESF), and Surface Based Testing Facilities (SBTF). These requirements include design, operation, and decommissioning requirements to the extent they impact on the physical development of the MGDS. The document also presents an overall description of the MGDS, its functions (derived using the functional analysis documented by the Physical System Requirements (PSR) documents as a starting point), its segments as described in Section 3.1.3, and the requirements allocated to the segments. In addition, the program-level interfaces of the MGDS are identified. As such, the MGDS-RD provides the technical baseline for the design of the MGDS

  5. Advanced Transport Operating System (ATOPS) color displays software description: MicroVAX system

    Science.gov (United States)

    Slominski, Christopher J.; Plyler, Valerie E.; Dickson, Richard W.

    1992-01-01

    This document describes the software created for the Display MicroVAX computer used for the Advanced Transport Operating Systems (ATOPS) project on the Transport Systems Research Vehicle (TSRV). The software delivery of February 27, 1991, known as the 'baseline display system', is the one described in this document. Throughout this publication, module descriptions are presented in a standardized format which contains module purpose, calling sequence, detailed description, and global references. The global references section includes subroutines, functions, and common variables referenced by a particular module. The system described supports the Research Flight Deck (RFD) of the TSRV. The RFD contains eight Cathode Ray Tubes (CRTs) which depict a Primary Flight Display, Navigation Display, System Warning Display, Takeoff Performance Monitoring System Display, and Engine Display.

  6. Integrated environment, safety, and health management system description

    International Nuclear Information System (INIS)

    Zoghbi, J. G.

    2000-01-01

    The Integrated Environment, Safety, and Health Management System Description that is presented in this document describes the approach and management systems used to address integrated safety management within the Richland Environmental Restoration Project

  7. Transportation system requirements document. Revision 1 DCN01. Supplement

    International Nuclear Information System (INIS)

    1995-05-01

    The original Transportation System Requirements Document described the functions to be performed by and the technical requirements for the Transportation System to transport spent nuclear fuel (SNF) and high-level radioactive waste (HLW) from Purchaser and Producer sites to a Civilian Radioactive Waste Management System (CRWMS) site, and between CRWMS sites. The purpose of that document was to define the system-level requirements. These requirements include design and operations requirements to the extent they impact on the development of the physical segments of Transportation. The document also presented an overall description of Transportation, its functions, its segments, and the requirements allocated to the segments and the system-level interfaces with Transportation. This revision of the document contains only the pages that have been modified

  8. 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

  9. The Ica-Atom using as access platform, dissemination and description of archival documents public institutions

    Directory of Open Access Journals (Sweden)

    Eliseu dos Santos Lima

    2016-12-01

    Full Text Available Introduction: Information technology has caused changes in various segments of society. In archival area its presence is remarkable, so much that lately has increased the quantity of institutions that make use of computerized systems, repositories and platforms that automate activities such as description, diffusion, and even provide access to archival documentary heritage. Objective: To discuss the functionality and usefulness of the platform International Archives Council - Access to Memory (ICA-AtoM in archival description of activities, dissemination and access to archival documentary heritage. Methodology: bibliographical research, drawn from the archival legislation, especially through research resulting from Master's dissertations, articles published in journals of the Science field of Information and manuals produced by members of the Group of CNPq-UFSM Research: Electronic Management of archival documents - Ged / A. Results: It was observed that the platform is used to describe both the permanent documents, and to provide access to information recorded in current and intermediate documents, in order to streamline access to documentary resources of public institutions. Conclusions: It is considered that the ICA-Atom besides serving the description, can provide an authentic environment for the secure storage and as a source of evidence of digital and digitized institutional documents, as well as to provide for preservation and long term access if It is connected to a RDC-Arq, like Archivematica, for example.

  10. 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

  11. Documentation for Grants Equal to Tax model: Volume 1, Technical description

    International Nuclear Information System (INIS)

    1986-01-01

    A computerized model, the Grants Equal to Tax (GETT) model, was developed to assist in evaluating the amount of federal grant monies that would go to state and local jurisdictions under the provisions outlined in the Nuclear Waste Policy Act of 1982. The GETT model is capable of forecasting the amount of tax liability associated with all property owned and all activities undertaken by the US Department of Energy (DOE) in site characterization and repository development. The GETT program is a user-friendly, menu-driven model developed using dBASE III/trademark/, a relational data base management system. The data base for GETT consists primarily of eight separate dBASE III/trademark/ files corresponding to each of the eight taxes levied by state and local jurisdictions on business property and activity. Additional smaller files help to control model inputs and reporting options. Volume 1 of the GETT model documentation is a technical description of the program and its capabilities providing (1) descriptions of the data management system and its procedures; (2) formulas for calculating taxes (illustrated with flow charts); (3) descriptions of tax data base variables for the Deaf Smith County, Texas, Richton Dome, Mississippi, and Davis Canyon, Utah, salt sites; and (4) data inputs for the GETT model. 10 refs., 18 figs., 3 tabs

  12. Integrated Project Management System description

    International Nuclear Information System (INIS)

    1994-09-01

    The Integrated Program Management System (IPMS) Description is a ''working'' document that describes the work processes of the Uranium Mill Tailings Remedial Action Project Office (UMTRA) and IPMS Group. This document has undergone many revisions since the UMTRA Project began; this revision not only updates the work processes but more clearly explains the relationships between the Project Office, contractors, and other participants. The work process flow style has been revised to better describe Project work and the relationships of participants. For each work process, more background and guidance on ''why'' and ''what is expected'' is given. For example, a description of activity data sheets has been added in the work organization and the Project performance and reporting processes, as well as additional detail about the federal budget process and funding management and improved flow charts and explanations of cost and schedule management. A chapter has been added describing the Cost Reduction/Productivity Improvement Program. The Change Control Board (CCB) procedures (Appendix A) have been updated. Project critical issues meeting (PCIM) procedures have been added as Appendix B. Budget risk assessment meeting procedures have been added as Appendix C. These appendices are written to act as stand-alone documentation for each process. As the procedures are improved and updated, the documentation can be updated separately

  13. Conceptual modular description of the high-level waste management system for system studies model development

    International Nuclear Information System (INIS)

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

    1992-08-01

    This document presents modular descriptions of possible alternative components of the federal high-level radioactive waste management system and the procedures for combining these modules to obtain descriptions for alternative configurations of that system. The 20 separate system component modules presented here can be combined to obtain a description of any of the 17 alternative system configurations (i.e., scenarios) that were evaluated in the MRS Systems Studies program (DOE 1989a). First-approximation descriptions of other yet-undefined system configurations could also be developed for system study purposes from this database. The descriptions include, in a modular format, both functional descriptions of the processes in the waste management system, plus physical descriptions of the equipment and facilities necessary for performance of those functions

  14. 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

  15. 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

  16. The OCaml system release 4.04: Documentation and user's manual

    OpenAIRE

    Leroy, Xavier; Doligez, Damien; Frisch, Alain; Garrigue, Jacques; Rémy, Didier; Vouillon, Jérôme

    2016-01-01

    This manual documents the release 4.04 of the OCaml system. It is organized as follows. Part I, "An introduction to OCaml", gives an overview of the language. Part II, "The OCaml language", is the reference description of the language. Part III, "The OCaml tools", documents the compilers, toplevel system, and programming utilities. Part IV, "The OCaml library", describes the modules provided in the standard library.

  17. The OCaml system release 4.02: Documentation and user's manual

    OpenAIRE

    Leroy, Xavier; Doligez, Damien; Frisch, Alain; Garrigue, Jacques; Rémy, Didier; Vouillon, Jérôme

    2014-01-01

    This manual documents the release 4.02 of the OCaml system. It is organized as follows. Part I, "An introduction to OCaml", gives an overview of the language. Part II, "The OCaml language", is the reference description of the language. Part III, "The OCaml tools", documents the compilers, toplevel system, and programming utilities. Part IV, "The OCaml library", describes the modules provided in the standard library.

  18. The OCaml system release 4.06: Documentation and user's manual

    OpenAIRE

    Leroy , Xavier; Doligez , Damien; Frisch , Alain; Garrigue , Jacques; Rémy , Didier; Vouillon , Jérôme

    2017-01-01

    This manual documents the release 4.06 of the OCaml system. It is organized as follows. Part I, "An introduction to OCaml", gives an overview of the language. Part II, "The OCaml language", is the reference description of the language. Part III, "The OCaml tools", documents the compilers, toplevel system, and programming utilities. Part IV, "The OCaml library", describes the modules provided in the standard library.

  19. Ways to integrate document management systems with industrial plant configuration management systems

    International Nuclear Information System (INIS)

    Munoz, M.

    1995-01-01

    Based on experience gained from tasks carried out for Almaraz Nuclear Power Plant, this paper describes computer platforms used both at the power plant and in the main offices of the engineering company. Subsequently, a description is given of the procedure followed for the continuous up-dating of plant documentation, in order to maintain consistency with other information stored in data bases in the Operation Management System, Maintenance System, Modification Management System, etc. The work method used for the unitary updating of all information (document images and attributes corresponding to the different data bases), following refuelling procedures is also described. Lastly, the paper describes the functions and the user interface of the system used in the power plant for document management. (Author)

  20. System design description PFP thermal stabilization

    International Nuclear Information System (INIS)

    RISENMAY, H.R.

    1998-01-01

    The purpose of this document is to provide a system design description and design basis for the Plutonium Finishing P1ant (PFP) Thermal Stabilization project. The sources of material for this project are residues scraped from glovebox floors and materials already stored in vault storage that need further stabilizing to meet the 3013 storage requirements. Stabilizing this material will promote long term storage and reduced worker exposure. This document addresses: function design, equipment, and safety requirements for thermal stabilization of plutonium residues and oxides

  1. Electric energy supply systems: description of available technologies

    Energy Technology Data Exchange (ETDEWEB)

    Eisenhauer, J.L.; Rogers, E.A.; King, J.C.; Stegen, G.E.; Dowis, W.J.

    1985-02-01

    When comparing coal transportation with electric transmission as a means of delivering electric power, it is desirable to compare entire energy systems rather than just the transportation/transmission components because the requirements of each option may affect the requirements of other energy system components. PNL's assessment consists of two parts. The first part, which is the subject of this document, is a detailed description of the technical, cost, resource and environmental characteristics of each system component and technologies available for these components. The second part is a computer-based model that PNL has developed to simulate construction and operation of alternative system configurations and to compare the performance of these systems under a variety of economic and technical conditions. This document consists of six chapters and two appendices. A more thorough description of coal-based electric energy systems is presented in the Introduction and Chapter 1. Each of the subsequent chapters describes technologies for five system components: Western coal resources (Chapter 2), coal transportation (Chapter 3), coal gasification and gas transmission (Chapter 4), and electric power transmission (Chapter 6).

  2. 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

  3. Subsurface Ventilation System Description Document

    Energy Technology Data Exchange (ETDEWEB)

    Eric Loros

    2001-07-25

    The Subsurface Ventilation System supports the construction and operation of the subsurface repository by providing air for personnel and equipment and temperature control for the underground areas. Although the system is located underground, some equipment and features may be housed or located above ground. The system ventilates the underground by providing ambient air from the surface throughout the subsurface development and emplacement areas. The system provides fresh air for a safe work environment and supports potential retrieval operations by ventilating and cooling emplacement drifts. The system maintains compliance within the limits established for approved air quality standards. The system maintains separate ventilation between the development and waste emplacement areas. The system shall remove a portion of the heat generated by the waste packages during preclosure to support thermal goals. The system provides temperature control by reducing drift temperature to support potential retrieval operations. The ventilation system has the capability to ventilate selected drifts during emplacement and retrieval operations. The Subsurface Facility System is the main interface with the Subsurface Ventilation System. The location of the ducting, seals, filters, fans, emplacement doors, regulators, and electronic controls are within the envelope created by the Ground Control System in the Subsurface Facility System. The Subsurface Ventilation System also interfaces with the Subsurface Electrical System for power, the Monitored Geologic Repository Operations Monitoring and Control System to ensure proper and safe operation, the Safeguards and Security System for access to the emplacement drifts, the Subsurface Fire Protection System for fire safety, the Emplacement Drift System for repository performance, and the Backfill Emplacement and Subsurface Excavation Systems to support ventilation needs.

  4. Subsurface Ventilation System Description Document

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-10-12

    The Subsurface Ventilation System supports the construction and operation of the subsurface repository by providing air for personnel and equipment and temperature control for the underground areas. Although the system is located underground, some equipment and features may be housed or located above ground. The system ventilates the underground by providing ambient air from the surface throughout the subsurface development and emplacement areas. The system provides fresh air for a safe work environment and supports potential retrieval operations by ventilating and cooling emplacement drifts. The system maintains compliance within the limits established for approved air quality standards. The system maintains separate ventilation between the development and waste emplacement areas. The system shall remove a portion of the heat generated by the waste packages during preclosure to support thermal goals. The system provides temperature control by reducing drift temperature to support potential retrieval operations. The ventilation system has the capability to ventilate selected drifts during emplacement and retrieval operations. The Subsurface Facility System is the main interface with the Subsurface Ventilation System. The location of the ducting, seals, filters, fans, emplacement doors, regulators, and electronic controls are within the envelope created by the Ground Control System in the Subsurface Facility System. The Subsurface Ventilation System also interfaces with the Subsurface Electrical System for power, the Monitored Geologic Repository Operations Monitoring and Control System to ensure proper and safe operation, the Safeguards and Security System for access to the emplacement drifts, the Subsurface Fire Protection System for fire safety, the Emplacement Drift System for repository performance, and the Backfill Emplacement and Subsurface Excavation Systems to support ventilation needs.

  5. CANISTER TRANSFER SYSTEM DESCRIPTION DOCUMENT

    International Nuclear Information System (INIS)

    B. Gorpani

    2000-01-01

    The Canister Transfer System receives transportation casks containing large and small disposable canisters, unloads the canisters from the casks, stores the canisters as required, loads them into disposal containers (DCs), and prepares the empty casks for re-shipment. Cask unloading begins with cask inspection, sampling, and lid bolt removal operations. The cask lids are removed and the canisters are unloaded. Small canisters are loaded directly into a DC, or are stored until enough canisters are available to fill a DC. Large canisters are loaded directly into a DC. Transportation casks and related components are decontaminated as required, and empty casks are prepared for re-shipment. One independent, remotely operated canister transfer line is provided in the Waste Handling Building System. The canister transfer line consists of a Cask Transport System, Cask Preparation System, Canister Handling System, Disposal Container Transport System, an off-normal canister handling cell with a transfer tunnel connecting the two cells, and Control and Tracking System. The Canister Transfer System operating sequence begins with moving transportation casks to the cask preparation area with the Cask Transport System. The Cask Preparation System prepares the cask for unloading and consists of cask preparation manipulator, cask inspection and sampling equipment, and decontamination equipment. The Canister Handling System unloads the canister(s) and places them into a DC. Handling equipment consists of a bridge crane hoist,; DC--loading manipulator, lifting fixtures, and small canister staging racks. Once the cask has been unloaded, the Cask Preparation System decontaminates the cask exterior and returns it to the Carrier/Cask Handling System via the Cask Transport System. After the; DC--is fully loaded, the Disposal Container Transport System moves the; DC--to the Disposal Container Handling System for welding. To handle off-normal canisters, a separate off-normal canister

  6. Canister Transfer System Description Document

    International Nuclear Information System (INIS)

    2000-01-01

    The Canister Transfer System receives transportation casks containing large and small disposable canisters, unloads the canisters from the casks, stores the canisters as required, loads them into disposal containers (DCs), and prepares the empty casks for re-shipment. Cask unloading begins with cask inspection, sampling, and lid bolt removal operations. The cask lids are removed and the canisters are unloaded. Small canisters are loaded directly into a DC, or are stored until enough canisters are available to fill a DC. Large canisters are loaded directly into a DC. Transportation casks and related components are decontaminated as required, and empty casks are prepared for re-shipment. One independent, remotely operated canister transfer line is provided in the Waste Handling Building System. The canister transfer line consists of a Cask Transport System, Cask Preparation System, Canister Handling System, Disposal Container Transport System, an off-normal canister handling cell with a transfer tunnel connecting the two cells, and Control and Tracking System. The Canister Transfer System operating sequence begins with moving transportation casks to the cask preparation area with the Cask Transport System. The Cask Preparation System prepares the cask for unloading and consists of cask preparation manipulator, cask inspection and sampling equipment, and decontamination equipment. The Canister Handling System unloads the canister(s) and places them into a DC. Handling equipment consists of a bridge crane/hoist, DC loading manipulator, lifting fixtures, and small canister staging racks. Once the cask has been unloaded, the Cask Preparation System decontaminates the cask exterior and returns it to the Carrier/Cask Handling System via the Cask Transport System. After the DC is fully loaded, the Disposal Container Transport System moves the DC to the Disposal Container Handling System for welding. To handle off-normal canisters, a separate off-normal canister handling

  7. Ground Control System Description Document

    International Nuclear Information System (INIS)

    Eric Loros

    2001-01-01

    The Ground Control System contributes to the safe construction and operation of the subsurface facility, including accesses and waste emplacement drifts, by maintaining the configuration and stability of the openings during construction, development, emplacement, and caretaker modes for the duration of preclosure repository life. The Ground Control System consists of ground support structures installed within the subsurface excavated openings, any reinforcement made to the rock surrounding the opening, and inverts if designed as an integral part of the system. The Ground Control System maintains stability for the range of geologic conditions expected at the repository and for all expected loading conditions, including in situ rock, construction, operation, thermal, and seismic loads. The system maintains the size and geometry of operating envelopes for all openings, including alcoves, accesses, and emplacement drifts. The system provides for the installation and operation of sensors and equipment for any required inspection and monitoring. In addition, the Ground Control System provides protection against rockfall for all subsurface personnel, equipment, and the engineered barrier system, including the waste package during the preclosure period. The Ground Control System uses materials that are sufficiently maintainable and that retain the necessary engineering properties for the anticipated conditions of the preclosure service life. These materials are also compatible with postclosure waste isolation performance requirements of the repository. The Ground Control System interfaces with the Subsurface Facility System for operating envelopes, drift orientation, and excavated opening dimensions, Emplacement Drift System for material compatibility, Monitored Geologic Repository Operations Monitoring and Control System for ground control instrument readings, Waste Emplacement/Retrieval System to support waste emplacement operations, and the Subsurface Excavation System

  8. ASSEMBLY TRANSFER SYSTEM DESCRIPTION DOCUMENT

    International Nuclear Information System (INIS)

    Gorpani, B.

    2000-01-01

    The Assembly Transfer System (ATS) receives, cools, and opens rail and truck transportation casks from the Carrier/Cask Handling System (CCHS). The system unloads transportation casks consisting of bare Spent Nuclear Fuel (SNF) assemblies, single element canisters, and Dual Purpose Canisters (DPCs). For casks containing DPCs, the system opens the DPCs and unloads the SNF. The system stages the assemblies, transfer assemblies to and from fuel-blending inventory pools, loads them into Disposal Containers (DCs), temporarily seals and inerts the DC, decontaminates the DC and transfers it to the Disposal Container Handling System. The system also prepares empty casks and DPCs for off-site shipment. Two identical Assembly Transfer System lines are provided in the Waste Handling Building (WHB). Each line operates independently to handle the waste transfer throughput and to support maintenance operations. Each system line primarily consists of wet and dry handling areas. The wet handling area includes a cask transport system, cask and DPC preparation system, and a wet assembly handling system. The basket transport system forms the transition between the wet and dry handling areas. The dry handling area includes the dry assembly handling system, assembly drying system, DC preparation system, and DC transport system. Both the wet and dry handling areas are controlled by the control and tracking system. The system operating sequence begins with moving transportation casks to the cask preparation area. The cask preparation operations consist of cask cavity gas sampling, cask venting, cask cool-down, outer lid removal, and inner shield plug lifting fixture attachment. Casks containing bare SNF (no DPC) are filled with water and placed in the cask unloading pool. The inner shield plugs are removed underwater. For casks containing a DPC, the cask lid(s) is removed, and the DPC is penetrated, sampled, vented, and cooled. A DPC lifting fixture is attached and the cask is placed

  9. 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

  10. Subsurface Facility System Description Document

    International Nuclear Information System (INIS)

    Eric Loros

    2001-01-01

    The Subsurface Facility System encompasses the location, arrangement, size, and spacing of the underground openings. This subsurface system includes accesses, alcoves, and drifts. This system provides access to the underground, provides for the emplacement of waste packages, provides openings to allow safe and secure work conditions, and interfaces with the natural barrier. This system includes what is now the Exploratory Studies Facility. The Subsurface Facility System physical location and general arrangement help support the long-term waste isolation objectives of the repository. The Subsurface Facility System locates the repository openings away from main traces of major faults, away from exposure to erosion, above the probable maximum flood elevation, and above the water table. The general arrangement, size, and spacing of the emplacement drifts support disposal of the entire inventory of waste packages based on the emplacement strategy. The Subsurface Facility System provides access ramps to safely facilitate development and emplacement operations. The Subsurface Facility System supports the development and emplacement operations by providing subsurface space for such systems as ventilation, utilities, safety, monitoring, and transportation

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

    International Nuclear Information System (INIS)

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

    1998-05-01

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

  12. Description of surface systems. Preliminary site description Simpevarp sub area - Version 1.2

    Energy Technology Data Exchange (ETDEWEB)

    Lindborg, Tobias [ed.

    2005-03-01

    Swedish Nuclear Fuel and Waste Management Co is currently conducting site characterisation in the Simpevarp area. The area is divided into two subareas, the Simpevarp and the Laxemar subarea. The two subareas are surrounded by a common regional model area, the Simpevarp area. This report describes both the regional area and the subareas. This report is an interim version (model version 1.2) of the description of the surface systems at the Simpevarp area, and should be seen as a background report to the site description of the Simpevarp area, version 1.2, SKB-R--05-08. The basis for this description is quality-assured field data available in the SKB SICADA and GIS databases, together with generic data from the literature. The Surface system, here defined as everything above the bedrock, comprises a number of separate disciplines (e.g. hydrology, geology, topography, oceanography and ecology). Each discipline has developed descriptions and models for a number of properties that together represent the site description. The current methodology for developing the surface system description and the integration to ecosystem models is documented in a methodology strategy report SKB-R--03-06. The procedures and guidelines given in that report were followed in this report. Compared with version 1.1 of the surface system description SKB-R--04-25, this report presents considerable additional features, especially in the ecosystem description (Chapter 4) and in the description of the surface hydrology (Section 3.4). A first attempt has also been made to connect the flow of matter (carbon) between the different ecosystems into an overall ecosystem model at a landscape level. A summarised version of this report is also presented in SKB-R--05-08 together with geological-, hydrogeological-, transport properties-, thermal properties-, rock mechanics- and hydrogeochemical descriptions.

  13. Description of surface systems. Preliminary site description Simpevarp sub area - Version 1.2

    International Nuclear Information System (INIS)

    Lindborg, Tobias

    2005-03-01

    Swedish Nuclear Fuel and Waste Management Co is currently conducting site characterisation in the Simpevarp area. The area is divided into two subareas, the Simpevarp and the Laxemar subarea. The two subareas are surrounded by a common regional model area, the Simpevarp area. This report describes both the regional area and the subareas. This report is an interim version (model version 1.2) of the description of the surface systems at the Simpevarp area, and should be seen as a background report to the site description of the Simpevarp area, version 1.2, SKB-R--05-08. The basis for this description is quality-assured field data available in the SKB SICADA and GIS databases, together with generic data from the literature. The Surface system, here defined as everything above the bedrock, comprises a number of separate disciplines (e.g. hydrology, geology, topography, oceanography and ecology). Each discipline has developed descriptions and models for a number of properties that together represent the site description. The current methodology for developing the surface system description and the integration to ecosystem models is documented in a methodology strategy report SKB-R--03-06. The procedures and guidelines given in that report were followed in this report. Compared with version 1.1 of the surface system description SKB-R--04-25, this report presents considerable additional features, especially in the ecosystem description (Chapter 4) and in the description of the surface hydrology (Section 3.4). A first attempt has also been made to connect the flow of matter (carbon) between the different ecosystems into an overall ecosystem model at a landscape level. A summarised version of this report is also presented in SKB-R--05-08 together with geological-, hydrogeological-, transport properties-, thermal properties-, rock mechanics- and hydrogeochemical descriptions

  14. System Description for Tank 241-AZ-101 Waste Retrieval Data Acquisition System

    International Nuclear Information System (INIS)

    ROMERO, S.G.

    2000-01-01

    The proposed activity provides the description of the Data Acquisition System for Tank 241-AZ-101. This description is documented in HNF-5572, Tank 241-AZ-101 Waste Retrieval Data Acquisition System (DAS). This activity supports the planned mixer pump tests for Tank 241-AZ-101. Tank 241-AZ-101 has been selected for the first full-scale demonstration of a mixer pump system. The tank currently holds over 960,000 gallons of neutralized current acid waste, including approximately 12.7 inches of settling solids (sludge) at the bottom of the tank. As described in Addendum 4 of the FSAR (LMHC 2000a), two 300 HP mixer pumps with associated measurement and monitoring equipment have been installed in Tank 241-AZ-101. The purpose of the Tank 241-AZ-101 retrieval system Data Acquisition System (DAS) is to provide monitoring and data acquisition of key parameters in order to confirm the effectiveness of the mixer pumps utilized for suspending solids in the tank. The suspension of solids in Tank 241-AZ-101 is necessary for pretreatment of the neutralized current acid waste and eventual disposal as glass via the Hanford Waste Vitrification Plant. HNF-5572 provides a basic description of the Tank 241-AZ-101 retrieval system DAS, including the field instrumentation and application software. The DAS is provided to fulfill requirements for data collection and monitoring. This document is not an operations procedure or is it intended to describe the mixing operation. This USQ screening provides evaluation of HNF-5572 (Revision 1) including the changes as documented on ECN 654001. The changes include (1) add information on historical trending and data backup, (2) modify DAS I/O list in Appendix E to reflect actual conditions in the field, and (3) delete IP address in Appendix F per Lockheed Martin Services, Inc. request

  15. Description and Methods of the Automated Document Management System Usage in Scientific Organizational Activities of the Joint Institute for Nuclear Research (ADS SOA JINR)

    CERN Document Server

    Borisovsky, V F; Kekelidze, M G; Nikonov, E G; Senchenko, V A

    2005-01-01

    This paper presents the structure description and user guide for Information program system for automation of a document flow for support of scientific arrangement planning (ADS SOA) which can be used for planning and carrying out seminars, workshops, conferences and other arrangements of research management. This work is intended for automation of scientific research management in the Joint Institute for Nuclear Research. The complex of programs represents the CDS Agenda system used in the European Organization for Nuclear Research (CERN), which is adapted to the conditions of JINR.

  16. Monitored Retrievable Storage System Requirements Document

    International Nuclear Information System (INIS)

    1994-03-01

    This Monitored Retrievable Storage System Requirements Document (MRS-SRD) describes the functions to be performed and technical requirements for a Monitored Retrievable Storage (MRS) facility subelement and the On-Site Transfer and Storage (OSTS) subelement. The MRS facility subelement provides for temporary storage, at a Civilian Radioactive Waste Management System (CRWMS) operated site, of spent nuclear fuel (SNF) contained in an NRC-approved Multi-Purpose Canister (MPC) storage mode, or other NRC-approved storage modes. The OSTS subelement provides for transfer and storage, at Purchaser sites, of spent nuclear fuel (SNF) contained in MPCs. Both the MRS facility subelement and the OSTS subelement are in support of the CRWMS. The purpose of the MRS-SRD is to define the top-level requirements for the development of the MRS facility and the OSTS. These requirements include design, operation, and decommissioning requirements to the extent they impact on the physical development of the MRS facility and the OSTS. The document also presents an overall description of the MRS facility and the OSTS, their functions (derived by extending the functional analysis documented by the Physical System Requirements (PSR) Store Waste Document), their segments, and the requirements allocated to the segments. In addition, the top-level interface requirements of the MRS facility and the OSTS are included. As such, the MRS-SRD provides the technical baseline for the MRS Safety Analysis Report (SAR) design and the OSTS Safety Analysis Report design

  17. Executive overview and introduction to the SMAP information system life-cycle and documentation standards

    Science.gov (United States)

    1989-01-01

    An overview of the five volume set of Information System Life-Cycle and Documentation Standards is provided with information on its use. The overview covers description, objectives, key definitions, structure and application of the standards, and document structure decisions. These standards were created to provide consistent NASA-wide structures for coordinating, controlling, and documenting the engineering of an information system (hardware, software, and operational procedures components) phase by phase.

  18. WASTE TREATMENT BUILDING SYSTEM DESCRIPTION DOCUMENT

    Energy Technology Data Exchange (ETDEWEB)

    F. Habashi

    2000-06-22

    The Waste Treatment Building System provides the space, layout, structures, and embedded subsystems that support the processing of low-level liquid and solid radioactive waste generated within the Monitored Geologic Repository (MGR). The activities conducted in the Waste Treatment Building include sorting, volume reduction, and packaging of dry waste, and collecting, processing, solidification, and packaging of liquid waste. The Waste Treatment Building System is located on the surface within the protected area of the MGR. The Waste Treatment Building System helps maintain a suitable environment for the waste processing and protects the systems within the Waste Treatment Building (WTB) from most of the natural and induced environments. The WTB also confines contaminants and provides radiological protection to personnel. In addition to the waste processing operations, the Waste Treatment Building System provides space and layout for staging of packaged waste for shipment, industrial and radiological safety systems, control and monitoring of operations, safeguards and security systems, and fire protection, ventilation and utilities systems. The Waste Treatment Building System also provides the required space and layout for maintenance activities, tool storage, and administrative facilities. The Waste Treatment Building System integrates waste processing systems within its protective structure to support the throughput rates established for the MGR. The Waste Treatment Building System also provides shielding, layout, and other design features to help limit personnel radiation exposures to levels which are as low as is reasonably achievable (ALARA). The Waste Treatment Building System interfaces with the Site Generated Radiological Waste Handling System, and with other MGR systems that support the waste processing operations. The Waste Treatment Building System interfaces with the General Site Transportation System, Site Communications System, Site Water System, MGR

  19. WASTE TREATMENT BUILDING SYSTEM DESCRIPTION DOCUMENT

    International Nuclear Information System (INIS)

    Habashi, F.

    2000-01-01

    The Waste Treatment Building System provides the space, layout, structures, and embedded subsystems that support the processing of low-level liquid and solid radioactive waste generated within the Monitored Geologic Repository (MGR). The activities conducted in the Waste Treatment Building include sorting, volume reduction, and packaging of dry waste, and collecting, processing, solidification, and packaging of liquid waste. The Waste Treatment Building System is located on the surface within the protected area of the MGR. The Waste Treatment Building System helps maintain a suitable environment for the waste processing and protects the systems within the Waste Treatment Building (WTB) from most of the natural and induced environments. The WTB also confines contaminants and provides radiological protection to personnel. In addition to the waste processing operations, the Waste Treatment Building System provides space and layout for staging of packaged waste for shipment, industrial and radiological safety systems, control and monitoring of operations, safeguards and security systems, and fire protection, ventilation and utilities systems. The Waste Treatment Building System also provides the required space and layout for maintenance activities, tool storage, and administrative facilities. The Waste Treatment Building System integrates waste processing systems within its protective structure to support the throughput rates established for the MGR. The Waste Treatment Building System also provides shielding, layout, and other design features to help limit personnel radiation exposures to levels which are as low as is reasonably achievable (ALARA). The Waste Treatment Building System interfaces with the Site Generated Radiological Waste Handling System, and with other MGR systems that support the waste processing operations. The Waste Treatment Building System interfaces with the General Site Transportation System, Site Communications System, Site Water System, MGR

  20. Reactive documentation system

    Science.gov (United States)

    Boehnlein, Thomas R.; Kramb, Victoria

    2018-04-01

    Proper formal documentation of computer acquired NDE experimental data generated during research is critical to the longevity and usefulness of the data. Without documentation describing how and why the data was acquired, NDE research teams lose capability such as their ability to generate new information from previously collected data or provide adequate information so that their work can be replicated by others seeking to validate their research. Despite the critical nature of this issue, NDE data is still being generated in research labs without appropriate documentation. By generating documentation in series with data, equal priority is given to both activities during the research process. One way to achieve this is to use a reactive documentation system (RDS). RDS prompts an operator to document the data as it is generated rather than relying on the operator to decide when and what to document. This paper discusses how such a system can be implemented in a dynamic environment made up of in-house and third party NDE data acquisition systems without creating additional burden on the operator. The reactive documentation approach presented here is agnostic enough that the principles can be applied to any operator controlled, computer based, data acquisition system.

  1. A documentation system for decommissioning of nuclear power plants

    International Nuclear Information System (INIS)

    Glock, H.J.; Mueller, F.; Schwarz, H.

    1984-01-01

    A NPP's life cycle from the beginning of planning to its complete dismantling will last about 80 to 100 years. For this long time a documentation system has to be kept in stable working condition which provides access to an information base including 1.5 to 2 million pages and 200 to 250 thousand engineering drawings. As an appropriate base the documentation system IFODOK is proposed which is supported by computer and data base management software. In cooperation with NPP operating people a ground level thesaurus has been developed which is structured according to the rules of INFODOK's documentation language. The form of the information units which INFODOK maintains has been adapted to the requirements of KKW documentation and the related data record is described. Within a layer model the requirements to the software resulting from the demanded performance of the system are explained. The model also describes the interfaces between the substantial system components (application programs, data base management system, operating system) as well as within the different layers. The requirements which the system's hardware has to meet are described functionally and quantitatively in details. The application program' components have been extended by some functions. An automatic microfilm storage and retrieval system which may be integrated to the overall system and coupled to the computer by an interface is specified. The organization of the computer assisted documentation process including the required backup and refreshment procedures is described in its basic characteristics. This description of an DP system's prototype presents the base for the application of INFODOK to the documentation of NPP's information bases during their whole life time

  2. 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

  3. World Energy Projection System model documentation

    International Nuclear Information System (INIS)

    Hutzler, M.J.; Anderson, A.T.

    1997-09-01

    The World Energy Projection System (WEPS) was developed by the Office of Integrated Analysis and Forecasting within the Energy Information Administration (EIA), the independent statistical and analytical agency of the US Department of Energy. WEPS is an integrated set of personal computer based spreadsheets containing data compilations, assumption specifications, descriptive analysis procedures, and projection models. The WEPS accounting framework incorporates projections from independently documented models and assumptions about the future energy intensity of economic activity (ratios of total energy consumption divided by gross domestic product GDP), and about the rate of incremental energy requirements met by natural gas, coal, and renewable energy sources (hydroelectricity, geothermal, solar, wind, biomass, and other renewable resources). Projections produced by WEPS are published in the annual report, International Energy Outlook. This report documents the structure and procedures incorporated in the 1998 version of the WEPS model. It has been written to provide an overview of the structure of the system and technical details about the operation of each component of the model for persons who wish to know how WEPS projections are produced by EIA

  4. World Energy Projection System model documentation

    Energy Technology Data Exchange (ETDEWEB)

    Hutzler, M.J.; Anderson, A.T.

    1997-09-01

    The World Energy Projection System (WEPS) was developed by the Office of Integrated Analysis and Forecasting within the Energy Information Administration (EIA), the independent statistical and analytical agency of the US Department of Energy. WEPS is an integrated set of personal computer based spreadsheets containing data compilations, assumption specifications, descriptive analysis procedures, and projection models. The WEPS accounting framework incorporates projections from independently documented models and assumptions about the future energy intensity of economic activity (ratios of total energy consumption divided by gross domestic product GDP), and about the rate of incremental energy requirements met by natural gas, coal, and renewable energy sources (hydroelectricity, geothermal, solar, wind, biomass, and other renewable resources). Projections produced by WEPS are published in the annual report, International Energy Outlook. This report documents the structure and procedures incorporated in the 1998 version of the WEPS model. It has been written to provide an overview of the structure of the system and technical details about the operation of each component of the model for persons who wish to know how WEPS projections are produced by EIA.

  5. DISPOSAL CONTAINER HANDLING SYSTEM DESCRIPTION DOCUMENT

    Energy Technology Data Exchange (ETDEWEB)

    E. F. Loros

    2000-06-30

    The Disposal Container Handling System receives and prepares new disposal containers (DCs) and transfers them to the Assembly Transfer System (ATS) or Canister Transfer System (CTS) for loading. The system receives the loaded DCs from ATS or CTS and welds the lids. When the welds are accepted the DCs are termed waste packages (WPs). The system may stage the WP for later transfer or transfer the WP directly to the Waste Emplacement/Retrieval System. The system can also transfer DCs/WPs to/from the Waste Package Remediation System. The Disposal Container Handling System begins with new DC preparation, which includes installing collars, tilting the DC upright, and outfitting the container for the specific fuel it is to receive. DCs and their lids are staged in the receipt area for transfer to the needed location. When called for, a DC is put on a cart and sent through an airlock into a hot cell. From this point on, all processes are done remotely. The DC transfer operation moves the DC to the ATS or CTS for loading and then receives the DC for welding. The DC welding operation receives loaded DCs directly from the waste handling lines or from interim lag storage for welding of the lids. The welding operation includes mounting the DC on a turntable, removing lid seals, and installing and welding the inner and outer lids. After the weld process and non-destructive examination are successfully completed, the WP is either staged or transferred to a tilting station. At the tilting station, the WP is tilted horizontally onto a cart and the collars removed. The cart is taken through an air lock where the WP is lifted, surveyed, decontaminated if required, and then moved into the Waste Emplacement/Retrieval System. DCs that do not meet the welding non-destructive examination criteria are transferred to the Waste Package Remediation System for weld preparation or removal of the lids. The Disposal Container Handling System is contained within the Waste Handling Building System

  6. Engineer/constructor description of work for Tank 241-SY-102 retrieval system, project W-211, initial tank retrieval systems

    International Nuclear Information System (INIS)

    Rieck, C.A.

    1996-02-01

    This document provides a description of work for the design and construction of a waste retrieval system for Tank 241-SY-102. The description of work includes a working estimate and schedule, as well as a narrative description and sketches of the waste retrieval system. The working estimate and schedule are within the established baselines for the Tank 241-SY-102 retrieval system. The technical baseline is provided in Functional Design Criteria, WHC-SD-W211-FDC-001, Revision 2

  7. Hot Spot Removal System: System description

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-09-01

    Hazardous wastes contaminated with radionuclides, chemicals, and explosives exist across the Department of Energy complex and need to be remediated due to environmental concerns. Currently, an opportunity is being developed to dramatically reduce remediation costs and to assist in the acceleration of schedules associated with these wastes by deploying a Hot Spot Removal System. Removing the hot spot from the waste site will remove risk driver(s) and enable another, more cost effective process/option/remedial alternative (i.e., capping) to be applied to the remainder of the site. The Hot Spot Removal System consists of a suite of technologies that will be utilized to locate and remove source terms. Components of the system can also be used in a variety of other cleanup activities. This Hot Spot Removal System Description document presents technologies that were considered for possible inclusion in the Hot Spot Removal System, technologies made available to the Hot Spot Removal System, industrial interest in the Hot Spot Removal System`s subsystems, the schedule required for the Hot Spot Removal System, the evaluation of the relevant technologies, and the recommendations for equipment and technologies as stated in the Plan section.

  8. Hot Spot Removal System: System description

    International Nuclear Information System (INIS)

    1997-09-01

    Hazardous wastes contaminated with radionuclides, chemicals, and explosives exist across the Department of Energy complex and need to be remediated due to environmental concerns. Currently, an opportunity is being developed to dramatically reduce remediation costs and to assist in the acceleration of schedules associated with these wastes by deploying a Hot Spot Removal System. Removing the hot spot from the waste site will remove risk driver(s) and enable another, more cost effective process/option/remedial alternative (i.e., capping) to be applied to the remainder of the site. The Hot Spot Removal System consists of a suite of technologies that will be utilized to locate and remove source terms. Components of the system can also be used in a variety of other cleanup activities. This Hot Spot Removal System Description document presents technologies that were considered for possible inclusion in the Hot Spot Removal System, technologies made available to the Hot Spot Removal System, industrial interest in the Hot Spot Removal System''s subsystems, the schedule required for the Hot Spot Removal System, the evaluation of the relevant technologies, and the recommendations for equipment and technologies as stated in the Plan section

  9. Earth System Documentation (ES-DOC) Preparation for CMIP6

    Science.gov (United States)

    Denvil, S.; Murphy, S.; Greenslade, M. A.; Lawrence, B.; Guilyardi, E.; Pascoe, C.; Treshanksy, A.; Elkington, M.; Hibling, E.; Hassell, D.

    2015-12-01

    During the course of 2015 the Earth System Documentation (ES-DOC) project began its preparations for CMIP6 (Coupled Model Inter-comparison Project 6) by further extending the ES-DOC tooling ecosystem in support of Earth System Model (ESM) documentation creation, search, viewing & comparison. The ES-DOC online questionnaire, the ES-DOC desktop notebook, and the ES-DOC python toolkit will serve as multiple complementary pathways to generating CMIP6 documentation. It is envisaged that institutes will leverage these tools at different points of the CMIP6 lifecycle. Institutes will be particularly interested to know that the documentation burden will be either streamlined or completely automated.As all the tools are tightly integrated with the ES-DOC web-service, institutes can be confident that the latency between documentation creation & publishing will be reduced to a minimum. Published documents will be viewable with the online ES-DOC Viewer (accessible via citable URL's). Model inter-comparison scenarios will be supported using the ES-DOC online Comparator tool. The Comparator is being extended to:• Support comparison of both Model descriptions & Simulation runs;• Greatly streamline the effort involved in compiling official tables.The entire ES-DOC ecosystem is open source and built upon open standards such as the Common Information Model (CIM) (versions 1 and 2).

  10. Document Level Assessment of Document Retrieval Systems in a Pairwise System Evaluation

    Science.gov (United States)

    Rajagopal, Prabha; Ravana, Sri Devi

    2017-01-01

    Introduction: The use of averaged topic-level scores can result in the loss of valuable data and can cause misinterpretation of the effectiveness of system performance. This study aims to use the scores of each document to evaluate document retrieval systems in a pairwise system evaluation. Method: The chosen evaluation metrics are document-level…

  11. Management plan documentation standard and Data Item Descriptions (DID). Volume of the information system life-cycle and documentation standards, volume 2

    Science.gov (United States)

    Callender, E. David; Steinbacher, Jody

    1989-01-01

    This is the second of five volumes of the Information System Life-Cycle and Documentation Standards. This volume provides a well-organized, easily used standard for management plans used in acquiring, assuring, and developing information systems and software, hardware, and operational procedures components, and related processes.

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2010-08-01

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

  13. Extended Subject Access to Hypertext Online Documentation. Part III: The Document-Boundaries Problem.

    Science.gov (United States)

    Girill, T. R.

    1991-01-01

    This article continues the description of DFT (Document, Find, Theseus), an online documentation system that provides computer-managed on-demand printing of software manuals as well as the interactive retrieval of reference passages. Document boundaries in the hypertext database are discussed, search vocabulary complexities are described, and text…

  14. An ultraviolet-visible spectrophotometer automation system. Part 3: Program documentation

    Science.gov (United States)

    Roth, G. S.; Teuschler, J. M.; Budde, W. L.

    1982-07-01

    The Ultraviolet-Visible Spectrophotometer (UVVIS) automation system accomplishes 'on-line' spectrophotometric quality assurance determinations, report generations, plot generations and data reduction for chlorophyll or color analysis. This system also has the capability to process manually entered data for the analysis of chlorophyll or color. For each program of the UVVIS system, this document contains a program description, flowchart, variable dictionary, code listing, and symbol cross-reference table. Also included are descriptions of file structures and of routines common to all automated analyses. The programs are written in Data General extended BASIC, Revision 4.3, under the RDOS operating systems, Revision 6.2. The BASIC code has been enhanced for real-time data acquisition, which is accomplished by CALLS to assembly language subroutines. Two other related publications are 'An Ultraviolet-Visible Spectrophotometer Automation System - Part I Functional Specifications,' and 'An Ultraviolet-Visible Spectrophotometer Automation System - Part II User's Guide.'

  15. Waste Management System Requirement document

    International Nuclear Information System (INIS)

    1990-04-01

    This volume defines the top level technical requirements for the Monitored Retrievable Storage (MRS) facility. It is designed to be used in conjunction with Volume 1, General System Requirements. Volume 3 provides a functional description expanding the requirements allocated to the MRS facility in Volume 1 and, when appropriate, elaborates on requirements by providing associated performance criteria. Volumes 1 and 3 together convey a minimum set of requirements that must be satisfied by the final MRS facility design without unduly constraining individual design efforts. The requirements are derived from the Nuclear Waste Policy Act of 1982 (NWPA), the Nuclear Waste Policy Amendments Act of 1987 (NWPAA), the Environmental Protection Agency's (EPA) Environmental Standards for the Management and Disposal of Spent Nuclear Fuel (40 CFR 191), NRC Licensing Requirements for the Independent Storage of Spent Nuclear and High-Level Radioactive Waste (10 CFR 72), and other federal statutory and regulatory requirements, and major program policy decisions. This document sets forth specific requirements that will be fulfilled. Each subsequent level of the technical document hierarchy will be significantly more detailed and provide further guidance and definition as to how each of these requirements will be implemented in the design. Requirements appearing in Volume 3 are traceable into the MRS Design Requirements Document. Section 2 of this volume provides a functional breakdown for the MRS facility. 1 tab

  16. Document representations for classification of short web-page descriptions

    Directory of Open Access Journals (Sweden)

    Radovanović Miloš

    2008-01-01

    Full Text Available Motivated by applying Text Categorization to classification of Web search results, this paper describes an extensive experimental study of the impact of bag-of- words document representations on the performance of five major classifiers - Naïve Bayes, SVM, Voted Perceptron, kNN and C4.5. The texts, representing short Web-page descriptions sorted into a large hierarchy of topics, are taken from the dmoz Open Directory Web-page ontology, and classifiers are trained to automatically determine the topics which may be relevant to a previously unseen Web-page. Different transformations of input data: stemming, normalization, logtf and idf, together with dimensionality reduction, are found to have a statistically significant improving or degrading effect on classification performance measured by classical metrics - accuracy, precision, recall, F1 and F2. The emphasis of the study is not on determining the best document representation which corresponds to each classifier, but rather on describing the effects of every individual transformation on classification, together with their mutual relationships. .

  17. Spent Nuclear Fuel Project document control and Records Management Program Description

    International Nuclear Information System (INIS)

    MARTIN, B.M.

    2000-01-01

    The Spent Nuclear Fuel (SNF) Project document control and records management program, as defined within this document, is based on a broad spectrum of regulatory requirements, Department of Energy (DOE) and Project Hanford and SNF Project-specific direction and guidance. The SNF Project Execution Plan, HNF-3552, requires the control of documents and management of records under the auspices of configuration control, conduct of operations, training, quality assurance, work control, records management, data management, engineering and design control, operational readiness review, and project management and turnover. Implementation of the controls, systems, and processes necessary to ensure compliance with applicable requirements is facilitated through plans, directives, and procedures within the Project Hanford Management System (PHMS) and the SNF Project internal technical and administrative procedures systems. The documents cited within this document are those which directly establish or define the SNF Project document control and records management program. There are many peripheral documents that establish requirements and provide direction pertinent to managing specific types of documents that, for the sake of brevity and clarity, are not cited within this document

  18. Monitored Retrievable Storage System Requirements Document. Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    1994-03-01

    This Monitored Retrievable Storage System Requirements Document (MRS-SRD) describes the functions to be performed and technical requirements for a Monitored Retrievable Storage (MRS) facility subelement and the On-Site Transfer and Storage (OSTS) subelement. The MRS facility subelement provides for temporary storage, at a Civilian Radioactive Waste Management System (CRWMS) operated site, of spent nuclear fuel (SNF) contained in an NRC-approved Multi-Purpose Canister (MPC) storage mode, or other NRC-approved storage modes. The OSTS subelement provides for transfer and storage, at Purchaser sites, of spent nuclear fuel (SNF) contained in MPCs. Both the MRS facility subelement and the OSTS subelement are in support of the CRWMS. The purpose of the MRS-SRD is to define the top-level requirements for the development of the MRS facility and the OSTS. These requirements include design, operation, and decommissioning requirements to the extent they impact on the physical development of the MRS facility and the OSTS. The document also presents an overall description of the MRS facility and the OSTS, their functions (derived by extending the functional analysis documented by the Physical System Requirements (PSR) Store Waste Document), their segments, and the requirements allocated to the segments. In addition, the top-level interface requirements of the MRS facility and the OSTS are included. As such, the MRS-SRD provides the technical baseline for the MRS Safety Analysis Report (SAR) design and the OSTS Safety Analysis Report design.

  19. Model documentation report: Transportation sector model of the National Energy Modeling System

    Energy Technology Data Exchange (ETDEWEB)

    1994-03-01

    This report documents the objectives, analytical approach and development of the National Energy Modeling System (NEMS) Transportation Model (TRAN). The report catalogues and describes the model assumptions, computational methodology, parameter estimation techniques, model source code, and forecast results generated by the model. This document serves three purposes. First, it is a reference document providing a detailed description of TRAN for model analysts, users, and the public. Second, this report meets the legal requirements of the Energy Information Administration (EIA) to provide adequate documentation in support of its statistical and forecast reports (Public Law 93-275, 57(b)(1)). Third, it permits continuity in model development by providing documentation from which energy analysts can undertake model enhancements, data updates, and parameter refinements.

  20. The Role of Documentation Quality in Anesthesia-Related Closed Claims: A Descriptive Qualitative Study.

    Science.gov (United States)

    Wilbanks, Bryan A; Geisz-Everson, Marjorie; Boust, Rebecca R

    2016-09-01

    Clinical documentation is a critical tool in supporting care provided to patients. Sound documentation provides a picture of clinical events that can be used to improve patient care. However, many other uses for clinical documentation are equally important. Such documentation informs clinical decision support tools, creates a legal record of patient care, assists in financial reimbursement of services, and serves as a repository for secondary data analysis. Conversely, poor documentation can impair patient safety and increase malpractice risk exposure by reflecting poor or inaccurate information that ultimately may guide patient care decisions.Through an examination of anesthesia-related closed claims, a descriptive qualitative study emerged, which explored the antecedents and consequences of documentation quality in the claims reviewed. A secondary data analysis utilized a database generated by the American Association of Nurse Anesthetists Foundation closed claim review team. Four major themes emerged from the analysis. Themes 1, 2, and 4 primarily describe how poor documentation quality can have negative consequences for clinicians. The third theme primarily describes how poor documentation quality that can negatively affect patient safety.

  1. Airspace Technology Demonstration 2 (ATD-2) Technology Description Document (TDD)

    Science.gov (United States)

    Ging, Andrew; Engelland, Shawn; Capps, Al; Eshow, Michelle; Jung, Yoon; Sharma, Shivanjli; Talebi, Ehsan; Downs, Michael; Freedman, Cynthia; Ngo, Tyler; hide

    2018-01-01

    This Technology Description Document (TDD) provides an overview of the technology for the Phase 1 Baseline Integrated Arrival, Departure, and Surface (IADS) prototype system of the National Aeronautics and Space Administration's (NASA) Airspace Technology Demonstration 2 (ATD-2) project, to be demonstrated beginning in 2017 at Charlotte Douglas International Airport (CLT). Development, integration, and field demonstration of relevant technologies of the IADS system directly address recommendations made by the Next Generation Air Transportation System (NextGen) Integration Working Group (NIWG) on Surface and Data Sharing and the Surface Collaborative Decision Making (Surface CDM) concept of operations developed jointly by the Federal Aviation Administration (FAA) and aviation industry partners. NASA is developing the IADS traffic management system under the ATD-2 project in coordination with the FAA, flight operators, CLT airport, and the National Air Traffic Controllers Association (NATCA). The primary goal of ATD-2 is to improve the predictability and operational efficiency of the air traffic system in metroplex environments, through the enhancement, development, and integration of the nation's most advanced and sophisticated arrival, departure, and surface prediction, scheduling, and management systems. The ATD-2 project is a 5-year research activity beginning in 2015 and extending through 2020. The Phase 1 Baseline IADS capability resulting from the ATD-2 research will be demonstrated at the CLT airport beginning in 2017. Phase 1 will provide the initial demonstration of the integrated system with strategic and tactical scheduling, tactical departure scheduling to an en route meter point, and an early implementation prototype of a Terminal Flight Data Manager (TFDM) Electronic Flight Data (EFD) system. The strategic surface scheduling element of the capability is consistent with the Surface CDM Concept of Operations published in 2014 by the FAA Surface

  2. TRANSPORTATION SYSTEM REQUIREMENTS DOCUMENT

    International Nuclear Information System (INIS)

    2004-01-01

    This document establishes the Transportation system requirements for the U.S. Department of Energy's (DOE's) Civilian Radioactive Waste Management System (CRWMS). These requirements are derived from the Civilian Radioactive Waste Management System Requirements Document (CRD). The Transportation System Requirements Document (TSRD) was developed in accordance with LP-3.1Q-OCRWM, Preparation, Review, and Approval of Office of National Transportation Level-2 Baseline Requirements. As illustrated in Figure 1, the TSRD forms a part of the DOE Office of Civilian Radioactive Waste Management (OCRWM) Technical Baseline

  3. Automated software system for checking the structure and format of ACM SIG documents

    Science.gov (United States)

    Mirza, Arsalan Rahman; Sah, Melike

    2017-04-01

    Microsoft (MS) Office Word is one of the most commonly used software tools for creating documents. MS Word 2007 and above uses XML to represent the structure of MS Word documents. Metadata about the documents are automatically created using Office Open XML (OOXML) syntax. We develop a new framework, which is called ADFCS (Automated Document Format Checking System) that takes the advantage of the OOXML metadata, in order to extract semantic information from MS Office Word documents. In particular, we develop a new ontology for Association for Computing Machinery (ACM) Special Interested Group (SIG) documents for representing the structure and format of these documents by using OWL (Web Ontology Language). Then, the metadata is extracted automatically in RDF (Resource Description Framework) according to this ontology using the developed software. Finally, we generate extensive rules in order to infer whether the documents are formatted according to ACM SIG standards. This paper, introduces ACM SIG ontology, metadata extraction process, inference engine, ADFCS online user interface, system evaluation and user study evaluations.

  4. KALIMER fuel system preliminary design description

    International Nuclear Information System (INIS)

    Hwang, Woan; Lee, B.O.; Nam, C.; Paek, S.K.

    1998-10-01

    This document provides general design concepts, design basis, preliminary design specification and design technologies which are needed for designing the fuel/non-fuel rods and assembly ducts of the KALIMER fuel system. The core of LMFBR consists of driver fuel assembly, blanket assembly, reflector assembly, shielding assembly, control assembly and GEM (Gas Expansion Module) as well as USS, dummy assembly, detector assembly. These core components must be designed to withstand the high temperature, high flux for a long irradiation exposure time. Due to the high temperature and high flux, irradiation creep and swelling as well as thermal-mechanical deformation are occurred at the fuel/non-fuel system and cause the deformations of materials and the geometric deflections at fuel/non-fuel rods, assembly ducts and components. In order to overcome these intricate phenomena through the engineering design, the design basis including theoretical analysis methodologies and design considerations, material characteristics of fuel system, and the specifications and drawings of fuel/non-fuel rods and assembly ducts, respectively, are presented. This document is preliminary design description which is produced in the conceptual design stage, and does not present the detailed and finalized design data which can be for the manufacturing. (author). 22 refs

  5. CNEA's quality system documentation

    International Nuclear Information System (INIS)

    Mazzini, M.M.; Garonis, O.H.

    1998-01-01

    Full text: To obtain an effective and coherent documentation system suitable for CNEA's Quality Management Program, we decided to organize the CNEA's quality documentation with : a- Level 1. Quality manual. b- Level 2. Procedures. c-Level 3. Qualities plans. d- Level 4: Instructions. e- Level 5. Records and other documents. The objective of this work is to present a standardization of the documentation of the CNEA's quality system of facilities, laboratories, services, and R and D activities. Considering the diversity of criteria and formats for elaboration the documentation by different departments, and since ultimately each of them generally includes the same quality management policy, we proposed the elaboration of a system in order to improve the documentation, avoiding unnecessary time wasting and costs. This will aloud each sector to focus on their specific documentation. The quality manuals of the atomic centers fulfill the rule 3.6.1 of the Nuclear Regulatory Authority, and the Safety Series 50-C/SG-Q of the International Atomic Energy Agency. They are designed by groups of competent and highly trained people of different departments. The normative procedures are elaborated with the same methodology as the quality manuals. The quality plans which describe the organizational structure of working group and the appropriate documentation, will asses the quality manuals of facilities, laboratories, services, and research and development activities of atomic centers. The responsibilities for approval of the normative documentation are assigned to the management in charge of the administration of economic and human resources in order to fulfill the institutional objectives. Another improvement aimed to eliminate unnecessary invaluable processes is the inclusion of all quality system's normative documentation in the CNEA intranet. (author) [es

  6. Tank waste remediation system technical baseline summary description

    International Nuclear Information System (INIS)

    Raymond, R.E.

    1998-01-01

    This document is one of the tools used to develop and control the mission work as depicted in the included figure. This Technical Baseline Summary Description document is the top-level tool for management of the Technical Baseline for waste storage operations

  7. International safeguards data management system. System description: Version 1.1.; Release PLI 82

    International Nuclear Information System (INIS)

    Argentesi, T.; Casilli, T.; Costantini, L.; Dondi, M.G.; Franklin, M.

    1982-01-01

    This document describes a nuclear material accountancy system which has been developed using the ADABAS data base management system and is implemented on the JRC-Ispra computer. Throughout the report, the data base system is referred to as ''ISADAM'', i.e. International Safeguards Data Management System. The system provides tools for a safeguards authority to decide whether an operators MUF (Material Unaccounted For) can be accounted for as an accumulation of operator measurement errors. The principle objective of the applications programs described here is to provide a variance analysis of MUF in which the variance of MUF is computed as a function of the accounting declarations and the error characteristics of the operator measurement system. A overview of ISADAM is presented; then, a detailed description of the processing applied by the system is given. A description of the parameter information required by the four autonomous programs ISADAM is presented. In developing ISADAM, one of the prime factors taken into consideration was the ease with which it could be used

  8. NASAwide electronic publishing system: Prototype STI electronic document distribution, stage-4 evaluation report

    Science.gov (United States)

    Tuey, Richard C.; Collins, Mary; Caswell, Pamela; Haynes, Bob; Nelson, Michael L.; Holm, Jeanne; Buquo, Lynn; Tingle, Annette; Cooper, Bill; Stiltner, Roy

    1996-01-01

    This evaluation report contains an introduction, seven chapters, and five appendices. The Introduction describes the purpose, conceptual frame work, functional description, and technical report server of the STI Electronic Document Distribution (EDD) project. Chapter 1 documents the results of the prototype STI EDD in actual operation. Chapter 2 documents each NASA center's post processing publication processes. Chapter 3 documents each center's STI software, hardware, and communications configurations. Chapter 7 documents STI EDD policy, practices, and procedures. The appendices, which arc contained in Part 2 of this document, consist of (1) STI EDD Project Plan, (2) Team members, (3) Phasing Schedules, (4) Accessing On-line Reports, and (5) Creating an HTML File and Setting Up an xTRS. In summary, Stage 4 of the NASAwide Electronic Publishing System is the final phase of its implementation through the prototyping and gradual integration of each NASA center's electronic printing systems, desktop publishing systems, and technical report servers to be able to provide to NASA's engineers, researchers, scientists, and external users the widest practicable and appropriate dissemination of information concerning its activities and the result thereof to their work stations.

  9. Model documentation report: Macroeconomic Activity Module (MAM) of the National Energy Modeling System

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-02-01

    This report documents the objectives, analytical approach, and development of the National Energy Modeling System (NEMS) Macroeconomic Activity Module (MAM) used to develop the Annual Energy Outlook for 1997 (AEO 97). The report catalogues and describes the module assumptions, computations, methodology, parameter estimation techniques, and mainframe source code. This document serves three purposes. First it is a reference document providing a detailed description of the NEMS MAM used for the AEO 1997 production runs for model analysts, users, and the public. Second, this report meets the legal requirement of the Energy Information Administration (EIA) to provide adequate documentation in support of its models. Third, it facilitates continuity in model development by providing documentation from which energy analysts can undertake model enhancements, data updates, and parameter refinements as future projects.

  10. SYSTEM «PlagiarismControl» AS THE TOOL FOR THE EXPERTISE OF THE TEXT DOCUMENTS

    Directory of Open Access Journals (Sweden)

    Yu. B. Krapivin

    2018-01-01

    Full Text Available The description and the operability analysis of the implemented instrumental software system «PlagiarismControl» has been done. The system affords to automatize solving the task of the identification of the adopted fragments in the given text document both from the local full-text user’s database and from the Internet. The system affords solving the task taking in account explicit as well as implicit adoptions with precision up to lexical units paradigms and both lexical and grammatical synonymy relations, according to the structural-functional schematic diagram of the system of the automatic recognition of reproduced fragments of the text documents. «PlagiarismControl» is able to work in different modes, to automatize the work of the expert and to speed up significantly the procedure of the analysis of the documents, with the purpose of recognition of the adoptions (plagiarism from other text documents.

  11. 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

  12. 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.

  13. 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

  14. Model documentation report: Industrial sector demand module of the National Energy Modeling System

    International Nuclear Information System (INIS)

    1997-01-01

    This report documents the objectives, analytical approach, and development of the National Energy Modeling System (NEMS) Industrial Demand Model. The report catalogues and describes model assumptions, computational methodology, parameter estimation techniques, and model source code. This document serves three purposes. First, it is a reference document providing a detailed description of the NEMS Industrial Model for model analysts, users, and the public. Second, this report meets the legal requirement of the Energy Information Administration (EIA) to provide adequate documentation in support of its models. Third, it facilitates continuity in model development by providing documentation from which energy analysts can undertake model enhancements, data updates, and parameter refinements as future projects. The NEMS Industrial Demand Model is a dynamic accounting model, bringing together the disparate industries and uses of energy in those industries, and putting them together in an understandable and cohesive framework. The Industrial Model generates mid-term (up to the year 2015) forecasts of industrial sector energy demand as a component of the NEMS integrated forecasting system. From the NEMS system, the Industrial Model receives fuel prices, employment data, and the value of industrial output. Based on the values of these variables, the Industrial Model passes back to the NEMS system estimates of consumption by fuel types

  15. 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.

  16. 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

  17. Management control and status reports documentation standard and Data Item Descriptions (DID). Volume of the information system life-cycle and documentation standards, volume 5

    Science.gov (United States)

    Callender, E. David; Steinbacher, Jody

    1989-01-01

    This is the fifth of five volumes on Information System Life-Cycle and Documentation Standards. This volume provides a well organized, easily used standard for management control and status reports used in monitoring and controlling the management, development, and assurance of informations systems and software, hardware, and operational procedures components, and related processes.

  18. Civilian Radioactive Waste Management System Requirements Document

    International Nuclear Information System (INIS)

    1992-12-01

    This document specifies the top-level requirements for the Civilian Radioactive Waste Management System (CRWMS). The document is referred to herein as the CRD, for CRWMS Requirements document. The OCRWM System Engineering Management Plan (SEMP) establishes the technical document hierarchy (hierarchy of technical requirements and configuration baseline documents) for the CRWMS program. The CRD is the top-level document in this hierarchy. The immediate subordinate documents are the System Requirements Documents (SRDS) for the four elements of the CRWMS and the Interface Specification (IFS). The four elements of the CRWMS are the Waste Acceptance System, the Transportation System, the Monitored Retrievable Storage (MRS) System and the Mined Geologic Disposal System (MGDS). The Interface Specification describes the six inter-element interfaces between the four elements. This hierarchy establishes the requirements to be addressed by the design of the system elements. Many of the technical requirements for the CRWMS are documented in a variety of Federal regulations, DOE directives and other Government documentation. It is the purpose of the CRD to establish the technical requirements for the entire program. In doing so, the CRD summarizes source documentation for requirements that must be addressed by the program, specifies particular requirements, and documents derived requirements that are not covered in regulatory and other Government documentation, but are necessary to accomplish the mission of the CRWMS. The CRD defines the CRWMS by identifying the top-level functions the elements must perform (These top-level functions were derived using functional analysis initially documented in the Physical System Requirements (PSR) documents). The CRD also defines the top-level physical architecture of the system and allocates the functions and requirements to the architectural elements of the system

  19. Nuclear power plants documentation system

    International Nuclear Information System (INIS)

    Schwartz, E.L.

    1991-01-01

    Since the amount of documents (type and quantity) necessary for the entire design of a NPP is very large, this implies that an overall and detailed identification, filling and retrieval system shall be implemented. This is even more applicable to the FINAL QUALITY DOCUMENTATION of the plant, as stipulated by IAEA Safety Codes and related guides. For such a purpose it was developed a DOCUMENTATION MANUAL, which describes in detail the before mentioned documentation system. Here we present the expected goals and results which we have to reach for Angra 2 and 3 Project. (author)

  20. WASTE HANDLING BUILDING FIRE PROTECTION SYSTEM DESCRIPTION DOCUMENT

    Energy Technology Data Exchange (ETDEWEB)

    J. D. Bigbee

    2000-06-21

    The Waste Handling Building Fire Protection System provides the capability to detect, control, and extinguish fires and/or mitigate explosions throughout the Waste Handling Building (WHB). Fire protection includes appropriate water-based and non-water-based suppression, as appropriate, and includes the distribution and delivery systems for the fire suppression agents. The Waste Handling Building Fire Protection System includes fire or explosion detection panel(s) controlling various detectors, system actuation, annunciators, equipment controls, and signal outputs. The system interfaces with the Waste Handling Building System for mounting of fire protection equipment and components, location of fire suppression equipment, suppression agent runoff, and locating fire rated barriers. The system interfaces with the Waste Handling Building System for adequate drainage and removal capabilities of liquid runoff resulting from fire protection discharges. The system interfaces with the Waste Handling Building Electrical Distribution System for power to operate, and with the Site Fire Protection System for fire protection water supply to automatic sprinklers, standpipes, and hose stations. The system interfaces with the Site Fire Protection System for fire signal transmission outside the WHB as needed to respond to a fire emergency, and with the Waste Handling Building Ventilation System to detect smoke and fire in specific areas, to protect building high-efficiency particulate air (HEPA) filters, and to control portions of the Waste Handling Building Ventilation System for smoke management and manual override capability. The system interfaces with the Monitored Geologic Repository (MGR) Operations Monitoring and Control System for annunciation, and condition status.

  1. WASTE HANDLING BUILDING FIRE PROTECTION SYSTEM DESCRIPTION DOCUMENT

    International Nuclear Information System (INIS)

    J. D. Bigbee

    2000-01-01

    The Waste Handling Building Fire Protection System provides the capability to detect, control, and extinguish fires and/or mitigate explosions throughout the Waste Handling Building (WHB). Fire protection includes appropriate water-based and non-water-based suppression, as appropriate, and includes the distribution and delivery systems for the fire suppression agents. The Waste Handling Building Fire Protection System includes fire or explosion detection panel(s) controlling various detectors, system actuation, annunciators, equipment controls, and signal outputs. The system interfaces with the Waste Handling Building System for mounting of fire protection equipment and components, location of fire suppression equipment, suppression agent runoff, and locating fire rated barriers. The system interfaces with the Waste Handling Building System for adequate drainage and removal capabilities of liquid runoff resulting from fire protection discharges. The system interfaces with the Waste Handling Building Electrical Distribution System for power to operate, and with the Site Fire Protection System for fire protection water supply to automatic sprinklers, standpipes, and hose stations. The system interfaces with the Site Fire Protection System for fire signal transmission outside the WHB as needed to respond to a fire emergency, and with the Waste Handling Building Ventilation System to detect smoke and fire in specific areas, to protect building high-efficiency particulate air (HEPA) filters, and to control portions of the Waste Handling Building Ventilation System for smoke management and manual override capability. The system interfaces with the Monitored Geologic Repository (MGR) Operations Monitoring and Control System for annunciation, and condition status

  2. Licensing systems and inspection of nuclear installations in NEA Member countries. Part 1, Description of licensing systems

    International Nuclear Information System (INIS)

    1977-01-01

    This study provides an assessment of the legislative and regulatory provisions applicable and of the practices followed in the countries concerned and is divided into two separate sections. This document is the first part only. It contains the description of national licensing and inspection systems for nuclear installations in the twenty OECD countries which have specific regulations in this field. Each analysis has been presented following a plan which is as standardised as possible so as to facilitate comparison between the national systems. Part II, which is not included in this document, contains the diagrams illustrating the steps in the licensing procedure and the duties of the bodies involved as well as certain additional documents. It also includes a table showing the sequence of the main steps in the licensing process in the countries covered by this Study

  3. POOL WATER TREATMENT AND COOLING SYSTEM DESCRIPTION DOCUMENT

    International Nuclear Information System (INIS)

    King, V.

    2000-01-01

    The Pool Water Treatment and Cooling System is located in the Waste Handling Building (WHB), and is comprised of various process subsystems designed to support waste handling operations. This system maintains the pool water temperature within an acceptable range, maintains water quality standards that support remote underwater operations and prevent corrosion, detects leakage from the pool liner, provides the capability to remove debris from the pool, controls the pool water level, and helps limit radiological exposure to personnel. The pool structure and liner, pool lighting, and the fuel staging racks in the pool are not within the scope of the Pool Water Treatment and Cooling System. Pool water temperature control is accomplished by circulating the pool water through heat exchangers. Adequate circulation and mixing of the pool water is provided to prevent localized thermal hotspots in the pool. Treatment of the pool water is accomplished by a water treatment system that circulates the pool water through filters, and ion exchange units. These water treatment units remove radioactive and non-radioactive particulate and dissolved solids from the water, thereby providing the water clarity needed to conduct waste handling operations. The system also controls pool water chemistry to prevent advanced corrosion of the pool liner, pool components, and fuel assemblies. Removal of radioactivity from the pool water contributes to the project ALARA (as low as is reasonably achievable) goals. A leak detection system is provided to detect and alarm leaks through the pool liner. The pool level control system monitors the water level to ensure that the minimum water level required for adequate radiological shielding is maintained. Through interface with a demineralized water system, adequate makeup is provided to compensate for loss of water inventory through evaporation and waste handling operations. Interface with the Site Radiological Monitoring System provides continuous

  4. Detailed description of a state system for accounting for and control of nuclear material at the state level

    International Nuclear Information System (INIS)

    Jones, R.J.

    1985-02-01

    The purpose of this document is to provide a detailed description of the technical elements of a system for the accounting for and control of nuclear material at the State Authority level which can be used by a state in the establishment of a national system for nuclear material accounting and control. It is expected that a state system designed along the lines described also will assist the IAEA in carrying out its safeguards responsibilities. The scope of this document is limited to descriptions of the technical elements of a state level system concerned with Laws and Regulations, the Information System, and the Establishment of Requirements for Nuclear Material Accounting and Control. The discussion shows the relationship of these technical elements at the state level to the principal elements of an SSAC at the facility levels

  5. Tank Monitoring and Document control System (TMACS) As Built Software Design Document

    International Nuclear Information System (INIS)

    GLASSCOCK, J.A.

    2000-01-01

    This document describes the software design for the Tank Monitor and Control System (TMACS). This document captures the existing as-built design of TMACS as of November 1999. It will be used as a reference document to the system maintainers who will be maintaining and modifying the TMACS functions as necessary. The heart of the TMACS system is the ''point-processing'' functionality where a sample value is received from the field sensors and the value is analyzed, logged, or alarmed as required. This Software Design Document focuses on the point-processing functions

  6. Mined Geologic Disposal System Requirements Document

    International Nuclear Information System (INIS)

    1993-01-01

    This Mined Geologic Disposal System Requirements document (MGDS-RD) describes the functions to be performed by, and the requirements for, a Mined Geologic Disposal System (MGDS) for the permanent disposal of spent nuclear fuel (SNF) and commercial and defense high level radioactive waste (HLW) in support of the Civilian Radioactive Waste Management System (CRWMS). The development and control of the MGDS-RD is quality-affecting work and is subject to the Department of Energy (DOE) Office of Civilian Radioactive Waste Management (OCRWM) Quality Assurance Requirements Document (QARD). As part of the technical requirements baseline, it is also subject to Baseline Management Plan controls. The MGDS-RD and the other program-level requirements documents have been prepared and managed in accordance with the Technical Document Preparation Plan (TDPP) for the Preparation of System Requirements Documents

  7. Shippingport Spent Fuel Canister System Description

    International Nuclear Information System (INIS)

    JOHNSON, D.M.

    2000-01-01

    In 1978 and 1979, a total of 72 blanket fuel assemblies (BFAs), irradiated during the operating cycles of the Shippingport Atomic Power Station's Pressurized Water Reactor (PWR) Core 2 from April 1965 to February 1974, were transferred to the Hanford Site and stored in underwater storage racks in Cell 2R at the 221-T Canyon (T-Plant). The initial objective was to recover the produced plutonium in the BFAs, but this never occurred and the fuel assemblies have remained within the water storage pool to the present time. The Shippingport Spent Fuel Canister (SSFC) is a confinement system that provides safe transport functions (in conjunction with the TN-WHC cask) and storage for the BFAs at the Canister Storage Building (CSB). The current plan is for these BFAs to be retrieved from wet storage and loaded into SSFCs for dry storage. The sealed SSFCs containing BFAs will be vacuum dried, internally backfilled with helium, and leak tested to provide suitable confinement for the BFAs during transport and storage. Following completion of the drying and inerting process, the SSFCs are to be delivered to the CSB for closure welding and long-term interim storage. The CSB will provide safe handling and dry storage for the SSFCs containing the BFAs. The purpose of this document is to describe the SSFC system and interface equipment, including the technical basis for the system, design descriptions, and operations requirements. It is intended that this document will be periodically updated as more equipment design and performance specification information becomes available

  8. Tank Monitoring and Document control System (TMACS) As Built Software Design Document

    Energy Technology Data Exchange (ETDEWEB)

    GLASSCOCK, J.A.

    2000-01-27

    This document describes the software design for the Tank Monitor and Control System (TMACS). This document captures the existing as-built design of TMACS as of November 1999. It will be used as a reference document to the system maintainers who will be maintaining and modifying the TMACS functions as necessary. The heart of the TMACS system is the ''point-processing'' functionality where a sample value is received from the field sensors and the value is analyzed, logged, or alarmed as required. This Software Design Document focuses on the point-processing functions.

  9. Replacement Saltwell Pumping System Document Bibliography

    International Nuclear Information System (INIS)

    BELLOMY, J.R.

    2000-01-01

    This document bibliography is prepared to identify engineering documentation developed during the design of the Replacement Saltwell Pumping System. The bibliography includes all engineering supporting documents and correspondence prepared prior to the deployment of the system in the field. All documents referenced are available electronically through the Records Management Information System (RMIS). Major components of the Replacement Saltwell Pumping System include the Sundyne Canned Motor Pump, the Water Filter Skid, the Injection Water Skid and the Backflow Preventer Assembly. Drawing H-14-104498 provides an index of drawings (fabrication details, PandIDs, etc.) prepared to support development of the Replacement Saltwell Pumping System. Specific information pertaining to new equipment can be found in Certified Vendor Information (CVI) File 50124. This CVI file has been established specifically for new equipment associated with the Replacement Saltwell Pumping System

  10. NASAwide electronic publishing system-prototype STI electronic document distribution: Stage-4 evaluation report. Part 2; Appendices

    Science.gov (United States)

    Tuey, Richard C.; Collins, Mary; Caswell, Pamela; Haynes, Bob; Nelson, Michael L.; Holm, Jeanne; Buquo, Lynn; Tingle, Annette; Cooper, Bill; Stiltner, Roy

    1996-01-01

    This evaluation report contains an introduction, seven chapters, and five appendices. The Introduction describes the purpose, conceptual framework, functional description, and technical report server of the Scientific and Technical Information (STI) Electronic Document Distribution (EDD) project. Chapter 1 documents the results of the prototype STI EDD in actual operation. Chapter 2 documents each NASA center's post processing publication processes. Chapter 3 documents each center's STI software, hardware. and communications configurations. Chapter 7 documents STI EDD policy, practices, and procedures. The appendices consist of (A) the STI EDD Project Plan, (B) Team members, (C) Phasing Schedules, (D) Accessing On-line Reports, and (E) Creating an HTML File and Setting Up an xTRS. In summary, Stage 4 of the NASAwide Electronic Publishing System is the final phase of its implementation through the prototyping and gradual integration of each NASA center's electronic printing systems, desk top publishing systems, and technical report servers, to be able to provide to NASA's engineers, researchers, scientists, and external users, the widest practicable and appropriate dissemination of information concerning its activities and the result thereof to their work stations.

  11. 2D arc-PIC code description: methods and documentation

    CERN Document Server

    Timko, Helga

    2011-01-01

    Vacuum discharges are one of the main limiting factors for future linear collider designs such as that of the Compact LInear Collider. To optimize machine efficiency, maintaining the highest feasible accelerating gradient below a certain breakdown rate is desirable; understanding breakdowns can therefore help us to achieve this goal. As a part of ongoing theoretical research on vacuum discharges at the Helsinki Institute of Physics, the build-up of plasma can be investigated through the particle-in-cell method. For this purpose, we have developed the 2D Arc-PIC code introduced here. We present an exhaustive description of the 2D Arc-PIC code in two parts. In the first part, we introduce the particle-in-cell method in general and detail the techniques used in the code. In the second part, we provide a documentation and derivation of the key equations occurring in the code. The code is original work of the author, written in 2010, and is therefore under the copyright of the author. The development of the code h...

  12. Consolidated Cab Display (CCD) System, Project Planning Document (PPD),

    Science.gov (United States)

    1981-02-01

    1980 1981 I 2 3 4 5 6 7 8 9 10 1112 1 2 3 4 5 6 7 8 9 1011112 1 2 31 12. Software Documentation a. Overall Computer Program Description ( OCPD ) b...Approve OCPD c. Computer Program Functional Specifications (CPFS) d. Data Base Table Design Specification (DBTDS) e. Software Interface Control Document...Parts List Master Pattern and Plan View Reproducible Drawings Instruction Book Training Aids/Materials b. Software: OCPD CPFS SI CD PDS DBTDS SDD

  13. Integrated Information Support System (IISS). Volume 8. User Interface Subsystem. Part 39. Electronic Documentation System (EDS) User’s Manual

    Science.gov (United States)

    1990-09-30

    conveying any rights or permission to manufacture, use, or market any patented invention that may in any way be related thereto. This technical report...24 Layout Editor A:’on D"D Nline luo ert Profile Description ED,7 tntrDSLEI * PM5SLE a, )catioq Figure 5-8 Edit Document Profile The system will now

  14. SITE GENERATED RADIOLOGICAL WASTE HANDLING SYSTEM DESCRIPTION DOCUMENT

    Energy Technology Data Exchange (ETDEWEB)

    S. C. Khamankar

    2000-06-20

    The Site Generated Radiological Waste Handling System handles radioactive waste products that are generated at the geologic repository operations area. The waste is collected, treated if required, packaged for shipment, and shipped to a disposal site. Waste streams include low-level waste (LLW) in solid and liquid forms, as-well-as mixed waste that contains hazardous and radioactive constituents. Liquid LLW is segregated into two streams, non-recyclable and recyclable. The non-recyclable stream may contain detergents or other non-hazardous cleaning agents and is packaged for shipment. The recyclable stream is treated to recycle a large portion of the water while the remaining concentrated waste is packaged for shipment; this greatly reduces the volume of waste requiring disposal. There will be no liquid LLW discharge. Solid LLW consists of wet solids such as ion exchange resins and filter cartridges, as-well-as dry active waste such as tools, protective clothing, and poly bags. Solids will be sorted, volume reduced, and packaged for shipment. The generation of mixed waste at the Monitored Geologic Repository (MGR) is not planned; however, if it does come into existence, it will be collected and packaged for disposal at its point of occurrence, temporarily staged, then shipped to government-approved off-site facilities for disposal. The Site Generated Radiological Waste Handling System has equipment located in both the Waste Treatment Building (WTB) and in the Waste Handling Building (WHB). All types of liquid and solid LLW are processed in the WTB, while wet solid waste from the Pool Water Treatment and Cooling System is packaged where received in the WHB. There is no installed hardware for mixed waste. The Site Generated Radiological Waste Handling System receives waste from locations where water is used for decontamination functions. In most cases the water is piped back to the WTB for processing. The WTB and WHB provide staging areas for storing and shipping LLW

  15. SITE GENERATED RADIOLOGICAL WASTE HANDLING SYSTEM DESCRIPTION DOCUMENT

    International Nuclear Information System (INIS)

    S. C. Khamankar

    2000-01-01

    The Site Generated Radiological Waste Handling System handles radioactive waste products that are generated at the geologic repository operations area. The waste is collected, treated if required, packaged for shipment, and shipped to a disposal site. Waste streams include low-level waste (LLW) in solid and liquid forms, as-well-as mixed waste that contains hazardous and radioactive constituents. Liquid LLW is segregated into two streams, non-recyclable and recyclable. The non-recyclable stream may contain detergents or other non-hazardous cleaning agents and is packaged for shipment. The recyclable stream is treated to recycle a large portion of the water while the remaining concentrated waste is packaged for shipment; this greatly reduces the volume of waste requiring disposal. There will be no liquid LLW discharge. Solid LLW consists of wet solids such as ion exchange resins and filter cartridges, as-well-as dry active waste such as tools, protective clothing, and poly bags. Solids will be sorted, volume reduced, and packaged for shipment. The generation of mixed waste at the Monitored Geologic Repository (MGR) is not planned; however, if it does come into existence, it will be collected and packaged for disposal at its point of occurrence, temporarily staged, then shipped to government-approved off-site facilities for disposal. The Site Generated Radiological Waste Handling System has equipment located in both the Waste Treatment Building (WTB) and in the Waste Handling Building (WHB). All types of liquid and solid LLW are processed in the WTB, while wet solid waste from the Pool Water Treatment and Cooling System is packaged where received in the WHB. There is no installed hardware for mixed waste. The Site Generated Radiological Waste Handling System receives waste from locations where water is used for decontamination functions. In most cases the water is piped back to the WTB for processing. The WTB and WHB provide staging areas for storing and shipping LLW

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

    Energy Technology Data Exchange (ETDEWEB)

    IRWIN, J.J.

    1998-11-30

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

  17. Spent nuclear fuel project cold vacuum drying facility process water conditioning system design description

    International Nuclear Information System (INIS)

    IRWIN, J.J.

    1998-01-01

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

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

    International Nuclear Information System (INIS)

    IRWIN, J.J.

    1998-01-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    None,

    1979-01-01

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

  20. Servir: an automated document delivery system

    International Nuclear Information System (INIS)

    Lima, E.C.; Azevedo Coutinho, O.C. de

    1986-01-01

    SERVIR, an automated document delivery system developed by CIN/CNEN, is described. Parametric procedures for reading bibliographic data bases and requesting documents from libraries through computer are specified. Statistical procedures, accounting system and the on-line fulfillment of requests are presented. (Author) [pt

  1. 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

  2. The transportation operations system: A description

    International Nuclear Information System (INIS)

    Best, R.E.; Danese, F.L.; Dixon, L.D.; Peterson, R.W.; Pope, R.B.

    1990-01-01

    This paper presents a description of the system for transporting radioactive waste that may be deployed to accomplish the assigned system mission, which includes accepting spent nuclear fuel (SNF) and high-level radioactive waste (HLW) from waste generator sites and transporting them to the FWMS destination facilities. The system description presented here contains, in part, irradiated fuel and waste casks, ancillary equipments, truck, rail, and barge transporters, cask and vehicle traffic management organizations, maintenance facilities, and other operations elements. The description is for a fully implemented system, which is not expected to be achieved, however, until several years after initial operations. 6 figs

  3. Electronic Document Management Using Inverted Files System

    Science.gov (United States)

    Suhartono, Derwin; Setiawan, Erwin; Irwanto, Djon

    2014-03-01

    The amount of documents increases so fast. Those documents exist not only in a paper based but also in an electronic based. It can be seen from the data sample taken by the SpringerLink publisher in 2010, which showed an increase in the number of digital document collections from 2003 to mid of 2010. Then, how to manage them well becomes an important need. This paper describes a new method in managing documents called as inverted files system. Related with the electronic based document, the inverted files system will closely used in term of its usage to document so that it can be searched over the Internet using the Search Engine. It can improve document search mechanism and document save mechanism.

  4. Electronic Document Management Using Inverted Files System

    Directory of Open Access Journals (Sweden)

    Suhartono Derwin

    2014-03-01

    Full Text Available The amount of documents increases so fast. Those documents exist not only in a paper based but also in an electronic based. It can be seen from the data sample taken by the SpringerLink publisher in 2010, which showed an increase in the number of digital document collections from 2003 to mid of 2010. Then, how to manage them well becomes an important need. This paper describes a new method in managing documents called as inverted files system. Related with the electronic based document, the inverted files system will closely used in term of its usage to document so that it can be searched over the Internet using the Search Engine. It can improve document search mechanism and document save mechanism.

  5. NILDE, Network Inter Library Document Exchange: An Italian Document Delivery System

    Science.gov (United States)

    Brunetti, F.; Gasperini, A.; Mangiaracina, S.

    2007-10-01

    This poster presents NILDE, a document delivery system supporting the exchange of documents via the internet. The system has been set up by the Central Library of the National Research Council of Bologna (Italy) in order to make use of new internet technology, to promote cooperation between Italian university libraries and research libraries, and to achieve quick response times in satisfying DD requests. The Arcetri Astrophysical Observatory Library was the first astronomical library to join the NILDE project from its earliest days in 2002. Many were the reasons for this choice: automation of the DD processes, security and reliability of the network, creation of usage statistics and reports, reduction of DD System management costs and so on. This work describes the benefits of NILDE and discusses the role of an organized document delivery system as an important tool to cope with the difficult constraints of the publishing market.

  6. 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)

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

    International Nuclear Information System (INIS)

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

    1996-12-01

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

  8. 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

  9. From Medieval Philosophy to the Virtual Library: a descriptive framework for scientific knowledge and documentation as basis for document retrieval

    Directory of Open Access Journals (Sweden)

    Frances Morrissey

    2001-11-01

    Full Text Available This paper examines the conceptual basis of document retrieval systems for the Virtual Library in science and technology. It does so through analysing some cognitive models for scientific knowledge, drawing on philosophy, sociology and linguistics. It is important to consider improvements in search/ retrieval functionalities for scientific documents because knowledge creation and transfer are integral to the functioning of scientific communities, and on a larger scale, science and technology are central to the knowledge economy. This paper proposes four new and innovative understandings. Firstly, it is proposed that formal scientific communication constitutes the documentation and dissemination of concepts, and that conceptualism is a useful philosophical basis for study. Second, it is proposed that the scientific document is a dyadic con-struct, being both the physical manifestation as an encoded medium, and also being the associated knowledge, or intangible ideation, that is carried within the document. Third, it is shown that major philosophers of science divide science into three main activities, dealing with data, derived or inferred laws, and the axioms or the paradigm. Fourth, it is demonstrated that the data, information and conceptual frameworks carried by a scientific document, as different levels of signification or semiotic systems, can each be characterised in ways assisting in search and retrieval functionalities for the Virtual Library.

  10. IDC Re-Engineering Phase 2 Architecture Document.

    Energy Technology Data Exchange (ETDEWEB)

    Burns, John F.

    2015-12-01

    This document contains a description of the system architecture for the IDC Re-Engineering Phase 2 project. This is a draft version that primarily provides background information for understanding delivered Use Case Realizations.

  11. Avionics Systems Laboratory/Building 16. Historical Documentation

    Science.gov (United States)

    Slovinac, Patricia; Deming, Joan

    2011-01-01

    As part of this nation-wide study, in September 2006, historical survey and evaluation of NASA-owned and managed facilities that was conducted by NASA s Lyndon B. Johnson Space Center (JSC) in Houston, Texas. The results of this study are presented in a report entitled, "Survey and Evaluation of NASA-owned Historic Facilities and Properties in the Context of the U.S. Space Shuttle Program, Lyndon B. Johnson Space Center, Houston, Texas," prepared in November 2007 by NASA JSC s contractor, Archaeological Consultants, Inc. As a result of this survey, the Avionics Systems Laboratory (Building 16) was determined eligible for listing in the NRHP, with concurrence by the Texas State Historic Preservation Officer (SHPO). The survey concluded that Building 5 is eligible for the NRHP under Criteria A and C in the context of the U.S. Space Shuttle program (1969-2010). Because it has achieved significance within the past 50 years, Criteria Consideration G applies. At the time of this documentation, Building 16 was still used to support the SSP as an engineering research facility, which is also sometimes used for astronaut training. This documentation package precedes any undertaking as defined by Section 106 of the NHPA, as amended, and implemented in 36 CFR Part 800, as NASA JSC has decided to proactively pursue efforts to mitigate the potential adverse affects of any future modifications to the facility. It includes a historical summary of the Space Shuttle program; the history of JSC in relation to the SSP; a narrative of the history of Building 16 and how it supported the SSP; and a physical description of the structure. In addition, photographs documenting the construction and historical use of Building 16 in support of the SSP, as well as photographs of the facility documenting the existing conditions, special technological features, and engineering details, are included. A contact sheet printed on archival paper, and an electronic copy of the work product on CD, are

  12. 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

  13. Electronic document management systems: an overview.

    Science.gov (United States)

    Kohn, Deborah

    2002-08-01

    For over a decade, most health care information technology (IT) professionals erroneously learned that document imaging, which is one of the many component technologies of an electronic document management system (EDMS), is the only technology of an EDMS. In addition, many health care IT professionals erroneously believed that EDMSs have either a limited role or no place in IT environments. As a result, most health care IT professionals do not understand documents and unstructured data and their value as structured data partners in most aspects of transaction and information processing systems.

  14. Guide for the realization of Design Base Documents (DBD)

    International Nuclear Information System (INIS)

    Roca Mallofre, G. la

    2010-01-01

    Guide for improving the consistency and quality content of the Design Base Documents. It's a short description of how to carry out and complete these Documents but focusing on those aspects that can be more confusing and harder to interpret. This guide aims to clarify the term Design Base distinguishing between production and safety, and it focuses on safety Design Base Documents and their values and references. It also emphasizes the difference between the support system and the interface system when there is a functional connection between different systems.

  15. The AutoBayes Program Synthesis System: System Description

    Science.gov (United States)

    Fischer, Bernd; Pressburger, Thomas; Rosu, Grigore; Schumann, Johann; Norvog, Peter (Technical Monitor)

    2001-01-01

    AUTOBAYES is a fully automatic program synthesis system for the statistical data analysis domain. Its input is a concise description of a data analysis problem in the form of a statistical model; its output is optimized and fully documented C/C++ code which can be linked dynamically into the Matlab and Octave environments. AUTOBAYES synthesizes code by a schema-guided deductive process. Schemas (i.e., code templates with associated semantic constraints) are applied to the original problem and recursively to emerging subproblems. AUTOBAYES complements this approach by symbolic computation to derive closed-form solutions whenever possible. In this paper, we concentrate on the interaction between the symbolic computations and the deductive synthesis process. A statistical model specifies for each problem variable (i.e., data or parameter) its properties and dependencies in the form of a probability distribution, A typical data analysis task is to estimate the best possible parameter values from the given observations or measurements. The following example models normal-distributed data but takes prior information (e.g., from previous experiments) on the data's mean value and variance into account.

  16. Waste Acceptance System Requirements document (WASRD)

    International Nuclear Information System (INIS)

    1993-01-01

    This Waste Acceptance System Requirements document (WA-SRD) describes the functions to be performed and the technical requirements for a Waste Acceptance System for accepting spent nuclear fuel (SNF) and high-level radioactive waste (HLW) into the Civilian Radioactive Waste Management System (CRWMS). This revision of the WA-SRD addresses the requirements for the acceptance of HLW. This revision has been developed as a top priority document to permit DOE's Office of Environmental Restoration and Waste Management (EM) to commence waste qualification runs at the Savannah River Site's (SRS) Defense Waste Processing Facility (DWPF) in a timely manner. Additionally, this revision of the WA-SRD includes the requirements from the Physical System Requirements -- Accept Waste document for the acceptance of SNF. A subsequent revision will fully address requirements relative to the acceptance of SNF

  17. 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.

  18. 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

  19. XML Diagnostics Description Standard

    International Nuclear Information System (INIS)

    Neto, A.; Fernandes, H.; Varandas, C.; Lister, J.; Yonekawa, I.

    2006-01-01

    A standard for the self-description of fusion plasma diagnostics will be presented, based on the Extensible Markup Language (XML). The motivation is to maintain and organise the information on all the components of a laboratory experiment, from the hardware to the access security, to save time and money when problems arises. Since there is no existing standard to organise this kind of information, every Association stores and organises each experiment in different ways. This can lead to severe problems when the organisation schema is poorly documented or written in national languages. The exchange of scientists, researchers and engineers between laboratories is a common practice nowadays. Sometimes they have to install new diagnostics or to update existing ones and frequently they lose a great deal of time trying to understand the currently installed system. The most common problems are: no documentation available; the person who understands it has left; documentation written in the national language. Standardisation is the key to solving all the problems mentioned. From the commercial information on the diagnostic (component supplier; component price) to the hardware description (component specifications; drawings) to the operation of the equipment (finite state machines) through change control (who changed what and when) and internationalisation (information at least in the native language and in English), a common XML schema will be proposed. This paper will also discuss an extension of these ideas to the self-description of ITER plant systems, since the problems will be identical. (author)

  20. South Florida freight advanced traveler information system : architecture and implementation as built documentation report.

    Science.gov (United States)

    2015-05-01

    The primary purpose of the As Built Documentation is to provide a description of any modifications made to the original architecture along with justification as to why the architecture was changed. In addition, this documentation provides the followi...

  1. Nuclear computerized library for assessing reactor reliability (NUCLARR): User's guide: Part 3, NUCLARR system description

    International Nuclear Information System (INIS)

    Gilmore, W.E.; Gentillon, C.D.; Gertman, D.I.; Beers, G.H.; Galyean, W.J.; Gilbert, B.G.

    1988-06-01

    The Nuclear Computerized Library for Assessing Reactor Reliability (NUCLARR) is an automated data base management system for processing and storing human error probability and hardware component failure data. The NUCLARR system software resides on an IBM (or compatible) personal micro-computer. NUCLARR can be used by the end user to furnish data inputs for both human and hardware reliability analysis in support of a variety of risk assessment activities. The NUCLARR system is documented in a five-volume series of reports. Volume IV of this series is the User's Guide for operating the NUCLARR software and is presented in three parts. This document, Part 3: NUCLARR System Description, provides an in-depth discussion of the design characteristics and special features of the NUCLARR software. Part 3 also presents the organization of the data base structures and techniques used to manipulate the data

  2. Honeywell modular automation system computer software documentation

    International Nuclear Information System (INIS)

    Cunningham, L.T.

    1997-01-01

    This document provides a Computer Software Documentation for a new Honeywell Modular Automation System (MAS) being installed in the Plutonium Finishing Plant (PFP). This system will be used to control new thermal stabilization furnaces in HA-21I

  3. ENDF/B summary documentation

    International Nuclear Information System (INIS)

    Kinsey, R.

    1979-07-01

    This publication provides a localized source of descriptions for the evaluations contained in the ENDF/B Library. The summary documentation presented is intended to be a more detailed description than the (File 1) comments contained in the computer readable data files, but not so detailed as the formal reports describing each ENDF/B evaluation. The summary documentations were written by the CSEWB (Cross Section Evaluation Working Group) evaluators and compiled by NNDC (National Nuclear Data Center). This edition includes documentation for materials found on ENDF/B Version V tapes 501 to 516 (General Purpose File) excluding tape 504. ENDF/B-V also includes tapes containing partial evaluations for the Special Purpose Actinide (521, 522), Dosimetry (531), Activation (532), Gas Production (533), and Fission Product (541-546) files. The materials found on these tapes are documented elsewhere. Some of the evaluation descriptions in this report contain cross sections or energy level information

  4. Detailed Design Documentation, without the Pain

    Science.gov (United States)

    Ramsay, C. D.; Parkes, S.

    2004-06-01

    Producing detailed forms of design documentation, such as pseudocode and structured flowcharts, to describe the procedures of a software system:(1) allows software developers to model and discuss their understanding of a problem and the design of a solution free from the syntax of a programming language,(2) facilitates deeper involvement of non-technical stakeholders, such as the customer or project managers, whose influence ensures the quality, correctness and timeliness of the resulting system,(3) forms comprehensive documentation of the system for its future maintenance, reuse and/or redeployment.However, such forms of documentation require effort to create and maintain.This paper describes a software tool which is currently being developed within the Space Systems Research Group at the University of Dundee which aims to improve the utility of, and the incentive for, creating detailed design documentation for the procedures of a software system. The rationale for creating such a tool is briefly discussed, followed by a description of the tool itself, a summary of its perceived benefits, and plans for future work.

  5. 28 CFR 20.23 - Documentation: Approval by OJARS.

    Science.gov (United States)

    2010-07-01

    ... description of State policy on dissemination of criminal history record information. (c) Six months after the... Section 20.23 Judicial Administration DEPARTMENT OF JUSTICE CRIMINAL JUSTICE INFORMATION SYSTEMS State and Local Criminal History Record Information Systems § 20.23 Documentation: Approval by OJARS. Within 90...

  6. XML: Solution for the integration of nuclear power plant data and technical documents

    International Nuclear Information System (INIS)

    Gordillo, F.

    2000-01-01

    Assuring proper operation of the systems that make up a nuclear power plant requires handling a massive amount of technical documents. This technical documentation, consisting mainly of system descriptions, operating and maintenance procedures, safety procedures, etc, presents particular characteristics, mainly: Great volume of information. High contents in figures and graphics. High reliability required. Multiple cross-references among documents. (Author)

  7. DOE-RL Integrated Safety Management System Description

    International Nuclear Information System (INIS)

    SHOOP, D.S.

    2000-01-01

    The purpose of this Integrated Safety Management System Description (ISMSD) is to describe the U.S. Department of Energy (DOE), Richland Operations Office (RL) ISMS as implemented through the RL Integrated Management System (RIMS). This ISMSD does not impose additional requirements but rather provides an overview describing how various parts of the ISMS fit together. Specific requirements for each of the core functions and guiding principles are established in other implementing processes, procedures, and program descriptions that comprise RIMS. RL is organized to conduct work through operating contracts; therefore, it is extremely difficult to provide an adequate ISMS description that only addresses RL functions. Of necessity, this ISMSD contains some information on contractor processes and procedures which then require RL approval or oversight. This ISMSD does not purport to contain a full description of the contractors' ISM System Descriptions

  8. DOE-RL Integrated Safety Management System Description

    CERN Document Server

    Shoop, D S

    2000-01-01

    The purpose of this Integrated Safety Management System Description (ISMSD) is to describe the U.S. Department of Energy (DOE), Richland Operations Office (RL) ISMS as implemented through the RL Integrated Management System (RIMS). This ISMSD does not impose additional requirements but rather provides an overview describing how various parts of the ISMS fit together. Specific requirements for each of the core functions and guiding principles are established in other implementing processes, procedures, and program descriptions that comprise RIMS. RL is organized to conduct work through operating contracts; therefore, it is extremely difficult to provide an adequate ISMS description that only addresses RL functions. Of necessity, this ISMSD contains some information on contractor processes and procedures which then require RL approval or oversight. This ISMSD does not purport to contain a full description of the contractors' ISM System Descriptions.

  9. ENDF/B summary documentation

    Energy Technology Data Exchange (ETDEWEB)

    Kinsey, R. (comp.)

    1979-07-01

    This publication provides a localized source of descriptions for the evaluations contained in the ENDF/B Library. The summary documentation presented is intended to be a more detailed description than the (File 1) comments contained in the computer readable data files, but not so detailed as the formal reports describing each ENDF/B evaluation. The summary documentations were written by the CSEWB (Cross Section Evaluation Working Group) evaluators and compiled by NNDC (National Nuclear Data Center). This edition includes documentation for materials found on ENDF/B Version V tapes 501 to 516 (General Purpose File) excluding tape 504. ENDF/B-V also includes tapes containing partial evaluations for the Special Purpose Actinide (521, 522), Dosimetry (531), Activation (532), Gas Production (533), and Fission Product (541-546) files. The materials found on these tapes are documented elsewhere. Some of the evaluation descriptions in this report contain cross sections or energy level information. (RWR)

  10. Critical issues in an electronic documentation system.

    Science.gov (United States)

    Weir, Charlene R; Nebeker, Jonathan R

    2007-10-11

    The Veterans Health Administration (VHA), of the U.S. Department of Veteran Affairs has instituted a medical record (EMR) that includes electronic documentation of all narrative components of the medical record. To support clinicians using the system, multiple efforts have been instituted to ease the creation of narrative reports. Although electronic documentation is easier to read and improves access to information, it also may create new and additional hazards for users. This study is the first step in a series of studies to evaluate the issues surrounding the creation and use of electronic documentation. Eighty-eight providers across multiple clinical roles were interviewed in 10 primary care sites in the VA system. Interviews were tape-recorded, transcribed and qualitatively analyzed for themes. In addition, specific questions were asked about perceived harm due to electronic documentation practices. Five themes relating to difficulties with electronic documentation were identified: 1) information overload; 2) hidden information; 3) lack of trust; 4) communication; 5) decision-making. Three providers reported that they knew of an incident where current documentation practices had caused patient harm and over 75% of respondents reported significant mis-trust of the system.

  11. Honeywell Modular Automation System Computer Software Documentation

    International Nuclear Information System (INIS)

    CUNNINGHAM, L.T.

    1999-01-01

    This document provides a Computer Software Documentation for a new Honeywell Modular Automation System (MAS) being installed in the Plutonium Finishing Plant (PFP). This system will be used to control new thermal stabilization furnaces in HA-211 and vertical denitration calciner in HC-230C-2

  12. Description of recommended non-thermal mixed waste treatment technologies: Version 1.0

    International Nuclear Information System (INIS)

    1995-08-01

    This document contains description of the technologies selected for inclusions in the Integrated Nonthermal Treatment Systems (INTS) Study. The purpose of these descriptions is to provide a more complete description of the INTS technologies. It supplements the summary descriptions of candidate nonthermal technologies that were considered for the INTS

  13. Description of recommended non-thermal mixed waste treatment technologies: Version 1.0

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-08-01

    This document contains description of the technologies selected for inclusions in the Integrated Nonthermal Treatment Systems (INTS) Study. The purpose of these descriptions is to provide a more complete description of the INTS technologies. It supplements the summary descriptions of candidate nonthermal technologies that were considered for the INTS.

  14. Detailed description of an SSAC at the facility level for research reactors

    International Nuclear Information System (INIS)

    Jones, R.J.

    1984-09-01

    The purpose of this document is to provide a detailed description of a system for the accounting for and control of nuclear material in a research reactor facility which can be used by a facility operator to establish his own system to comply with a national system for nuclear material accounting and control and to facilitate application of IAEA safeguards. The scope of this document is limited to descriptions of the following SSAC elements: (1) Nuclear Material Measurements; (2) Measurement Quality; (3) Records and Reports; (4) Physical Inventory Taking; (5) Material Balance Closing

  15. GlottoVis : Visualizing Language Endangerment and Documentation

    NARCIS (Netherlands)

    Castermans, T.H.A.; Speckmann, B.; Verbeek, K.A.B.; Westenberg, M.A.; Hammarström, H.

    2017-01-01

    We present GlottoVis, a system designed to visualize language endangerment as collected by UNESCO and descriptive status as collected by the Glottolog project. Glottolog records bibliographic data for the world’s (lesser known) languages. Languages are documented with increasing detail, but the

  16. Defense High Level Waste Disposal Container System Description Document

    International Nuclear Information System (INIS)

    2000-01-01

    The Defense High Level Waste Disposal Container System supports the confinement and isolation of waste within the Engineered Barrier System of the Monitored Geologic Repository (MGR). Disposal containers are loaded and sealed in the surface waste handling facilities, transferred to the underground through the accesses using a rail mounted transporter, and emplaced in emplacement drifts. The defense high level waste (HLW) disposal container provides long-term confinement of the commercial HLW and defense HLW (including immobilized plutonium waste forms (IPWF)) placed within disposable canisters, and withstands the loading, transfer, emplacement, and retrieval loads and environments. U.S. Department of Energy (DOE)-owned spent nuclear fuel (SNF) in disposable canisters may also be placed in a defense HLW disposal container along with commercial HLW waste forms, which is known as 'co-disposal'. The Defense High Level Waste Disposal Container System provides containment of waste for a designated period of time, and limits radionuclide release. The disposal container/waste package maintains the waste in a designated configuration, withstands maximum handling and rockfall loads, limits the individual canister temperatures after emplacement, resists corrosion in the expected handling and repository environments, and provides containment of waste in the event of an accident. Defense HLW disposal containers for HLW disposal will hold up to five HLW canisters. Defense HLW disposal containers for co-disposal will hold up to five HLW canisters arranged in a ring and one DOE SNF canister in the ring. Defense HLW disposal containers also will hold two Multi-Canister Overpacks (MCOs) and two HLW canisters in one disposal container. The disposal container will include outer and inner cylinders, outer and inner cylinder lids, and may include a canister guide. An exterior label will provide a means by which to identify the disposal container and its contents. Different materials

  17. A documentation tool for product configuration systems - improving the documentation task

    DEFF Research Database (Denmark)

    Hvam, Lars; Jensen, Klaes Ladeby

    2005-01-01

    's experience with the procedure and the hitherto empirical experience from companies having applied the procedure have revealed that there is a need for an IT-based docu-mentation tool to support the process of constructing product configuration systems. Time can be saved by letting a documentation tool handle......Configuration systems are increasingly applied to automate the configuration of complex products. A configuration system is an expert system designed to combine specified modules according to constraints. The constraints are stored as product data and rules in a product model, and one of the most...... essential tasks is thus to develop a complete and consistent product model which can reflect the actual product. A procedure for building product models has been developed at the Centre for Product Modelling (CPM), and the pro-cedure has been successfully applied in several industrial companies. CPM...

  18. Multiple sclerosis documentation system (MSDS): moving from documentation to management of MS patients.

    Science.gov (United States)

    Ziemssen, Tjalf; Kempcke, Raimar; Eulitz, Marco; Großmann, Lars; Suhrbier, Alexander; Thomas, Katja; Schultheiss, Thorsten

    2013-09-01

    The long disease duration of multiple sclerosis and the increasing therapeutic options require a individualized therapeutic approach which should be carefully documented over years of observation. To switch from MS documentation to an innovative MS management, new computer- and internet-based tools could be implemented as we could demonstrate with the novel computer-based patient management system "multiple sclerosis management system 3D" (MSDS 3D). MSDS 3D allows documentation and management of visit schedules and mandatory examinations via defined study modules by integration of data input from various sources (patients, attending physicians and MS nurses). It provides forms for the documentation of patient visits as well as clinical and diagnostic findings. Information can be collected via interactive touch screens. Specific modules allow the management of highly efficacious treatments as natalizumab or fingolimod. MSDS can be used to transfer the documented data to databases as, e.g. the registry of the German MS society or REGIMS. MSDS has already been implemented successfully in clinical practice and is currently being evaluated in a multicenter setting. High-quality management and documentation are crucial for improvements in clinical practice and research work.

  19. 48 CFR 811.104 - Use of brand name or equal purchase descriptions.

    Science.gov (United States)

    2010-10-01

    ... 48 Federal Acquisition Regulations System 5 2010-10-01 2010-10-01 false Use of brand name or equal purchase descriptions. 811.104 Section 811.104 Federal Acquisition Regulations System DEPARTMENT OF... Requirements Documents 811.104 Use of brand name or equal purchase descriptions. ...

  20. Software System for Vocal Rendering of Printed Documents

    Directory of Open Access Journals (Sweden)

    Marian DARDALA

    2008-01-01

    Full Text Available The objective of this paper is to present a software system architecture developed to render the printed documents in a vocal form. On the other hand, in the paper are described the software solutions that exist as software components and are necessary for documents processing as well as for multimedia device controlling used by the system. The usefulness of this system is for people with visual disabilities that can access the contents of documents without that they be printed in Braille system or to exist in an audio form.

  1. Wind system documentation

    Energy Technology Data Exchange (ETDEWEB)

    Froggatt, J.R.; Tatum, C.P.

    1993-01-15

    Atmospheric transport and diffusion models have been developed by the Environmental Technology Section (ETS) of the Savannah River Technology Center to calculate the location and concentration of toxic or radioactive materials during an accidental release at the Savannah River Site (SRS). The output from these models has been used to support initial on-site and off-site emergency response activities such as protective action decision making and field monitoring coordination. These atmospheric transport and diffusion models have been incorporated into an automated computer-based system called the (Weather Information and Display) System and linked to real-time meteorological and radiological monitoring instruments to provide timely information for these emergency response activities (Hunter, 1990). This report documents various aspects of the WIND system.

  2. ENDF/B summary documentation

    International Nuclear Information System (INIS)

    Garber, D.

    1975-10-01

    Descriptions of the evaluations contained in the ENDF/B library are given. The summary documentation presented is intended to be a more detailed description than the (File 1) comments contained in the computer-readable data files, but not so detailed as the formal reports describing each ENDF/B evaluation. The documentations were written by the CSEWG evaluators and compiled by NNCSC. Selected materials which comprise this volume include from 1 H to 244 Cm

  3. Use of an advanced document system in post-refuelling updating of nuclear power plant documentation

    International Nuclear Information System (INIS)

    Puech Suanzes, P.; Cortes Soler, M.

    1993-01-01

    This paper discusses the results of the extensive use of an advanced document system to update documentation prepared by traditional methods and affected by changes in the period between two plant refuellings. The implementation of a system for the capture, retrieval and storage of drawings using optical discs is part of a plan to modernize production and management tools and to thus achieve better control of document configuration. These processes are consequently optimized in that: 1. The deterioration of drawings is detained with the help of an identical, updated, legible, reliable support for all users. 2. The time required to update documentation is reduced. Given the large number of drawings, the implementation method should effectively combine costs and time. The document management tools ensure optical disc storage control so that from the moment a drawing resides in the system, any modification to it is made through the system utilities, thus ensuring quality and reducing schedules. The system described was used to update the electrical drawings of Almaraz Nuclear Power Plant. Changes made during the eighth refuelling of Unit I were incorporated and the time needed to issue the updated drawings was reduced by one month. (author)

  4. Uncanistered Spent Nuclear fuel Disposal Container System Description Document

    International Nuclear Information System (INIS)

    Pettit, N. E.

    2001-01-01

    The Uncanistered Spent Nuclear Fuel (SNF) Disposal Container System supports the confinement and isolation of waste within the Engineered Barrier System of the Monitored Geologic Repository (MGR). Disposal containers are loaded with intact uncanistered assemblies and/or individually canistered SNF assemblies and sealed in the surface waste handling facilities, transferred to the underground through the access drifts, and emplaced in emplacement drifts. The Uncanistered SNF Disposal Container provides long-term confinement of the commercial SNF placed inside, and withstands the loading, transfer, emplacement, and retrieval loads and environments. The Uncanistered SNF Disposal Container System provides containment of waste for a designated period of time, and limits radionuclide release. The disposal container maintains the waste in a designated configuration, withstands maximum handling and rockfall loads, limits the individual SNF assembly temperatures after emplacement, limits the introduction of moderator into the disposal container during the criticality control period, resists corrosion in the expected handling and repository environments, and provides containment of waste in the event of an accident

  5. Integrated system for automated financial document processing

    Science.gov (United States)

    Hassanein, Khaled S.; Wesolkowski, Slawo; Higgins, Ray; Crabtree, Ralph; Peng, Antai

    1997-02-01

    A system was developed that integrates intelligent document analysis with multiple character/numeral recognition engines in order to achieve high accuracy automated financial document processing. In this system, images are accepted in both their grayscale and binary formats. A document analysis module starts by extracting essential features from the document to help identify its type (e.g. personal check, business check, etc.). These features are also utilized to conduct a full analysis of the image to determine the location of interesting zones such as the courtesy amount and the legal amount. These fields are then made available to several recognition knowledge sources such as courtesy amount recognition engines and legal amount recognition engines through a blackboard architecture. This architecture allows all the available knowledge sources to contribute incrementally and opportunistically to the solution of the given recognition query. Performance results on a test set of machine printed business checks using the integrated system are also reported.

  6. System Documentation AS Basis For Company Business Process Improvement

    OpenAIRE

    Pelawi, Dewan

    2012-01-01

    Business process is an activity performed together to achieve business goals. Good business process will support the achievement of the organization’s plan to make profit for the company. In order to understand the business process, the business process needs to be documented and analyzed. The purpose of research is to make the system documentation as a basis to improve or complete the ongoing business process. The research method is system documentation. System documentation is a way to desc...

  7. Tank waste remediation system functions and requirements document

    Energy Technology Data Exchange (ETDEWEB)

    Carpenter, K.E

    1996-10-03

    This is the Tank Waste Remediation System (TWRS) Functions and Requirements Document derived from the TWRS Technical Baseline. The document consists of several text sections that provide the purpose, scope, background information, and an explanation of how this document assists the application of Systems Engineering to the TWRS. The primary functions identified in the TWRS Functions and Requirements Document are identified in Figure 4.1 (Section 4.0) Currently, this document is part of the overall effort to develop the TWRS Functional Requirements Baseline, and contains the functions and requirements needed to properly define the top three TWRS function levels. TWRS Technical Baseline information (RDD-100 database) included in the appendices of the attached document contain the TWRS functions, requirements, and architecture necessary to define the TWRS Functional Requirements Baseline. Document organization and user directions are provided in the introductory text. This document will continue to be modified during the TWRS life-cycle.

  8. Tank waste remediation system functions and requirements document

    International Nuclear Information System (INIS)

    Carpenter, K.E

    1996-01-01

    This is the Tank Waste Remediation System (TWRS) Functions and Requirements Document derived from the TWRS Technical Baseline. The document consists of several text sections that provide the purpose, scope, background information, and an explanation of how this document assists the application of Systems Engineering to the TWRS. The primary functions identified in the TWRS Functions and Requirements Document are identified in Figure 4.1 (Section 4.0) Currently, this document is part of the overall effort to develop the TWRS Functional Requirements Baseline, and contains the functions and requirements needed to properly define the top three TWRS function levels. TWRS Technical Baseline information (RDD-100 database) included in the appendices of the attached document contain the TWRS functions, requirements, and architecture necessary to define the TWRS Functional Requirements Baseline. Document organization and user directions are provided in the introductory text. This document will continue to be modified during the TWRS life-cycle

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

    International Nuclear Information System (INIS)

    IRWIN, J.J.

    1998-01-01

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

  10. Detailed description of an SSAC at the facility level for research laboratory facilities

    International Nuclear Information System (INIS)

    Jones, R.J.

    1985-08-01

    The purpose of this document is to provide a detailed description of a system for the accounting for and control of nuclear material in a research laboratory facility which can be used by a facility operator to establish his own system to comply with a national system for nuclear material accounting and control and to facilitate application of IAEA safeguards. The scope of this document is limited to descriptions of the following SSAC elements: (1) Nuclear Material Measurements; (2) Measurement Quality; (3) Records and Reports; (4) Physical Inventory Taking; (5) Material Balance Closing

  11. Recommended documentation for computer users at ANL

    Energy Technology Data Exchange (ETDEWEB)

    Heiberger, A.A.

    1992-04-01

    Recommended Documentation for Computer Users at ANL is for all users of the services available from the Argonne National Laboratory (ANL) Computing and Telecommunications Division (CTD). This document will guide you in selecting available documentation that will best fill your particular needs. Chapter 1 explains how to use this document to select documents and how to obtain them from the CTD Document Distribution Counter. Chapter 2 contains a table that categorizes available publications. Chapter 3 gives descriptions of the online DOCUMENT command for CMS, and VAX, and the Sun workstation. DOCUMENT allows you to scan for and order documentation that interests you. Chapter 4 lists publications by subject. Categories I and IX cover publications of a general nature and publications on telecommunications and networks respectively. Categories II, III, IV, V, VI, VII, VIII, and X cover publications on specific computer systems. Category XI covers publications on advanced scientific computing at Argonne. Chapter 5 contains abstracts for each publication, all arranged alphabetically. Chapter 6 describes additional publications containing bibliographies and master indexes that the user may find useful. The appendix identifies available computer systems, applications, languages, and libraries.

  12. Topology of Document Retrieval Systems.

    Science.gov (United States)

    Everett, Daniel M.; Cater, Steven C.

    1992-01-01

    Explains the use of a topological structure to examine the closeness between documents in retrieval systems and analyzes the topological structure of a vector-space model, a fuzzy-set model, an extended Boolean model, a probabilistic model, and a TIRS (Topological Information Retrieval System) model. Proofs for the results are appended. (17…

  13. Model documentation coal market module of the National Energy Modeling System

    International Nuclear Information System (INIS)

    1997-02-01

    This report documents the objectives and the conceptual and methodological approach used in the development of the Coal Production Submodule (CPS). It provides a description of the CPS for model analysts and the public. The Coal Market Module provides annual forecasts of prices, production, and consumption of coal

  14. Model documentation coal market module of the National Energy Modeling System

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-02-01

    This report documents the objectives and the conceptual and methodological approach used in the development of the Coal Production Submodule (CPS). It provides a description of the CPS for model analysts and the public. The Coal Market Module provides annual forecasts of prices, production, and consumption of coal.

  15. System design document for the INFLO prototype.

    Science.gov (United States)

    2014-03-01

    This report documents the high level System Design Document (SDD) for the prototype development and : demonstration of the Intelligent Network Flow Optimization (INFLO) application bundle, with a focus on the Speed : Harmonization (SPD-HARM) and Queu...

  16. 14 CFR 406.113 - Filing documents with the Docket Management System (DMS) and sending documents to the...

    Science.gov (United States)

    2010-01-01

    ... 14 Aeronautics and Space 4 2010-01-01 2010-01-01 false Filing documents with the Docket Management System (DMS) and sending documents to the administrative law judge and Assistant Chief Counsel for... Management System (DMS) and sending documents to the administrative law judge and Assistant Chief Counsel for...

  17. World energy projection system: Model documentation

    Science.gov (United States)

    1992-06-01

    The World Energy Project System (WEPS) is an accounting framework that incorporates projects from independently documented models and assumptions about the future energy intensity of economic activity (ratios of total energy consumption divided by gross domestic product) and about the rate of incremental energy requirements met by hydropower, geothermal, coal, and natural gas to produce projections of world energy consumption published annually by the Energy Information Administration (EIA) in the International Energy Outlook (IEO). Two independently documented models presented in Figure 1, the Oil Market Simulation (OMS) model and the World Integrated Nuclear Evaluation System (WINES), provide projections of oil and nuclear power consumption published in the IEO. Output from a third independently documented model, and the International Coal Trade Model (ICTM), is not published in the IEO but is used in WEPS as a supply check on projections of world coal consumption produced by WEPS and published in the IEO. A WEPS model of natural gas production documented in this report provides the same type of implicit supply check on the WEPS projections of world natural gas consumption published in the IEO. Two additional models are included in Figure 1, the OPEC Capacity model and the Non-OPEC Oil Production model. These WEPS models provide inputs to the OMS model and are documented in this report.

  18. World energy projection system: Model documentation

    International Nuclear Information System (INIS)

    1992-06-01

    The World Energy Project System (WEPS) is an accounting framework that incorporates projects from independently documented models and assumptions about the future energy intensity of economic activity (ratios of total energy consumption divided by gross domestic product) and about the rate of incremental energy requirements met by hydropower, geothermal, coal, and natural gas to produce projections of world energy consumption published annually by the Energy Information Administration (EIA) in the International Energy Outlook (IEO) (Figure 1). Two independently documented models presented in Figure 1, the Oil Market Simulation (OMS) model and the World Integrated Nuclear Evaluation System (WINES) provide projections of oil and nuclear power consumption published in the IEO. Output from a third independently documented model, and the International Coal Trade Model (ICTM), is not published in the IEO but is used in WEPS as a supply check on projections of world coal consumption produced by WEPS and published in the IEO. A WEPS model of natural gas production documented in this report provides the same type of implicit supply check on the WEPS projections of world natural gas consumption published in the IEO. Two additional models are included in Figure 1, the OPEC Capacity model and the Non-OPEC Oil Production model. These WEPS models provide inputs to the OMS model and are documented in this report

  19. Document control system as an integral part of RA documentation database application

    International Nuclear Information System (INIS)

    Steljic, M.M; Ljubenov, V.Lj. . E-mail address of corresponding author: milijanas@vin.bg.ac.yu; Steljic, M.M.)

    2005-01-01

    The decision about the final shutdown of the RA research reactor in Vinca Institute has been brought in 2002, and therefore the preparations for its decommissioning have begun. All activities are supervised by the International Atomic Energy Agency (IAEA), which also provides technical and experts' support. This paper describes the document control system is an integral part of the existing RA documentation database. (author)

  20. An Intelligent System for Document Retrieval in Distributed Office Environments.

    Science.gov (United States)

    Mukhopadhyay, Uttam; And Others

    1986-01-01

    MINDS (Multiple Intelligent Node Document Servers) is a distributed system of knowledge-based query engines for efficiently retrieving multimedia documents in an office environment of distributed workstations. By learning document distribution patterns and user interests and preferences during system usage, it customizes document retrievals for…

  1. DALIS: a computer-assisted document retrieval system for the FFTF

    International Nuclear Information System (INIS)

    Harves, W.G.

    1981-01-01

    The FFTF (Fast Flux Test Facility) is a liquid sodium cooled, fast flux reactor designed specifically for irradiation testing of fuels and components for liquid metal fast breeder reactors. The Department of Energy and the Nuclear Regulatory Commission require that all pertinent documentation for maintenance, operation, and safety of the FFTF be readily accessible and retrievable, both during initial startup and for the lifetime of the plant. That amounts to a lot of information which has to be retrievable. The indexing system finally developed is called the DALIS system, short for Document and Location Indexing System. This system was designed by an engineer (Michael Theo) for use by engineers. DALIS uses descriptiors and keywords to identify each document in the system. The descriptors give such information as document number, date of issuance of the document, the title, the originating organization, and the microfilm or hardcopy location of the document. The keywords are words or phrases that describe the content of the document and permit retrieval by means of a computer search for documents with the stated keywords

  2. Reconciling disparate information in continuity of care documents: Piloting a system to consolidate structured clinical documents.

    Science.gov (United States)

    Hosseini, Masoud; Jones, Josette; Faiola, Anthony; Vreeman, Daniel J; Wu, Huanmei; Dixon, Brian E

    2017-10-01

    Due to the nature of information generation in health care, clinical documents contain duplicate and sometimes conflicting information. Recent implementation of Health Information Exchange (HIE) mechanisms in which clinical summary documents are exchanged among disparate health care organizations can proliferate duplicate and conflicting information. To reduce information overload, a system to automatically consolidate information across multiple clinical summary documents was developed for an HIE network. The system receives any number of Continuity of Care Documents (CCDs) and outputs a single, consolidated record. To test the system, a randomly sampled corpus of 522 CCDs representing 50 unique patients was extracted from a large HIE network. The automated methods were compared to manual consolidation of information for three key sections of the CCD: problems, allergies, and medications. Manual consolidation of 11,631 entries was completed in approximately 150h. The same data were automatically consolidated in 3.3min. The system successfully consolidated 99.1% of problems, 87.0% of allergies, and 91.7% of medications. Almost all of the inaccuracies were caused by issues involving the use of standardized terminologies within the documents to represent individual information entries. This study represents a novel, tested tool for de-duplication and consolidation of CDA documents, which is a major step toward improving information access and the interoperability among information systems. While more work is necessary, automated systems like the one evaluated in this study will be necessary to meet the informatics needs of providers and health systems in the future. Copyright © 2017 Elsevier Inc. All rights reserved.

  3. IDAPS (Image Data Automated Processing System) System Description

    Science.gov (United States)

    1988-06-24

    This document describes the physical configuration and components used in the image processing system referred to as IDAPS (Image Data Automated ... Processing System). This system was developed by the Environmental Research Institute of Michigan (ERIM) for Eglin Air Force Base. The system is designed

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

    International Nuclear Information System (INIS)

    1995-01-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-09-22

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

  6. Regulatory systems-based licensing guidance documentation

    International Nuclear Information System (INIS)

    Delligatti, M.S.

    1991-01-01

    The US Nuclear Regulatory Commission (NRC) has developed a series of licensing guidance documents based on the regulatory requirements in Part 60 of Title 10 of the Code of Federal Regulations (10 CFR Part 60). This regulatory systems-based approach to licensing guidance documentation relies on the definition of the high-level waste repository in 10 CFR Part 60. A document which is important for the frame-work it gives to other programmatic licensing guidance is the Draft Regulatory Guide open-quotes Format and Content for the License Application for the High-Level Waste Repositoryclose quotes (FCRG). The FCRG describes a format and content acceptable to NRC for a high-level waste repository license application pursuant to the requirements of 10 CFR Part 60. Other licensing guidance documents will be compatible with the FCRG

  7. Classification process in a text document recommender system

    Directory of Open Access Journals (Sweden)

    Dan MUNTEANU

    2005-12-01

    Full Text Available This paper presents the classification process in a recommender system used for textual documents taken especially from web. The system uses in the classification process a combination of content filters, event filters and collaborative filters and it uses implicit and explicit feedback for evaluating documents.

  8. Description of surface systems. Preliminary site description. Forsmark area Version 1.2

    Energy Technology Data Exchange (ETDEWEB)

    Lindborg, Tobias [ed.

    2005-06-01

    Swedish Nuclear Fuel and Waste Management Co (SKB) started site investigations for a deep repository for spent nuclear fuel in 2002 at two different sites in Sweden, Forsmark and Oskarshamn. The investigations should provide necessary information for a license application aimed at starting underground exploration. For this reason, ecosystem data need to be interpreted and assessed into site descriptive models, which in turn are used for safety assessment studies and for environmental impact assessment. Descriptions of the surface system are also needed for further planning of the site investigations. This report describes the surface ecosystems of the Forsmark site (e.g. hydrology, Quaternary deposits, chemistry, vegetation, animals and the human land use). The ecosystem description is an integration of the site and its regional setting, covering the current state of the biosphere as well as the ongoing natural processes affecting the longterm development. Improving the descriptions is important during both the initial and the complete site investigation phase. Before starting of the initial phase in Forsmark, version 0 of the site descriptive model was developed. The results of the initial site investigation phase is compiled into a preliminary site description of Forsmark (version 1.2) in June 2005. This report provides the major input and background to the biosphere description, in the 1.2 version of the Forsmark site description. The basis for this interim version is quality-assured field data from the Forsmark sub area and regional area, available in the SKB SICADA, and GIS data bases as of July 31th 2004 as well as version 1.1 of the Site Descriptive Model. To achieve an ecosystem site description there is a need to develop discipline-specific models by interpreting and analysing primary data. The different discipline-specific models are then integrated into a system describing interactions and flows and stocks of matter between and within functional units in

  9. Description of surface systems. Preliminary site description. Forsmark area Version 1.2

    International Nuclear Information System (INIS)

    Lindborg, Tobias

    2005-06-01

    Swedish Nuclear Fuel and Waste Management Co (SKB) started site investigations for a deep repository for spent nuclear fuel in 2002 at two different sites in Sweden, Forsmark and Oskarshamn. The investigations should provide necessary information for a license application aimed at starting underground exploration. For this reason, ecosystem data need to be interpreted and assessed into site descriptive models, which in turn are used for safety assessment studies and for environmental impact assessment. Descriptions of the surface system are also needed for further planning of the site investigations. This report describes the surface ecosystems of the Forsmark site (e.g. hydrology, Quaternary deposits, chemistry, vegetation, animals and the human land use). The ecosystem description is an integration of the site and its regional setting, covering the current state of the biosphere as well as the ongoing natural processes affecting the longterm development. Improving the descriptions is important during both the initial and the complete site investigation phase. Before starting of the initial phase in Forsmark, version 0 of the site descriptive model was developed. The results of the initial site investigation phase is compiled into a preliminary site description of Forsmark (version 1.2) in June 2005. This report provides the major input and background to the biosphere description, in the 1.2 version of the Forsmark site description. The basis for this interim version is quality-assured field data from the Forsmark sub area and regional area, available in the SKB SICADA, and GIS data bases as of July 31th 2004 as well as version 1.1 of the Site Descriptive Model. To achieve an ecosystem site description there is a need to develop discipline-specific models by interpreting and analysing primary data. The different discipline-specific models are then integrated into a system describing interactions and flows and stocks of matter between and within functional units in

  10. Maury Documentation

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — Supporting documentation for the Maury Collection of marine observations. Includes explanations from Maury himself, as well as guides and descriptions by the U.S....

  11. ARCHITECTURE SOFTWARE SOLUTION TO SUPPORT AND DOCUMENT MANAGEMENT QUALITY SYSTEM

    Directory of Open Access Journals (Sweden)

    Milan Eric

    2010-12-01

    Full Text Available One of the basis of a series of standards JUS ISO 9000 is quality system documentation. An architecture of the quality system documentation depends on the complexity of business system. An establishment of an efficient management documentation of system of quality is of a great importance for the business system, as well as in the phase of introducing the quality system and in further stages of its improvement. The study describes the architecture and capability of software solutions to support and manage the quality system documentation in accordance with the requirements of standards ISO 9001:2001, ISO 14001:2005 HACCP etc.

  12. Model documentation: Natural Gas Transmission and Distribution Model of the National Energy Modeling System; Volume 1

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1994-02-24

    The Natural Gas Transmission and Distribution Model (NGTDM) is a component of the National Energy Modeling System (NEMS) used to represent the domestic natural gas transmission and distribution system. NEMS is the third in a series of computer-based, midterm energy modeling systems used since 1974 by the Energy Information Administration (EIA) and its predecessor, the Federal Energy Administration, to analyze domestic energy-economy markets and develop projections. This report documents the archived version of NGTDM that was used to produce the natural gas forecasts used in support of the Annual Energy Outlook 1994, DOE/EIA-0383(94). The purpose of this report is to provide a reference document for model analysts, users, and the public that defines the objectives of the model, describes its basic design, provides detail on the methodology employed, and describes the model inputs, outputs, and key assumptions. It is intended to fulfill the legal obligation of the EIA to provide adequate documentation in support of its models (Public Law 94-385, Section 57.b.2). This report represents Volume 1 of a two-volume set. (Volume 2 will report on model performance, detailing convergence criteria and properties, results of sensitivity testing, comparison of model outputs with the literature and/or other model results, and major unresolved issues.) Subsequent chapters of this report provide: (1) an overview of the NGTDM (Chapter 2); (2) a description of the interface between the National Energy Modeling System (NEMS) and the NGTDM (Chapter 3); (3) an overview of the solution methodology of the NGTDM (Chapter 4); (4) the solution methodology for the Annual Flow Module (Chapter 5); (5) the solution methodology for the Distributor Tariff Module (Chapter 6); (6) the solution methodology for the Capacity Expansion Module (Chapter 7); (7) the solution methodology for the Pipeline Tariff Module (Chapter 8); and (8) a description of model assumptions, inputs, and outputs (Chapter 9).

  13. Guidelines for Description

    NARCIS (Netherlands)

    Links, P.; Horsman, Peter; Kühnel, Karsten; Priddy, M.; Reijnhoudt, Linda; Merenmies, Mark

    2013-01-01

    The Guidelines follow the conceptual metadata model (deliverable 17.2). They include guidelines for description of collection-holding institutions, document collections, organisations, personalities, events, camps and ghettos. As much as possible the guidelines comply with the descriptive standards

  14. 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

  15. Defense High Level Waste Disposal Container System Description Document

    International Nuclear Information System (INIS)

    Pettit, N. E.

    2001-01-01

    The Defense High Level Waste Disposal Container System supports the confinement and isolation of waste within the Engineered Barrier System of the Monitored Geologic Repository (MGR). Disposal containers are loaded and sealed in the surface waste handling facilities, transferred to the underground through the accesses using a rail mounted transporter, and emplaced in emplacement drifts. The defense high level waste (HLW) disposal container provides long-term confinement of the commercial HLW and defense HLW (including immobilized plutonium waste forms [IPWF]) placed within disposable canisters, and withstands the loading, transfer, emplacement, and retrieval loads and environments. US Department of Energy (DOE)-owned spent nuclear fuel (SNF) in disposable canisters may also be placed in a defense HLW disposal container along with commercial HLW waste forms, which is known as co-disposal. The Defense High Level Waste Disposal Container System provides containment of waste for a designated period of time, and limits radionuclide release. The disposal container/waste package maintains the waste in a designated configuration, withstands maximum handling and rockfall loads, limits the individual canister temperatures after emplacement, resists corrosion in the expected handling and repository environments, and provides containment of waste in the event of an accident. Defense HLW disposal containers for HLW disposal will hold up to five HLW canisters. Defense HLW disposal containers for co-disposal will hold up to five HLW canisters arranged in a ring and one DOE SNF canister inserted in the center and/or one or more DOE SNF canisters displacing a HLW canister in the ring. Defense HLW disposal containers also will hold two Multi-Canister Overpacks (MCOs) and two HLW canisters in one disposal container. The disposal container will include outer and inner cylinders, outer and inner cylinder lids, and may include a canister guide. An exterior label will provide a means by

  16. 48 CFR 811.104-70 - Brand name or equal purchase descriptions.

    Science.gov (United States)

    2010-10-01

    ... 48 Federal Acquisition Regulations System 5 2010-10-01 2010-10-01 false Brand name or equal... Requirements Documents 811.104-70 Brand name or equal purchase descriptions. (a) The specification writer may use purchase descriptions that contain references to one or more brand name products only in...

  17. Nuclear Computerized Library for Assessing Reactor Reliability (NUCLARR): Summary description

    International Nuclear Information System (INIS)

    Gertman, D.I.; Gilmore, W.E.; Galyean, W.J.; Groh, M.R.; Gentillon, C.D.; Gilbert, B.G.; Reece, W.J.

    1990-05-01

    The Nuclear Computerized Library for Assessing Reactor Reliability (NUCLARR) is an automate data base management system for storing and processing human error probability and hardware component failure rate data. The NUCLARR system software resides on an IBM (or compatible) personal microcomputer. NUCLARR can be accessed by the end user to furnish data suitable for input in human and/or hardware reliability analysis to support a variety of risk assessment activities. The NUCLARR system is documented in a five-volume series of reports. This document Volume 1, of this series is the Summary Description, which presents an overview of the data management system, including a description of data collection, data qualification, data structure, and taxonomies. Programming activities, procedures for processing data, a user's guide, and hard copy data manual are presented in Volumes 2 through 5, NUREG/CR-4639

  18. Title List of documents made publicly available

    International Nuclear Information System (INIS)

    1982-05-01

    This document contains descriptions of the information received and generated by the US NRC. This information includes: (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials and (2) nondocketed material received and generated by NRC pertinent to its role as a regulatory agency. As used here, docketed does not refer to court dockets; it refers to the system by which NRC maintains its regulatory records. This series of documents is indexed by a Personal Author Index, a Corporate Source Index, and a Report Number Index

  19. Detailed description of an SSAC at the facility level for mixed oxide fuel fabrication facilities

    International Nuclear Information System (INIS)

    Jones, R.J.

    1985-09-01

    The purpose of this document is to provide a detailed description of a system for the accounting for and control of nuclear material in a mixed oxide fuel fabrication facility which can be used by a facility operator to establish his own system to comply with a national system for nuclear material accounting and control and to facilitate application of IAEA safeguards. The scope of this document is limited to descriptions of the following SSAC elements: (1) Nuclear Material Measurements; (2) Measurement Quality; (3) Records and Reports; (4) Physical Inventory Taking; (5) Material Balance Closing

  20. Analysis of compatibility of current Czech initial documentation in the area of technical assurance of nuclear safety with the requirements of the EUR document

    International Nuclear Information System (INIS)

    Zdebor, J.; Zdebor, R.; Kratochvil, L.

    2001-11-01

    The publication is structured as follows: Description of existing documentation. General requirements, goals, principles and design principles: Documents being compared; Method of comparison; Results and partial evaluation of comparison of requirements between EUR and Czech regulations (basic goals and safety philosophy; quantitative safety objectives; basic design requirements; extended design requirements; external and internal threats; technical requirements; site conditions); Summary of the comparison of safety requirements. Comparison of requirements for the systems: Requirements for the nuclear reactor unit systems; Barrier systems (fuel system; reactor cooling system; containment system); Remaining systems (control systems; protection systems; coolant makeup and purification system; residual heat removal system; emergency cooling system; power systems); Common technical requirements for systems (technical requirements for systems; internal and external events). (P.A.)

  1. Automatic TLI recognition system. Part 1: System description

    Energy Technology Data Exchange (ETDEWEB)

    Partin, J.K.; Lassahn, G.D.; Davidson, J.R.

    1994-05-01

    This report describes an automatic target recognition system for fast screening of large amounts of multi-sensor image data, based on low-cost parallel processors. This system uses image data fusion and gives uncertainty estimates. It is relatively low cost, compact, and transportable. The software is easily enhanced to expand the system`s capabilities, and the hardware is easily expandable to increase the system`s speed. This volume gives a general description of the ATR system.

  2. The water reactor safety research project index: a description of the computerized system for its databank

    International Nuclear Information System (INIS)

    Della Loggia, E.; Primavera, R.

    1993-01-01

    The water reactor nuclear safety research project index has been published by the CEC for many years as a compilation of information on research projects relating to LWR nuclear safety. Since 1981, it has been published, alternatively with NEA (OECD), every second year. The number of contributions from research organizations in Community member countries has steadily increased and reached the level of 1 700 pages, in which more than 600 project descriptions have been collected. In 1988, for the first time, the document was produced using a computerized system developed with the assistance of the ISEI (Institute for Systems Engineering and Informatics) of JRC Ispra. The data have been stored in a computer based in Ispra. The system allows searching a preselected set of subjects through the information stored in the computer: it makes the updating of the projects description much easier and makes the retrieval of the data possible. This report presents a short description of the computerized system developed for the databank of the index. The computerized system presented in this report is structured in a quite general way and for that reason can be adapted very easily to every field where a databank needs to be constituted in order to collect extended information on several projects. (authors). 6 figs., 5 tabs., 5 refs

  3. Seamless Management of Paper and Electronic Documents for Task Knowledge Sharing

    Science.gov (United States)

    Kojima, Hiroyuki; Iwata, Ken

    Due to the progress of Internet technology and the increase of distributed information on networks, the present knowledge management has been based more and more on the performance of various experienced users. In addition to the increase of electronic documents, the use of paper documents has not been reduced because of their convenience. This paper describes a method of tracking paper document locations and contents using radio frequency identification (RFID) technology. This research also focuses on the expression of a task process and the seamless structuring of related electronic and paper documents as a result of task knowledge formalization using information organizing. A system is proposed here that implements information organization for both Web documents and paper documents with the task model description and RFID technology. Examples of a prototype system are also presented.

  4. 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

  5. HANFORD TANK WASTE OPERATIONS SIMULATOR VERSION DESCRIPTION DOCUMENT

    International Nuclear Information System (INIS)

    ALLEN, G.K.

    2003-01-01

    This document describes the software version controls established for the Hanford Tank Waste Operations Simulator (HTWOS). It defines: the methods employed to control the configuration of HTWOS; the version of each of the 26 separate modules for the version 1.0 of HTWOS; the numbering rules for incrementing the version number of each module; and a requirement to include module version numbers in each case results documentation. Version 1.0 of HTWOS is the first version under formal software version control. HTWOS contains separate revision numbers for each of its 26 modules. Individual module version numbers do not reflect the major release HTWOS configured version number

  6. 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

  7. Rancang Bangun Document Management System Untuk Mengelola Dokumen Standart Operational Procedure

    Directory of Open Access Journals (Sweden)

    I Putu Susila Handika

    2017-09-01

    Standard Operational Procedure (SOP is one important document in a company because it is useful to improve the quality of the company. PT. Global Retailindo Pratama is one of the companies engaged in retail that using standard of quality management ISO 9001: 2008. Currently the management of SOP documents at PT. Global Retailindo Pratama still use manual way. Manual way cause some problems such as the search process and document distribution process takes quite a long time. This research aims to design and build Document Management System to manage SOP documents. The system development model used in this research is prototyping model. This application is built in web-based with PHP as programming language. Testing the application using Blak Box Testing and Usability Testing shows that the Document Management System can run in accordance with the needs and can be used easily so that the process of document management SOP becomes faster. Keywords: Document Management System, Standart Operational Procedure, Information System, PHP.

  8. General Controls Over the Electronic Document Access System

    National Research Council Canada - National Science Library

    2000-01-01

    ...) system as part of the DoD Paper-Free Contracting Initiative. EDA contributes to the initiative by digitizing paper documents and offering web-based read-only access to official contracting, finance and accounting documents...

  9. AHTR Refueling Systems and Process Description

    Energy Technology Data Exchange (ETDEWEB)

    Varma, V.K.; Holcomb, D.E.; Bradley, E.C.; Zaharia, N.M.; Cooper, E.J.

    2012-07-15

    The Advanced High-Temperature Reactor (AHTR) is a design concept for a central station-type [1500 MW(e)] Fluoride salt–cooled High-temperature Reactor (FHR) that is currently undergoing development by Oak Ridge National Laboratory for the US. Department of Energy, Office of Nuclear Energy’s Advanced Reactor Concepts program. FHRs, by definition, feature low-pressure liquid fluoride salt cooling, coated-particle fuel, a high-temperature power cycle, and fully passive decay heat rejection. The overall goal of the AHTR development program is to demonstrate the technical feasibility of FHRs as low-cost, large-size power producers while maintaining full passive safety. The AHTR is approaching a preconceptual level of maturity. An initial integrated layout of its major systems, structures, and components (SSCs), and an initial, high-level sequence of operations necessary for constructing and operating the plant is nearing completion. An overview of the current status of the AHTR concept has been recently published [1], and a report providing a more detailed overview of the AHTR structures and mechanical systems is currently in preparation. This report documents the refueling components and processes envisioned at this early development phase. The report is limited to the refueling aspects of the AHTR and does not include overall reactor or power plant design information. The report, however, does include a description of the materials envisioned for the various components and the instrumentation necessary to control the refueling process. The report begins with an overview of the refueling strategy. Next a mechanical description of the AHTR fuel assemblies and core is provided. The reactor vessel upper assemblies are then described. Following this the refueling path structures and the refueling mechanisms and components are described. The sequence of operations necessary to fuel and defuel the reactor is then discussed. The report concludes with a discussion of the

  10. AHTR Refueling Systems and Process Description

    Energy Technology Data Exchange (ETDEWEB)

    Varma, Venugopal Koikal [ORNL; Holcomb, David Eugene [ORNL; Bradley, Eric Craig [ORNL; Zaharia, Nathaniel M [ORNL; Cooper, Eliott J [ORNL

    2012-07-01

    The Advanced High-Temperature Reactor (AHTR) is a design concept for a central station-type [1500 MW(e)] Fluoride salt-cooled High-temperature Reactor (FHR) that is currently undergoing development by Oak Ridge National Laboratory for the US. Department of Energy, Office of Nuclear Energy's Advanced Reactor Concepts program. FHRs, by definition, feature low-pressure liquid fluoride salt cooling, coated-particle fuel, a high-temperature power cycle, and fully passive decay heat rejection. The overall goal of the AHTR development program is to demonstrate the technical feasibility of FHRs as low-cost, large-size power producers while maintaining full passive safety. The AHTR is approaching a preconceptual level of maturity. An initial integrated layout of its major systems, structures, and components (SSCs), and an initial, high-level sequence of operations necessary for constructing and operating the plant is nearing completion. An overview of the current status of the AHTR concept has been recently published and a report providing a more detailed overview of the AHTR structures and mechanical systems is currently in preparation. This report documents the refueling components and processes envisioned at this early development phase. The report is limited to the refueling aspects of the AHTR and does not include overall reactor or power plant design information. The report, however, does include a description of the materials envisioned for the various components and the instrumentation necessary to control the refueling process. The report begins with an overview of the refueling strategy. Next a mechanical description of the AHTR fuel assemblies and core is provided. The reactor vessel upper assemblies are then described. Following this the refueling path structures and the refueling mechanisms and components are described. The sequence of operations necessary to fuel and defuel the reactor is then discussed. The report concludes with a discussion of the

  11. An Introduction to the Nuclear Document Crawling System

    International Nuclear Information System (INIS)

    Tae, Jae Woong; Yoon, Sung Ho; Shin, Dong Hoon

    2016-01-01

    The NSG(Nuclear Suppliers Group) guidelines state that controls on 'technology' transfer do not apply to information 'in the public domain' or to 'basic scientific research'. According to the guidelines, 'basic scientific research' is an experimental or theoretical work undertaken principally to acquire new knowledge of the fundamental principles of phenomena and observable facts, not primarily directed towards a specific practical aim or objective. 'Technology in the public domain' means 'technology' or 'software' that has been made available without restrictions upon its further dissemination. It is a difficult problem to determine whether a document is in the public domain or it is a basic scientific research because its criteria are ambiguous and unclear. In this paper, we introduce an approach using documents on the web and a system to manage electronic documents on the web. In this paper, we proposed an approach to determine whether a document is open to public or it is a basic scientific research and we developed the document crawling system to collect open documents on the web. We can take open documents into a review process in a new way. It supports to prevent reviewers from classifying an open document into a strategic technology. It is expected to improve reliability of classification results

  12. An Introduction to the Nuclear Document Crawling System

    Energy Technology Data Exchange (ETDEWEB)

    Tae, Jae Woong; Yoon, Sung Ho; Shin, Dong Hoon [Korea Institute of Nuclear Nonproliferation and Control, Daejeon (Korea, Republic of)

    2016-05-15

    The NSG(Nuclear Suppliers Group) guidelines state that controls on 'technology' transfer do not apply to information 'in the public domain' or to 'basic scientific research'. According to the guidelines, 'basic scientific research' is an experimental or theoretical work undertaken principally to acquire new knowledge of the fundamental principles of phenomena and observable facts, not primarily directed towards a specific practical aim or objective. 'Technology in the public domain' means 'technology' or 'software' that has been made available without restrictions upon its further dissemination. It is a difficult problem to determine whether a document is in the public domain or it is a basic scientific research because its criteria are ambiguous and unclear. In this paper, we introduce an approach using documents on the web and a system to manage electronic documents on the web. In this paper, we proposed an approach to determine whether a document is open to public or it is a basic scientific research and we developed the document crawling system to collect open documents on the web. We can take open documents into a review process in a new way. It supports to prevent reviewers from classifying an open document into a strategic technology. It is expected to improve reliability of classification results.

  13. BASIC Instructional Program: System Documentation.

    Science.gov (United States)

    Dageforde, Mary L.

    This report documents the BASIC Instructional Program (BIP), a "hands-on laboratory" that teaches elementary programming in the BASIC language, as implemented in the MAINSAIL language, a machine-independent revision of SAIL which should facilitate implementation of BIP on other computing systems. Eight instructional modules which make up…

  14. Integration of electronic document management system with other systems in a company

    OpenAIRE

    Pintar, Matej

    2016-01-01

    This master's thesis presents specific model of integration between electronic document management system and other systems in a medium-sized company in Slovenia. The introduction part of the thesis begins with theoretical basis of the research, which is the integration of computer systems. The introduction part is folowed by presentation of a concrete electronic document management system EBA DMS. Central part of the master's thesis presents different methods of integration of electronic doc...

  15. Tank Waste Remediation System Projects Document Control Plan

    International Nuclear Information System (INIS)

    Slater, G.D.; Halverson, T.G.

    1994-01-01

    The purpose of this Tank Waste Remediation System Projects Document Control Plan is to provide requirements and responsibilities for document control for the Hanford Waste Vitrification Plant (HWVP) Project and the Initial Pretreatment Module (IPM) Project

  16. Three-dimensional measurement system for crime scene documentation

    Science.gov (United States)

    Adamczyk, Marcin; Hołowko, Elwira; Lech, Krzysztof; Michoński, Jakub; MÄ czkowski, Grzegorz; Bolewicki, Paweł; Januszkiewicz, Kamil; Sitnik, Robert

    2017-10-01

    Three dimensional measurements (such as photogrammetry, Time of Flight, Structure from Motion or Structured Light techniques) are becoming a standard in the crime scene documentation process. The usage of 3D measurement techniques provide an opportunity to prepare more insightful investigation and helps to show every trace in the context of the entire crime scene. In this paper we would like to present a hierarchical, three-dimensional measurement system that is designed for crime scenes documentation process. Our system reflects the actual standards in crime scene documentation process - it is designed to perform measurement in two stages. First stage of documentation, the most general, is prepared with a scanner with relatively low spatial resolution but also big measuring volume - it is used for the whole scene documentation. Second stage is much more detailed: high resolution but smaller size of measuring volume for areas that required more detailed approach. The documentation process is supervised by a specialised application CrimeView3D, that is a software platform for measurements management (connecting with scanners and carrying out measurements, automatic or semi-automatic data registration in the real time) and data visualisation (3D visualisation of documented scenes). It also provides a series of useful tools for forensic technicians: virtual measuring tape, searching for sources of blood spatter, virtual walk on the crime scene and many others. In this paper we present our measuring system and the developed software. We also provide an outcome from research on metrological validation of scanners that was performed according to VDI/VDE standard. We present a CrimeView3D - a software-platform that was developed to manage the crime scene documentation process. We also present an outcome from measurement sessions that were conducted on real crime scenes with cooperation with Technicians from Central Forensic Laboratory of Police.

  17. B-Plant Canyon Ventilation Control System Description; FINAL

    International Nuclear Information System (INIS)

    MCDANIEL, K.S.

    1999-01-01

    Project W-059 installed a new B Plant Canyon Ventilation System. Monitoring and control of the system is implemented by the Canyon Ventilation Control System (CVCS). This document describes the CVCS system components which include a Programmable Logic Controller (PLC) coupled with an Operator Interface Unit (OIU) and application software. This document also includes an Alarm Index specifying the setpoints and technical basis for system analog and digital alarms

  18. Predicate Argument Structure Analysis for Use Case Description Modeling

    Science.gov (United States)

    Takeuchi, Hironori; Nakamura, Taiga; Yamaguchi, Takahira

    In a large software system development project, many documents are prepared and updated frequently. In such a situation, support is needed for looking through these documents easily to identify inconsistencies and to maintain traceability. In this research, we focus on the requirements documents such as use cases and consider how to create models from the use case descriptions in unformatted text. In the model construction, we propose a few semantic constraints based on the features of the use cases and use them for a predicate argument structure analysis to assign semantic labels to actors and actions. With this approach, we show that we can assign semantic labels without enhancing any existing general lexical resources such as case frame dictionaries and design a less language-dependent model construction architecture. By using the constructed model, we consider a system for quality analysis of the use cases and automated test case generation to keep the traceability between document sets. We evaluated the reuse of the existing use cases and generated test case steps automatically with the proposed prototype system from real-world use cases in the development of a system using a packaged application. Based on the evaluation, we show how to construct models with high precision from English and Japanese use case data. Also, we could generate good test cases for about 90% of the real use cases through the manual improvement of the descriptions based on the feedback from the quality analysis system.

  19. 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

  20. Recommended documentation for computer users at ANL. Revision 3

    Energy Technology Data Exchange (ETDEWEB)

    Heiberger, A.A.

    1992-04-01

    Recommended Documentation for Computer Users at ANL is for all users of the services available from the Argonne National Laboratory (ANL) Computing and Telecommunications Division (CTD). This document will guide you in selecting available documentation that will best fill your particular needs. Chapter 1 explains how to use this document to select documents and how to obtain them from the CTD Document Distribution Counter. Chapter 2 contains a table that categorizes available publications. Chapter 3 gives descriptions of the online DOCUMENT command for CMS, and VAX, and the Sun workstation. DOCUMENT allows you to scan for and order documentation that interests you. Chapter 4 lists publications by subject. Categories I and IX cover publications of a general nature and publications on telecommunications and networks respectively. Categories II, III, IV, V, VI, VII, VIII, and X cover publications on specific computer systems. Category XI covers publications on advanced scientific computing at Argonne. Chapter 5 contains abstracts for each publication, all arranged alphabetically. Chapter 6 describes additional publications containing bibliographies and master indexes that the user may find useful. The appendix identifies available computer systems, applications, languages, and libraries.

  1. Descriptions and diagrams of the primary and annulus ventilation systems of the double-shell tank farms as of January 1988

    International Nuclear Information System (INIS)

    Blackman, A.E.; Waters, E.D.

    1994-01-01

    This document is a compilation of information describing the ventilation systems of the Double-Shell Tank farms (214-AN, -AP, -AW, -AW, -AY, -AZ, and -SY). A general description of the primary tank and annulus ventilation systems is given along with specific information on the high efficiency particulate air (HEPA) filters, condensers, preheaters, exhaust fans, and piping. This information is considered to be current as of January 1988. 38 refs, 20 figs, 30 tabs

  2. An Automated System for the Maintenance of Multiform Documentation

    Science.gov (United States)

    Rousseau, Bertrand; Ruggier, Mario; Smith, Matthiew

    Software documentation for the user often exists in several forms including paper, electronic, on-line help, etc. We have build a system to help with the writing and maintenance of such kinds of documentation which relies on the FrameMaker product. As an example, we show how it is used to maintain the ADAMO documentation, delivered in 4 incarnations on paper, WWW hypertext, KUIP and running examples. The use of the system results in both time saving and quality improvements.

  3. INFORMATION SYSTEM OF AUTOMATION OF PREPARATION EDUCATIONAL PROCESS DOCUMENTS

    Directory of Open Access Journals (Sweden)

    V. A. Matyushenko

    2016-01-01

    Full Text Available Information technology is rapidly conquering the world, permeating all spheres of human activity. Education is not an exception. An important direction of information of education is the development of university management systems. Modern information systems improve and facilitate the management of all types of activities of the institution. The purpose of this paper is development of system, which allows automating process of formation of accounting documents. The article describes the problem of preparation of the educational process documents. Decided to project and create the information system in Microsoft Access environment. The result is four types of reports obtained by using the developed system. The use of this system now allows you to automate the process and reduce the effort required to prepare accounting documents. All reports was implement in Microsoft Excel software product and can be used for further analysis and processing.

  4. Development of digital library system on regulatory documents for nuclear power plants

    International Nuclear Information System (INIS)

    Lee, K. H.; Kim, K. J.; Yoon, Y. H.; Kim, M. W.; Lee, J. I.

    2001-01-01

    The main objective of this study is to establish nuclear regulatory document retrieval system based on internet. With the advancement of internet and information processing technology, information management patterns are going through a new paradigm. Getting along the current of the time, it is general tendency to transfer paper-type documents into electronic-type documents through document scanning and indexing. This system consists of nuclear regulatory documents, nuclear safety documents, digital library, and information system with index and full text

  5. The standard calibration instrument automation system for the atomic absorption spectrophotometer. Part 3: Program documentation

    Science.gov (United States)

    Ryan, D. P.; Roth, G. S.

    1982-04-01

    Complete documentation of the 15 programs and 11 data files of the EPA Atomic Absorption Instrument Automation System is presented. The system incorporates the following major features: (1) multipoint calibration using first, second, or third degree regression or linear interpolation, (2) timely quality control assessments for spiked samples, duplicates, laboratory control standards, reagent blanks, and instrument check standards, (3) reagent blank subtraction, and (4) plotting of calibration curves and raw data peaks. The programs of this system are written in Data General Extended BASIC, Revision 4.3, as enhanced for multi-user, real-time data acquisition. They run in a Data General Nova 840 minicomputer under the operating system RDOS, Revision 6.2. There is a functional description, a symbol definitions table, a functional flowchart, a program listing, and a symbol cross reference table for each program. The structure of every data file is also detailed.

  6. MPEG-7-based description infrastructure for an audiovisual content analysis and retrieval system

    Science.gov (United States)

    Bailer, Werner; Schallauer, Peter; Hausenblas, Michael; Thallinger, Georg

    2005-01-01

    We present a case study of establishing a description infrastructure for an audiovisual content-analysis and retrieval system. The description infrastructure consists of an internal metadata model and access tool for using it. Based on an analysis of requirements, we have selected, out of a set of candidates, MPEG-7 as the basis of our metadata model. The openness and generality of MPEG-7 allow using it in broad range of applications, but increase complexity and hinder interoperability. Profiling has been proposed as a solution, with the focus on selecting and constraining description tools. Semantic constraints are currently only described in textual form. Conformance in terms of semantics can thus not be evaluated automatically and mappings between different profiles can only be defined manually. As a solution, we propose an approach to formalize the semantic constraints of an MPEG-7 profile using a formal vocabulary expressed in OWL, which allows automated processing of semantic constraints. We have defined the Detailed Audiovisual Profile as the profile to be used in our metadata model and we show how some of the semantic constraints of this profile can be formulated using ontologies. To work practically with the metadata model, we have implemented a MPEG-7 library and a client/server document access infrastructure.

  7. Detailed description of an SSAC at the facility level for on-load refueled power reactor facilities

    International Nuclear Information System (INIS)

    Jones, R.J.

    1985-11-01

    The purpose of this document is to provide a detailed description of a system for the accounting for and control of nuclear material in an on-load refueled power reactor facility which can be used by a facility operator to establish his own system to comply with a national system for nuclear material accounting and control and to facilitate application of IAEA safeguards. The scope of this document is limited to descriptions of the following SSAC elements: (1) Nuclear Material Measurements; (2) Measurement Quality; (3) Records and Reports; (4) Physical Inventory Taking; (5) Material Balance Closing

  8. 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...

  9. An electronic regulatory document management system for a clinical trial network.

    Science.gov (United States)

    Zhao, Wenle; Durkalski, Valerie; Pauls, Keith; Dillon, Catherine; Kim, Jaemyung; Kolk, Deneil; Silbergleit, Robert; Stevenson, Valerie; Palesch, Yuko

    2010-01-01

    A computerized regulatory document management system has been developed as a module in a comprehensive Clinical Trial Management System (CTMS) designed for an NIH-funded clinical trial network in order to more efficiently manage and track regulatory compliance. Within the network, several institutions and investigators are involved in multiple trials, and each trial has regulatory document requirements. Some of these documents are trial specific while others apply across multiple trials. The latter causes a possible redundancy in document collection and management. To address these and other related challenges, a central regulatory document management system was designed. This manuscript shares the design of the system as well as examples of it use in current studies. Copyright (c) 2009 Elsevier Inc. All rights reserved.

  10. 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.

  11. Integrated Management System, Configuration and Document Control for Research Reactors

    International Nuclear Information System (INIS)

    Steynberg, B.J.; Bruyn, J.F. du

    2017-01-01

    An integrated management system is a single management framework establishing all the processes necessary for the organisation to address all its goals and objectives. Very often only quality, environment and health & safety goals are included when referred to an integrated management system. However, within the research reactor environment such system should include goals pertinent to economic, environmental, health, operational, quality, safeguards, safety, security, and social considerations. One of the important objectives of an integrated management is to create the environment for a healthy safety culture. Configuration management is a disciplined process that involves both management and technical direction to establish and document the design requirements and the physical configuration of the research reactor and to ensure that they remain consistent with each other and the documentation. Configuration is the combination of the physical, functional, and operational characteristics of the structures, systems, and components (SSCs) or parts of the research reactor, operation, or activity. The basic objectives and general principles of configuration management are the same for all research reactors. The objectives of configuration management are to: a) Establish consistency among design requirements, physical configuration, and documentation (including analyses, drawings, and procedures) for the research reactor; b) Maintain this consistency throughout the life of the research reactor, particularly as changes are being made; and c) Retain confidence in the safety of the research reactor. The key elements needed to manage the configuration of research reactors are design requirements, work control, change control, document control, and configuration management assessments. The objective of document control is to ensure that only the most recently approved versions of documents are used in the process of operating, maintaining, and modifying the research reactor

  12. Title list of documents made publicly available

    International Nuclear Information System (INIS)

    1994-06-01

    The Title List of Documents Made Publicly Available is a monthly publication. It contains descriptions of the information received and generated by the US Nuclear Regulatory Commission (NRC). This information includes (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials and (2) nondocketed material received and generated by NRC pertinent to its role as a regulatory agency. As used here, docketed does not refer to Court dockets; it refers to the system by which NRC maintains its regulatory records. This series of documents is indexed by a Personal Author Index, a Corporate Source Index, and a Report Number Index

  13. Title list of documents made publicly available

    International Nuclear Information System (INIS)

    1982-03-01

    The Title List of Documents Made Publicly Available is a monthly publication. It contains descriptions of the information received and generated by the US Nuclear Regulatory Commission (NRC). This information includes (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials and (2) nondocketed material received and generated by NRC pertinent to its role as a regulatory agency. As used here, docketed does not refer to Court dockets; it refers to the system by which NRC maintains its regulatory records. This series of documents is indexed by a Personal Author Index, a Corporate Source Index, and a Report Number Index

  14. IDC Re-Engineering Phase 2 System Specification Document Version 1.5

    Energy Technology Data Exchange (ETDEWEB)

    Satpathi, Meara Allena [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Burns, John F. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Harris, James M. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2017-01-01

    This document contains the system specifications derived to satisfy the system requirements found in the IDC System Requirements Document for the IDC Re-Engineering Phase 2 project. This System Specification Document (SSD) defines waveform data processing requirements for the International Data Centre (IDC) of the Comprehensive Nuclear Test Ban Treaty Organization (CTBTO). The routine processing includes characterization of events with the objective of screening out events considered to be consistent with natural phenomena or non-nuclear, man-made phenomena. This document does not address requirements concerning acquisition, processing and analysis of radionuclide data but does include requirements for the dissemination of radionuclide data and products.

  15. Theoretical and Practical Aspects of Logistic Quality Management System Documentation Development Process

    Directory of Open Access Journals (Sweden)

    Linas Šaulinskas

    2013-12-01

    Full Text Available This paper addresses aspects of logistics quality management system documentation development and suggests models for quality management system documentation development, documentation hierarchical systems and authorization approval. It also identifies logistic processes and a responsibilities model and a detailed document development and approval process that can be practically applied. Our results are based upon an analysis of advanced Lithuanian and foreign corporate business practices, a review of current literature and recommendations for quality management system standards.

  16. [Recommendations for the control of documents and the establishment of a documentary system].

    Science.gov (United States)

    Vinner, E

    2013-06-01

    The quality management system that must be implemented in a MBL to meet the requirements of the standard NF EN ISO 15189 is based, among other things, on the creation and use by staff of a documentary system approved and updated. This documentary system is constituted by external documents (standards, suppliers' documents...) and internal documents (quality manual, procedures, instructions, technical and quality recordings...). A procedure of the documentary system control must be formalized. The documentary system should be modeled in order to identify the various procedures to be drafted and the incurred risks in the case a document would be missing in this system. Each document must be indexed in a unique way and document management must be carried out rigorously. The use of document management software is a great help to manage the life cycle of documents.

  17. Continuous Release-Emergency Response Notification System and Priority Assessment Model: Model documentation

    International Nuclear Information System (INIS)

    1991-01-01

    The purpose of the model documentation is to provide a detailed description of the modeling and risk analysis procedures used in CR-ERNS/PAM to assist OSCs and other Superfund decision-makers in interpreting the system results. PAM is a screening-level model; to properly interpret PAM's outputs, the user must understand the limitations and uncertainties in the equations and data used to generate these results. Chapter 2 presents the system's fate and transport models and describes the assumptions associated with these equations. Chapter 3 describes PAM's auxiliary data bases and provides the source(s) of each parameter and the methods by which values were selected. Chapter 4 explains the methods and exposure assumptions used to estimate exposures to hazardous substances and to evaluate the risks and hazards associated with these exposures. Chapter 5 presents examples of reports generated by PAM and explains the meaning of the 'flags' assigned to hazardous substances, media, and facilities. Appendix A contains versions of the fate and transport equations used for radionuclides. Appendix B contains copies of PAM's reports

  18. Reliability and reproducibility of subaxial cervical injury description system: a standardized nomenclature schema.

    Science.gov (United States)

    Bono, Christopher M; Schoenfeld, Andrew; Gupta, Giri; Harrop, James S; Anderson, Paul; Patel, Alpesh A; Dimar, John; Aarabi, Bizhan; Dailey, Andrew; Vaccaro, Alexander R; Gahr, Ralf; Shaffrey, Christopher; Anderson, David G; Rampersaud, Raj

    2011-08-01

    Radiographic measurement study. To develop a standardized cervical injury nomenclature system to facilitate description, communication, and classification among health care providers. The reliability and reproducibility of this system was then examined. Description of subaxial cervical injuries is critical for treatment decision making and comparing scientific reports of outcomes. Despite a number of available classification systems, surgeons, and researchers continue to use descriptive nomenclature, such as "burst" and "teardrop" fractures, to describe injuries. However, there is considerable inconsistency with use of such terms in the literature. Eleven distinct injury types and associated definitions were established for the subaxial cervical spine and subsequently refined by members of the Spine Trauma Study Group. A series of 18 cases of patients with a broad spectrum of subaxial cervical spine injuries was prepared and distributed to surgeon raters. Each rater was provided with the full nomenclature document and asked to select primary and secondary injury types for each case. After receipt of the raters' first round of classifications, the cases were resorted and returned to the raters for a second round of review. Interrater and intrarater reliabilities were calculated as percent agreement and Cohen kappa (κ) values. Intrarater reliability was assessed by comparing a given rater's diagnosis from the first and second rounds. Nineteen surgeons completed the first and second rounds of the study. Overall, the system demonstrated 56.4% interrater agreement and 72.8% intrarater agreement. Overall, interrater κ values demonstrated moderate agreement while intrarater κ values showed substantial agreement. Analyzed by injury types, only four (burst fractures, lateral mass fractures, flexion teardrop fractures, and anterior distraction injuries) demonstrated greater than 50% interrater agreement. This study demonstrated that, even in ideal circumstances, there is

  19. Chemical and Metallurgy Research (CMR) Sample Tracking System Design Document

    International Nuclear Information System (INIS)

    Bargelski, C. J.; Berrett, D. E.

    1998-01-01

    The purpose of this document is to describe the system architecture of the Chemical and Metallurgy Research (CMR) Sample Tracking System at Los Alamos National Laboratory. During the course of the document observations are made concerning the objectives, constraints and limitations, technical approaches, and the technical deliverables

  20. Pilot production system cost/benefit analysis: Digital document storage project

    Science.gov (United States)

    1989-01-01

    The Digital Document Storage (DDS)/Pilot Production System (PPS) will provide cost effective electronic document storage, retrieval, hard copy reproduction, and remote access for users of NASA Technical Reports. The DDS/PPS will result in major benefits, such as improved document reproduction quality within a shorter time frame than is currently possible. In addition, the DDS/PPS will provide an important strategic value through the construction of a digital document archive. It is highly recommended that NASA proceed with the DDS Prototype System and a rapid prototyping development methodology in order to validate recent working assumptions upon which the success of the DDS/PPS is dependent.

  1. ASC-PROBA Interface Control Document

    DEFF Research Database (Denmark)

    Betto, Maurizio; Jørgensen, John Leif; Jørgensen, Finn E

    1999-01-01

    of Automation of the Technical University of Denmark. The document is structured as follows. First we present the ASC - heritage, system description, performance - then we address more specifically the environmental properties, like the EMC compatibility and thermal characteristics, and the design...... and reliability issues. Section 6 deals with the testing and the calibration procedures and in section 7 the mechanical and electrical interfaces are given. In section 8 and 9 we address issues like manufacturing, transportation and storage and to conclude we review the ASC specifications against the PROBA...

  2. YUCCA MOUNTAIN SITE DESCRIPTION

    International Nuclear Information System (INIS)

    Simmons, A.M.

    2004-01-01

    The ''Yucca Mountain Site Description'' summarizes, in a single document, the current state of knowledge and understanding of the natural system at Yucca Mountain. It describes the geology; geochemistry; past, present, and projected future climate; regional hydrologic system; and flow and transport within the unsaturated and saturated zones at the site. In addition, it discusses factors affecting radionuclide transport, the effect of thermal loading on the natural system, and tectonic hazards. The ''Yucca Mountain Site Description'' is broad in nature. It summarizes investigations carried out as part of the Yucca Mountain Project since 1988, but it also includes work done at the site in earlier years, as well as studies performed by others. The document has been prepared under the Office of Civilian Radioactive Waste Management quality assurance program for the Yucca Mountain Project. Yucca Mountain is located in Nye County in southern Nevada. The site lies in the north-central part of the Basin and Range physiographic province, within the northernmost subprovince commonly referred to as the Great Basin. The basin and range physiography reflects the extensional tectonic regime that has affected the region during the middle and late Cenozoic Era. Yucca Mountain was initially selected for characterization, in part, because of its thick unsaturated zone, its arid to semiarid climate, and the existence of a rock type that would support excavation of stable openings. In 1987, the United States Congress directed that Yucca Mountain be the only site characterized to evaluate its suitability for development of a geologic repository for high-level radioactive waste and spent nuclear fuel

  3. Documentation of currently operating low-level radioactive waste treatment systems: Shredder/compactor report

    International Nuclear Information System (INIS)

    1987-04-01

    The report documents a volume reduction waste treatment system for dry active waste, a shredder/compactor, and includes specifics on system selection, system descriptions, and detailed system performance data from three operational nuclear power plants. Data gathered from the plants have shown the ability to increase the density (thereby reducing the volume) of dry active waste to /approximately/50 pounds per cubic foot when using shredder/compactors and/approximately/80 to 100 pounds per cubic foot for shredder/high pressure compactors depending on reactor type and plant specific waste characteristics. An economic evaluation of various alternative volume reduction systems for dry active waste is also presented. The report presents a method on calculating the associated costs and paybacks achieved using various volume reduction alternatives. A 10 year cost (operating expenses and capital outlay for equipment) for a shredder/high pressure compactor is 1.85 million dollars for a BWR as compared to /approximately/3 million for a conventional drum compactor. The resulting payback for the shredder/compactor is as low as 1.7 years. The report provides generators of low level waste additional information to understand the nuances of shredder/compactor systems to select a system which best suits their individual needs. 4 refs., 6 figs., 10 tabs

  4. Subject categories and scope descriptions

    International Nuclear Information System (INIS)

    2002-01-01

    This document is one in a series of publications known as the ETDE/INIS Joint Reference Series. It defines the subject categories and provides the scope descriptions to be used for categorization of the nuclear literature for the preparation of INIS and ETDE input by national and regional centres. Together with the other volumes of the INIS Reference Series it defines the rules, standards and practices and provides the authorities to be used in the International Nuclear Information System and ETDE. A complete list of the volumes published in the INIS Reference Series may be found on the inside front cover of this publication. This INIS/ETDE Reference Series document is intended to serve two purposes: to define the subject scope of the International Nuclear Information System (INIS) and the Energy Technology Data Exchange (ETDE) and to define the subject classification scheme of INIS and ETDE. It is thus the guide to the inputting centres in determining which items of literature should be reported, and in determining where the full bibliographic entry and abstract of each item should be included in INIS or ETDE database. Each category is identified by a category code consisting of three alphanumeric characters. A scope description is given for each subject category. The scope of INIS is the sum of the scopes of all the categories. With most categories cross references are provided to other categories where appropriate. Cross references should be of assistance in finding the appropriate category; in fact, by indicating topics that are excluded from the category in question, the cross references help to clarify and define the scope of the category to which they are appended. A Subject Index is included as an aid to subject classifiers, but it is only an aid and not a means for subject classification. It facilitates the use of this document, but is no substitute for the description of the scope of the subject categories

  5. ON EXPERIENCE OF THE ELECTRONIC DOCUMENT MANAGEMENT SYSTEM IMPLEMENTATION IN THE MEDICAL UNIVERSITY

    Directory of Open Access Journals (Sweden)

    A. V. Semenets

    2015-05-01

    Full Text Available An importance of the application of the electronic document management to the Ukraine healthcare is shown. The electronic document management systems market overview is presented. Example of the usage of the open-source electronic document management system in the Ternopil State Medical University by I. Ya. Horbachevsky is shown. The implementation capabilities of the electronic document management system within a cloud services are shown. The electronic document management features of the Microsoft Office 365 and Google Apps For Education are compared. Some results of the usage of the Google Apps For Education inTSMUas electronic document management system are presented.

  6. Document Management and Exchange System – Supporting Education Process

    Directory of Open Access Journals (Sweden)

    Emil Egredzija

    2010-03-01

    Full Text Available Development and implementation of new technologies are very important in education. One of the most challenging tasks in the education process is to build efficient and cost-friendly system for content management and exchange. The system has to be reliable, easy manageable and open. Centralized storage, secured access, and ubiquitous client technologies have emerged as best-practice solutions in engineering that kind of services. Users can easily publish or exchange documents and not need to worry about their distribution, storage or technical skills required for efficient document management. The system that will be presented is built on open source technologies and is deployable on all today's popular web software platforms. The web server, the programming language and operating system that are used to build and deploy such a system are all non-proprietary and completely open because our mission was to build system that can be easily extended and not limited by its corporate license. The system uses security mechanisms such as user group access policy, operating system level security (file system and secured data storage in database. Because of the growing need for document management in education process we believe that this project will find its place in practice.

  7. Pengembangan Electronic Document Management System (EDMS) Sebagai Alternatif Pengarsipan Di Perguruan Tinggi

    OpenAIRE

    Amin, M. Miftakul

    2010-01-01

    The purpose of this paper is to develop an electronic document management system (EDMS). With a system is expected to be an alternative in the management of electronic documents in the college environment. Writing this using qualitative research approach with observation, document analysis, and interviews for data collection process. The system used a web-based system that is expected to reach the users of the system at large. This system has the functionality to store, archive, and retrieve...

  8. Delve: A Data Set Retrieval and Document Analysis System

    KAUST Repository

    Akujuobi, Uchenna Thankgod

    2017-12-29

    Academic search engines (e.g., Google scholar or Microsoft academic) provide a medium for retrieving various information on scholarly documents. However, most of these popular scholarly search engines overlook the area of data set retrieval, which should provide information on relevant data sets used for academic research. Due to the increasing volume of publications, it has become a challenging task to locate suitable data sets on a particular research area for benchmarking or evaluations. We propose Delve, a web-based system for data set retrieval and document analysis. This system is different from other scholarly search engines as it provides a medium for both data set retrieval and real time visual exploration and analysis of data sets and documents.

  9. TINTE. Nuclear calculation theory description report

    Energy Technology Data Exchange (ETDEWEB)

    Gerwin, H.; Scherer, W.; Lauer, A. [Forschungszentrum Juelich GmbH (DE). Institut fuer Energieforschung (IEF), Sicherheitsforschung und Reaktortechnik (IEF-6); Clifford, I. [Pebble Bed Modular Reactor (Pty) Ltd. (South Africa)

    2010-01-15

    The Time Dependent Neutronics and Temperatures (TINTE) code system deals with the nuclear and the thermal transient behaviour of the primary circuit of the High-temperature Gas-cooled Reactor (HTGR), taking into consideration the mutual feedback effects in twodimensional axisymmetric geometry. This document contains a complete description of the theoretical basis of the TINTE nuclear calculation, including the equations solved, solution methods and the nuclear data used in the solution. (orig.)

  10. Preliminary site description Forsmark area - version 1.2

    Energy Technology Data Exchange (ETDEWEB)

    Skagius, Kristina [ed.

    2005-06-01

    The Swedish Nuclear Fuel and Waste Management Company (SKB) is undertaking site characterisation at two different locations, the Forsmark and Simpevarp areas, with the objective of siting a geological repository for spent nuclear fuel. An integrated component in the characterisation work is the development of a site descriptive model that constitutes a description of the site and its regional setting, covering the current state of the geosphere and the biosphere as well as those ongoing natural processes that affect their long-term evolution. The present report documents the site descriptive modelling activities (version 1.2) for the Forsmark area. The overall objectives of the version 1.2 site descriptive modelling are to produce and document an integrated description of the site and its regional environments based on the site-specific data available from the initial site investigations and to give recommendations on continued investigations. The modelling work is based on primary data, i.e. quality-assured, geoscientific and ecological field data available in the SKB databases SICADA and GIS, available July 31, 2004. The work has been conducted by a project group and associated discipline-specific working groups. The members of the project group represent the disciplines of geology, rock mechanics, thermal properties, hydrogeology, hydrogeochemistry, transport properties and surface ecosystems (including overburden, surface hydrogeochemistry and hydrology). In addition, some group members have specific qualifications of importance in this type of project e.g. expertise in RVS (Rock Visualisation System) modelling, GIS-modelling and in statistical data analysis. The overall strategy to achieve a site description is to develop discipline-specific models by interpretation and analyses of the primary data. The different discipline-specific models are then integrated into a site description. Methodologies for developing the discipline-specific models are documented in

  11. Preliminary site description Forsmark area - version 1.2

    International Nuclear Information System (INIS)

    Skagius, Kristina

    2005-06-01

    The Swedish Nuclear Fuel and Waste Management Company (SKB) is undertaking site characterisation at two different locations, the Forsmark and Simpevarp areas, with the objective of siting a geological repository for spent nuclear fuel. An integrated component in the characterisation work is the development of a site descriptive model that constitutes a description of the site and its regional setting, covering the current state of the geosphere and the biosphere as well as those ongoing natural processes that affect their long-term evolution. The present report documents the site descriptive modelling activities (version 1.2) for the Forsmark area. The overall objectives of the version 1.2 site descriptive modelling are to produce and document an integrated description of the site and its regional environments based on the site-specific data available from the initial site investigations and to give recommendations on continued investigations. The modelling work is based on primary data, i.e. quality-assured, geoscientific and ecological field data available in the SKB databases SICADA and GIS, available July 31, 2004. The work has been conducted by a project group and associated discipline-specific working groups. The members of the project group represent the disciplines of geology, rock mechanics, thermal properties, hydrogeology, hydrogeochemistry, transport properties and surface ecosystems (including overburden, surface hydrogeochemistry and hydrology). In addition, some group members have specific qualifications of importance in this type of project e.g. expertise in RVS (Rock Visualisation System) modelling, GIS-modelling and in statistical data analysis. The overall strategy to achieve a site description is to develop discipline-specific models by interpretation and analyses of the primary data. The different discipline-specific models are then integrated into a site description. Methodologies for developing the discipline-specific models are documented in

  12. A Type System for Dynamic Web Documents

    DEFF Research Database (Denmark)

    Schwartzbach, Michael Ignatieff; Sandholm, Anders

    2000-01-01

    Many interactive Web services use the CGI interface for communication with clients. They will dynamically create HTML documents that are presented to the client who then resumes the interaction by submitting data through incorporated form fields. This protocol is difficult to statically type-chec...... system is based on a flow analysis of which we prove soundness. We present an efficient runtime implementation that respects the semantics of only well-typed programs. This work is fully implemented as part of the system for defining interactive Web services.......Many interactive Web services use the CGI interface for communication with clients. They will dynamically create HTML documents that are presented to the client who then resumes the interaction by submitting data through incorporated form fields. This protocol is difficult to statically type...

  13. Document Examination: Applications of Image Processing Systems.

    Science.gov (United States)

    Kopainsky, B

    1989-12-01

    Dealing with images is a familiar business for an expert in questioned documents: microscopic, photographic, infrared, and other optical techniques generate images containing the information he or she is looking for. A recent method for extracting most of this information is digital image processing, ranging from the simple contrast and contour enhancement to the advanced restoration of blurred texts. When combined with a sophisticated physical imaging system, an image pricessing system has proven to be a powerful and fast tool for routine non-destructive scanning of suspect documents. This article reviews frequent applications, comprising techniques to increase legibility, two-dimensional spectroscopy (ink discrimination, alterations, erased entries, etc.), comparison techniques (stamps, typescript letters, photo substitution), and densitometry. Computerized comparison of handwriting is not included. Copyright © 1989 Central Police University.

  14. ON EXPERIENCE OF THE ELECTRONIC DOCUMENT MANAGEMENT SYSTEM IMPLEMENTATION IN THE MEDICAL UNIVERSITY

    OpenAIRE

    A. V. Semenets; V. Yu. Kovalok

    2015-01-01

    An importance of the application of the electronic document management to the Ukraine healthcare is shown. The electronic document management systems market overview is presented. Example of the usage of the open-source electronic document management system in the Ternopil State Medical University by I. Ya. Horbachevsky is shown. The implementation capabilities of the electronic document management system within a cloud services are shown. The electronic document management features of the Mi...

  15. Improving documentation of a beta-blocker quality measure through an anesthesia information management system and real-time notification of documentation errors.

    Science.gov (United States)

    Nair, Bala G; Peterson, Gene N; Newman, Shu-Fang; Wu, Wei-Ying; Kolios-Morris, Vickie; Schwid, Howard A

    2012-06-01

    Continuation of perioperative beta-blockers for surgical patients who are receiving beta-blockers prior to arrival for surgery is an important quality measure (SCIP-Card-2). For this measure to be considered successful, name, date, and time of the perioperative beta-blocker must be documented. Alternately, if the beta-blocker is not given, the medical reason for not administering must be documented. Before the study was conducted, the institution lacked a highly reliable process to document the date and time of self-administration of beta-blockers prior to hospital admission. Because of this, compliance with the beta-blocker quality measure was poor (-65%). To improve this measure, the anesthesia care team was made responsible for documenting perioperative beta-blockade. Clear documentation guidelines were outlined, and an electronic Anesthesia Information Management System (AIMS) was configured to facilitate complete documentation of the beta-blocker quality measure. In addition, real-time electronic alerts were generated using Smart Anesthesia Messenger (SAM), an internally developed decision-support system, to notify users concerning incomplete beta-blocker documentation. Weekly compliance for perioperative beta-blocker documentation before the study was 65.8 +/- 16.6%, which served as the baseline value. When the anesthesia care team started documenting perioperative beta-blocker in AIMS, compliance was 60.5 +/- 8.6% (p = .677 as compared with baseline). Electronic alerts with SAM improved documentation compliance to 94.6 +/- 3.5% (p documentation and (2) enhance features in the electronic medical systems to alert the user concerning incomplete documentation.

  16. QCS: a system for querying, clustering and summarizing documents.

    Energy Technology Data Exchange (ETDEWEB)

    Dunlavy, Daniel M.; Schlesinger, Judith D. (Center for Computing Sciences, Bowie, MD); O' Leary, Dianne P. (University of Maryland, College Park, MD); Conroy, John M. (Center for Computing Sciences, Bowie, MD)

    2006-10-01

    Information retrieval systems consist of many complicated components. Research and development of such systems is often hampered by the difficulty in evaluating how each particular component would behave across multiple systems. We present a novel hybrid information retrieval system--the Query, Cluster, Summarize (QCS) system--which is portable, modular, and permits experimentation with different instantiations of each of the constituent text analysis components. Most importantly, the combination of the three types of components in the QCS design improves retrievals by providing users more focused information organized by topic. We demonstrate the improved performance by a series of experiments using standard test sets from the Document Understanding Conferences (DUC) along with the best known automatic metric for summarization system evaluation, ROUGE. Although the DUC data and evaluations were originally designed to test multidocument summarization, we developed a framework to extend it to the task of evaluation for each of the three components: query, clustering, and summarization. Under this framework, we then demonstrate that the QCS system (end-to-end) achieves performance as good as or better than the best summarization engines. Given a query, QCS retrieves relevant documents, separates the retrieved documents into topic clusters, and creates a single summary for each cluster. In the current implementation, Latent Semantic Indexing is used for retrieval, generalized spherical k-means is used for the document clustering, and a method coupling sentence 'trimming', and a hidden Markov model, followed by a pivoted QR decomposition, is used to create a single extract summary for each cluster. The user interface is designed to provide access to detailed information in a compact and useful format. Our system demonstrates the feasibility of assembling an effective IR system from existing software libraries, the usefulness of the modularity of the design

  17. QCS : a system for querying, clustering, and summarizing documents.

    Energy Technology Data Exchange (ETDEWEB)

    Dunlavy, Daniel M.

    2006-08-01

    Information retrieval systems consist of many complicated components. Research and development of such systems is often hampered by the difficulty in evaluating how each particular component would behave across multiple systems. We present a novel hybrid information retrieval system--the Query, Cluster, Summarize (QCS) system--which is portable, modular, and permits experimentation with different instantiations of each of the constituent text analysis components. Most importantly, the combination of the three types of components in the QCS design improves retrievals by providing users more focused information organized by topic. We demonstrate the improved performance by a series of experiments using standard test sets from the Document Understanding Conferences (DUC) along with the best known automatic metric for summarization system evaluation, ROUGE. Although the DUC data and evaluations were originally designed to test multidocument summarization, we developed a framework to extend it to the task of evaluation for each of the three components: query, clustering, and summarization. Under this framework, we then demonstrate that the QCS system (end-to-end) achieves performance as good as or better than the best summarization engines. Given a query, QCS retrieves relevant documents, separates the retrieved documents into topic clusters, and creates a single summary for each cluster. In the current implementation, Latent Semantic Indexing is used for retrieval, generalized spherical k-means is used for the document clustering, and a method coupling sentence ''trimming'', and a hidden Markov model, followed by a pivoted QR decomposition, is used to create a single extract summary for each cluster. The user interface is designed to provide access to detailed information in a compact and useful format. Our system demonstrates the feasibility of assembling an effective IR system from existing software libraries, the usefulness of the modularity of

  18. AVIS: analysis method for document coherence

    International Nuclear Information System (INIS)

    Henry, J.Y.; Elsensohn, O.

    1994-06-01

    The present document intends to give a short insight into AVIS, a method which permits to verify the quality of technical documents. The paper includes the presentation of the applied approach based on the K.O.D. method, the definition of quality criteria of a technical document, as well as a description of the means of valuating these criteria. (authors). 9 refs., 2 figs

  19. Use of an advanced document system in post-refuelling updating of nuclear power plant documentation; Utilizacion de un sistema documental avanzado en la actualizacion de documentacion post recarga

    Energy Technology Data Exchange (ETDEWEB)

    Puech Suanzes, P; Cortes Soler, M [Empresarios Agrupados, A.I.E., Madrid (Spain)

    1993-12-15

    This paper discusses the results of the extensive use of an advanced document system to update documentation prepared by traditional methods and affected by changes in the period between two plant refuellings. The implementation of a system for the capture, retrieval and storage of drawings using optical discs is part of a plan to modernize production and management tools and to thus achieve better control of document configuration. These processes are consequently optimized in that: 1. The deterioration of drawings is detained with the help of an identical, updated, legible, reliable support for all users. 2. The time required to update documentation is reduced. Given the large number of drawings, the implementation method should effectively combine costs and time. The document management tools ensure optical disc storage control so that from the moment a drawing resides in the system, any modification to it is made through the system utilities, thus ensuring quality and reducing schedules. The system described was used to update the electrical drawings of Almaraz Nuclear Power Plant. Changes made during the eighth refuelling of Unit I were incorporated and the time needed to issue the updated drawings was reduced by one month. (author)

  20. Using Electronic Systems for Document Management in Economic Entities

    Directory of Open Access Journals (Sweden)

    2007-01-01

    Full Text Available Document workflow and management, be them scanned documents, computer-generated e-documents or complex file formats, are critical elements for the success of an organization. Delivering the correct information to the right person, at the right moment is a fundamental element of daily activity. In the Internet era, documents have a new format; and what is more important: completely new functions. Paper is replaced by electronic formats such as .html, .xms, .pdf or .doc. The price for this progress is the increasing technological complexity, and with this complexity comes the need for more efficient techniques of management and organization such as a document management electronic system. This paper aims to present document management not as a separate software category on the IT market, but as an element integrated with any software solution, maximizing its capacity of making business more efficient.

  1. Predicting Document Retrieval System Performance: An Expected Precision Measure.

    Science.gov (United States)

    Losee, Robert M., Jr.

    1987-01-01

    Describes an expected precision (EP) measure designed to predict document retrieval performance. Highlights include decision theoretic models; precision and recall as measures of system performance; EP graphs; relevance feedback; and computing the retrieval status value of a document for two models, the Binary Independent Model and the Two Poisson…

  2. Issues in Designing a Hypermedia Document System: The Intermedia Case Study.

    Science.gov (United States)

    Yankelovich, Nicole; And Others

    1986-01-01

    Intermedia, a hypermedia system developed at Brown University's Institute for Research (Rhode Island) in Information and Scholarship, is first described, and then used as a case study to explore a number of key issues that software designers must consider in the development of hypermedia document systems. A hypermedia document system is defined as…

  3. Securing XML Documents

    Directory of Open Access Journals (Sweden)

    Charles Shoniregun

    2004-11-01

    Full Text Available XML (extensible markup language is becoming the current standard for establishing interoperability on the Web. XML data are self-descriptive and syntax-extensible; this makes it very suitable for representation and exchange of semi-structured data, and allows users to define new elements for their specific applications. As a result, the number of documents incorporating this standard is continuously increasing over the Web. The processing of XML documents may require a traversal of all document structure and therefore, the cost could be very high. A strong demand for a means of efficient and effective XML processing has posed a new challenge for the database world. This paper discusses a fast and efficient indexing technique for XML documents, and introduces the XML graph numbering scheme. It can be used for indexing and securing graph structure of XML documents. This technique provides an efficient method to speed up XML data processing. Furthermore, the paper explores the classification of existing methods impact of query processing, and indexing.

  4. Using Addenda in Documented Safety Analysis Reports

    International Nuclear Information System (INIS)

    Swanson, D.S.; Thieme, M.A.

    2003-01-01

    This paper discusses the use of addenda to the Radioactive Waste Management Complex (RWMC) Documented Safety Analysis (DSA) located at the Idaho National Engineering and Environmental Laboratory (INEEL). Addenda were prepared for several systems and processes at the facility that lacked adequate descriptive information and hazard analysis in the DSA. They were also prepared for several new activities involving unreviewed safety questions (USQs). Ten addenda to the RWMC DSA have been prepared since the last annual update

  5. Technical description of the CANDU nuclear power system

    International Nuclear Information System (INIS)

    Husseini, S.D.

    1977-01-01

    The lecture consists of: 1.) KANUPP description: general - Containment- Reactor Cooling System - Moderator Helium System. 2.) Operating experience: Plant Performances (as applicable to Kanupp) - Major failures of primary system - Performance of primary circulating pumps. - Heavy Water Leakage Control. - Radiation Dose Control - Inadvertant Operations. (orig.) [de

  6. A descriptive study of consent documentation.

    LENUS (Irish Health Repository)

    Murphy, K

    2011-09-01

    The aim of this study was to observe the error rate in the consent process of a university hospital and to illicit the opinions of the consenting doctors on the process. A prospective observational review of theatre consent forms was performed along with an anonymous survey of non-consultant hospital doctors (NCHD\\'s). No potential risks were documented in 95.3% of the 64 scrutinized consents and late alterations were required in 9%. Respondents to the NCHD survey estimated that they were unsure of the procedure or risks involved in an average of 29% of occasions. Interns admitted to being unsure of the details of the procedure in almost a third (32%) of cases, making them less well informed than their senior colleagues (p=0.024). This study highlights the difficulties encountered by consenting doctors, an issue which may lead to patient dissatisfaction, threaten the efficient running of a surgical unit and potentially expose its staff to avoidable litigation. It also recommends the use of multimedia adjuncts to facilitate both patient and doctor education in the consent process.

  7. YUCCA MOUNTAIN SITE DESCRIPTION

    Energy Technology Data Exchange (ETDEWEB)

    A.M. Simmons

    2004-04-16

    The ''Yucca Mountain Site Description'' summarizes, in a single document, the current state of knowledge and understanding of the natural system at Yucca Mountain. It describes the geology; geochemistry; past, present, and projected future climate; regional hydrologic system; and flow and transport within the unsaturated and saturated zones at the site. In addition, it discusses factors affecting radionuclide transport, the effect of thermal loading on the natural system, and tectonic hazards. The ''Yucca Mountain Site Description'' is broad in nature. It summarizes investigations carried out as part of the Yucca Mountain Project since 1988, but it also includes work done at the site in earlier years, as well as studies performed by others. The document has been prepared under the Office of Civilian Radioactive Waste Management quality assurance program for the Yucca Mountain Project. Yucca Mountain is located in Nye County in southern Nevada. The site lies in the north-central part of the Basin and Range physiographic province, within the northernmost subprovince commonly referred to as the Great Basin. The basin and range physiography reflects the extensional tectonic regime that has affected the region during the middle and late Cenozoic Era. Yucca Mountain was initially selected for characterization, in part, because of its thick unsaturated zone, its arid to semiarid climate, and the existence of a rock type that would support excavation of stable openings. In 1987, the United States Congress directed that Yucca Mountain be the only site characterized to evaluate its suitability for development of a geologic repository for high-level radioactive waste and spent nuclear fuel.

  8. Development of a system for managing document delivery schedule(DDS) for NSSS system design

    International Nuclear Information System (INIS)

    Baek, S. H.; Baek, J. M.; Sohn, Y. S.; Shon, G. H.

    1999-01-01

    The construction of nuclear power plant is a long-term project from initial design to commercial operation. To accomplish NSSS (Nuclear Steam Supply System) system design successfully, the systematic and effective method for managing the system design product and interface correspondence with other organizations is required. To meet this requirement, a system has been developed to control the document delivery schedule, approval process and interface correspondence transmittal, and to report the documentation status periodically from the beginning of the YGN 5 and 6 project. This system is expected to contribute as the beginning step to development of integrated project management system. (author)

  9. Documentation and Development. Experience in Algeria

    Science.gov (United States)

    Tchuigoua, J. Founou

    1972-01-01

    A description of the activities of the Documentation, Library and Archives Department of the Algiers Chamber of Commerce and Industry, which is run by a small staff on a modest budget, provides documentation services for the staff of the Chamber of Commerce and also assists other centers in Algeria. (Author)

  10. [Development and integration of the Oncological Documentation System ODS].

    Science.gov (United States)

    Raab, G; van Den Bergh, M

    2001-08-01

    To simplify clinical routine and to improve medical quality without exceeding the existing resources. Intensifying communication and cooperation between all institutions of patients' health care. The huge amount of documentation work of physicians can no longer be done without modern tools of paperless data processing. The development of ODS was a tight cooperation between physician and technician which resulted in a mutual understanding and led to a high level of user convenience. - At present all cases of gynecology, especially gynecologic oncology can be documented and processed by ODS. Users easily will adopt the system as data entry within different program areas follows the same rules. In addition users can choose between an individual input of data and assistants guiding them through highly specific areas of documentation. ODS is a modern, modular structured and very fast multiuser database environment for in- and outpatient documentation. It automatically generates a lot of reports for clinical day to day business. Statistical routines will help the user reflecting his work and its quality. Documentation of clinical trials according to the GCP guidelines can be done by ODS using the internet or offline datasharing. As ODS is the synthesis of a computer based patient administration system and an oncological documentation database, it represents the basis for the construction of the electronical patient chart as well as the digital documentation of clinical trials. The introduction of this new technology to physicians and nurses has to be done slowly and carefully, in order to increase motivation and to improve the results.

  11. Data Description of a System

    Directory of Open Access Journals (Sweden)

    P. Nevriva

    1996-04-01

    Full Text Available In this paper, a brief discussion on description of process by memorized data is given. The insight into the problem can offer modified views on optimal control, on data compression at communication systems with respect to information content of message, etc.The idea of process description by memorized data with different information content will be presented here on the classical case study of optimal control: the data based control algorithm (data algorithm, DA gathers data from the controlled process and derives control signal (control from data accumulated in the data base. The implementation of the DA on the ideal computer which is not limited by its speed or capacity of memory is expected for simplicity. Accuracy of the data algorithm is then given by a-priori knowledge of the task and by information exchange between the controlled process and the computer.

  12. Documentation of the Oil and Gas Supply Module (OGSM). Appendix, Model developers report

    International Nuclear Information System (INIS)

    1995-01-01

    The Office of Integrated Analysis and Forecasting (OIAF) is required to provide complete model documentation to meet the EIA Model Acceptance Standards. The Documentation for the Oil and Gas Supply Module (OGSM) provides a complete description of the OGSM methodology, structure, and relation to other modules in the National Energy Modeling System (NEMS). This Model Developers Report (MDR) serves as an appendix to the methodology documentation. This report provides an overview of the model and an assessment of the sensitivity of OGSM results to changes in input data or parameters

  13. Documents needed for obtaining the operation licence for the HERBE system at the RB reactor; Dokumentacija za dobijanje dozvole za rad sistema HERBE na reaktoru RB

    Energy Technology Data Exchange (ETDEWEB)

    Pesic, M et al [Boris Kidric Institute of Nuclear Sciences Vinca, Belgrade (Yugoslavia)

    1989-10-15

    Documents included in this volume are needed for obtaining the operation licence for the coupled fast-thermal system HERBE constructed at the RB reactor. It contains the following chapters: description of the system; nuclear calculations; performed changes at the RB reactor; proofs about static and dynamic stability of the built construction; normal operation regime of HERBE; accident analysis; dosimetry data; additional instructions and regulations for reactor operation; program of start-up; program for testing the HERBE system.

  14. Verifying Real-Time Systems using Explicit-time Description Methods

    Directory of Open Access Journals (Sweden)

    Hao Wang

    2009-12-01

    Full Text Available Timed model checking has been extensively researched in recent years. Many new formalisms with time extensions and tools based on them have been presented. On the other hand, Explicit-Time Description Methods aim to verify real-time systems with general untimed model checkers. Lamport presented an explicit-time description method using a clock-ticking process (Tick to simulate the passage of time together with a group of global variables for time requirements. This paper proposes a new explicit-time description method with no reliance on global variables. Instead, it uses rendezvous synchronization steps between the Tick process and each system process to simulate time. This new method achieves better modularity and facilitates usage of more complex timing constraints. The two explicit-time description methods are implemented in DIVINE, a well-known distributed-memory model checker. Preliminary experiment results show that our new method, with better modularity, is comparable to Lamport's method with respect to time and memory efficiency.

  15. CERN Document Server (CDS): Introduction

    CERN Multimedia

    CERN. Geneva; Costa, Flavio

    2017-01-01

    A short online tutorial introducing the CERN Document Server (CDS). Basic functionality description, the notion of Revisions and the CDS test environment. Links: CDS Production environment CDS Test environment  

  16. Systems Security Engineering Capability Maturity Model SSE-CMM Model Description Document

    National Research Council Canada - National Science Library

    1999-01-01

    The Systems Security Engineering Capability Maturity Model (SSE-CMM) describes the essential characteristics of an organization's security engineering process that must exist to ensure good security engineering...

  17. Advanced Stellar Compass - Adeos II - Interface Control Document

    DEFF Research Database (Denmark)

    Betto, Maurizio; Jørgensen, John Leif; Kilsgaard, Søren

    of Automation of the Technical University of Denmark.The document is structured as follows. First we present the ASC - heritage, system description, performance - then we address more specifically the environmental properties, like the EMC compatibility and thermal characteristics, and the design...... and reliability issues. Section 6 deals with the testing and the calibration procedures and in section 7 the mechanical and electrical interfaces are given. In section 8 and 9 we address issues like manufacturing, transportation and storage, in section 10 the requirements imposed by the ASC on the system...

  18. Molten Salt Test Loop (MSTL) system customer interface document.

    Energy Technology Data Exchange (ETDEWEB)

    Gill, David Dennis; Kolb, William J.; Briggs, Ronald D.

    2013-09-01

    The National Solar Thermal Test Facility at Sandia National Laboratories has a unique test capability called the Molten Salt Test Loop (MSTL) system. MSTL is a test capability that allows customers and researchers to test components in flowing, molten nitrate salt. The components tested can range from materials samples, to individual components such as flex hoses, ball joints, and valves, up to full solar collecting systems such as central receiver panels, parabolic troughs, or linear Fresnel systems. MSTL provides realistic conditions similar to a portion of a concentrating solar power facility. The facility currently uses 60/40 nitrate %E2%80%9Csolar salt%E2%80%9D and can circulate the salt at pressure up to 40 bar (600psi), temperature to 585%C2%B0C, and flow rate of 44-50kg/s(400-600GPM) depending on temperature. The purpose of this document is to provide a basis for customers to evaluate the applicability to their testing needs, and to provide an outline of expectations for conducting testing on MSTL. The document can serve as the basis for testing agreements including Work for Others (WFO) and Cooperative Research and Development Agreements (CRADA). While this document provides the basis for these agreements and describes some of the requirements for testing using MSTL and on the site at Sandia, the document is not sufficient by itself as a test agreement. The document, however, does provide customers with a uniform set of information to begin the test planning process.

  19. Large Scale Document Inversion using a Multi-threaded Computing System.

    Science.gov (United States)

    Jung, Sungbo; Chang, Dar-Jen; Park, Juw Won

    2017-06-01

    Current microprocessor architecture is moving towards multi-core/multi-threaded systems. This trend has led to a surge of interest in using multi-threaded computing devices, such as the Graphics Processing Unit (GPU), for general purpose computing. We can utilize the GPU in computation as a massive parallel coprocessor because the GPU consists of multiple cores. The GPU is also an affordable, attractive, and user-programmable commodity. Nowadays a lot of information has been flooded into the digital domain around the world. Huge volume of data, such as digital libraries, social networking services, e-commerce product data, and reviews, etc., is produced or collected every moment with dramatic growth in size. Although the inverted index is a useful data structure that can be used for full text searches or document retrieval, a large number of documents will require a tremendous amount of time to create the index. The performance of document inversion can be improved by multi-thread or multi-core GPU. Our approach is to implement a linear-time, hash-based, single program multiple data (SPMD), document inversion algorithm on the NVIDIA GPU/CUDA programming platform utilizing the huge computational power of the GPU, to develop high performance solutions for document indexing. Our proposed parallel document inversion system shows 2-3 times faster performance than a sequential system on two different test datasets from PubMed abstract and e-commerce product reviews. •Information systems➝Information retrieval • Computing methodologies➝Massively parallel and high-performance simulations.

  20. Integrated Project Management System description

    International Nuclear Information System (INIS)

    1987-03-01

    The Uranium Mill Tailings Remedial Action (UMTRA) Project is a Department of Energy (DOE) designated Major System Acquisition (MSA). To execute and manage the Project mission successfully and to comply with the MSA requirements, the UMTRA Project Office (''Project Office'') has implemented and operates an Integrated Project Management System (IPMS). The Project Office is assisted by the Technical Assistance Contractor's (TAC) Project Integration and Control (PIC) Group in system operation. Each participant, in turn, provides critical input to system operation and reporting requirements. The IPMS provides a uniform structured approach for integrating the work of Project participants. It serves as a tool for planning and control, workload management, performance measurement, and specialized reporting within a standardized format. This system description presents the guidance for its operation. Appendices 1 and 2 contain definitions of commonly used terms and abbreviations and acronyms, respectively. 17 figs., 5 tabs

  1. Application of system-process-goal approach for description of TRIGA RC-1 system

    International Nuclear Information System (INIS)

    Gadomski, Adam M.

    1986-01-01

    The new methodology of the goal oriented description of an artificial system is presented. In the SPG approach (System-Process-Goal) it is assumed that the knowledge necessary for achieving the goal is available but it is not ordered or ordered for other purposes. The aim of SPG is to give the description of the analyzed system in form of network by decomposition of goal-system relationships using uniform and mathematical formalism. The SPG approach is useful to build a reactor operator aid system. This paper presents the conception of the application of the SPG approach to the decomposition of TRIGA RC-1 dynamics and for designing of TRIGA diagnostic algorithms. (author)

  2. Accelerator System Model (ASM) user manual with physics and engineering model documentation. ASM version 1.0

    International Nuclear Information System (INIS)

    1993-07-01

    The Accelerator System Model (ASM) is a computer program developed to model proton radiofrequency accelerators and to carry out system level trade studies. The ASM FORTRAN subroutines are incorporated into an intuitive graphical user interface which provides for the open-quotes constructionclose quotes of the accelerator in a window on the computer screen. The interface is based on the Shell for Particle Accelerator Related Codes (SPARC) software technology written for the Macintosh operating system in the C programming language. This User Manual describes the operation and use of the ASM application within the SPARC interface. The Appendix provides a detailed description of the physics and engineering models used in ASM. ASM Version 1.0 is joint project of G. H. Gillespie Associates, Inc. and the Accelerator Technology (AT) Division of the Los Alamos National Laboratory. Neither the ASM Version 1.0 software nor this ASM Documentation may be reproduced without the expressed written consent of both the Los Alamos National Laboratory and G. H. Gillespie Associates, Inc

  3. Implementation of a Document Management System in an Operating Nuclear Power Plan

    International Nuclear Information System (INIS)

    Martinez Ladron de Guevara, J.

    1996-01-01

    The difficulty of implementing a document management system in an operating nuclear power plant basically lies in the high volume of information to be handled, in the different storage devices used and in the complexity of relations existing between the documentation and the physical elements of the facility. The documentation used in a power plant, mainly technical, is often stored on different devices (paper, microfilm, aperture cards, test files, vector files, raster files, etc) and usually features various identification criteria (engineering, manufacturing, plant staff, etc). Consequently, the system must be aimed at the management of multiformatted documentation, providing appropriate means of identification, capture and display for each case. The document management system must satisfy all information needs of each department of the plant, and should be adapted to the work cycles of the plant. Moreover, it should be integrated into other computer application in operation (maintenance, operation, procurement, etc), so that links can be established between the documentation and configuration elements. Although this is a complex procedure in operating power plants, there are integrating tools that facilitate the gradual implementation of this type of system. (Author)

  4. System design description for mini-dacs data acquisition and control system

    International Nuclear Information System (INIS)

    Vargo, F.G. Jr.; Trujillo, L.T.; Smith, S.O.

    1994-01-01

    This document describes the hardware computer system, for the mini data acquisition and control system (DACS) that was fabricated by Los Alamos National Laboratory (LANL), to support the testing of the spare mixer pump for SY-101

  5. Software simulator for property investigation of document management system with RFID tags

    Directory of Open Access Journals (Sweden)

    Kiedrowicz Maciej

    2016-01-01

    Full Text Available The study outlines the method for examining the properties of the RFID-tagged document management system. The system is composed of computers, where the software for supporting processes of the RFID-tagged doc-uments was installed. Furthermore, the system cooperates with many other elements of the secret office (cabinets, sluices, photocopiers, desks. The examination of the properties of the RFID-tagged document management system is, in this case, complex due to the number of a possible examination scenarios. The simulation method for examining the system properties was proposed. It allows to conduct the examination of the properties in a short period of time for numerous testing scenarios.

  6. Large Scale Document Inversion using a Multi-threaded Computing System

    Science.gov (United States)

    Jung, Sungbo; Chang, Dar-Jen; Park, Juw Won

    2018-01-01

    Current microprocessor architecture is moving towards multi-core/multi-threaded systems. This trend has led to a surge of interest in using multi-threaded computing devices, such as the Graphics Processing Unit (GPU), for general purpose computing. We can utilize the GPU in computation as a massive parallel coprocessor because the GPU consists of multiple cores. The GPU is also an affordable, attractive, and user-programmable commodity. Nowadays a lot of information has been flooded into the digital domain around the world. Huge volume of data, such as digital libraries, social networking services, e-commerce product data, and reviews, etc., is produced or collected every moment with dramatic growth in size. Although the inverted index is a useful data structure that can be used for full text searches or document retrieval, a large number of documents will require a tremendous amount of time to create the index. The performance of document inversion can be improved by multi-thread or multi-core GPU. Our approach is to implement a linear-time, hash-based, single program multiple data (SPMD), document inversion algorithm on the NVIDIA GPU/CUDA programming platform utilizing the huge computational power of the GPU, to develop high performance solutions for document indexing. Our proposed parallel document inversion system shows 2-3 times faster performance than a sequential system on two different test datasets from PubMed abstract and e-commerce product reviews. CCS Concepts •Information systems➝Information retrieval • Computing methodologies➝Massively parallel and high-performance simulations.

  7. Title list of documents made publicly available, March 1--31, 1993

    International Nuclear Information System (INIS)

    1993-05-01

    The Title List of Documents Made Publicly Available is a monthly publication. It contains descriptions of the information received and generated by the US Nuclear Regulatory Commission (NRC). This information includes (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials and (2) nondocketed material received and generated by NRC pertinent to its role as a regulatory agency. As used here, docketed does not refer to Court dockets; it refers to the system by which NRC maintains its regulatory records. This series of documents is indexed by a Personal Author Index, a Corporate Source Index, and a Report Number Index. The docketed information contained in the Title List includes the information formerly issued through the Department of Energy publication Power Reactor Docket Information, last published in January 1979. NRC documents that are publicly available may be examined without charge at the NRC Public Document Room (PDR). Duplicate copies may be obtained for a fee. Standing orders for certain categories of documents are also available. Clients may search for and order desired titles through the PDR computerized Bibliographic Retrieval System, which is accessible both at the PDR and remotely. The PDR is staffed by professional technical librarians, who provide reference assistance to users. See NOTES at the end of the preface for information about reaching the PDR. Microfiche of the docketed information listed in the Title List is available for sale on a subscription basis from the National Technical Information Service (NTIS). See NOTES at the end of the Preface for the complete NTIS address. We encourage your comments, criticisms, and suggestions. In particular, if there are title descriptions that are not meaningful, please let us know so that we can correct the data base. Insofar as possible, we would like this document to be a valuable part of your reference material

  8. [Document management systems to support quality management systems at university hospitals - an interview-based study].

    Science.gov (United States)

    Holderried, Martin; Bökel, Ann-Catrin; Ochsmann, Elke

    2018-05-01

    In order to save and control the processes and quality of medical services, a suitable steering system of all relevant documents is essential from the point of view of clinical quality management. Systems supporting an automated steering system of documents are called document management systems (DMS), and they also enter the healthcare sector. The use of DMS in the German healthcare sector has hardly been investigated so far. To close this knowledge gap, interviews were carried out with German university hospitals over a six-month period and subjected to a qualitative content analysis according to Mayring. In total, 25 university hospitals agreed to participate in this study, 19 of which have been working with a digital DMS for about six years on average. There was a great variety among the IT systems used. Document management and usability of the DMS as well as its integration into existing IT structures were key decision-making criteria for the selection of a digital DMS. In general, the long-term usability of the DMS is supported by regular evaluation of one's own requirements for the system, administration and training programs. In addition, DMS have a positive effect on patient safety and the quality of medical care. Copyright © 2018. Published by Elsevier GmbH.

  9. 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

  10. Model documentation renewable fuels module of the National Energy Modeling System

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-04-01

    This report documents the objectives, analytical approach, and design of the National Energy Modeling System (NEMS) Renewable Fuels Module (RFM) as it relates to the production of the 1997 Annual Energy Outlook forecasts. The report catalogues and describes modeling assumptions, computational methodologies, data inputs. and parameter estimation techniques. A number of offline analyses used in lieu of RFM modeling components are also described. This documentation report serves three purposes. First, it is a reference document for model analysts, model users, and the public interested in the construction and application of the RFM. Second, it meets the legal requirement of the Energy Information Administration (EIA) to provide adequate documentation in support of its models. Finally, such documentation facilitates continuity in EIA model development by providing information sufficient to perform model enhancements and data updates as part of EIA`s ongoing mission to provide analytical and forecasting information systems.

  11. Model documentation renewable fuels module of the National Energy Modeling System

    International Nuclear Information System (INIS)

    1997-04-01

    This report documents the objectives, analytical approach, and design of the National Energy Modeling System (NEMS) Renewable Fuels Module (RFM) as it relates to the production of the 1997 Annual Energy Outlook forecasts. The report catalogues and describes modeling assumptions, computational methodologies, data inputs. and parameter estimation techniques. A number of offline analyses used in lieu of RFM modeling components are also described. This documentation report serves three purposes. First, it is a reference document for model analysts, model users, and the public interested in the construction and application of the RFM. Second, it meets the legal requirement of the Energy Information Administration (EIA) to provide adequate documentation in support of its models. Finally, such documentation facilitates continuity in EIA model development by providing information sufficient to perform model enhancements and data updates as part of EIA's ongoing mission to provide analytical and forecasting information systems

  12. Using Specification and Description Language (SDL) for capturing and reusing human experts' knowledge

    International Nuclear Information System (INIS)

    Far, B.H.; Koono, Zenya

    1994-01-01

    Conventional knowledge engineering techniques for acquiring experts' knowledge can not produce quality knowledge due to improper knowledge documentation and informal knowledge acquisition method. We propose a new method for knowledge documentation and acquisition using Specification and Description Language (SDL). SDL is used to describe both the target system and the reasoning process. The main idea is to follow deterministic problem solving behavior of human experts and document it. Then knowledge can be extracted by comparing documents of the successive steps. This knowledge is recorded and reused in similar or novel cases. We present an implementation of this method in a tool for software design. The implemented system consists of a SDL CASE tool and an expert system for applying the design knowledge. This system serves as an experimental platform for the study of human design by simulating the design at the lowest level. However, we have found that by acquiring enough domain knowledge, this system can simulate general problem solving of human experts. (author)

  13. 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...

  14. Solar Energy System Description Document: Scattergood School, Site ID 009, PON 2249.

    Science.gov (United States)

    International Business Machines Corp., Huntsville, AL.

    Described are the components, functions, and monitoring instrumentation of a solar heating system at Scattergood School, a Quaker school located in Iowa. The system provides the school gymnasium's space heating and preheating for domestic hot water. This project was constructed and is being evaluated under the United States Department of Energy's…

  15. The documentation of product configuration systems: A framework and an IT solution

    DEFF Research Database (Denmark)

    Shafiee, Sara; Hvam, Lars; Haug, Anders

    2017-01-01

    for maintenance, further development, system quality and communication with domain experts. Product models are the main communication and documentation tools used in PCS projects. Recent studies have shown that up-to-date documentation for the PCS is often lacking due to the significant amount of work required...... system is proposed that is capable of retrieving knowledge from the PCS and thus generating the product model. Our framework and IT documentation system were developed and tested at a case company on five different projects. The results confirm that benefits can be achieved by using the proposed...

  16. Idaho National Laboratory Ten-Year Site Plan Project Description Document

    Energy Technology Data Exchange (ETDEWEB)

    Not Listed

    2012-03-01

    This document describes the currently active and proposed infrastructure projects listed in Appendix B of the Idaho National Laboratory 2013-2022 Ten Year Site Plan (DOE/ID-11449). It was produced in accordance with Contract Data Requirements List I.06. The projects delineated in this document support infrastructure needs at INL's Research and Education Campus, Materials and Fuels Complex, Advanced Test Reactor Complex and the greater site-wide area. The projects provide critical infrastructure needed to meet current and future INL opereational and research needs. Execution of these projects will restore, rebuild, and revitalize INL's physical infrastructure; enhance program execution, and make a significant contribution toward reducing complex-wide deferred maintenance.

  17. 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)

  18. 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...

  19. Green-function description of dense polymeric systems

    NARCIS (Netherlands)

    Schoot, van der P.P.A.M.

    2000-01-01

    A self-consistent Green-function description of concentrated polymer solutions and dense polymeric melts is presented. The method, which applies to both uniform and nonuniform systems, is used in this work to calculate the static structure factor of a homogeneous fluid of Gaussian model chains.

  20. Description and Analysis Pattern for Theses and Dissertations

    Directory of Open Access Journals (Sweden)

    Sirous Alidousti

    2009-07-01

    Full Text Available Dissertations and theses that are generated in course of research at PhD and Masters levels are considered to be important scientific documents in every country. Data description and analysis of such documents collected together, could automatically - especially when compared with data from other resources - provide new information that is very valuable. Nevertheless, no comprehensive, integrated pattern exists for such description and analysis. The present paper offers the findings of a research conducted for devising an information analysis pattern for dissertations and theses. It also puts forward information categories derived from such documents that could be described and analyzed.

  1. Field-Testing a PC Electronic Documentation System using the Clinical Care Classification© System with Nursing Students

    Directory of Open Access Journals (Sweden)

    Jennifer E. Mannino

    2011-01-01

    Full Text Available Schools of nursing are slow in training their students to keep up with the fast approaching era of electronic healthcare documentation. This paper discusses the importance of nursing documentation, and describes the field-testing of an electronic health record, the Sabacare Clinical Care Classification (CCC© system. The PC-CCC©, designed as a Microsoft Access® application, is an evidence-based electronic documentation system available via free download from the internet. A sample of baccalaureate nursing students from a mid-Atlantic private college used this program to document the nursing care they provided to patients during their sophomore level clinical experience. This paper summarizes the design, training, and evaluation of using the system in practice.

  2. EIA model documentation: Electricity market module - electricity fuel dispatch

    International Nuclear Information System (INIS)

    1997-01-01

    This report documents the National Energy Modeling System Electricity Fuel Dispatch Submodule (EFD), a submodule of the Electricity Market Module (EMM) as it was used for EIA's Annual Energy Outlook 1997. It replaces previous documentation dated March 1994 and subsequent yearly update revisions. The report catalogues and describes the model assumptions, computational methodology, parameter estimation techniques, model source code, and forecast results generated through the synthesis and scenario development based on these components. This document serves four purposes. First, it is a reference document providing a detailed description of the model for reviewers and potential users of the EFD including energy experts at the Energy Information Administration (EIA), other Federal agencies, state energy agencies, private firms such as utilities and consulting firms, and non-profit groups such as consumer and environmental groups. Second, this report meets the legal requirement of the Energy Information Administration (EIA) to provide adequate documentation in support of its statistical and forecast reports. Third, it facilitates continuity in model development by providing documentation which details model enhancements that were undertaken for AE097 and since the previous documentation. Last, because the major use of the EFD is to develop forecasts, this documentation explains the calculations, major inputs and assumptions which were used to generate the AE097

  3. EIA model documentation: Electricity market module - electricity fuel dispatch

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-01-01

    This report documents the National Energy Modeling System Electricity Fuel Dispatch Submodule (EFD), a submodule of the Electricity Market Module (EMM) as it was used for EIA`s Annual Energy Outlook 1997. It replaces previous documentation dated March 1994 and subsequent yearly update revisions. The report catalogues and describes the model assumptions, computational methodology, parameter estimation techniques, model source code, and forecast results generated through the synthesis and scenario development based on these components. This document serves four purposes. First, it is a reference document providing a detailed description of the model for reviewers and potential users of the EFD including energy experts at the Energy Information Administration (EIA), other Federal agencies, state energy agencies, private firms such as utilities and consulting firms, and non-profit groups such as consumer and environmental groups. Second, this report meets the legal requirement of the Energy Information Administration (EIA) to provide adequate documentation in support of its statistical and forecast reports. Third, it facilitates continuity in model development by providing documentation which details model enhancements that were undertaken for AE097 and since the previous documentation. Last, because the major use of the EFD is to develop forecasts, this documentation explains the calculations, major inputs and assumptions which were used to generate the AE097.

  4. Documenting control system functionality for digital control implementations

    International Nuclear Information System (INIS)

    Harber, J.; Borairi, M.; Tikku, S.; Josefowicz, A.

    2006-01-01

    In past CANDU designs, plant control was accomplished by a combination of digital control computers, analogue controllers, and hardwired relay logic. Functionality for these various control systems, each using different hardware, was documented in varied formats such as text based program specifications, relay logic diagrams, and other various specification documents. The choice of formats was influenced by the hardware used and often required different specialized skills for different applications. The programmable electronic systems in new CANDU designs are realized in a manner consistent with latest international standards (e.g., the IEC 61513 standard). New CANDU designs make extensive use of modern digital control technology, with the benefit that functionality can be implemented on a limited number of control platforms, reducing development and maintenance cost. This approach can take advantage of tools that allow the plant control system functional and performance requirements to be documented using graphical representations. Modern graphical methods supplemented by information databases can be used to provide a clear and comprehensive set of requirements for software and system development. Overview diagrams of system functionality provide a common understanding of the system boundaries and interfaces. Important requirements are readily traced through the development process. This improved reviewability helps to ensure consistency with the safety and and production design requirements of the system. Encapsulation of commonly used functions into custom-defined function blocks, such as typical motor control centre interfaces, process interlocks, median selects etc, eases the burden on designers to understand and analyze the detailed functionality of each instance of use of this logic. A library of encapsulated functions will be established for complex functions that are reused in the control logic development. By encapsulation and standardisation of such

  5. Documentation Driven Development for Complex Real-Time Systems

    Science.gov (United States)

    2004-12-01

    This paper presents a novel approach for development of complex real - time systems , called the documentation-driven development (DDD) approach. This... time systems . DDD will also support automated software generation based on a computational model and some relevant techniques. DDD includes two main...stakeholders to be easily involved in development processes and, therefore, significantly improve the agility of software development for complex real

  6. 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).

  7. System Description for the K-25/K-27 D and D Project Polyurethane Foam Delivery System, East Tennessee Technology Park, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    Boris, G.

    2008-01-01

    The Foam Delivery System used in the decontamination and decommissioning (D and D) project for the K-25/K-27 Buildings at the East Tennessee Technology Park (ETTP) is comprised of a trailer-mounted Gusmer(reg s ign) H20/35 Pro-TEC Proportioning Unit and the associated equipment to convey electrical power, air, and foam component material to the unit. This high-pressure, plural-component polyurethane foam pouring system will be used to fill process gas and non-process equipment/piping (PGE/P) within the K-25/K-27 Buildings with polyurethane foam to immobilize contaminants prior to removal. The system creates foam by mixing isocyanate and polyol resin (Resin) component materials. Currently, the project plans to utilize up to six foaming units simultaneously during peak foaming activities. Also included in this system description are the foam component material storage containers that will be used for storage of the component material drums in a staging area outside of the K-25/K-27 Buildings. The Foam Delivery System and foam component material storage enclosures (i.e., Foaming Component Protective Enclosures) used to store polymeric methylene diphenyl diisocyanate (PMDI) component material are identified as Safety Significant (SS) Structures, Systems and Components (SSC) in the Documented Safety Analysis (DSA) for the project, Documented Safety Analysis for the K-25 and K-27 Facilities at the East Tennessee Technology Park, Oak Ridge, Tennessee, DSA-ET-K-25/K-27-0001

  8. Information Management Platform for Data Analytics and Aggregation (IMPALA) System Design Document

    Science.gov (United States)

    Carnell, Andrew; Akinyelu, Akinyele

    2016-01-01

    The System Design document tracks the design activities that are performed to guide the integration, installation, verification, and acceptance testing of the IMPALA Platform. The inputs to the design document are derived from the activities recorded in Tasks 1 through 6 of the Statement of Work (SOW), with the proposed technical solution being the completion of Phase 1-A. With the documentation of the architecture of the IMPALA Platform and the installation steps taken, the SDD will be a living document, capturing the details about capability enhancements and system improvements to the IMPALA Platform to provide users in development of accurate and precise analytical models. The IMPALA Platform infrastructure team, data architecture team, system integration team, security management team, project manager, NASA data scientists and users are the intended audience of this document. The IMPALA Platform is an assembly of commercial-off-the-shelf (COTS) products installed on an Apache-Hadoop platform. User interface details for the COTS products will be sourced from the COTS tools vendor documentation. The SDD is a focused explanation of the inputs, design steps, and projected outcomes of every design activity for the IMPALA Platform through installation and validation.

  9. Title list of documents made publicly available. Volume 16, Number 5

    Energy Technology Data Exchange (ETDEWEB)

    1994-07-01

    The Title List of Documents Made Publicly Available contains descriptions of the information received and generated by the US Nuclear Regulatory Commission (NRC). This information includes (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials and (2) nondocketed material received and generated by NRC pertinent to its role as a regulatory agency. As used here, docketed does not refer to Court dockets; it refers to the system by which NRC maintains its regulatory records. This series of documents is indexed by a Personal Author Index, a Corporate Source Index, and a Report Number Index.

  10. Title list of documents made publicly available. Volume 16, Number 5

    International Nuclear Information System (INIS)

    1994-07-01

    The Title List of Documents Made Publicly Available contains descriptions of the information received and generated by the US Nuclear Regulatory Commission (NRC). This information includes (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials and (2) nondocketed material received and generated by NRC pertinent to its role as a regulatory agency. As used here, docketed does not refer to Court dockets; it refers to the system by which NRC maintains its regulatory records. This series of documents is indexed by a Personal Author Index, a Corporate Source Index, and a Report Number Index

  11. Title list of documents made publicly available, April 1-30, 1988

    International Nuclear Information System (INIS)

    1988-06-01

    This document is a monthly publication descriptions of the information received and generated by the U.S. Nuclear Regulatory commission (NRC). This information includes (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials and (2) nondocketed material received and generated by NRC pertinent to its role as a regulatory agency. As used her, docketed does no refer to Court dockets; it refers to the system by which NRC maintains its regulatory records. This series of documents is indexed by a Personal Author Index, a Corporate Source Index, and a Report Number Index

  12. Documents made publicly available. Title lists, September 1-30, 1979

    International Nuclear Information System (INIS)

    1979-01-01

    The Title List of Documents Made Publicly Available is a monthly publication. It contains descriptions of the information received and generated by the US Nuclear Regulatory Commission (NRC). This information includes (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials and (2) nondocketed material received and generated by NRC pertinent to its role as a regulatory agency. As used here, docketed does not refer to Court dockets; it refers to the system by which NRC maintains its regulatory records. This series of documents is indexed by a Personal Author Index, a Corporate Source Index, and a Report Number Index

  13. 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

  14. U-AVLIS feed conversion using continuous metallothermic reduction of UF4: System description and cost estimate

    International Nuclear Information System (INIS)

    1994-04-01

    The purpose of this document is to present a system description and develop baseline capital and operating cost estimates for commercial facilities which produced U-Fe feedstock for AVLIS enrichment plants using the continuous fluoride reduction (CFR) process. These costs can then be used together with appropriate economic assumptions to calculate estimated unit costs to the AVLIS plant owner (or utility customer) for such conversion services. Six cases are being examined. All cases assume that the conversion services are performed by a private company at a commercial site which has an existing NRC license to possess source material and which has existing uranium processing operations. The cases differ in terms of annual production capacity and whether the new process system is installed in a new building or in an existing building on the site. The six cases are summarized here

  15. On the thermodynamic description of real systems

    International Nuclear Information System (INIS)

    Bernardes, N.

    1984-01-01

    A new method of approach to the theory of the thermodynamic properties of real systems is proposed, to include interactions among the constituent particles of the system. The method consists in obtaining the entropy of a real system from the entropy of the corresponding ideal system by a translation in the internal energy and other relevant extensive variables. The usefulness of the method is displayed by application to the cases of: (i) real gases, and (ii) spin paramagnetism with interactions among spins. It is shown that this description corresponds to a generalization of the molecular field approximation. (Author) [pt

  16. Electronic document management system analysis report and system plan for the Environmental Restoration Program

    International Nuclear Information System (INIS)

    Frappaolo, C.

    1995-09-01

    Lockheed Martin Energy Systems, Inc. (LMES) has established and maintains Document Management Centers (DMCs) to support Environmental Restoration Program (ER) activities undertaken at three Oak Ridge facilities: Oak Ridge National Laboratory, Oak Ridge K-25 Site, Oak Ridge Y-12 Plant; and two sister sites: Portsmouth Gaseous Diffusion Plant in Portsmouth, Ohio, and Paducah Gaseous Diffusion Plant in Paducah, Kentucky. The role of the DMCs is to receive, store, retrieve, and properly dispose of records. In an effort to make the DMCs run more efficiently and to more proactively manage the records' life cycles from cradle to grave, ER has decided to investigate ways in which Electronic Document Management System (EDMS) technologies can be used to redefine the DMCs and their related processes. Specific goals of this study are tightening control over the ER documents, establishing and enforcing record creation and retention procedures, speeding up access to information, and increasing the accessibility of information. A working pilot of the solution is desired within the next six months. Based on a series of interviews conducted with personnel from each of the DMCs, key management, and individuals representing related projects, it is recommended that ER utilize document management, full-text retrieval, and workflow technologies to improve and automate records management for the ER program. A phased approach to solution implementation is suggested starting with the deployment of an automated storage and retrieval system at Portsmouth. This should be followed with a roll out of the system to the other DMCs, the deployment of a workflow-enabled authoring system at Portsmouth, and a subsequent roll out of this authoring system to the other sites

  17. Description of Transmutation Library for Fuel Cycle System Analyses

    International Nuclear Information System (INIS)

    Piet, Steven J.; Bays, Samuel E.; Hoffman, Edward A.

    2010-01-01

    This report documents the Transmutation Library that is used in Fuel Cycle System Analyses. This version replaces the 2008 version.(Piet2008) The Transmutation Library has the following objectives: (1) Assemble past and future transmutation cases for system analyses. (2) For each case, assemble descriptive information such as where the case was documented, the purpose of the calculation, the codes used, source of feed material, transmutation parameters, and the name of files that contain raw or source data. (3) Group chemical elements so that masses in separation and waste processes as calculated in dynamic simulations or spreadsheets reflect current thinking of those processes. For example, the CsSr waste form option actually includes all Group 1A and 2A elements. (4) Provide mass fractions at input (charge) and output (discharge) for each case. (5) Eliminate the need for either ''fission product other'' or ''actinide other'' while conserving mass. Assessments of waste and separation cannot use ''fission product other'' or ''actinide other'' as their chemical behavior is undefined. (6) Catalog other isotope-specific information in one place, e.g., heat and dose conversion factors for individual isotopes. (7) Describe the correlations for how input and output compositions change as a function of UOX burnup (for LWR UOX fuel) or fast reactor (FR) transuranic (TRU) conversion ratio (CR) for either FR-metal or FR-oxide. This document therefore includes the following sections: (1) Explanation of the data set information, i.e., the data that describes each case. In no case are all of the data presented in the Library included in previous documents. In assembling the Library, we return to raw data files to extract the case and isotopic data, into the specified format. (2) Explanation of which isotopes and elements are tracked. For example, the transition metals are tracked via the following: two Zr isotopes, Zr-other, Tc99, Tc-other, two Mo-Ru-Rh-Pd isotopes, Mo

  18. 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)

  19. 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

  20. 44 CFR 334.5 - GMR system description.

    Science.gov (United States)

    2010-10-01

    ... problems. (b) Stage 2, Crisis Management. During the crisis management stage, GMR plans are reviewed and... developed). For example, a Federal department or agency might divide “Crisis Management” into two, three, or... 44 Emergency Management and Assistance 1 2010-10-01 2010-10-01 false GMR system description. 334.5...

  1. 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

  2. Accelerator System Model (ASM) user manual with physics and engineering model documentation. ASM version 1.0

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1993-07-01

    The Accelerator System Model (ASM) is a computer program developed to model proton radiofrequency accelerators and to carry out system level trade studies. The ASM FORTRAN subroutines are incorporated into an intuitive graphical user interface which provides for the {open_quotes}construction{close_quotes} of the accelerator in a window on the computer screen. The interface is based on the Shell for Particle Accelerator Related Codes (SPARC) software technology written for the Macintosh operating system in the C programming language. This User Manual describes the operation and use of the ASM application within the SPARC interface. The Appendix provides a detailed description of the physics and engineering models used in ASM. ASM Version 1.0 is joint project of G. H. Gillespie Associates, Inc. and the Accelerator Technology (AT) Division of the Los Alamos National Laboratory. Neither the ASM Version 1.0 software nor this ASM Documentation may be reproduced without the expressed written consent of both the Los Alamos National Laboratory and G. H. Gillespie Associates, Inc.

  3. Honeywell Modular Automation System Computer Software Documentation

    International Nuclear Information System (INIS)

    STUBBS, A.M.

    2000-01-01

    The purpose of this Computer Software Document (CSWD) is to provide configuration control of the Honeywell Modular Automation System (MAS) in use at the Plutonium Finishing Plant (PFP). This CSWD describes hardware and PFP developed software for control of stabilization furnaces. The Honeywell software can generate configuration reports for the developed control software. These reports are described in the following section and are attached as addendum's. This plan applies to PFP Engineering Manager, Thermal Stabilization Cognizant Engineers, and the Shift Technical Advisors responsible for the Honeywell MAS software/hardware and administration of the Honeywell System

  4. Software requirements specification document for the AREST code development

    International Nuclear Information System (INIS)

    Engel, D.W.; McGrail, B.P.; Whitney, P.D.; Gray, W.J.; Williford, R.E.; White, M.D.; Eslinger, P.W.; Altenhofen, M.K.

    1993-11-01

    The Analysis of the Repository Source Term (AREST) computer code was selected in 1992 by the U.S. Department of Energy. The AREST code will be used to analyze the performance of an underground high level nuclear waste repository. The AREST code is being modified by the Pacific Northwest Laboratory (PNL) in order to evaluate the engineered barrier and waste package designs, model regulatory compliance, analyze sensitivities, and support total systems performance assessment modeling. The current version of the AREST code was developed to be a very useful tool for analyzing model uncertainties and sensitivities to input parameters. The code has also been used successfully in supplying source-terms that were used in a total systems performance assessment. The current version, however, has been found to be inadequate for the comparison and selection of a design for the waste package. This is due to the assumptions and simplifications made in the selection of the process and system models. Thus, the new version of the AREST code will be designed to focus on the details of the individual processes and implementation of more realistic models. This document describes the requirements of the new models that will be implemented. Included in this document is a section describing the near-field environmental conditions for this waste package modeling, description of the new process models that will be implemented, and a description of the computer requirements for the new version of the AREST code

  5. Rock Visualization System. Technical description (RVS v.3.5)

    Energy Technology Data Exchange (ETDEWEB)

    Curtis, P.; Elfstroem, M.; Markstroem, I. [FB Engineering, Goeteborg (Sweden)

    2004-03-01

    The Rock Visualization System (RVS) has been developed by SKB for use in visualizing geological and engineering data in 3D. The purpose of this report is to provide a technical description of RVS aimed at potential program users and interested parties as well as fulfilling the function of a more general RVS reference that can be cited when writing other technical reports. It is a description of RVS version 3.5. Updated versions of this report or addenda will be made available following further development of RVS and the release of subsequent versions of the program. The report covers the following main items: Technical description of the program with illustrations and examples; Limitations of the program and of functionality. For most RVS functions step-by-step tutorials are available describing how a particular function can be used to carryout a specific task. A complete set of updated tutorials is issued with each new version release of the RVS program. However, the tutorials do not cover all the possible uses of all the individual functions but rather give an overall view of their functionality. A detailed description of every RVS function and how it can be used is included in the RVS online Help system.

  6. Rock Visualization System. Technical description (RVS v.3.5)

    International Nuclear Information System (INIS)

    Curtis, P.; Elfstroem, M.; Markstroem, I.

    2004-03-01

    The Rock Visualization System (RVS) has been developed by SKB for use in visualizing geological and engineering data in 3D. The purpose of this report is to provide a technical description of RVS aimed at potential program users and interested parties as well as fulfilling the function of a more general RVS reference that can be cited when writing other technical reports. It is a description of RVS version 3.5. Updated versions of this report or addenda will be made available following further development of RVS and the release of subsequent versions of the program. The report covers the following main items: Technical description of the program with illustrations and examples; Limitations of the program and of functionality. For most RVS functions step-by-step tutorials are available describing how a particular function can be used to carryout a specific task. A complete set of updated tutorials is issued with each new version release of the RVS program. However, the tutorials do not cover all the possible uses of all the individual functions but rather give an overall view of their functionality. A detailed description of every RVS function and how it can be used is included in the RVS online Help system

  7. On the perceived usefulness of risk descriptions for decision-making in disaster risk management

    International Nuclear Information System (INIS)

    Lin, Lexin; Nilsson, Anders; Sjölin, Johan; Abrahamsson, Marcus; Tehler, Henrik

    2015-01-01

    Managing risk using an “all-hazards” and “whole of society”-approach involves extensive communication of risk descriptions among many stakeholders. In the present study we investigate how professionals working with disaster risk management in such contexts perceive the usefulness of different descriptions of risk. Empirical data from the Swedish disaster risk management system were used in an attempt to investigate the aspects of a risk description that affect its usefulness (as perceived by professionals). Thirty-three local municipal risk and vulnerability assessments (RVA documents) produced in the region of Scania in 2012 were analyzed in terms of six variables. The documents were then ranked by professionals based on their perceived usefulness for decision-making. Statistical analysis was conducted to identify any possible correlations between the overall ranking of the usefulness of the municipal RVA:s and each of the variables. We conclude that the way the likelihood and consequences of scenarios are described influence the perceived usefulness of a risk description. Furthermore, whether descriptions of scenarios are included in a risk description or not, and whether background information concerning the likelihood of scenarios are included also influence perceived usefulness of risk descriptions. - Highlights: • Written communication of risk between professionals is investigated. • The way likelihood is described influences a risk description's usefulness. • The way consequences are described influence a risk description's usefulness. • Whether background information is included in a risk description influences its usefulness

  8. The Norwegian Electric Power System - System Description and Future Developments; Norsk kraftforsyning - dagens system og fremtidig utvikling

    Energy Technology Data Exchange (ETDEWEB)

    Hagen, Janne Merete; Nystuen, Kjell Olav; Fridheim, Haavard; Rutledal, Frode

    2000-09-01

    This report presents a description of the present Norwegian electric power system, as well as a discussion of emerging trends and future developments in this system. The report provides the basis for FFI's current vulnerability analysis of the electric power system. Norway's electric power system is getting increasingly complex, due to a large-scale implementation of electronic components and information systems. Workforce reductions and efficiency improvements dominate the development of the electric power sector. Norway is also becoming increasingly dependent on foreign power sources. These trends provide for an entirely different electric power system than just a few years ago. Also, these trends make it virtually impossible to present a ''static'' description of the system. Thus, the report also contains a scenario, describing possible future developments of the system until 2010. (author)

  9. Program prioritization system user requirements document for Gas Cooled Reactor Associates

    International Nuclear Information System (INIS)

    1981-01-01

    Efficient management of the national HTGR program requires the establishment of an information system that will facilitate a more rational allocation of resources and task prioritization consistent with program policies. The system described in this document provides a data analysis mechanism for processing top level summary status and planning information in a rapid, timely and selective manner. Data produced by the system can be used by management to provide a rational basis for prioritizing tasks, evaluating program changes and program planning regarding costs, schedules and overall program development logic. The purpose of this document is to delineate the program prioritization system (PPS) requirements for use as a guide to acquiring and implementing the system

  10. Automated 741 document preparation: Oak Ridge National Laboratory's Automated Safeguards Information System (OASIS)

    International Nuclear Information System (INIS)

    Austin, H.C.; Gray, L.M.

    1982-01-01

    OASIS has been providing for Oak Ridge National Laboratory's total safeguards needs since being place on line in April 1980. The system supports near real-time nuclear materials safeguards and accountability control. The original design of OASIS called for an automated facsimile of a 741 document to be prepared as a functional by-product of updating the inventory. An attempt was made to utilize, intact, DOE-Albuquerque's automated 741 system to generate the facsimile; however, the five page document produced proved too cumbersome. Albuquerque's programs were modified to print an original 741 document utilizing standard DOE/NRC 741 forms. It is felt that the best features of both the automated and manually generated 741 documents have been incorporated. Automation of the source data for 741 shipping documents produces greater efficiency while reducing possible errors. Through utilization of the standard DOE/NRC form, continuity within the NMMSS system is maintained, thus minimizing the confusion and redundancy associated with facsimiles. OASIS now fulfills the original concept of near real-time accountability by furnishing a viable 741 document as a function of updating the inventory

  11. An integrated information retrieval and document management system

    Science.gov (United States)

    Coles, L. Stephen; Alvarez, J. Fernando; Chen, James; Chen, William; Cheung, Lai-Mei; Clancy, Susan; Wong, Alexis

    1993-01-01

    This paper describes the requirements and prototype development for an intelligent document management and information retrieval system that will be capable of handling millions of pages of text or other data. Technologies for scanning, Optical Character Recognition (OCR), magneto-optical storage, and multiplatform retrieval using a Standard Query Language (SQL) will be discussed. The semantic ambiguity inherent in the English language is somewhat compensated-for through the use of coefficients or weighting factors for partial synonyms. Such coefficients are used both for defining structured query trees for routine queries and for establishing long-term interest profiles that can be used on a regular basis to alert individual users to the presence of relevant documents that may have just arrived from an external source, such as a news wire service. Although this attempt at evidential reasoning is limited in comparison with the latest developments in AI Expert Systems technology, it has the advantage of being commercially available.

  12. Advanced Transport Operating System (ATOPS) control display unit software description

    Science.gov (United States)

    Slominski, Christopher J.; Parks, Mark A.; Debure, Kelly R.; Heaphy, William J.

    1992-01-01

    The software created for the Control Display Units (CDUs), used for the Advanced Transport Operating Systems (ATOPS) project, on the Transport Systems Research Vehicle (TSRV) is described. Module descriptions are presented in a standardized format which contains module purpose, calling sequence, a detailed description, and global references. The global reference section includes subroutines, functions, and common variables referenced by a particular module. The CDUs, one for the pilot and one for the copilot, are used for flight management purposes. Operations performed with the CDU affects the aircraft's guidance, navigation, and display software.

  13. A maintenance support system with document handling capability

    International Nuclear Information System (INIS)

    Fukumoto, A.; Tsumura, K.; Fujii, M.; Tai, I.; Makimo, M.; Watanabe, T.

    1990-01-01

    An operation and maintenance support system, called 'Advanced Man-Machine System for Nuclear Power Plants' (MMS-NPP) is under development with the support of the Japanese Government. Taking full advantage of Artificial Intelligence technology, the system aims to enhance the capability of already developed 'Computerized Operator Support System (COSS)' and gives wider and more advanced support for operation and maintenance. With a brief overview of MMS-NPP, this paper describes a support system for plant patrol and equipment inspection. The system gives guidance for plant patrol and for equipment inspection and provides easy access to plant drawings and documents. A unique knowledge acquisition method, utilizing image processing technology, was proposed in building the system

  14. A Document Analysis of Teacher Evaluation Systems Specific to Physical Education

    Science.gov (United States)

    Norris, Jason M.; van der Mars, Hans; Kulinna, Pamela; Kwon, Jayoun; Amrein-Beardsley, Audrey

    2017-01-01

    Purpose: The purpose of this document analysis study was to examine current teacher evaluation systems, understand current practices, and determine whether the instrumentation is a valid measure of teaching quality as reflected in teacher behavior and effectiveness specific to physical education (PE). Method: An interpretive document analysis…

  15. Electronic Document Management Systems: Where Are They Today?

    Science.gov (United States)

    Koulopoulos, Thomas M.; Frappaolo, Carl

    1993-01-01

    Discusses developments in document management systems based on a survey of over 400 corporations and government agencies. Text retrieval and imaging markets, architecture and integration, purchasing plans, and vendor market leaders are covered. Five graphs present data on user preferences for improvements. A sidebar article reviews the development…

  16. Title list of documents made publicly available, March 1-31, 1982

    International Nuclear Information System (INIS)

    1982-01-01

    The Title List of Documents Made Publicly Available is a monthly publication. It contains descriptions of the information received and generated by the US Nuclear Regulatory Commission (NRC). This information includes (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials and (2) nondocketed material received and generated by NRC pertinent to its role as a regulatory agency. As used here, docketed does not refer to Court dockets; it refers to the system by which NRC maintains its regulatory records. This series of documents is indexed by a Personal Author Index, a Corporate Source Index, and a Report Number Index

  17. Title list of documents made publicly available. Volume 17, No. 5

    International Nuclear Information System (INIS)

    1995-07-01

    The Title List of Documents Made Publicly Available is a monthly publication. It contains descriptions of the information received and generated by the US Nuclear Regulatory Commission (NRC). This information includes (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials and (3) nondocketed material received and generated by NRC pertinent to its role as a regulatory agency. As used here, docketed does not refer to Court dockets; it refers to the system by which NRC maintains its regulatory records. This series of documents is indexed by a Personal Author Index, a Corporate Source Index, and a Report Number Index

  18. Title list of documents made publicly available, November 1-30, 1979

    International Nuclear Information System (INIS)

    1979-11-01

    The Title List of Documents Made Publicly Available is a monthly publication. It contains descriptions of the information received and generated by the US Nuclear Regulatory Commission (NRC). This information includes (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials and (2) nondocketed material received and generated by NRC pertinent to its role as a regulatory agency. As used here, docketed does not refer to Court dockets; it refers to the system by which NRC maintains its regulatory records. This series of documents is indexed by a Personal Author Index, a Corporate Source Index, and a Report Number Index

  19. Title list of documents made publicly available, December 1-31, 1994

    International Nuclear Information System (INIS)

    1995-02-01

    The Title List of Documents Made Publicly Available is a monthly publication. It contains descriptions of the information received and generated by the US Nuclear Regulatory Commission (NRC). This information includes (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials and (2) nondocketed material received and generated by NRC pertinent to its role as a regulatory agency. As used here, docketed does not refer to Court dockets; it refers to the system by which NRC maintains its regulatory records. This series of documents is indexed by a Personal Author Index, a Corporate Source Index, and a Report Number Index

  20. Title list of documents made publicly available. Volume 17, No. 7

    International Nuclear Information System (INIS)

    1995-09-01

    The Title List of Documents Made Publicly Available is a monthly publication. It contains descriptions of the information received and generated by the US Nuclear Regulatory Commission (NRC). This information includes (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials and (2) nondocketed material received and generated by NRC pertinent to its role as a regulatory agency. As used here, docketed does not refer to Court dockets; it refers to the system by which NRC maintains its regulatory records. This series of documents is indexed by a Personal Author Index, a Corporate Source Index, and a Report Number Index

  1. Title List of Documents Made Publicly Available, December 1-31, 1986

    International Nuclear Information System (INIS)

    1987-02-01

    The Title List of Documents Made Publicly Available is a monthly publication. It contains descriptions of the information received and generated by the US Nuclear Regulatory Commission (NRC). This information includes (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials and (2) nondocketed material received and generated by NRC pertinent to its role as a regulatory agency. As used here, docketed does not refer to Court dockets; it refers to the system by which NRC maintains its regulatory records. This series of documents is indexed by a Personal Author Index, a Corporate Source Index, and a Report Number Index

  2. Title list of documents made publicly available. Volume 17, No. 5

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-07-01

    The Title List of Documents Made Publicly Available is a monthly publication. It contains descriptions of the information received and generated by the US Nuclear Regulatory Commission (NRC). This information includes (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials and (3) nondocketed material received and generated by NRC pertinent to its role as a regulatory agency. As used here, docketed does not refer to Court dockets; it refers to the system by which NRC maintains its regulatory records. This series of documents is indexed by a Personal Author Index, a Corporate Source Index, and a Report Number Index.

  3. Title list of documents made publicly available, February 1--28, 1994

    International Nuclear Information System (INIS)

    1994-04-01

    The Title List of Documents Made Publicly Available is a monthly publication. It contains descriptions of the information received and generated by the US Nuclear Regulatory Commission (NRC). This information includes (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials and (2) nondocketed material received and generated by NRC pertinent to its role as a regulatory agency. As used here, docketed does not refer to Court dockets; it refers to the system by which NRC maintains its regulatory records. This series of documents is indexed by a Personal Author Index, a Corporate Source Index, and a Report Number Index

  4. Title list of documents made publicly available. Volume 17, No. 7

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-09-01

    The Title List of Documents Made Publicly Available is a monthly publication. It contains descriptions of the information received and generated by the US Nuclear Regulatory Commission (NRC). This information includes (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials and (2) nondocketed material received and generated by NRC pertinent to its role as a regulatory agency. As used here, docketed does not refer to Court dockets; it refers to the system by which NRC maintains its regulatory records. This series of documents is indexed by a Personal Author Index, a Corporate Source Index, and a Report Number Index.

  5. Title list of documents made publicly available, August 1--31, 1989

    International Nuclear Information System (INIS)

    1989-10-01

    The Title List of Documents Made Publicly Available is a monthly publication. It contains descriptions of the information received and generated by the US Nuclear Regulatory Commission (NRC). This information includes (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials and (2) nondocketed material received and generated by NRC pertinent to its role as a regulatory agency. As used here, docketed does not refer to Court dockets; it refers to the system by which NRC maintains its regulatory records. This series of documents is indexed by a Personal Author Index, a Corporate Source Index, and a Report Number Index

  6. 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

  7. A consistent description of kinetics and hydrodynamics of quantum Bose-systems

    Directory of Open Access Journals (Sweden)

    P.A.Hlushak

    2004-01-01

    Full Text Available A consistent approach to the description of kinetics and hydrodynamics of many-Boson systems is proposed. The generalized transport equations for strongly and weakly nonequilibrium Bose systems are obtained. Here we use the method of nonequilibrium statistical operator by D.N. Zubarev. New equations for the time distribution function of the quantum Bose system with a separate contribution from both the kinetic and potential energies of particle interactions are obtained. The generalized transport coefficients are determined accounting for the consistent description of kinetic and hydrodynamic processes.

  8. Computerising documentation

    International Nuclear Information System (INIS)

    Anon.

    1992-01-01

    The nuclear power generation industry is faced with public concern and government pressures over safety, efficiency and risk. Operators throughout the industry are addressing these issues with the aid of a new technology - technical document management systems (TDMS). Used for strategic and tactical advantage, the systems enable users to scan, archive, retrieve, store, edit, distribute worldwide and manage the huge volume of documentation (paper drawings, CAD data and film-based information) generated in building, maintaining and ensuring safety in the UK's power plants. The power generation industry has recognized that the management and modification of operation critical information is vital to the safety and efficiency of its power plants. Regulatory pressure from the Nuclear Installations Inspectorate (NII) to operate within strict safety margins or lose Site Licences has prompted the need for accurate, up-to-data documentation. A document capture and management retrieval system provides a powerful cost-effective solution, giving rapid access to documentation in a tightly controlled environment. The computerisation of documents and plans is discussed in this article. (Author)

  9. Universal Documentation System

    Science.gov (United States)

    2012-07-01

    Follow preparation instructions in Section 5.2.1 for the entries ITEM NO. and REMARKS. FLOTATION DURATION: Enter flotation duration of the test unit...Teflon, carbon steel, copper and copper alloys, and stainless steel (martensitic, ferritic, austenitic). • Quantity: Enter the quantity of components...DESCRIPTION 1470 ITEM NO.: FLOTATION DURATION: ELECTRONIC AIDS • TYPE: • POWER OUT (WATTS): • FREQUENCY (MHz): C-22 • MODULATION

  10. U-AVLIS feed conversion using continuous metallothermic reduction of UF{sub 4}: System description and cost estimate

    Energy Technology Data Exchange (ETDEWEB)

    1994-04-01

    The purpose of this document is to present a system description and develop baseline capital and operating cost estimates for commercial facilities which produced U-Fe feedstock for AVLIS enrichment plants using the continuous fluoride reduction (CFR) process. These costs can then be used together with appropriate economic assumptions to calculate estimated unit costs to the AVLIS plant owner (or utility customer) for such conversion services. Six cases are being examined. All cases assume that the conversion services are performed by a private company at a commercial site which has an existing NRC license to possess source material and which has existing uranium processing operations. The cases differ in terms of annual production capacity and whether the new process system is installed in a new building or in an existing building on the site. The six cases are summarized here.

  11. 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

  12. Customer interface document for the Molten Salt Test Loop (MSTL) system.

    Energy Technology Data Exchange (ETDEWEB)

    Pettit, Kathleen; Kolb, William J.; Gill, David Dennis; Briggs, Ronald D.

    2012-03-01

    The National Solar Thermal Test Facility at Sandia National Laboratories has a unique test capability called the Molten Salt Test Loop (MSTL) system. MSTL is a test capability that allows customers and researchers to test components in flowing, molten nitrate salt. The components tested can range from materials samples, to individual components such as flex hoses, ball joints, and valves, up to full solar collecting systems such as central receiver panels, parabolic troughs, or linear Fresnel systems. MSTL provides realistic conditions similar to a portion of a concentrating solar power facility. The facility currently uses 60/40 nitrate 'solar salt' and can circulate the salt at pressure up to 600psi, temperature to 585 C, and flow rate of 400-600GPM depending on temperature. The purpose of this document is to provide a basis for customers to evaluate the applicability to their testing needs, and to provide an outline of expectations for conducting testing on MSTL. The document can serve as the basis for testing agreements including Work for Others (WFO) and Cooperative Research and Development Agreements (CRADA). While this document provides the basis for these agreements and describes some of the requirements for testing using MSTL and on the site at Sandia, the document is not sufficient by itself as a test agreement. The document, however, does provide customers with a uniform set of information to begin the test planning process.

  13. Irreducible descriptive sets of attributes for information systems

    KAUST Repository

    Moshkov, Mikhail; Skowron, Andrzej; Suraj, Zbigniew

    2010-01-01

    . 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

  14. Cold Vacuum Drying facility potable water system design description

    International Nuclear Information System (INIS)

    PITKOFF, C.C.

    1999-01-01

    This document describes the Cold Vacuum Drying Facility (CVDF) potable water (PW) system. The PW system provides potable water to the CVDF for supply to sinks, water closets, urinals, showers, custodial service sinks, drinking fountains, the decontamination shower, supply water to the non-PW systems, and makeup water for the de-ionized water system

  15. The System 80+ Standard Plant design control document. Volume 20

    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 contains 2 technical specifications bases as part of Appendix 16 A Tech Spec Bases. They are TS B3.8 Electrical Power Technical Systems Bases and TS B3.9 Refueling Operations Bases. All 3 parts of section 17 (QA) and all 10 parts of section 18 (Human Factors) of the ADM Design and Analysis are contained in this volume. Topics covered in section 17 are: design phase QA; operations phase QA; and design phase reliability assurance. Topics covered by section 18 are: design team organization; design goals; design process; functional task analysis; control room configuration; information presentation; control and monitoring; verification and validation; and review documents

  16. System design document for the plutonium stabilization and packaging system

    International Nuclear Information System (INIS)

    1996-01-01

    The objective of this system is to stabilize and package plutonium metals and oxides of greater than 50% wt, as well as other selected isotopes, in accordance with the requirements for DOE standards for safe storage of these materials for 50 years. This document describes the highest level design information and user characteristics from an operational perspective. It provides guidance for developing procurement and installation specifications, interface requirements, and test plans

  17. System design document for the plutonium stabilization and packaging system

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-05-08

    The objective of this system is to stabilize and package plutonium metals and oxides of greater than 50% wt, as well as other selected isotopes, in accordance with the requirements for DOE standards for safe storage of these materials for 50 years. This document describes the highest level design information and user characteristics from an operational perspective. It provides guidance for developing procurement and installation specifications, interface requirements, and test plans.

  18. Title list of documents made publicly available, November 1-30, 1995

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-01-01

    The Title List of Documents Made Publicly Available is a monthly publication. It contains descriptions of the information received and generated by the U.S. Nuclear Regulatory Commission (NRC). This information includes (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials and (2) nondocketed material received and generated by NRC pertinent to its role as a regulatory agency. As used here, docketed does not refer to Court dockets; it refers to the system by which NRC maintains its regulatory records. This series of documents is indexed by a Personal Author Index, a Corporate Source Index and a Report Number Index. The docketed information contained in the Title List includes the information formerly issued through the Department of Energy publication Power Reactor Docker Information, last published in January 1979. NRC documents that are publicly available may be examined without charge at the NRC Public Document Room (PDR). Duplicate copies may be obtained for a fee. Standing orders for certain categories of documents are also available. Clients may search for and order desired titles through the PDR computerized Bibliographic Retrieval System, which is accessible both at the PDR and remotely. The PDR is staffed by professional technical librarians, who provide reference assistance to users.

  19. Title list of documents made publicly available, November 1-30, 1995

    International Nuclear Information System (INIS)

    1996-01-01

    The Title List of Documents Made Publicly Available is a monthly publication. It contains descriptions of the information received and generated by the U.S. Nuclear Regulatory Commission (NRC). This information includes (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials and (2) nondocketed material received and generated by NRC pertinent to its role as a regulatory agency. As used here, docketed does not refer to Court dockets; it refers to the system by which NRC maintains its regulatory records. This series of documents is indexed by a Personal Author Index, a Corporate Source Index and a Report Number Index. The docketed information contained in the Title List includes the information formerly issued through the Department of Energy publication Power Reactor Docker Information, last published in January 1979. NRC documents that are publicly available may be examined without charge at the NRC Public Document Room (PDR). Duplicate copies may be obtained for a fee. Standing orders for certain categories of documents are also available. Clients may search for and order desired titles through the PDR computerized Bibliographic Retrieval System, which is accessible both at the PDR and remotely. The PDR is staffed by professional technical librarians, who provide reference assistance to users

  20. NEMS integrating module documentation report

    Energy Technology Data Exchange (ETDEWEB)

    1993-12-14

    The National Energy Modeling System (NEMS) is a computer modeling system that produces a general equilibrium solution for energy supply and demand in the US energy markets. The model achieves a supply and demand balance in the end-use demand regions, defined as the nine Census Divisions, by solving for the prices of each energy type such that the quantities producers are willing to supply equal the quantities consumers wish to consume. The system reflects market economics, industry structure, and energy policies and regulations that influence market behavior. The NEMS Integrating Module is the central integrating component of a complex modeling system. As such, a thorough understanding of its role in the modeling process can only be achieved by placing it in the proper context with respect to the other modules. To that end, this document provides an overview of the complete NEMS model, and includes brief descriptions of the modules with which the Integrating Module interacts. The emphasis and focus, however, is on the structure and function of the Integrating Module of NEMS.

  1. Social Work Assessment Notes: A Comprehensive Outcomes-Based Hospice Documentation System.

    Science.gov (United States)

    Hansen, Angela Gregory; Martin, Ellen; Jones, Barbara L; Pomeroy, Elizabeth C

    2015-08-01

    This article describes the development of an integrated psychosocial patient and caregiver assessment and plan of care for hospice social work documentation. A team of hospice social workers developed the Social Work Assessment Notes as a quality improvement project in collaboration with the information technology department. Using the Social Work Assessment Tool as an organizing framework, this comprehensive hospice social work documentation system is designed to integrate assessment, planning, and outcomes measurement. The system was developed to guide the assessment of patients' and caregivers' needs related to end-of-life psychosocial issues, to facilitate collaborative care plan development, and to measure patient- and family-centered outcomes. Goals established with the patient and the caregiver are documented in the plan of care and become the foundation for patient-centered, strengths-based interventions. Likert scales are used to assign numerical severity levels for identified issues and progress made toward goals and to track the outcome of social work interventions across nine psychosocial constructs. The documentation system was developed for use in an electronic health record but can be used for paper charting. Future plans include automated aggregate outcomes measurement to identify the most effective interventions and best practices in end-of-life care.

  2. Site descriptive modelling - strategy for integrated evaluation

    International Nuclear Information System (INIS)

    Andersson, Johan

    2003-02-01

    The current document establishes the strategy to be used for achieving sufficient integration between disciplines in producing Site Descriptive Models during the Site Investigation stage. The Site Descriptive Model should be a multidisciplinary interpretation of geology, rock mechanics, thermal properties, hydrogeology, hydrogeochemistry, transport properties and ecosystems using site investigation data from deep bore holes and from the surface as input. The modelling comprise the following iterative steps, evaluation of primary data, descriptive and quantitative modelling (in 3D), overall confidence evaluation. Data are first evaluated within each discipline and then the evaluations are checked between the disciplines. Three-dimensional modelling (i.e. estimating the distribution of parameter values in space and its uncertainty) is made in a sequence, where the geometrical framework is taken from the geological model and in turn used by the rock mechanics, thermal and hydrogeological modelling etc. The three-dimensional description should present the parameters with their spatial variability over a relevant and specified scale, with the uncertainty included in this description. Different alternative descriptions may be required. After the individual discipline modelling and uncertainty assessment a phase of overall confidence evaluation follows. Relevant parts of the different modelling teams assess the suggested uncertainties and evaluate the feedback. These discussions should assess overall confidence by, checking that all relevant data are used, checking that information in past model versions is considered, checking that the different kinds of uncertainty are addressed, checking if suggested alternatives make sense and if there is potential for additional alternatives, and by discussing, if appropriate, how additional measurements (i.e. more data) would affect confidence. The findings as well as the modelling results are to be documented in a Site Description

  3. The changes in caregivers' perceptions about the quality of information and benefits of nursing documentation associated with the introduction of an electronic documentation system in a nursing home.

    Science.gov (United States)

    Munyisia, Esther N; Yu, Ping; Hailey, David

    2011-02-01

    To date few studies have compared nursing home caregivers' perceptions about the quality of information and benefits of nursing documentation in paper and electronic formats. With the increased interest in the use of information technology in nursing homes, it is important to obtain information on the benefits of newer approaches to nursing documentation so as to inform investment, organisational and care service decisions in the aged care sector. This study aims to investigate caregivers' perceptions about the quality of information and benefits of nursing documentation before and after the introduction of an electronic documentation system in a nursing home. A self-administered questionnaire survey was conducted three months before, and then six, 18 and 31 months after the introduction of an electronic documentation system. Further evidence was obtained through informal discussions with caregivers. Scores for questionnaire responses showed that the benefits of the electronic documentation system were perceived by the caregivers as provision of more accurate, legible and complete information, and reduction of repetition in data entry, with consequential managerial benefits. However, caregivers' perceptions of relevance and reliability of information, and of their communication and decision-making abilities were perceived to be similar either using an electronic or a paper-based documentation system. Improvement in some perceptions about the quality of information and benefits of nursing documentation was evident in the measurement conducted six months after the introduction of the electronic system, but were not maintained 18 or 31 months later. The electronic documentation system was perceived to perform better than the paper-based system in some aspects, with subsequent benefits to management of aged care services. In other areas, perceptions of additional benefits from the electronic documentation system were not maintained. In a number of attributes, there

  4. Operator-centered technical documentation of the power plant control system. Betreibergerechte, betriebstechnische Dokumentation der Kraftwerks-Leittechnik

    Energy Technology Data Exchange (ETDEWEB)

    Welfonder, E

    1986-01-01

    The report - starting with an overview of the general structure of documentation - includes in chapter 3 an assortment of the main expectations to be had by the technical staff towards control system documentation. These are divided into: general basic requirements; testable compulsory requirements; practical recommendations and information for the manufacturer. In chapter 4 these documentation requirements are reflected to the present state of technical documentation. The main emphasis of the report however is laid on the sample documentation for one control system area presented in chapter 5. This sample documentation is based on a hierarchically structured and function related documentary method developed by the University of Stuttgart on the basis of the derived requirements and the present usual control system documentation. This function-related documentary method proves to be useful, not only for the technical staff in his rapid search for control system disturbances, but also offers - due to its clear and homogeneous meshed structure - considerable advantages for control system planning, projecting and initial start ups. As the presented documentation method is furthermore independent of the control system manufacturers, it is important that all participants try to use it uniformly.

  5. System design description for sampling fuel in K basins

    International Nuclear Information System (INIS)

    Baker, R.B.

    1996-01-01

    This System Design Description provides: (1) statements of the Spent Nuclear Fuel Projects (SNFP) needs requiring sampling of fuel in the K East and K West Basins, (2) the sampling equipment functions and requirements, (3) a general work plan and the design logic being followed to develop the equipment, and (4) a summary description of the design for the sampling equipment. The report summarizes the integrated application of both the subject equipment and the canister sludge sampler in near-term characterization campaigns at K Basins

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

    International Nuclear Information System (INIS)

    Schneider, T.C.

    1996-01-01

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

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

    International Nuclear Information System (INIS)

    Schneider, T.C.

    1995-01-01

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

  8. Tank waste remediation system privatization infrastructure program requirements and document management process guide

    International Nuclear Information System (INIS)

    ROOT, R.W.

    1999-01-01

    This guide provides the Tank Waste Remediation System Privatization Infrastructure Program management with processes and requirements to appropriately control information and documents in accordance with the Tank Waste Remediation System Configuration Management Plan (Vann 1998b). This includes documents and information created by the program, as well as non-program generated materials submitted to the project. It provides appropriate approval/control, distribution and filing systems

  9. Business process modeling for processing classified documents using RFID technology

    Directory of Open Access Journals (Sweden)

    Koszela Jarosław

    2016-01-01

    Full Text Available The article outlines the application of the processing approach to the functional description of the designed IT system supporting the operations of the secret office, which processes classified documents. The article describes the application of the method of incremental modeling of business processes according to the BPMN model to the description of the processes currently implemented (“as is” in a manual manner and target processes (“to be”, using the RFID technology for the purpose of their automation. Additionally, the examples of applying the method of structural and dynamic analysis of the processes (process simulation to verify their correctness and efficiency were presented. The extension of the process analysis method is a possibility of applying the warehouse of processes and process mining methods.

  10. CRAC2 model description

    International Nuclear Information System (INIS)

    Ritchie, L.T.; Alpert, D.J.; Burke, R.P.; Johnson, J.D.; Ostmeyer, R.M.; Aldrich, D.C.; Blond, R.M.

    1984-03-01

    The CRAC2 computer code is a revised version of CRAC (Calculation of Reactor Accident Consequences) which was developed for the Reactor Safety Study. This document provides an overview of the CRAC2 code and a description of each of the models used. Significant improvements incorporated into CRAC2 include an improved weather sequence sampling technique, a new evacuation model, and new output capabilities. In addition, refinements have been made to the atmospheric transport and deposition model. Details of the modeling differences between CRAC2 and CRAC are emphasized in the model descriptions

  11. Detailed description of an SSAC at the facility level for light water moderated (off-load refueled) power reactor facilities

    International Nuclear Information System (INIS)

    Jones, R.J.

    1985-03-01

    This report is intended to provide the technical details of an effective State Systems of Accounting for and Control of Nuclear Material (SSAC) which Member States may use, if they wish, to establish and maintain their SSACs. It is expected that systems designed along the lines described would be effective in meeting the objectives of both national and international systems for nuclear material accounting and control. This document accordingly provides a detailed description of a system for the accounting for and control of nuclear material in an off-load refueled light water moderated power reactor facility which can be used by a facility operator to establish his own system to comply with a national system for nuclear material accounting and control and to facilitate application of IAEA safeguards. The scope of this document is limited to descriptions of the following elements: (1) Nuclear Material Measurements; (2) Measurement Quality; (3) Records and Reports; (4) Physical Inventory Taking; (5) Material Balance Closing

  12. Demonstration Advanced Avionics System (DAAS) function description

    Science.gov (United States)

    Bailey, A. J.; Bailey, D. G.; Gaabo, R. J.; Lahn, T. G.; Larson, J. C.; Peterson, E. M.; Schuck, J. W.; Rodgers, D. L.; Wroblewski, K. A.

    1982-01-01

    The Demonstration Advanced Avionics System, DAAS, is an integrated avionics system utilizing microprocessor technologies, data busing, and shared displays for demonstrating the potential of these technologies in improving the safety and utility of general aviation operations in the late 1980's and beyond. Major hardware elements of the DAAS include a functionally distributed microcomputer complex, an integrated data control center, an electronic horizontal situation indicator, and a radio adaptor unit. All processing and display resources are interconnected by an IEEE-488 bus in order to enhance the overall system effectiveness, reliability, modularity and maintainability. A detail description of the DAAS architecture, the DAAS hardware, and the DAAS functions is presented. The system is designed for installation and flight test in a NASA Cessna 402-B aircraft.

  13. Job Analysis and the Preparation of Job Descriptions. Mendip Papers MP 037.

    Science.gov (United States)

    Saunders, Bob

    This document provides guidelines for conducting job analyses and writing job descriptions. It covers the following topics: the rationale for job descriptions, the terminology of job descriptions, who should write job descriptions, getting the information to write job descriptions, preparing for staff interviews, conducting interviews, writing the…

  14. Title list of documents made publicly available: February 1--28, 1995. Volume 17, Number 2

    International Nuclear Information System (INIS)

    1995-04-01

    This monthly publication contains descriptions of the information received and generated by the US Nuclear Regulatory Commission (NRC). This information includes (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials and (2) nondocketed material received and generated by NRC pertinent to its role as a regulatory agency. As used here, docketed refers to the system by which NRC maintains its regulatory records. This series of documents is indexed by a Personal Author Index, a Corporate Source Index, and a Report Number Index. NRC documents that are publicly available may be examined without charge at the NRC Public Document Room (PDR)

  15. Title list of documents made publicly available: February 1--28, 1995. Volume 17, Number 2

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-04-01

    This monthly publication contains descriptions of the information received and generated by the US Nuclear Regulatory Commission (NRC). This information includes (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials and (2) nondocketed material received and generated by NRC pertinent to its role as a regulatory agency. As used here, docketed refers to the system by which NRC maintains its regulatory records. This series of documents is indexed by a Personal Author Index, a Corporate Source Index, and a Report Number Index. NRC documents that are publicly available may be examined without charge at the NRC Public Document Room (PDR).

  16. An Automated Weather Research and Forecasting (WRF)-Based Nowcasting System: Software Description

    Science.gov (United States)

    2013-10-01

    14. ABSTRACT A Web service /Web interface software package has been engineered to address the need for an automated means to run the Weather Research...An Automated Weather Research and Forecasting (WRF)- Based Nowcasting System: Software Description by Stephen F. Kirby, Brian P. Reen, and...Based Nowcasting System: Software Description Stephen F. Kirby, Brian P. Reen, and Robert E. Dumais Jr. Computational and Information Sciences

  17. Étude Descriptive du Processus D’ÉValuation et de Documentation de la Douleur Postopératoire dans un Hôpital Universitaire

    Directory of Open Access Journals (Sweden)

    Dave A Bergeron

    2011-01-01

    Full Text Available Plusieurs études démontrent que les patients reçoivent souvent un traitement insatisfaisant de la douleur en contexte postopératoire. Le but de la présente étude descriptive était d’examiner et d’analyser diverses données ayant trait au soulagement de 40 patients après une intervention chirurgicale non urgente. Les patients ont rempli un journal de douleur afin d’évaluer le niveau d’intensité et de désagrément engendré par la douleur durant les trois premières journées postopératoires. Une analyse du dossier a permis de vérifier la documentation de l’évaluation de la douleur par le personnel infirmier. Les résultats indiquent que la douleur en contexte postopératoire est peu et inadéquatement évaluée et peu documentée par le personnel infirmier. Lorsque la douleur est évaluée selon une échelle numérique, les infirmières ont tendance à la sous-évaluer en comparaison avec l’évaluation notée par les patients. Pour la première journée postopératoire, l’intensité moyenne de la douleur documentée par les infirmières est de 1,57 (±0,23 sur une échelle numérique de 0 à 10, alors que l’intensité moyenne documentée par les patients est de 3,82 (±0,41. Cette étude fait ainsi ressortir qu’il n’y a pas de corrélation significative entre l’intensité de la douleur documentée par l’infirmière et celle notée par le patient, ce qui peut expliquer en partie un soulagement non optimal.

  18. Civilian Radioactive Waste Management System Requirements Document (CRP)

    International Nuclear Information System (INIS)

    C.A. Kouts

    2006-01-01

    The CRD addresses the requirements of Department of Energy (DOE) Order 413.3-Change 1, ''Program and Project Management for the Acquisition of Capital Assets'', by providing the Secretarial Acquisition Executive (Level 0) scope baseline and the Program-level (Level 1) technical baseline. The Secretarial Acquisition Executive approves the Office of Civilian Radioactive Waste Management's (OCRWM) critical decisions and changes against the Level 0 baseline; and in turn, the OCRWM Director approves all changes against the Level 1 baseline. This baseline establishes the top-level technical scope of the CRMWS and its three system elements, as described in section 1.3.2. The organizations responsible for design, development, and operation of system elements described in this document must therefore prepare subordinate project-level documents that are consistent with the CRD. Changes to requirements will be managed in accordance with established change and configuration control procedures. The CRD establishes requirements for the design, development, and operation of the CRWMS. It specifically addresses the top-level governing laws and regulations (e.g., ''Nuclear Waste Policy Act'' (NWPA), 10 Code of Federal Regulations (CFR) Part 63, 10 CFR Part 71, etc.) along with specific policy, performance requirements, interface requirements, and system architecture. The CRD shall be used as a vehicle to incorporate specific changes in technical scope or performance requirements that may have significant program implications. Such may include changes to the program mission, changes to operational capability, and high visibility stakeholder issues. The CRD uses a systems approach to: (1) identify key functions that the CRWMS must perform, (2) allocate top-level requirements derived from statutory, regulatory, and programmatic sources, and (3) define the basic elements of the system architecture and operational concept. Project-level documents address CRD requirements by further

  19. Quantum description of microscopic and macroscopic systems: Old problems and recent investigations

    International Nuclear Information System (INIS)

    Ghirardi, G.C.

    1986-04-01

    We review some open problems and some proposed solutions which are encountered in the quantum description of the microscopic systems, of the macroscopic ones, and of the interactions between these two types of objects. We describe a recent attempt allowing a unified description of all phenomena, reproducing the quantum mechanical situation for microscopic systems and inducing in a completely consistent way the classical behaviour of macro object and the phenomena of wave packet reduction in the system-apparatus interaction. (author)

  20. Title List of documents made publicly available

    International Nuclear Information System (INIS)

    1982-07-01

    The Title List of Documents Made Publicly Available is a monthly publication. It contains descriptions of the information received and generated by the US Nuclear Regulatory Commission (NRC). This information includes: (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials and (2) nondocketed material received and generated by NRC pertinent to its role as a regulatory agency. As used here, docketed does not refer to Court dockets; it refers to the system by which NRC maintains its regulatory records. This series of documents is indexed by a Personal Author Index, a Corporate Source Index, and a Report Number Index. The docketed information contained in the Title List includes the information formerly issued through the Department of Energy publication Power Reactor Docket Information, last published in January 1979. Microfiche of the docketed information listed in the Title List is available for sale on a subscription basis from the National Technical Information Service (NTIS)

  1. Title List of documents made publicly available

    International Nuclear Information System (INIS)

    1982-06-01

    The Title List of Documents Made Publicly Available is a monthly publication. It contains descriptions of the information received and generated by the US Nuclear Regulatory Commission (NRC). This information includes: (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials and (2) nondocketed material received and generated by NRC pertinent to its role as a regulatory agency. As used here, docketed does not refer to Court dockets; it refers to the system by which NRC maintains its regulatory records. This series of documents is indexed by a Personal Author Index, a Corporate Source Index, and a Report Number Index. The docketed information contained in the Title List includes the information formerly issued throught the Department of Energy publication Power Reactor Docket Information, last published in January 1979. Microfiche of the docketed information listed in the Title List is available for sale on a subscription basis from the National Technical Information Service (NTIS)

  2. Holographic associative memories in document retrieval systems

    International Nuclear Information System (INIS)

    Becker, P.J.; Bolle, H.; Keller, A.; Kistner, W.; Riecke, W.D.; Wagner, U.

    1979-03-01

    The objective of this work was the implementation of a holographic memory with associative readout for a document retrieval system. Taking advantage of the favourable properties of holography - associative readout of the memory, parallel processing in the response store - may give shorter response times than sequentially organized data memories. Such a system may also operate in the interactive mode including chain associations. In order to avoid technological difficulties, the experimental setup made use of commercially available components only. As a result an improved holographic structure is proposed which uses volume holograms in photorefractive crystals as storage device. In two chapters of appendix we give a review of the state of the art of electrooptic devices for coherent optical data processing and of competing technologies (semiconductor associative memories and associative program systems). (orig.) [de

  3. An observational study of the accuracy and completeness of an anesthesia information management system: recommendations for documentation system changes.

    Science.gov (United States)

    Wilbanks, Bryan A; Moss, Jacqueline A; Berner, Eta S

    2013-08-01

    Anesthesia information management systems must often be tailored to fit the environment in which they are implemented. Extensive customization necessitates that systems be analyzed for both accuracy and completeness of documentation design to ensure that the final record is a true representation of practice. The purpose of this study was to determine the accuracy of a recently installed system in the capture of key perianesthesia data. This study used an observational design and was conducted using a convenience sample of nurse anesthetists. Observational data of the nurse anesthetists'delivery of anesthesia care were collected using a touch-screen tablet computer utilizing an Access database customized observational data collection tool. A questionnaire was also administered to these nurse anesthetists to assess perceived accuracy, completeness, and satisfaction with the electronic documentation system. The major sources of data not documented in the system were anesthesiologist presence (20%) and placement of intravenous lines (20%). The major sources of inaccuracies in documentation were gas flow rates (45%), medication administration times (30%), and documentation of neuromuscular function testing (20%)-all of the sources of inaccuracies were related to the use of charting templates that were not altered to reflect the actual interventions performed.

  4. THE MANAGEMENT OF DOCUMENTS AN OPTIMISING COMPONENT FOR A COMPANIES IT SYSTEM

    Directory of Open Access Journals (Sweden)

    Vaduva Florin

    2008-05-01

    Full Text Available In order to ensure success in the competitive world of business, companies must accommodate the needs of their clients, partners, employees and capital owner. Companies that pay attention to the way their documents and information are administrated are more prepared to face cost reduction and can respond much faster to the changes occurred on Basically, it is all about information and controlling it and thus the response time is minimum to any inquiries or demands that come from inside the informational system of the company. So, you need an efficient document management. Software solutions that come to your aid, in order to optimize this process are Electronic Document Management System.

  5. 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

  6. Cold Vacuum Drying facility fire protection system design description

    International Nuclear Information System (INIS)

    PITKOFF, C.C.

    1999-01-01

    This document describes the Cold Vacuum Drying Facility (CVDF) fire protection system (FPS). The FPS provides fire detection, suppression, and loss limitation for the CVDF structure, personnel, and in-process spent nuclear fuel. The system provides, along with supporting interfacing systems, detection, alarm, and activation instrumentation and controls, distributive piping system, isolation valves, and materials and controls to limit combustibles and the associated fire loadings

  7. 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)

  8. Operating data documentation system for a research reactor

    International Nuclear Information System (INIS)

    Kasparec, F.; Hammer, J.

    1988-01-01

    The documentation system developed for the reactor to replace the automatic data logger is described in the paper. It is based on former experiences with the data logger which had led to a selection of representative data and useful data formats, but also made clear that the paper reports produced by the hardcopy terminal were not useful for further evaluation. A special pre-buffer hardware was provided to connect the data logger to the VAX. Because of its proven reliability an Epson-HX20 microcomputer was selected for this purpose. The documentation system hardware and the software are presented. The system has been operational for about ten months, collecting a daily average of 30kByte of data, and overcome a number of VAX system crashes, maintenance days and VAX/VMS updates. Various software extensions have been developed for processing the daily reports. Among these extensions there are programs for convenient tape backup, procedures for formatted printer output, and other. It is especially helpful to use commercial personal computer software for further data processing, in particular when PCs are connected in a network with the VAX or, on the other hand, emulate VAX terminals. There is a vast number of spread-sheet or database programs with excellent computational and graphic support available for PCs. Most of them allow data import, though format conversion programs will be necessary in most of the cases

  9. User and Document Group Approach of Clustering in Tagging Systems

    DEFF Research Database (Denmark)

    Pan, Rong; Xu, Guandong; Dolog, Peter

    2010-01-01

    In this paper, we propose a spectral clustering approach for users and documents group modeling in order to capture the common preference and relatedness of users and documents, and to reduce the time complexity of similarity calculations. In experiments, we investigate the selection of the optim...... amount of clusters. We also show a reduction of the time consuming in calculating the similarity for the recommender systems by selecting a centroid first, and then compare the inside item on behalf of each group....

  10. Report on AECB consultative document C-70: The use of fault trees in licensing submissions

    International Nuclear Information System (INIS)

    1984-01-01

    The Atomic Energy Control Board (AECB) has issued Consultative Document C-70, 'The Use of Fault Trees in Licensing Submissions', for public comment. The Advisory Committee on Nuclear Safety (ACNS) has examined this document and ACNS members have met with AECB staff and representatives of the nuclear industry to discuss it. The ACNS presents its comments and recommendations in this report. The consultative document defines a fault tree as a hierarchically-structured graphical representation of system failures and their potential causes. The document then states certain basic characteristics or attributes which fault trees should possess, and certain conditions affecting the use of fault trees. It defines fault tree fundamentals, sets criteria for the application of fault trees to systems and defines ground rules for a fault tree format. Finally, in two appendices, it includes specific rules for fault tree symbols and fault tree description files for computer use. The appendices are referred to in the text as 'acceptable' standards or methods

  11. Design criteria document, electrical system, K-Basin essential systems recovery, Project W-405

    International Nuclear Information System (INIS)

    Hoyle, J.R.

    1994-01-01

    This Design Criteria Document provides the criteria for design and construction of electrical system modifications for 100K Area that are essential to protect the safe operation and storage of spent nuclear fuel in the K-Basin facilities

  12. 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.

  13. Title list of documents made publicly available

    International Nuclear Information System (INIS)

    1990-04-01

    This document is a monthly publication containing descriptions of information received and generated by the US Nuclear Regulatory Commission (NRC). This information includes (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials, and (2) nondocketed material received and generated by NRC pertinent to its role as a regulatory agency. The following indexes are included: Personal Author, Corporate Source, Report Number, and Cross Reference to Principal Documents

  14. Side effects of cancer therapies. International classification and documentation systems

    International Nuclear Information System (INIS)

    Seegenschmiedt, M.H.

    1998-01-01

    The publication presents and explains verified, international classification and documentation systems for side effects induced by cancer treatments, applicable in general and clinical practice and clinical research, and covers in a clearly arranged manner the whole range of treatments, including acute and chronic side effects of chemotherapy and radiotherapy, surgery, or combined therapies. The book fills a long-felt need in tumor documentation and is a major contribution to quality assurance in clinical oncology in German-speaking countries. As most parts of the book are bilingual, presenting German and English texts and terminology, it satisfies the principles of interdisciplinarity and internationality. The tabulated form chosen for presentation of classification systems and criteria facilitate the user's approach as well as application in daily work. (orig./CB) [de

  15. Modeling Documents with Event Model

    Directory of Open Access Journals (Sweden)

    Longhui Wang

    2015-08-01

    Full Text Available Currently deep learning has made great breakthroughs in visual and speech processing, mainly because it draws lessons from the hierarchical mode that brain deals with images and speech. In the field of NLP, a topic model is one of the important ways for modeling documents. Topic models are built on a generative model that clearly does not match the way humans write. In this paper, we propose Event Model, which is unsupervised and based on the language processing mechanism of neurolinguistics, to model documents. In Event Model, documents are descriptions of concrete or abstract events seen, heard, or sensed by people and words are objects in the events. Event Model has two stages: word learning and dimensionality reduction. Word learning is to learn semantics of words based on deep learning. Dimensionality reduction is the process that representing a document as a low dimensional vector by a linear mode that is completely different from topic models. Event Model achieves state-of-the-art results on document retrieval tasks.

  16. Establishment of ''Internal Rules'' and EDMS - Electronic Document Management System at NPP NEK

    International Nuclear Information System (INIS)

    Mandic, D.

    2012-01-01

    The main purpose of this paper is to present NPP's plans regarding the on-going project that started in November 2011, and that is related to the establishment of ''Internal Rules'' and EDMS - Electronic Document Management System.The term ''Internal Rules'' has been directly translated from Slovenian language (''Notranja pravila'') and adopted from the translated version of appropriate Slovenian national codes (ZVDAGA [1] in Slovenian language or PDAAIA [2] in English version). ''Internal Rules on capture and storage of materials in digital form'' refer to the rules adopted by a person as his/her internal act with reference to storage of his/her material. The main purpose for the establishment of the Internal Rules is to be able to justify that Krsko NPP is organized in compliance with the national codes covering that subject and strictly performing according to those Internal Rules. Once a Slovenian company achieves recognized and registered status in accordance with the Internal Rules document that has been certified and approved by the ARS (Archives of the Republic Slovenia), such company can utilize e-documents in the same way as they would utilize physical documents. Furthermore, a Slovenian company with approved Internal Rules can use e-documents in any legal aspect associated with the document's life cycle and the document's content as they would use the physical document or an authorized and approved copy of the physical document. Related to the nuclear regulatory background, NEK operates in compliance with the Slovenian legislation and also the US codes, regulations and guidelines; therefore, regarding the NPP specific documents, the Internal Rules and EDMS must also be in compliance with them. Since early 1990's, NEK has implemented document/records management system oriented towards supporting storage and management of physical documents/records and controlling distribution of active document copies. Document/records management system was supported by

  17. Spent nuclear fuel technical baseline description, Fiscal Year 1996: Volume II, supporting data

    International Nuclear Information System (INIS)

    Womack, J.C.

    1995-11-01

    The Technical Baseline Description documents the Project-Level functions and requirements, along with associated enabling assumptions, issues, trade studies, interfaces, and products. It is a snapshot in time of the baseline at the beginning of September 1995. It supports the individual subprojects in the development of lower-tier functions, requirements, and specifications in FY 1996. It also supports the need for Hanford site planning to be based on an integrated Hanford site systems engineering technical baseline; and is traceable to that baseline. This document replaces and supercedes WHC-SD-SNF-SD-003

  18. System Description for the KW Basin Integrated Water Treatment System (IWTS) (70.3)

    International Nuclear Information System (INIS)

    DERUSSEAU, R.R.

    2000-01-01

    This is a description of the system that collects and processes the sludge and radioactive ions released by the spent nuclear fuel (SNF) processing operations conducted in the 105 KW Basin. The system screens, settles, filters, and conditions the basin water for reuse. Sludge and most radioactive ions are removed before the water is distributed back to the basin pool. This system is part of the Spent Nuclear Fuel Project (SNFP)

  19. Documentation of spectrom-32

    International Nuclear Information System (INIS)

    Callahan, G.D.; Fossum, A.F.; Svalstad, D.K.

    1989-01-01

    SPECTROM-32 is a finite element program for analyzing two-dimensional and axisymmetric inelastic thermomechanical problems related to the geological disposal of nuclear waste. The code is part of the SPECTROM series of special-purpose computer programs that are being developed by RE/SPEC Inc. to address many unique rock mechanics problems encountered in analyzing radioactive wastes stored in geologic formations. This document presents the theoretical basis for the mathematical models, the finite element formulation and solution procedure of the program, a description of the input data for the program, verification problems, and details about program support and continuing documentation. The computer code documentation is intended to satisfy the requirements and guidelines outlined in the document entitled Final Technical Position on Documentation of Computer Codes for High-Level Waste Management. The principal component models used in the program involve thermoelastic, thermoviscoelastic, thermoelastic-plastic, and thermoviscoplastic types of material behavior. Special material considerations provide for the incorporation of limited-tension material behavior and consideration of jointed material behavior. Numerous program options provide the capabilities for various boundary conditions, sliding interfaces, excavation, backfill, arbitrary initial stresses, multiple material domains, load incrementation, plotting database storage and access of results, and other features unique to the geologic disposal of radioactive wastes. Numerous verification problems that exercise many of the program options and illustrate the required data input and printed results are included in the documentation

  20. MANAGING HUMAN FACTORS IN IMPLEMENTING ELECTRONIC DOCUMENT SYSTEM IN THE PUBLIC SECTOR

    Directory of Open Access Journals (Sweden)

    TOMS LEIKUMS

    2012-05-01

    Full Text Available Document management underlies the activities of almost every organization. Correctly managed correspondence and organized document circulation characterize successful performance particularly in the public sector organizations. Even though production of documents itself is not the main task of governmental institutions, document creation and processing are crucial processes for the provision of basic functions in public sector. In the 21st century it gets more important to use the new possibilities offered by modern technologies, including electronic document management. Public sector itself is a heavy bureaucratic apparatus in the need of elasticity and ability to change its working processes and habits in order to gradually switch to the digital environment. Western European countries have already turned to electronic document management whilst most of the Eastern European countries, including Latvia, have just recently started a gradual electronization of document circulation. When implementing electronic document management systems in the public sector organizations, it often comes to resistance of the staff and unwillingness to change the accustomed methods of work – paper format document circulation. Both lower level staff and higher level managers put obstacles to electronic document management. In this article author inspects cases of successful practice and analyses possible action mechanisms that could convince public sector personnel of advantages of electronic document circulation and prepare them to switch to work with digital documents.

  1. Title list of documents made publicly available, December 1--31, 1989

    International Nuclear Information System (INIS)

    1990-04-01

    The Title List of Documents Made Publicly Available is a monthly publication. It contains descriptions of the information received and generated by the US Nuclear Regulatory Commission (NRC). This information includes (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials and (2) nondocketed material received and generated by NRC pertinent to its role as a regulatory agency. As used here, docketed does not refer to Court dockets; it refers to the system by which NRC maintains its regulatory records. This series of documents is indexed by a Personal Author Index, a Corporate Source Index, and a Report Number Index. The docketed information contained in the Title List includes the information formerly issued through the Department of Energy publication Power Reactor Docket Information, last published in January 1979. Microfiche of the docketed information listed in the Title List is available for sale on a subscription basis from the National Technical Information Service (NTIS). See NOTES at the end of the Preface for the complete NTIS address. We encourage your comments, criticisms, and suggestions. In particular, if there are title descriptions that are not meaningful, please let us know so that we can correct the data base. Insofar as possible, we would like this document to be a valuable part of your reference material

  2. Rock Visualization System. Technical description (RVS version 3.8)

    International Nuclear Information System (INIS)

    Curtis, P.; Elfstroem, M.; Markstroem, I.

    2007-06-01

    The Rock Visualization System (RVS) has been developed by SKB for use in visualizing geological and engineering data in 3D. The purpose of this report is to provide a technical description of RVS aimed at potential program users and interested parties as well as fulfilling the function of a more general RVS reference that can be cited when writing other technical reports. The report describes RVS version 4.0. Updated versions of this report or addenda will be made available following further development of RVS and the release of subsequent versions of the program. The report covers the following main items: Technical description of the program with illustrations and examples. Limitations of the program and of functionality. For most RVS functions step-by-step tutorials are available describing how a particular function can be used to carry out a specific task. A complete set of updated tutorials is issued with each new version release of the RVS program. However, the tutorials do not cover all the possible uses of all the individual functions but rather give an overall view of their functionality. A detailed description of every RVS function and how it can be used is included in the RVS online Help system

  3. Rock Visualization System. Technical description (RVS version 3.8)

    Energy Technology Data Exchange (ETDEWEB)

    Curtis, P.; Elfstroem, M.; Markstroem, I. [FB Engineering, Goeteborg (Sweden)

    2005-04-01

    The Rock Visualization System (RVS) has been developed by SKB for use in visualizing geological and engineering data in 3D. The purpose of this report is to provide a technical description of RVS aimed at potential program users and interested parties as well as fulfilling the function of a more general RVS reference that can be cited when writing other technical reports. The report describes RVS version 3.8. Updated versions of this report or addenda will be made available following further development of RVS and the release of subsequent versions of the program. The report covers the following main items: Technical description of the program with illustrations and examples. Limitations of the program and of functionality. For most RVS functions step-by-step tutorials are available describing how a particular function can be used to carryout a specific task. A complete set of updated tutorials is issued with each new version release of the RVS program. However, the tutorials do not cover all the possible uses of all the individual functions but rather give an overall view of their functionality. A detailed description of every RVS function and how it can be used is included in the RVS online Help system.

  4. Rock Visualization System. Technical description (RVS version 3.8)

    Energy Technology Data Exchange (ETDEWEB)

    Curtis, P.; Elfstroem, M.; Markstroem, I. [Golder Associates AB (Sweden)

    2007-06-15

    The Rock Visualization System (RVS) has been developed by SKB for use in visualizing geological and engineering data in 3D. The purpose of this report is to provide a technical description of RVS aimed at potential program users and interested parties as well as fulfilling the function of a more general RVS reference that can be cited when writing other technical reports. The report describes RVS version 4.0. Updated versions of this report or addenda will be made available following further development of RVS and the release of subsequent versions of the program. The report covers the following main items: Technical description of the program with illustrations and examples. Limitations of the program and of functionality. For most RVS functions step-by-step tutorials are available describing how a particular function can be used to carry out a specific task. A complete set of updated tutorials is issued with each new version release of the RVS program. However, the tutorials do not cover all the possible uses of all the individual functions but rather give an overall view of their functionality. A detailed description of every RVS function and how it can be used is included in the RVS online Help system.

  5. Rock Visualization System. Technical description (RVS version 3.8)

    International Nuclear Information System (INIS)

    Curtis, P.; Elfstroem, M.; Markstroem, I.

    2005-04-01

    The Rock Visualization System (RVS) has been developed by SKB for use in visualizing geological and engineering data in 3D. The purpose of this report is to provide a technical description of RVS aimed at potential program users and interested parties as well as fulfilling the function of a more general RVS reference that can be cited when writing other technical reports. The report describes RVS version 3.8. Updated versions of this report or addenda will be made available following further development of RVS and the release of subsequent versions of the program. The report covers the following main items: Technical description of the program with illustrations and examples. Limitations of the program and of functionality. For most RVS functions step-by-step tutorials are available describing how a particular function can be used to carryout a specific task. A complete set of updated tutorials is issued with each new version release of the RVS program. However, the tutorials do not cover all the possible uses of all the individual functions but rather give an overall view of their functionality. A detailed description of every RVS function and how it can be used is included in the RVS online Help system

  6. 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.

  7. Using electronic document management systems to manage highway project files.

    Science.gov (United States)

    2011-12-12

    "WisDOTs Bureau of Technical Services is interested in learning about the practices of other state departments of : transportation in developing and implementing an electronic document management system to manage highway : project files"

  8. Systems Biology Graphical Notation: Process Description language Level 1 Version 1.3.

    Science.gov (United States)

    Moodie, Stuart; Le Novère, Nicolas; Demir, Emek; Mi, Huaiyu; Villéger, Alice

    2015-09-04

    The Systems Biological Graphical Notation (SBGN) is an international community effort for standardized graphical representations of biological pathways and networks. The goal of SBGN is to provide unambiguous pathway and network maps for readers with different scientific backgrounds as well as to support efficient and accurate exchange of biological knowledge between different research communities, industry, and other players in systems biology. Three SBGN languages, Process Description (PD), Entity Relationship (ER) and Activity Flow (AF), allow for the representation of different aspects of biological and biochemical systems at different levels of detail. The SBGN Process Description language represents biological entities and processes between these entities within a network. SBGN PD focuses on the mechanistic description and temporal dependencies of biological interactions and transformations. The nodes (elements) are split into entity nodes describing, e.g., metabolites, proteins, genes and complexes, and process nodes describing, e.g., reactions and associations. The edges (connections) provide descriptions of relationships (or influences) between the nodes, such as consumption, production, stimulation and inhibition. Among all three languages of SBGN, PD is the closest to metabolic and regulatory pathways in biological literature and textbooks, but its well-defined semantics offer a superior precision in expressing biological knowledge.

  9. A Fundamental Scale of Descriptions for Analyzing Information Content of Communication Systems

    Directory of Open Access Journals (Sweden)

    Gerardo Febres

    2015-03-01

    Full Text Available The complexity of the description of a system is a function of the entropy of its symbolic description. Prior to computing the entropy of the system’s description, an observation scale has to be assumed. In texts written in artificial and natural languages, typical scales are binary, characters, and words. However, considering languages as structures built around certain preconceived set of symbols, like words or characters, limits the level of complexity that can be revealed analytically. This study introduces the notion of the fundamental description scale to analyze the essence of the structure of a language. The concept of Fundamental Scale is tested for English and musical instrument digital interface (MIDI music texts using an algorithm developed to split a text in a collection of sets of symbols that minimizes the observed entropy of the system. This Fundamental Scale reflects more details of the complexity of the language than using bits, characters or words. Results show that this Fundamental Scale allows to compare completely different languages, such as English and MIDI coded music regarding its structural entropy. This comparative power facilitates the study of the complexity of the structure of different communication systems.

  10. Description of the IV + V System Software Package.

    Science.gov (United States)

    Microcomputers for Information Management: An International Journal for Library and Information Services, 1984

    1984-01-01

    Describes the IV + V System, a software package designed by the Institut fur Maschinelle Dokumentation for the United Nations General Information Programme and UNISIST to support automation of local information and documentation services. Principle program features and functions outlined include input/output, databank, text image, output, and…

  11. 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.

  12. Title list of documents made publicly available, April 1-30, 1995. Volume 17, No. 4

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-06-01

    This document is NUREG-0540, Volume 17, Number 4. The Title List of Documents Made Publicly Available is a monthly publication, It contains descriptions of the information received and generated by the US NRC. This information includes (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials, and (2) nondocketed material received and generated by the NRC pertinent to its role as a regulatory agency. As used here, docketed does not refer to Court dockets; it refers to the system by which the NRC maintains its regulatory records. This series of documents is indexed by a personal author index, a corporate source index, and a report number index.

  13. Title list of documents made publicly available, April 1-30, 1995. Volume 17, No. 4

    International Nuclear Information System (INIS)

    1995-06-01

    This document is NUREG-0540, Volume 17, Number 4. The Title List of Documents Made Publicly Available is a monthly publication, It contains descriptions of the information received and generated by the US NRC. This information includes (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials, and (2) nondocketed material received and generated by the NRC pertinent to its role as a regulatory agency. As used here, docketed does not refer to Court dockets; it refers to the system by which the NRC maintains its regulatory records. This series of documents is indexed by a personal author index, a corporate source index, and a report number index

  14. Ahmad's NPRT System: A Practical Innovation for Documenting Male Pattern Baldness

    OpenAIRE

    Ahmad, Muhammad

    2016-01-01

    Various classifications for male pattern baldness are mentioned in the literature. The 'Norwood's classification is the most commonly used but it has certain limitations. The new system has included 'three' extra features which were not mentioned in any other classification. It provides an opportunity to document the full and correct picture while documenting male pattern baldness. It also aids in assessing the treatment for various degrees of baldness.

  15. Ahmad's NPRT system: A practical innovation for documenting male pattern baldness

    Directory of Open Access Journals (Sweden)

    Muhammad Ahmad

    2016-01-01

    Full Text Available Various classifications for male pattern baldness are mentioned in the literature. The 'Norwood's classification is the most commonly used but it has certain limitations. The new system has included 'three' extra features which were not mentioned in any other classification. It provides an opportunity to document the full and correct picture while documenting male pattern baldness. It also aids in assessing the treatment for various degrees of baldness.

  16. A decision support system for the reading of ancient documents

    DEFF Research Database (Denmark)

    Roued-Cunliffe, Henriette

    2011-01-01

    The research presented in this thesis is based in the Humanities discipline of Ancient History and begins by attempting to understand the interpretation process involved in reading ancient documents and how this process can be aided by computer systems such as Decision Support Systems (DSS...... this process in the five areas: remembering complex reasoning, searching huge datasets, international collaboration, publishing editions, and image enhancement. This research contains a large practical element involving the development of a DSS prototype. The prototype is used to illustrate how a DSS......, by remembering complex reasoning, can aid the process of interpretation that is reading ancient documents. It is based on the idea that the interpretation process goes through a network of interpretation. The network of interpretation illustrates a recursive process where scholars move between reading levels...

  17. GENII Version 2 Software Design Document

    Energy Technology Data Exchange (ETDEWEB)

    Napier, Bruce A.; Strenge, Dennis L.; Ramsdell, James V.; Eslinger, Paul W.; Fosmire, Christian J.

    2004-03-08

    This document describes the architectural design for the GENII-V2 software package. This document defines details of the overall structure of the software, the major software components, their data file interfaces, and specific mathematical models to be used. The design represents a translation of the requirements into a description of the software structure, software components, interfaces, and necessary data. The design focuses on the major components and data communication links that are key to the implementation of the software within the operating framework. The purpose of the GENII-V2 software package is to provide the capability to perform dose and risk assessments of environmental releases of radionuclides. The software also has the capability of calculating environmental accumulation and radiation doses from surface water, groundwater, and soil (buried waste) media when an input concentration of radionuclide in these media is provided. This report represents a detailed description of the capabilities of the software product with exact specifications of mathematical models that form the basis for the software implementation and testing efforts. This report also presents a detailed description of the overall structure of the software package, details of main components (implemented in the current phase of work), details of data communication files, and content of basic output reports. The GENII system includes the capabilities for calculating radiation doses following chronic and acute releases. Radionuclide transport via air, water, or biological activity may be considered. Air transport options include both puff and plume models, each allow use of an effective stack height or calculation of plume rise from buoyant or momentum effects (or both). Building wake effects can be included in acute atmospheric release scenarios. The code provides risk estimates for health effects to individuals or populations; these can be obtained using the code by applying

  18. Informational system. Documents management

    Directory of Open Access Journals (Sweden)

    Vladut Iacob

    2009-12-01

    Full Text Available Productivity growing, as well as reducing of operational costs in a company can be achieved by adopting a document management solutions. Such application will allow management and structured and efficient transmission of information within the organization.

  19. 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

  20. SWEPP Gamma-Ray Spectrometer System software design description

    International Nuclear Information System (INIS)

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

    1994-08-01

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

  1. SWEPP Gamma-Ray Spectrometer System software design description

    Energy Technology Data Exchange (ETDEWEB)

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

    1994-08-01

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

  2. Communications data delivery system analysis : public workshop read-ahead document.

    Science.gov (United States)

    2012-04-09

    This document presents an overview of work conducted to date around development and analysis of communications data delivery systems for : supporting transactions in the connected vehicle environment. It presents the results of technical analysis of ...

  3. Title list of documents made publicly available: [Monthly report], January 1-31, 1988

    International Nuclear Information System (INIS)

    1988-03-01

    The Title List of Documents Made Publicly Available is a monthly publication. It contains descriptions of the information received and generated by the US Nuclear Regulatory Commission (NRC). This information includes (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials and (2) nondocketed material received and generated by NRC pertinent to its role as a regulatory agency. As used here, docketed does not refer to Court dockets; it refers to the system by which NRC maintains its regulatory records. This series of documents is indexed by a Personal Author Index, a Corporate Source Index, and a Report Number index

  4. Documentation is Documentation and Theory is Theory: A Reply to Daniel Avorgbedor's Commentary "Documenting Spoken and Sung Texts of the Dagaaba of West Africa"

    Directory of Open Access Journals (Sweden)

    Manolete Mora

    2007-11-01

    Full Text Available In a response to an article that appeared in Empirical Musicology Review (Bodomo and Mora 2007, Avorgbedor (2007 takes issue with aspects of the paper. In our reply to Avorgbedor’s response we will firstly clarify some issues raised therein and secondly address the issue about the relationship between theory, description and documentation within linguistics and musicology.

  5. Hanford Waste Vitrification Plant: Preliminary description of waste form and canister

    International Nuclear Information System (INIS)

    Mitchell, D.E.

    1986-01-01

    In July 1985, the US Department of Energy's Office of Civilian Radioactive Waste Management established the Waste Acceptance Process as the means by which defense high-level waste producers, such as the Hanford Waste Vitrification Plant, will develop waste acceptance requirements with the candidate geologic repositories. A complete description of the Waste Acceptance Process is contained in the Preliminary Hanford Waste Vitrification Plant Waste Form Qualification Plan. The Waste Acceptance Process defines three documents that high-level waste producers must prepare as a part of the process of assuming that a high-level waste product will be acceptable for disposal in a geologic repository. These documents are the Description of Waste Form and Canister, Waste Compliance Plan, and Waste Qualification Report. This document is the Hanford Waste Vitrification Plant Preliminary Description of Waste Form and Canister for disposal of Neutralized Current Acid Waste. The Waste Acceptance Specifications for the Hanford Waste Vitrification Plant have not yet been developed, therefore, this document has been structured to corresponds to the Waste Acceptance Preliminary Specifications for the Defense Waste Processing Facility High-Level Waste Form. Not all of the information required by these specifications is appropriate for inclusion in this Preliminary Description of Waste Form and Canister. Rather, this description is limited to information that describes the physical and chemical characteristics of the expected high-level waste form. The content of the document covers three major areas: waste form characteristics, canister characteristics, and canistered waste form characteristics. This information will be used by the candidate geologic repository projects as the basis for preliminary repository design activities and waste form testing. Periodic revisions are expected as the Waste Acceptance Process progresses

  6. 242-A Control System device logic software documentation. Revision 2

    International Nuclear Information System (INIS)

    Berger, J.F.

    1995-01-01

    A Distributive Process Control system was purchased by Project B-534. This computer-based control system, called the Monitor and Control System (MCS), was installed in the 242-A Evaporator located in the 200 East Area. The purpose of the MCS is to monitor and control the Evaporator and Monitor a number of alarms and other signals from various Tank Farm facilities. Applications software for the MCS was developed by the Waste Treatment System Engineering Group of Westinghouse. This document describes the Device Logic for this system

  7. Model documentation report: Transportation sector model of the National Energy Modeling System

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-02-01

    Over the past year, several modifications have been made to the NEMS Transportation Model, incorporating greater levels of detail and analysis in modules previously represented in the aggregate or under a profusion of simplifying assumptions. This document is intended to amend those sections of the Model Documentation Report (MDR) which describe these superseded modules. Significant changes have been implemented in the LDV Fuel Economy Model, the Alternative Fuel Vehicle Model, the LDV Fleet Module, and the Highway Freight Model. The relevant sections of the MDR have been extracted from the original document, amended, and are presented in the following pages. A brief summary of the modifications follows: In the Fuel Economy Model, modifications have been made which permit the user to employ more optimistic assumptions about the commercial viability and impact of selected technological improvements. This model also explicitly calculates the fuel economy of an array of alternative fuel vehicles (AFV`s) which are subsequently used in the estimation of vehicle sales. In the Alternative Fuel Vehicle Model, the results of the Fuel Economy Model have been incorporated, and the program flows have been modified to reflect that fact. In the Light Duty Vehicle Fleet Module, the sales of vehicles to fleets of various size are endogenously calculated in order to provide a more detailed estimate of the impacts of EPACT legislation on the sales of AFV`s to fleets. In the Highway Freight Model, the previous aggregate estimation has been replaced by a detailed Freight Truck Stock Model, where travel patterns, efficiencies, and energy intensities are estimated by industrial grouping. Several appendices are provided at the end of this document, containing data tables and supplementary descriptions of the model development process which are not integral to an understanding of the overall model structure.

  8. A Document-Based EHR System That Controls the Disclosure of Clinical Documents Using an Access Control List File Based on the HL7 CDA Header.

    Science.gov (United States)

    Takeda, Toshihiro; Ueda, Kanayo; Nakagawa, Akito; Manabe, Shirou; Okada, Katsuki; Mihara, Naoki; Matsumura, Yasushi

    2017-01-01

    Electronic health record (EHR) systems are necessary for the sharing of medical information between care delivery organizations (CDOs). We developed a document-based EHR system in which all of the PDF documents that are stored in our electronic medical record system can be disclosed to selected target CDOs. An access control list (ACL) file was designed based on the HL7 CDA header to manage the information that is disclosed.

  9. Arizona TeleMedicine Network: System Procurement Specifications.

    Science.gov (United States)

    Atlantic Research Corp., Alexandria, VA.

    Providing general specifications and system descriptions for segments within the Arizona TeleMedicine Project (a telecommunication system designed to deliver health services to rurally isolated American Indians in Arizona), this document, when used with the appropriate route segment document, will completely describe the project's required…

  10. Reference design description for a geologic repository. Revision 02

    International Nuclear Information System (INIS)

    1999-01-01

    This Reference Design Description explains the current design for a potential geologic repository that may be located at Yucca Mountain in Nevada. It describes the proposed design for a surface facility, subsurface repository, and waste packaging; it also presents the current design of the key engineering systems for the final four phases: operations, monitoring, closure, and postclosure. In addition, this Reference Design Description reviews the expected long-term performance of the potential repository. In accordance with current law, this design does not include an interim storage option. This document has six major sections. Section 1 describes the physical layout of the proposed repository. The second section describes the 4-phase evolution of the development of the proposed repository. Section 3 describes the reception of waste from offsite locations. The fourth section details the various systems that will package the waste and move it below ground as well as safety monitoring and closure. Section 5 describes the systems (both physical and analytical) that ensure continued safety after closure. The final section offers design options that may be adopted to increase the margin of safety

  11. Preliminary System Design of the SWRL Financial System.

    Science.gov (United States)

    Ikeda, Masumi

    The preliminary system design of the computer-based Southwest Regional Laboratory's (SWRL) Financial System is outlined. The system is designed to produce various management and accounting reports needed to maintain control of SWRL operational and financial activities. Included in the document are descriptions of the various types of system…

  12. Document understanding for a broad class of documents

    NARCIS (Netherlands)

    Aiello, Marco; Monz, Christof; Todoran, Leon; Worring, Marcel

    2002-01-01

    We present a document analysis system able to assign logical labels and extract the reading order in a broad set of documents. All information sources, from geometric features and spatial relations to the textual features and content are employed in the analysis. To deal effectively with these

  13. IDC Re-Engineering Phase 2 System Requirements Document V1.3.

    Energy Technology Data Exchange (ETDEWEB)

    Harris, James M. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Burns, John F. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Satpathi, Meara Allena [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2015-12-01

    This System Requirements Document (SRD) defines waveform data processing requirements for the International Data Centre (IDC) of the Comprehensive Nuclear Test Ban Treaty Organization (CTBTO). The IDC applies, on a routine basis, automatic processing methods and interactive analysis to raw International Monitoring System (IMS) data in order to produce, archive, and distribute standard IDC products on behalf of all States Parties. The routine processing includes characterization of events with the objective of screening out events considered to be consistent with natural phenomena or non-nuclear, man-made phenomena. This document does not address requirements concerning acquisition, processing and analysis of radionuclide data but includes requirements for the dissemination of radionuclide data and products.

  14. IDC Re-Engineering Phase 2 System Requirements Document Version 1.4

    Energy Technology Data Exchange (ETDEWEB)

    Harris, James M. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Burns, John F. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Satpathi, Meara Allena [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2017-01-01

    This System Requirements Document (SRD) defines waveform data processing requirements for the International Data Centre (IDC) of the Comprehensive Nuclear Test Ban Treaty Organization (CTBTO). The IDC applies, on a routine basis, automatic processing methods and interactive analysis to raw International Monitoring System (IMS) data in order to produce, archive, and distribute standard IDC products on behalf of all States Parties. The routine processing includes characterization of events with the objective of screening out events considered to be consistent with natural phenomena or non-nuclear, man-made phenomena. This document does not address requirements concerning acquisition, processing and analysis of radionuclide data, but includes requirements for the dissemination of radionuclide data and products.

  15. Model and information abstraction for description-driven systems

    International Nuclear Information System (INIS)

    Estrella, F.; McClatchey, R.; Kovacs, Z.; Goff, J.-M.L.

    2001-01-01

    A crucial factor in the creation of adaptable systems dealing with changing requirements is the suitability of the underlying technology in allowing the evolution of the system. A reflective system utilizes an open architecture where implicit system aspects are reified to become explicit first-class (meta-data) objects. These implicit system aspects are often fundamental structures which are inaccessible and immutable, and their reification as meta-data objects can serve as the basis for changes and extensions to the system, making it self-describing. To address the evolvability issue, the author proposes a reflective architecture based on two orthogonal abstractions-model abstraction and information abstraction. In this architecture the modeling abstractions allow for the separation of the description meta-data from the system aspects they represent so that they can be managed and versioned independently, asynchronously and explicitly

  16. System design description for Waste Information and Control System

    International Nuclear Information System (INIS)

    Harris, R.R.

    1994-01-01

    The Westinghouse Hanford Company (WHC) Hazardous Material Control Group (HMC) of the 222-S Laboratory has requested the development of a system to help resolve many of the difficulties associated with tracking and data collection of containers and drums of waste. This system has been identified as the Waste Information and Control System (WICS). WICS shall partially automate the procedure for acquisition, tracking and reporting of the container, drum, and waste data that is currently manually processed. The WICS project shall use handheld computer units (HCU) to collect laboratory data, a local database with an user friendly interface to import the laboratory data from the HCUs, and barcode technology with associated software and operational procedures. After the container, drum, and waste data has been collected and verified, WICS shall be manipulated to provide informal reports containing data required to properly document waste disposal. 8 refs, 82 figs, 69 tabs

  17. Cold Vacuum Drying facility deionized water system design description

    International Nuclear Information System (INIS)

    PITKOFF, C.C.

    1999-01-01

    This document describes the Cold Vacuum Drying Facility (CVDF) de-ionized water system. The de-ionized water system is used to provide clean, conditioned water, free from contaminants, chlorides and iron for the CVD Facility. Potable water is supplied to the deionized water system, isolated by a backflow prevention device. After the de-ionization process is complete, via a packaged de-ionization unit, de-ionized water is supplied to the process deionization unit

  18. Working document dispersion models

    International Nuclear Information System (INIS)

    Dop, H. van

    1988-01-01

    This report is a summary of the most important results from June 1985 of the collaboration of the RIVM (Dutch National Institute for Public Health and Environment Hygiene) and KNMI (Royal Dutch Meteorologic Institute) on the domain of dispersion models. It contains a short description of the actual SO x /NO x -model. Furthermore it contains recommendations for modifications of some numerical-mathematical aspects and an impulse to a more complete description of chemical processes in the atmosphere and the (wet) deposition process. A separate chapter is devoted to the preparation of meteorologic data which are relevant for dispersion as well as atmospheric chemistry and deposition. This report serves as working document for the final formulation of a acidifying- and oxidant-model. (H.W.). 69 refs.; 51 figs.; 13 tabs.; 3 schemes

  19. 2008 HIMSS Survey results: best practices in implementing nursing/interdisciplinary documentation systems.

    Science.gov (United States)

    Newbold, Susan K; Kimmel, Kathleen C; O'Steen, Randy; Morgan, Gina Sauls

    2008-11-06

    Health care organizations are increasingly using computer systems to support nursing care documentation; however, processes used to deploy such systems are widely varied. The purpose of this survey was to understand current practices related to implementation of computerized nursing and interdisciplinary documentation systems with the goal to establish best practice guidelines. In Spring 2007, members from the Healthcare Information Management and Systems Society Nursing Informatics Working Group interviewed a sample of 15 hospitals to solicit information regarding the following processes: leadership activities, clinical transformation processes, project management activities, implementation processes, evaluation metrics, terminology and other standards used, and methods used to facilitate end-user adoption. This poster will report the results of this survey. Implications for Nurses will be discussed. The results are valuable to nursing informatics professionals who plan to implement systems and to their nursing executives responsible for the systems that are implemented.

  20. Communication Between Devices in the Viola Document Delivery System

    Directory of Open Access Journals (Sweden)

    Theodor Tolstoy

    2015-01-01

    Full Text Available Viola is a newly developed document delivery system that handles incoming and outgoing requests for printed books, articles, sharing electronic resources, and other document delivery services on the local level in a library organisation. An important part of Viola is the stack fetching Android application that enables librarians to collect books in the open and closed stacks in an efficient manner using a smartphone and a Bluetooth connected portable printer. The aim of this article is to show how information is transferred between systems and devices in Viola. The article presents code examples from Viola that use current .NET technologies. The examples span from the creation of high-level REST-based JSON APIs to byte array communication with a Bluetooth connected printer and the reading of RFID tags. Please note that code examples in this article are for illustration purposes only. Null checking and other exception handling has been removed for clarity. Code that is separated in Viola for testability and other reasons has been brought together to make it more readable.

  1. The System 80+ Standard Plant design control document. Volume 1

    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 DCD introduction and contains sections 1 and parts 1--7 of section 2 of the CDM. Parts 1--7 included the following: (2.1) Design of SSC; (2.2) Reactor; (2.3) RCS and connected systems; (2.4) Engineered Safety Features; (2.5) Instrumentation and Control; (2.6) Electric Power; and (2.7) Auxiliary Systems

  2. The System 80+ Standard Plant design control document. Volume 19

    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 contains five technical specification bases that are part of Appendix 16 A of the ADM Design and Analysis. They are: TS B3.3 Instrumentation Bases; TS B3.4 RCS Bases; TS B3.5 ECCS Bases; TS B3.6 Containment Systems Bases; and TS B3.7 Plant Systems Bases

  3. A Petri Net Definition of a System Description Language

    DEFF Research Database (Denmark)

    Jensen, Kurt; Kyng, Morten; Madsen, Ole Lehrmann

    1979-01-01

    This paper introduces a language for the description of systems with concurrency, and presents a formal definition of its semantics. The language is based on Delta and the semantic model is an extension of Petri nets with a data part and with expressions attached to transitions and to places....

  4. Television system for verification and documentation of treatment fields during intraoperative radiation therapy

    International Nuclear Information System (INIS)

    Fraass, B.A.; Harrington, F.S.; Kinsella, T.J.; Sindelar, W.F.

    1983-01-01

    Intraoperative radiation therapy (IORT) involves direct treatment of tumors or tumor beds with large single doses of radiation. The verification of the area to be treated before irradiation and the documentation of the treated area are critical for IORT, just as for other types of radiation therapy. A television system which allows the target area to be directly imaged immediately before irradiation has been developed. Verification and documentation of treatment fields has made the IORT television system indispensable

  5. Wound Documentation by Using 3G Mobile as Acquisition Terminal: An Appropriate Proposal for Community Wound Care.

    Science.gov (United States)

    Ge, Kui; Wu, Minjie; Liu, Hu; Gong, Jiahong; Zhang, Yi; Hu, Qiang; Fang, Min; Tao, Yanping; Cai, Minqiang; Chen, Hua; Wang, Jianbo; Xie, Ting; Lu, Shuliang

    2015-06-01

    The increasing numbers of cases of wound disease are now posing a big challenge in China. For more convenience of wound patients, wound management in community health care centers under the supervision of a specialist at general hospitals is an ideal solution. To ensure an accurate diagnosis in community health clinics, it is important that "the same language" for wound description, which may be composed of unified format description, including wound image, must be achieved. We developed a wound information management system that was built up by acquisition terminal, wound description, data bank, and related software. In this system, a 3G mobile phone was applied as acquisition terminal, which could be used to access to the data bank. This documentation system was thought to be an appropriate proposal for community wound care because of its objectivity, uniformity, and facilitation. It also provides possibility for epidemiological study in the future. © The Author(s) 2014.

  6. User Manual for the AZ-101 Data Acquisition System (AS-101 DAS)

    Energy Technology Data Exchange (ETDEWEB)

    BRAYTON, D.D.

    2000-02-17

    User manual for the TK AZ-101 Waste Retrieval System Data Acquisition System. The purpose of this document is to describe use of the AZ-101 Data Acquisition System (AZ-101 DAS). The AZ-101 DAS is provided to fulfill the requirements for data collection and monitoring as defined in Letters of Instruction (LOI) from Numatec Hanford Corporation (NHC) to Fluor Federal Services (FFS). For a complete description of the system, including design, please refer to the AZ-101 DAS System Description document, RPP-5572.

  7. User Manual for the AZ-101 Data Acquisition System (AS-101 DAS)

    International Nuclear Information System (INIS)

    BRAYTON, D.D.

    2000-01-01

    User manual for the TK AZ-101 Waste Retrieval System Data Acquisition System. The purpose of this document is to describe use of the AZ-101 Data Acquisition System (AZ-101 DAS). The AZ-101 DAS is provided to fulfill the requirements for data collection and monitoring as defined in Letters of Instruction (LOI) from Numatec Hanford Corporation (NHC) to Fluor Federal Services (FFS). For a complete description of the system, including design, please refer to the AZ-101 DAS System Description document, RPP-5572

  8. The System 80+ Standard Plant design control document. Volume 11

    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 parts 6 and 7 and appendix 7A for section 7 (Instrumentation and Control) of the ADM Design and Analysis. The topics covered by these are: other systems required for safety; control systems not required by safety; and CMF evaluation of limiting faults. Parts 1--3 of section 8 (Electric Power) of the ADM are also included in this volume. Topics covered by these parts are: introduction; offsite power system; and onsite power system

  9. Observing Participating Observation—A Re-description Based on Systems Theory

    Directory of Open Access Journals (Sweden)

    Tina Bering Keiding

    2010-09-01

    Full Text Available Current methodology concerning participating observation in general leaves the act of observation unobserved. Approaching participating observation from systems theory offers fundamental new insights into the topic. Observation is always participation. There is no way to escape becoming a participant and, as such, co-producer of the observed phenomenon. There is no such thing as a neutral or objective description. As observation deals with differences and process meaning, all descriptions are re-constructions and interpretations of the observed. Hence, the idea of neutral descriptions as well as the idea of the naïve observer becomes a void. Not recognizing and observing oneself as observer and co-producer of empirical data simply leaves the process of observation as the major unobserved absorber of contingency in data production based on participating observation. URN: urn:nbn:de:0114-fqs1003119

  10. Title list of documents made publicly available, August 1-31, 1982

    International Nuclear Information System (INIS)

    1982-01-01

    The Title List of Documents Made Publicly Available is a monthly publication. It contains descriptions of the information received and generated by the US Nuclear Regulatory Commission (NRC). This information includes (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials and (2) nondocketed material received and generated by NRC pertinent to its role as a regulatory agency. As used here, docketed does not refer to Court dockets; it refers to the system by which NRC maintains its regulatory records. This series of documents is indexed by a Personal Author Index, a Corporate Source Index, and a Report Number Index. The docketed information contained in the Title List includes the information formerly issued through the Department of Energy publication Power Reactor Docket Information, last published in January 1979

  11. Title list of documents made publicly available, September 1--30, 1991

    International Nuclear Information System (INIS)

    1991-11-01

    The Title List of Documents Made Publicly Available is a monthly publication. It contains descriptions of the information received and generated by the US Nuclear Regulatory Commission (NRC). This information includes (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials and (2) nondocketed material received and generated by NRC pertinent to its role as a regulatory agency. As used here, docketed does not refer to Court dockets; it refers to the system by which NRC maintains its regulatory records. This series of documents is indexed by a Personal Author Index, a Corporate Source Index, and a Report Number Index. The docketed information contained in the Title List includes the information formerly issued through the Department of Energy publication Power Reactor Docket Information, last published in January 1979

  12. Title list of documents made publicly available, December 1-31, 1982

    International Nuclear Information System (INIS)

    1982-01-01

    The Title List of Documents Made Publicly Available is a monthly publication. It contains descriptions of the information received and generated by the US Nuclear Regulatory Commission (NRC). This information includes (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials and (2) nondocketed material received and generated by NRC pertinent to its role as a regulatory agency. As used here, docketed does not refer to Court dockets; it refers to the system by which NRC maintains its regulatory records. This series of documents is indexed by a Personal Author Index, a Corporate Source Index, and a Report Number Index. The docketed information contained in the Title List includes the information formerly issued through the Department of Energy publication Power Reactor Docket Information, last published in January 1979

  13. The System 80+ Standard Plant design control document. Volume 10

    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 contains Appendices 6A, 6B, and 6C for section 6 (Engineered Safety Features) of the ADM Design and Analysis. Also, parts 1--5 of section 7 (Instrumentation and Control) of the ADM Design and Analysis are covered. The following information is covered in these parts: introduction; reactor protection system; ESF actuation system; system required for safe shutdown; and safety-related display instrumentation

  14. The System 80+ Standard Plant design control document. Volume 24

    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 contains sections 7--11 of the ADM Emergency Operations Guidelines. Topics covered are: excess steam demand recovery; loss of all feedwater; loss of offsite power; station blackout recovery; and functional recovery guideline. Appendix A Severe Accident Management Guidelines and Appendix B Lower Mode Operational Guidelines are also included

  15. Cold Vacuum Drying facility sanitary sewage collection system design description

    International Nuclear Information System (INIS)

    PITKOFF, C.C.

    1999-01-01

    This document describes the Cold Vacuum Drying Facility (CVDF) sanitary sewage collection system. The sanitary sewage collection system provides collection and storage of effluents and raw sewage from the CVDF to support the cold vacuum drying process. This system is comprised of a sanitary sewage holding tank and pipes for collection and transport of effluents to the sanitary sewage holding tank

  16. Longitudinal analysis on utilization of medical document management system in a hospital with EPR implementation.

    Science.gov (United States)

    Kuwata, Shigeki; Yamada, Hitomi; Park, Keunsik

    2011-01-01

    Document management systems (DMS) have widespread in major hospitals in Japan as a platform to digitize the paper-based records being out of coverage by EPR. This study aimed to examine longitudinal trends of actual use of DMS in a hospital in which EPR had been in operation, which would be conducive to planning the further information management system in the hospital. Degrees of utilization of electronic documents and templates with DMS were analyzed based on data extracted from a university-affiliated hospital with EPR. As a result, it was found that the number of electronic documents as well as scanned documents circulating at the hospital tended to increase. The result indicated that replacement of paper-based documents with electronic documents did not occur. Therefore it was anticipated that the need for DMS would continue to increase in the hospital. The methods used this study to analyze the trend of DMS utilization would be applicable to other hospitals with with a variety of DMS implementation, such as electronic storage by scanning documents or paper preservation that is compatible with EPR.

  17. AREVA - 2012 Reference document

    International Nuclear Information System (INIS)

    2013-03-01

    After a presentation of the person responsible for this Reference Document, of statutory auditors, and of a summary of financial information, this report address the different risk factors: risk management and coverage, legal risk, industrial and environmental risk, operational risk, risk related to major projects, liquidity and market risk, and other risks (related to political and economic conditions, to Group's structure, and to human resources). The next parts propose information about the issuer, a business overview (markets for nuclear power and renewable energies, customers and suppliers, group's strategy, operations), a brief presentation of the organizational structure, a presentation of properties, plants and equipment (principal sites, environmental issues which may affect these items), analysis and comments on the group's financial position and performance, a presentation of capital resources, a presentation of research and development activities (programs, patents and licenses), a brief description of financial objectives and profit forecasts or estimates, a presentation of administration, management and supervision bodies, a description of the operation of corporate bodies, an overview of personnel, of principal shareholders, and of transactions with related parties, a more detailed presentation of financial information concerning assets, financial positions and financial performance. Addition information regarding share capital is given, as well as an indication of major contracts, third party information, available documents, and information on holdings

  18. Discussion on the compilation of document of iso quality management system for radiation sterilization enterprises

    International Nuclear Information System (INIS)

    Li Chunhong; Ha Yiming; Zhou Hongjie; Feng Zhiguo; Wang Feng

    2006-01-01

    According to the character of cooperation of radiation sterilization, and association with request of ISO9001, ISO13485 and ISO11137, compilation of document in quality manual, procedure document and technological document during certification of ISO quality management system of cooperation of radiation sterilization was discussed. (authors)

  19. Documentation of spectrom-41

    International Nuclear Information System (INIS)

    Svalstad, D.K.

    1989-01-01

    SPECTROM-41 is a finite element heat transfer computer program developed to analyze thermal problems related to nuclear waste disposal. The code is part of the SPECTROM (Special Purpose Engineering Codes for Thermal/ROck Mechanics) series of special purpose finite element programs that are continually being developed by RE/SPEC Inc. (RSI) to address the many unique formations. This document presents the theoretical basis for the mathematical model, the finite element formulation of the program, and a description of the input data for the program, along with details about program support and continuing documentation. The documentation is intended to satisfy the requirements and guidelines outlined in NUREG-0856. The principal component model used in the programs based on Fourier's law of conductance. Numerous program options provide the capability of considering various boundary conditions, material stratification and anisotropy, and time-dependent heat generation that are characteristic of problems involving the disposal of nuclear waste in geologic formation. Numerous verification problems are included in the documentation in addition to highlights of past and ongoing verification and validation efforts. A typical repository problem is solving using SPECTROM-41 to demonstrate the use of the program in addressing problems related to the disposal of nuclear waste

  20. The System 80+ Standard Plant design control document. Volume 18

    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 contains the following technical specifications of section 16 (Technical Specifications) of the ADM Design and Analysis: TS 3.3 Instrumentation; TS 3.4 Reactor Coolant System; TS 3.5 Emergency Core Cooling System; TS 3.6 Containment Systems; TS 3.7 Plant Systems; TS 3.8 Electrical Power Systems; TS 3.9 Refueling Operations; TS 4.0 Design Features; TS 5.0 Administrative Controls. Appendix 16 A Tech Spec Bases is also included. It contains the following: TS B2.0 Safety Limits Bases; TS B3.0 LCO Applicability Bases; TS B3.1 Reactivity Control Bases; TS B3.2 Power Distribution Bases

  1. Integrated management systems and workflow-based electronic document management: An empirical study

    Directory of Open Access Journals (Sweden)

    Hang Thu Pho

    2014-01-01

    Full Text Available Purpose: Many global organizations have aligned their strategy and operation via the ISO-based framework of integrated management system (IMS that allows them to merge quality, environment, health and safety management systems. In such context, having a robust electronic document management system (EDMS is essential, especially at global enterprises where a large amount of documents generated by processes flows through different work cultures. However, there is no "one-size-fits-all" design for EDMS because it depends on organizations' needs, size and resource allocation. This article discusses the interrelation between EDMS and IMS in order to suggest a best practice. Design/methodology/approach: This article methodologically based upon a qualitative, interpretivistic, longitudinal empirical study in a wind turbine factory. Findings and Originality/value: IMS improvement and effectiveness has been overlooking EDMS as a key factor in establishing appropriate technological support of the IMS processes. Rightful application of EDMS can further contribute to organizational learning, precision of documentation and cross-organisational collaboration. Research limitations/implications: Theorising on IMS needs a stronger perspective of the technological limitations and potentials of basing IMS on EDMS. Practical implications: IMS are complex systems involving a large number of administrative functions. EDMS provides a formal representation with automation potentials both heightening and securing document trustworthiness. Social implications: IMS has a tendency to stay with professionals, e.g. line managers and QA/QC/QMS professionals. The EDMS line of discussion suggests a broader inclusion. Originality/value: Researching IMS as a technological implementation is giving a better platform of aligning the IMS with other business processes and is bringing IMS closer to the operational activities within the enterprise.

  2. Automatic public access to documents and maps stored on and internal secure system.

    Science.gov (United States)

    Trench, James; Carter, Mary

    2013-04-01

    The Geological Survey of Ireland operates a Document Management System for providing documents and maps stored internally in high resolution and in a high level secure environment, to an external service where the documents are automatically presented in a lower resolution to members of the public. Security is devised through roles and Individual Users where role level and folder level can be set. The application is an electronic document/data management (EDM) system which has a Geographical Information System (GIS) component integrated to allow users to query an interactive map of Ireland for data that relates to a particular area of interest. The data stored in the database consists of Bedrock Field Sheets, Bedrock Notebooks, Bedrock Maps, Geophysical Surveys, Geotechnical Maps & Reports, Groundwater, GSI Publications, Marine, Mine Records, Mineral Localities, Open File, Quaternary and Unpublished Reports. The Konfig application Tool is both an internal and public facing application. It acts as a tool for high resolution data entry which are stored in a high resolution vault. The public facing application is a mirror of the internal application and differs only in that the application furnishes high resolution data into low resolution format which is stored in a low resolution vault thus, making the data web friendly to the end user for download.

  3. US Department of Energy, Richland Operations Office Integrated Safety Management System Program Description

    International Nuclear Information System (INIS)

    SHOOP, D.S.

    2000-01-01

    The purpose of this Integrated Safety Management System (ISMS) Program Description (PD) is to describe the U.S. Department of Energy (DOE), Richland Operations Office (RL) ISMS as implemented through the RL Integrated Management System (RIMS). This PD does not impose additional requirements but rather provides an overview describing how various parts of the ISMS fit together. Specific requirements for each of the core functions and guiding principles are established in other implementing processes, procedures, and program descriptions that comprise RIMS. RL is organized to conduct work through operating contracts; therefore, it is extremely difficult to provide an adequate ISMS description that only addresses RL functions. Of necessity, this PD contains some information on contractor processes and procedures which then require RL approval or oversight

  4. What Can Pictures Tell Us About Web Pages? Improving Document Search Using Images.

    Science.gov (United States)

    Rodriguez-Vaamonde, Sergio; Torresani, Lorenzo; Fitzgibbon, Andrew W

    2015-06-01

    Traditional Web search engines do not use the images in the HTML pages to find relevant documents for a given query. Instead, they typically operate by computing a measure of agreement between the keywords provided by the user and only the text portion of each page. In this paper we study whether the content of the pictures appearing in a Web page can be used to enrich the semantic description of an HTML document and consequently boost the performance of a keyword-based search engine. We present a Web-scalable system that exploits a pure text-based search engine to find an initial set of candidate documents for a given query. Then, the candidate set is reranked using visual information extracted from the images contained in the pages. The resulting system retains the computational efficiency of traditional text-based search engines with only a small additional storage cost needed to encode the visual information. We test our approach on one of the TREC Million Query Track benchmarks where we show that the exploitation of visual content yields improvement in accuracies for two distinct text-based search engines, including the system with the best reported performance on this benchmark. We further validate our approach by collecting document relevance judgements on our search results using Amazon Mechanical Turk. The results of this experiment confirm the improvement in accuracy produced by our image-based reranker over a pure text-based system.

  5. Breeding description for fast reactors and symbiotic reactor systems

    International Nuclear Information System (INIS)

    Hanan, N.A.

    1979-01-01

    A mathematical model was developed to provide a breeding description for fast reactors and symbiotic reactor systems by means of figures of merit type quantities. The model was used to investigate the effect of several parameters and different fuel usage strategies on the figures of merit which provide the breeding description. The integrated fuel cycle model for a single-reactor is reviewed. The excess discharge is automatically used to fuel identical reactors. The resulting model describes the accumulation of fuel in a system of identical reactors. Finite burnup and out-of-pile delays and losses are treated in the model. The model is then extended from fast breeder park to symbiotic reactor systems. The asymptotic behavior of the fuel accumulation is analyzed. The asymptotic growth rate appears as the largest eigenvalue in the solution of the characteristic equations of the time dependent differential balance equations for the system. The eigenvector corresponding to the growth rate is the core equilibrium composition. The analogy of the long-term fuel cycle equations, in the framework of this model, and the neutron balance equations is explored. An eigenvalue problem adjoint to the one generated by the characteristic equations of the system is defined. The eigenvector corresponding to the largest eigenvalue, i.e. to the growth rate, represents the ''isotopic breeding worths.'' Analogously to the neutron adjoint flux it is shown that the isotopic breeding worths represent the importance of an isotope for breeding, i.e. for the growth rate of a system

  6. The System 80+ Standard Plant design control document. Volume 21

    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 contains parts 1--10 of section 19 (Probabilistic Risk Assessment) of the ADM Design and Analysis. Topics covered are: methodology; initiating event evaluation; accident sequence determination; data analysis; systems analysis; external events analysis; shutdown risk assessment; accident sequence quantification; and sensitivity analysis. Also included in this volume are Appendix 19.8A Shutdown Risk Assessment and Appendix A to Appendix 19.8A Request for Information

  7. Evaluation of the functional performance and technical quality of an Electronic Documentation System of the Nursing Process.

    Science.gov (United States)

    de Oliveira, Neurilene Batista; Peres, Heloisa Helena Ciqueto

    2015-01-01

    To evaluate the functional performance and the technical quality of the Electronic Documentation System of the Nursing Process of the Teaching Hospital of the University of São Paulo. exploratory-descriptive study. The Quality Model of regulatory standard 25010 and the Evaluation Process defined under regulatory standard 25040, both of the International Organization for Standardization/International Electrotechnical Commission. The quality characteristics evaluated were: functional suitability, reliability, usability, performance efficiency, compatibility, security, maintainability and portability. The sample was made up of 37 evaluators. in the evaluation of the specialists in information technology, only the characteristic of usability obtained a rate of positive responses of less than 70%. For the nurse lecturers, all the quality characteristics obtained a rate of positive responses of over 70%. The staff nurses of the medical and surgical clinics with experience in using the system) and staff nurses from other units of the hospital and from other health institutions (without experience in using the system) obtained rates of positive responses of more than 70% referent to the functional suitability, usability, and security. However, performance efficiency, reliability and compatibility all obtained rates below the parameter established. the software achieved rates of positive responses of over 70% for the majority of the quality characteristics evaluated.

  8. Cold Vacuum Drying facility personnel monitoring system design description

    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

  9. Strengthening the Role of Part-Time Faculty in Community Colleges. Example Job Description for Part-Time Faculty: Valencia College--Job Description and Essential Competencies

    Science.gov (United States)

    Center for Community College Student Engagement, 2013

    2013-01-01

    In an effort to support college conversations regarding strengthening the role of part-time faculty, this brief document presents the job description for a Valencia College part-time/adjunct professor (revised as of July 19, 2013). The description includes essential functions, qualifications, and knowledge, skills, and abilities. This is followed…

  10. Guidance and Control Software Project Data - Volume 2: Development Documents

    Science.gov (United States)

    Hayhurst, Kelly J. (Editor)

    2008-01-01

    The Guidance and Control Software (GCS) project was the last in a series of software reliability studies conducted at Langley Research Center between 1977 and 1994. The technical results of the GCS project were recorded after the experiment was completed. Some of the support documentation produced as part of the experiment, however, is serving an unexpected role far beyond its original project context. Some of the software used as part of the GCS project was developed to conform to the RTCA/DO-178B software standard, "Software Considerations in Airborne Systems and Equipment Certification," used in the civil aviation industry. That standard requires extensive documentation throughout the software development life cycle, including plans, software requirements, design and source code, verification cases and results, and configuration management and quality control data. The project documentation that includes this information is open for public scrutiny without the legal or safety implications associated with comparable data from an avionics manufacturer. This public availability has afforded an opportunity to use the GCS project documents for DO-178B training. This report provides a brief overview of the GCS project, describes the 4-volume set of documents and the role they are playing in training, and includes the development documents from the GCS project. Volume 2 contains three appendices: A. Guidance and Control Software Development Specification; B. Design Description for the Pluto Implementation of the Guidance and Control Software; and C. Source Code for the Pluto Implementation of the Guidance and Control Software

  11. On the description of classical Einstein relativistic two-particle systems

    International Nuclear Information System (INIS)

    Aaberge, T.

    1978-01-01

    The author starts by considering the system of one free particle, and gives a sufficiently general description of this system to include the center of mass of systems of several particles. He then passes to the system of two particles. The coordinates separating the center of mass and the internal system are defined and the dynamics discussed. Finally the author outlines the construction of a more restrictive two-particle theory, and studies some consequences of the definition of a particle in an external field as a two-particle system in the limit where the mass of one of the particles becomes infinite. (Auth.)

  12. Subsurface conditions description for the S-SX waste management area

    International Nuclear Information System (INIS)

    WOOD, M.I.

    1999-01-01

    This document provides a discussion of the subsurface conditions relevant to the occurrence and migration of contaminants in the vadose zone and groundwater underlying the 241-5 and 241-SX tank farms This document provides a concise summary of existing information in support of characterization planning This document includes a description of the available environmental contamination data and a limited qualitative interpretation of these data

  13. Representation and traversal of documentation space. Data analysis, neuron networks and image banks

    International Nuclear Information System (INIS)

    Lelu, A.; Rosenblatt, D.

    1986-01-01

    Improvements in the visual representation of considerable amounts of data for the user is necessary for progress in documentation systems. We review practical implementations in this area, which additionally integrate concepts arising from data analysis in the most general sense. The relationship between data analysis and neuron networks is then established. Following a description of simulation experiments, we finally present software for outputting and traversing image banks which integrate most of the concept developed in this article [fr

  14. [Support of the nursing process through electronic nursing documentation systems (UEPD) – Initial validation of an instrument].

    Science.gov (United States)

    Hediger, Hannele; Müller-Staub, Maria; Petry, Heidi

    2016-01-01

    Electronic nursing documentation systems, with standardized nursing terminology, are IT-based systems for recording the nursing processes. These systems have the potential to improve the documentation of the nursing process and to support nurses in care delivery. This article describes the development and initial validation of an instrument (known by its German acronym UEPD) to measure the subjectively-perceived benefits of an electronic nursing documentation system in care delivery. The validity of the UEPD was examined by means of an evaluation study carried out in an acute care hospital (n = 94 nurses) in German-speaking Switzerland. Construct validity was analyzed by principal components analysis. Initial references of validity of the UEPD could be verified. The analysis showed a stable four factor model (FS = 0.89) scoring in 25 items. All factors loaded ≥ 0.50 and the scales demonstrated high internal consistency (Cronbach's α = 0.73 – 0.90). Principal component analysis revealed four dimensions of support: establishing nursing diagnosis and goals; recording a case history/an assessment and documenting the nursing process; implementation and evaluation as well as information exchange. Further testing with larger control samples and with different electronic documentation systems are needed. Another potential direction would be to employ the UEPD in a comparison of various electronic documentation systems.

  15. Precise Documentation: The Key to Better Software

    Science.gov (United States)

    Parnas, David Lorge

    The prime cause of the sorry “state of the art” in software development is our failure to produce good design documentation. Poor documentation is the cause of many errors and reduces efficiency in every phase of a software product's development and use. Most software developers believe that “documentation” refers to a collection of wordy, unstructured, introductory descriptions, thousands of pages that nobody wanted to write and nobody trusts. In contrast, Engineers in more traditional disciplines think of precise blueprints, circuit diagrams, and mathematical specifications of component properties. Software developers do not know how to produce precise documents for software. Software developments also think that documentation is something written after the software has been developed. In other fields of Engineering much of the documentation is written before and during the development. It represents forethought not afterthought. Among the benefits of better documentation would be: easier reuse of old designs, better communication about requirements, more useful design reviews, easier integration of separately written modules, more effective code inspection, more effective testing, and more efficient corrections and improvements. This paper explains how to produce and use precise software documentation and illustrate the methods with several examples.

  16. The System 80+ Standard Plant design control document. Volume 23

    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 contains part 16 References and Appendix 19 A Design Alternatives for section 19 (Probabilistic Risk Assessment) of the ADM Design and Analysis. Also covered is section 20 Unresolved Safety Issues of the ADM Design and Analysis. Finally sections 1--6 of the ADM Emergency Operations Guidelines are contained in this volume. Information covered in these sections include: standard post-trip actions; diagnostic actions; reactor trip recovery guideline; LOCA recovery; SG tube rupture recovery

  17. GASCAP: Wellhead Gas Productive Capacity Model documentation, June 1993

    International Nuclear Information System (INIS)

    1993-01-01

    The Wellhead Gas Productive Capacity Model (GASCAP) has been developed by EIA to provide a historical analysis of the monthly productive capacity of natural gas at the wellhead and a projection of monthly capacity for 2 years into the future. The impact of drilling, oil and gas price assumptions, and demand on gas productive capacity are examined. Both gas-well gas and oil-well gas are included. Oil-well gas productive capacity is estimated separately and then combined with the gas-well gas productive capacity. This documentation report provides a general overview of the GASCAP Model, describes the underlying data base, provides technical descriptions of the component models, diagrams the system and subsystem flow, describes the equations, and provides definitions and sources of all variables used in the system. This documentation report is provided to enable users of EIA projections generated by GASCAP to understand the underlying procedures used and to replicate the models and solutions. This report should be of particular interest to those in the Congress, Federal and State agencies, industry, and the academic community, who are concerned with the future availability of natural gas

  18. Model documentation: Renewable Fuels Module of the National Energy Modeling System

    Energy Technology Data Exchange (ETDEWEB)

    1994-04-01

    This report documents the objectives, analytical approach, and design of the National Energy Modeling System (NEMS) Renewable Fuels Module (RFM) as it related to the production of the 1994 Annual Energy Outlook (AEO94) forecasts. The report catalogues and describes modeling assumptions, computational methodologies, data inputs, and parameter estimation techniques. A number of offline analyses used in lieu of RFM modeling components are also described. This documentation report serves two purposes. First, it is a reference document for model analysts, model users, and the public interested in the construction and application of the RFM. Second, it meets the legal requirement of the Energy Information Administration (EIA) to provide adequate documentation in support of its models. The RFM consists of six analytical submodules that represent each of the major renewable energy resources -- wood, municipal solid waste (MSW), solar energy, wind energy, geothermal energy, and alcohol fuels. Of these six, four are documented in the following chapters: municipal solid waste, wind, solar and biofuels. Geothermal and wood are not currently working components of NEMS. The purpose of the RFM is to define the technological and cost characteristics of renewable energy technologies, and to pass these characteristics to other NEMS modules for the determination of mid-term forecasted renewable energy demand.

  19. Title list of documents made publicly available: October 1--31, 1994. Volume 16, Number 10

    Energy Technology Data Exchange (ETDEWEB)

    1994-12-01

    The Title List of Documents Made Publicly Available is a monthly publication. It contains descriptions of the information received and generated by the US Nuclear Regulatory Commission (NRC). This information includes (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials and (2) nondocketed material received and generated by NRC pertinent to its role as a regulatory agency. As used here, docketed does not refer to Court dockets; it refers to the system by which NRC maintains its regulatory records. This series of documents is indexed by a Personal Author Index, a Corporate Source Index, and a Report Number Index.

  20. Title list of documents made publicly available June 1-30, 1984. Volume 6, No. 6

    International Nuclear Information System (INIS)

    1984-08-01

    The Title List of Documents Made Publicly Available is a monthly publication. It contains descriptions of the information received and generated by the US Nuclear Regulatory Commission (NRC). This information includes: (1) docketed material asociated with civilian nuclear power plants and other uses of radioactive materials; and (2) nondocketed material received and generated by NRC pertinent to its role as a regulatory agency. As used here, docketed does not refer to Court dockets; it refers to the system by which NRC maintains its regulatory records. This series of documents is indexed by a Personal Author Index, a Corporate Source Index, and a Report Number Index

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