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Sample records for program description document

  1. 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

  2. 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.

  3. Fuel Handling Facility Description Document

    International Nuclear Information System (INIS)

    M.A. LaFountain

    2005-01-01

    The purpose of the facility description document (FDD) is to establish the requirements and their bases that drive the design of the Fuel Handling Facility (FHF) to allow the design effort to proceed to license application. This FDD is a living document that will be revised at strategic points as the design matures. It identifies the requirements and describes the facility design as it currently exists, with emphasis on design attributes provided to meet the requirements. This FDD was developed as an engineering tool for design control. Accordingly, the primary audience and users are design engineers. It leads the design process with regard to the flow down of upper tier requirements onto the facility. Knowledge of these requirements is essential to performing the design process. It trails the design with regard to the description of the facility. This description is a reflection of the results of the design process to date

  4. 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

  5. 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.

  6. 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)

  7. 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

  8. 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

  9. Hanford Waste Vitrification Plant quality assurance program description: Overview and applications

    International Nuclear Information System (INIS)

    Caplinger, W.H.

    1990-12-01

    This document describes the Hanford Waste Vitrification Plant Project Quality Assurance Program. This program is being implemented to ensure the acceptability of high-level radioactive canistered waste forms produced by the Hanford Waste Vitrification Plant for disposal in a licensed federal repository. The Hanford Waste Vitrification Plant Quality Assurance Program is comprised of this Quality Assurance Program Description as well as the associated contractors' quality assurance programs. The objective of this Quality Assurance Program Description is to provide the Hanford Waste Vitrification Plant Project participants with guidance and direction for program implementation while satisfying the US Department of Energy Office of Civilian Radioactive Waste Management needs in repository licensing activities with regard to canistered waste forms. To accomplish this objective, this description will be prepared in three parts: Part 1 - Overview and applications document; Part 2 - Development and qualification of the canistered waste form; Part 3 - Production of canistered waste forms. Part 1 describes the background, strategy, application, and content of the Hanford Waste Vitrification Plant Quality Assurance Program. This Quality Assurance Program Description, when complete, is designed to provide a level of confidence in the integrity of the canistered waste forms. 8 refs

  10. 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.

  11. 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

  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. 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

  14. 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.

  15. 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)

  16. 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)

  17. Concept document of the repository-based software engineering program: A constructive appraisal

    Science.gov (United States)

    1992-01-01

    A constructive appraisal of the Concept Document of the Repository-Based Software Engineering Program is provided. The Concept Document is designed to provide an overview of the Repository-Based Software Engineering (RBSE) Program. The Document should be brief and provide the context for reading subsequent requirements and product specifications. That is, all requirements to be developed should be traceable to the Concept Document. Applied Expertise's analysis of the Document was directed toward assuring that: (1) the Executive Summary provides a clear, concise, and comprehensive overview of the Concept (rewrite as necessary); (2) the sections of the Document make best use of the NASA 'Data Item Description' for concept documents; (3) the information contained in the Document provides a foundation for subsequent requirements; and (4) the document adequately: identifies the problem being addressed; articulates RBSE's specific role; specifies the unique aspects of the program; and identifies the nature and extent of the program's users.

  18. 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.

  19. 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

  20. Toward Documentation of Program Evolution

    DEFF Research Database (Denmark)

    Vestdam, Thomas; Nørmark, Kurt

    2005-01-01

    The documentation of a program often falls behind the evolution of the program source files. When this happens it may be attractive to shift the documentation mode from updating the documentation to documenting the evolution of the program. This paper describes tools that support the documentatio....... It is concluded that our approach can help revitalize older documentation, and that discovery of the fine grained program evolution steps help the programmer in documenting the evolution of the program....

  1. 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

  2. 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

  3. Mathematical description and program documentation for CLASSY, an adaptive maximum likelihood clustering method

    Science.gov (United States)

    Lennington, R. K.; Rassbach, M. E.

    1979-01-01

    Discussed in this report is the clustering algorithm CLASSY, including detailed descriptions of its general structure and mathematical background and of the various major subroutines. The report provides a development of the logic and equations used with specific reference to program variables. Some comments on timing and proposed optimization techniques are included.

  4. The Vicinity of Program Documentation Tools

    DEFF Research Database (Denmark)

    Nørmark, Kurt

    between program development tools.  In the central part of the paper we introduce a mapping of documentation flow between program development tools.  In addition we discuss a set of locally developed tools which is related to program documentation.  The use of test cases as examples in an interface......Program documentation plays a vital role in almost all programming processes.  Program documentation flows between separate tools of a modularized environment, and in between the components of an integrated development environment as well.  In this paper we discuss the flow of program documentation...... documentation tool is a noteworthy and valuable contribution to the documentation flow.  As an additional contribution we identify several circular relationships which illustrate feedback of documentation to the program editor from other tools in the development environment....

  5. 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.

  6. 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

  7. 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.

  8. ELESTRES.M11K program users'manual and description

    International Nuclear Information System (INIS)

    Suk, H. C.; Hwang, W.; Kim, B. G.; Sim, K. S.; Heo, Y. H.; Byun, T. S.; Park, G. S.

    1992-12-01

    ELESTRES.M11K is a computer program for simulating the behaviour of UO 2 fuel elements under normal operating conditions of a CANDU reactor. It computers the one-dimensional temperature distribution and thermal expansion of the fuel pellets, and computes two-dimensional pellet deformation using FEM. The amount of fission gas released and sheath strain/stress are also computed. This document is intended as a users' manual and description for ELESTRES.M11K program. (Author)

  9. RECON: a computer program for analyzing repository economics. Documentation and user's manual

    International Nuclear Information System (INIS)

    Clark, L.L.; Cole, B.M.; McNair, G.W.; Schutz, M.E.

    1983-05-01

    From 1981 through 1983 the Pacific Northwest Laboratory has been developing a computer model named RECON to calculate repository costs from parametric data input. The objective of the program has been to develop the capability to evalute the effect on costs of changes in repository design parameters and operating scenario assumptions. This report documents the development of the model through March of 1983. Included in the report are: (1) descriptions of model development and the underlying equations, assumptions and definitions; (2) descriptions of data input either using card images or an interactive data input program; and (3) detailed listings of the program and definitions of program variables. Cost estimates generated using the model have been verified against independent estimates and good agreement has been obtained

  10. 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

  11. 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.'

  12. KAFEPA-II program users' manual and description

    International Nuclear Information System (INIS)

    Suk, H. C.; Hwang, W.; Kim, B. G.; Sim, K. S.; Heo, Y. H.; Byun, T. S.; Park, G. S.

    1992-04-01

    KAFEPA-II is a computer program for simulating the behaviour of UO 2 fuel elements under normal operating conditions of a CANDU reactor. It computes the one-dimensional temperature distribution and thermal expansion of the fuel pellets. The amount of gas released during irradiation of the fuel is also computed. Thermal expansion and gas pressure inside the fuel element are then used to compute the strains and stresses in the sheath. This document is intended as a user's manual and description for KAFEPA-II. (Author)

  13. Precise documentation of well-structured programs

    Energy Technology Data Exchange (ETDEWEB)

    Parnas, D.L.; Madey, J.; Iglewski, M. [McMaster Univ., Hamilton, Ontario (Canada)

    1997-11-01

    This paper describes a new form of program documentation that is precise, systematic and readable. This documentation comprises a set of displays supplemented by a lexicon and an index. Each display presents a program fragment in such a way that its correctness can be examined without looking at any other display. Each display has three parts: (1) the specification of the program presented in the display, (2) the program itself, and (3) the specifications of programs invoked by this program. The displays are intended to be used by Software Engineers as a reference document during inspection and maintenance. This paper also introduces a specification technique that is a refinement of Mills functional approach to program documentation and verification; programs are specified and described in tabular form.

  14. Instruction in Documentation for Computer Programming

    Science.gov (United States)

    Westley, John W.

    1976-01-01

    In addition to the input/output record format, the program flowchart, the program listing, and the program test output, eight documentation items are suggested in order that they may serve as a base from which to start teaching program documentation. (Author/AG)

  15. Quality assurance program description: Hanford Waste Vitrification Plant, Part 1

    International Nuclear Information System (INIS)

    1992-01-01

    This document describes the Department of Energy's Richland Field Office (DOE-RL) quality assurance (QA) program for the processing of high-level waste as well as the Vitrification Project Quality Assurance Program for the design and construction of the Hanford Waste Vitrification Plant (HWVP). It also identifies and describes the planned activities that constitute the required quality assurance program for the HWVP. This program applies to the broad scope of quality-affecting activities associated with the overall HWVP Facility. Quality-affecting activities include designing, purchasing, fabricating, handling, shipping, storing, cleaning, erecting, installing, inspecting, testing, maintaining, repairing, and modifying. Also included are the development, qualification, and production of waste forms which may be safely used to dispose of high-level radioactive waste resulting from national defense activities. The HWVP QA program is made up of many constituent programs that are being implemented by the participating organizations. This Quality Assurance program description is intended to outline and define the scope and application of the major programs that make up the HWVP QA program. It provides a means by which the overall program can be managed and directed to achieve its objectives. Subsequent parts of this description will identify the program's objectives, its scope, application, and structure

  16. RECON: a computer program for analyzing repository economics. Documentation and user's manual. Revision 1

    International Nuclear Information System (INIS)

    Clark, L.L.; Schutz, M.E.; Luksic, A.T.

    1985-07-01

    From 1981 through 1984 the Pacific Northwest Laboratory has been developing a computer model named RECON to calculate repository costs from parametric data input. The objective of the program has been to develop the capability to evaluate the effect on costs of changes in repository design parameters and operating scenario assumptions. This report documents the development of the model through September of 1984. Included in the report are: (1) descriptions of model development and the underlying equations, assumptions and definitions; (2) descriptions of data input using either card images or an interactive data input program; and (3) detailed listings of the program and definitions of program variables. Cost estimates generated using the model have been verified against independent estimates and good agreement has been obtained. 2 refs

  17. Plutonium immobilization project development and testing quality assurance program description - February 1999

    International Nuclear Information System (INIS)

    MacLean, L. M.; Ziemba, J.

    1999-01-01

    Lawrence Livermore National Laboratory Immobilization Development and Testing organization (LLNL ID and T) is a Participant in the Plutonium Immobilization Project (PIP). The LLNL D and T has lead responsibilities for form characterization and qualification, ceramic form development, process/equipment development with plutonium, and process systems testing and validation for both conversion and immobilization. This work must be performed in accordance with the graded approach of a Quality Assurance (QA) Program. A QA Program has been developed at LLNL to meet the requirements of the DOE/MD Quality Assurance Requirements. The LLNL QA Program consists of a Quality Assurance Program Description (QAPD) and Quality Implementing Procedures. These documents interface and are a subset of the overall PIP QA Program Documents. The PIP QA Program is described in the PIP ID and T QA Plan, PIP QAPD, and QA Procedures. Other Participant Organizations also must document and describe their PIP compliant QA Programs in a QAPD and implementing procedures. The purpose of this LLNL QAPD is to describe the organization, management processes, QA Controls for Grading, functional responsibilities, levels of authority, and interfaces for those managing, performing, and assessing the adequacy of work

  18. Repository-based software engineering program: Concept document

    Science.gov (United States)

    1992-01-01

    This document provides the context for Repository-Based Software Engineering's (RBSE's) evolving functional and operational product requirements, and it is the parent document for development of detailed technical and management plans. When furnished, requirements documents will serve as the governing RBSE product specification. The RBSE Program Management Plan will define resources, schedules, and technical and organizational approaches to fulfilling the goals and objectives of this concept. The purpose of this document is to provide a concise overview of RBSE, describe the rationale for the RBSE Program, and define a clear, common vision for RBSE team members and customers. The document also provides the foundation for developing RBSE user and system requirements and a corresponding Program Management Plan. The concept is used to express the program mission to RBSE users and managers and to provide an exhibit for community review.

  19. Defense Transuranic Waste Program Strategy Document

    International Nuclear Information System (INIS)

    1984-01-01

    The Defense Transuranic Waste Program (DTWP) Strategy Document presents the general strategy for managing transuranic (TRU) waste materials generated during defense and research activities regulated by the US Department of Energy. The Strategy Document includes discussion of objectives and activities relating to the entire Defense Transuranic Waste Program. However, the primary focus is on the specific management responsibilities of the Transuranic Waste Lead Organization (TLO). The document also includes an updated summary of progress on TLO-managed activities over the past year

  20. Strategic environmental safety inspection for the National disposal program. Description of the inspection volume. Documentation for the scoping team

    International Nuclear Information System (INIS)

    2015-01-01

    The Strategic environmental safety inspection for the National disposal program covers the following topics: Legal framework: determination of the requirement for an environmental inspection program, coordination of the scoping team into the overall context; environmental targets; approach for assessment and evaluation of environmental impact, description of the inspection targets for the strategic environmental inspection; consideration of alternatives.

  1. Solid Waste Program technical baseline description

    Energy Technology Data Exchange (ETDEWEB)

    Carlson, A.B.

    1994-07-01

    The system engineering approach has been taken to describe the technical baseline under which the Solid Waste Program is currently operating. The document contains a mission analysis, function analysis, system definition, documentation requirements, facility and project bases, and uncertainties facing the program.

  2. Quality assurance requirements and description for the Civilian Radioactive Waste Management Program

    International Nuclear Information System (INIS)

    1992-01-01

    The Quality Assurance Requirements and Description (QARD) is the principal quality assurance document for the Civilian Radioactive Waste Management Program (Program). It establishes the minimum requirements for the Quality Assurance Program. The QARD contains regulatory requirements and program commitments necessary for the development of an effective quality assurance program. Quality assurance implementing documents must be based on, and consistent with, QARD requirements. The QARD applies to the following: (1) acceptance of spent nuclear fuel and high-level radioactive waste; (2) transport of spent nuclear fuel and high-level radioactive waste; (3) the Monitored Retrievable Storage (MRS) facility through application for an operating license; (4) Mined Geologic Disposal System (MGDS), including the site characterization activities (exploratory studies facility (ESF) and surface based testing), through application for an operating license; (5) the high-level-waste form from production through acceptance. Section 2.0 defines in greater detail criteria for determining work subject to QARD requirements. The QARD is organized into sections, supplements, appendices, and a glossary. The sections contain requirements that are common to all Program elements. The supplements contain requirements for specialized activities. The appendices contain requirements that are specific to an individual Program element. The glossary establishes a common vocabulary for the Quality Assurance Program

  3. 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…

  4. 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

  5. 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)

  6. Nuclear Waste Management Program summary document, FY 1981

    Energy Technology Data Exchange (ETDEWEB)

    Meyers, Sheldon

    1980-03-01

    The Nuclear Waste Management Program Summary Document outlines the operational and research and development (R and D) activities of the Office of Nuclear Waste Management (NEW) under the Assistant Secretary for Nuclear Energy, US Department of Energy (DOE). This document focuses on the current and planned activities in waste management for FY 1981. This Program Summary Document (PSD) was prepared in order to explain the Federal nuclear waste management and spent fuel storage programs to Congress and its committees and to interested members of the public, the private sector, and the research community. The national energy policy as it applies to waste management and spent fuel storage is presented first. The program strategy, structure, budget, management approach, and public participation programs are then identified. The next section describes program activities and outlines their status. Finally, the applicability of departmental policies to NEW programs is summarized, including field and regional activities, commercialization plans, and environmental and socioeconomic implications of waste management activities, and international programs. This Nuclear Waste Management Program Summary Document is meant to serve as a guide to the progress of R and D and other energy technology programs in radioactive waste management. The R and D objective is to provide the Nation with acceptable solutions to short- and long-term management problems for all forms of radioactive waste and spent fuel.

  7. Nuclear Waste Management Program summary document, FY 1981

    International Nuclear Information System (INIS)

    1980-03-01

    The Nuclear Waste Management Program Summary Document outlines the operational and research and development (R and D) activities of the Office of Nuclear Waste Management (NEW) under the Assistant Secretary for Nuclear Energy, US Department of Energy (DOE). This document focuses on the current and planned activities in waste management for FY 1981. This Program Summary Document (PSD) was prepared in order to explain the Federal nuclear waste management and spent fuel storage programs to Congress and its committees and to interested members of the public, the private sector, and the research community. The national energy policy as it applies to waste management and spent fuel storage is presented first. The program strategy, structure, budget, management approach, and public participation programs are then identified. The next section describes program activities and outlines their status. Finally, the applicability of departmental policies to NEW programs is summarized, including field and regional activities, commercialization plans, and environmental and socioeconomic implications of waste management activities, and international programs. This Nuclear Waste Management Program Summary Document is meant to serve as a guide to the progress of R and D and other energy technology programs in radioactive waste management. The R and D objective is to provide the Nation with acceptable solutions to short- and long-term management problems for all forms of radioactive waste and spent fuel

  8. GROUNDWATER PROTECTION MANAGEMENT PROGRAM DESCRIPTION.

    Energy Technology Data Exchange (ETDEWEB)

    PAQUETTE,D.E.; BENNETT,D.B.; DORSCH,W.R.; GOODE,G.A.; LEE,R.J.; KLAUS,K.; HOWE,R.F.; GEIGER,K.

    2002-05-31

    THE DEPARTMENT OF ENERGY ORDER 5400.1, GENERAL ENVIRONMENTAL PROTECTION PROGRAM, REQUIRES THE DEVELOPMENT AND IMPLEMENTATION OF A GROUNDWATER PROTECTION PROGRAM. THE BNL GROUNDWATER PROTECTION MANAGEMENT PROGRAM DESCRIPTION PROVIDES AN OVERVIEW OF HOW THE LABORATORY ENSURES THAT PLANS FOR GROUNDWATER PROTECTION, MONITORING, AND RESTORATION ARE FULLY DEFINED, INTEGRATED, AND MANAGED IN A COST EFFECTIVE MANNER THAT IS CONSISTENT WITH FEDERAL, STATE, AND LOCAL REGULATIONS.

  9. 40 CFR 239.4 - Narrative description of state permit program.

    Science.gov (United States)

    2010-07-01

    ... 40 Protection of Environment 24 2010-07-01 2010-07-01 false Narrative description of state permit program. 239.4 Section 239.4 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) SOLID... Narrative description of state permit program. The description of a state's program must include: (a) An...

  10. 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.

  11. 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

  12. 40 CFR 233.11 - Program description.

    Science.gov (United States)

    2010-07-01

    ... organization and structure of the State agency (agencies) which will have responsibility for administering the... under § 233.10 shall include: (a) A description of the scope and structure of the State's program. The... will coordinate its enforcement strategy with that of the Corps and EPA; (h) A description of the...

  13. Program information architecture/document hierarchy

    International Nuclear Information System (INIS)

    Woods, T.W.

    1991-09-01

    The Nuclear Waste Management System (NWMS) Management Systems Improvement Strategy (MSIS) (DOE 1990) requires that the information within the computer program and information management system be ordered into a precedence hierarchy for consistency. Therefore, the US Department of Energy (DOE). Office of Civilian Radioactive Waste Management (OCRWM) requested Westinghouse Hanford Company to develop a plan for NWMS program information which the MSIS calls a document hierarchy. This report provides the results of that effort and describes the management system as a ''program information architecture.'' 3 refs., 3 figs

  14. Assessment model validity document. NAMMU: A program for calculating groundwater flow and transport through porous media

    International Nuclear Information System (INIS)

    Cliffe, K.A.; Morris, S.T.; Porter, J.D.

    1998-05-01

    NAMMU is a computer program for modelling groundwater flow and transport through porous media. This document provides an overview of the use of the program for geosphere modelling in performance assessment calculations and gives a detailed description of the program itself. The aim of the document is to give an indication of the grounds for having confidence in NAMMU as a performance assessment tool. In order to achieve this the following topics are discussed. The basic premises of the assessment approach and the purpose of and nature of the calculations that can be undertaken using NAMMU are outlined. The concepts of the validation of models and the considerations that can lead to increased confidence in models are described. The physical processes that can be modelled using NAMMU and the mathematical models and numerical techniques that are used to represent them are discussed in some detail. Finally, the grounds that would lead one to have confidence that NAMMU is fit for purpose are summarised

  15. 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

  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. 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.

  18. 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.

  19. 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.

  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. 24 CFR 92.62 - Review of program description and certifications.

    Science.gov (United States)

    2010-04-01

    ... and Urban Development HOME INVESTMENT PARTNERSHIPS PROGRAM Allocation Formula Insular Areas Program... description unless the insular area has failed to submit information sufficient to allow HUD to make the... projects or activities in its program description. (c) HOME Investment Partnership Agreement. After HUD...

  2. Guidelines for the documentation of digital computer programs - approved 1974

    International Nuclear Information System (INIS)

    Anon.

    1975-01-01

    This standard presents guidelines for the documentation of engineering and scientific computer programs. Good documentation promotes understanding, reduces duplication of effort, eases conversion to different computer environments and aids modification for extended applications. Good documentation is essential for implementation and effective use of programs obtained from other installations. Since the intention of this standard is to encourage better communication between the developer and user, it should be regarded as a guide rather than a set of rigid specifications. As a guide, it is sufficiently comprehensive to apply to large-scale programs intended for extensive external use. Not all features of this document are appropriate in all circumstances. In general, as the project complexity increases so does the need for more complete documentation. An organization may have special documentation requirements which supersede or extend these guidelines. This standard is a revision of ANS-STD.2-1967 and supersedes it

  3. International Nuclear Model. Volume 3. Program description

    International Nuclear Information System (INIS)

    Andress, D.

    1985-01-01

    This is Volume 3 of three volumes of documentation of the International Nuclear Model (INM). This volume presents the Program Description of the International Nuclear Model, which was developed for the Nuclear and Alternate Fuels Division (NAFD), Office of Coal, Nuclear, Electric and Alternate Fuels, Energy Information Administration (EIA), US Department of Energy (DOE). The International Nuclear Model (INM) is a comprehensive model of the commercial nuclear power industry. It simulates economic decisions for reactor deployment and fuel management decision based on an input set of technical economic and scenario parameters. The technical parameters include reactor operating characteristics, fuel cycle timing and mass loss factors, and enrichment tails assays. Economic parameters include fuel cycle costs, financial data, and tax alternatives. INM has a broad range of scenario options covering, for example, process constraints, interregional activities, reprocessing, and fuel management selection. INM reports reactor deployment schedules, electricity generation, and fuel cycle requirements and costs. It also has specialized reports for extended burnup and permanent disposal. Companion volumes to Volume 3 are: Volume 1 - Model Overview, and Volume 2 - Data Base Relationships

  4. GGP Program Description, 2006-2011 | IDRC - International ...

    International Development Research Centre (IDRC) Digital Library (Canada)

    2010-12-22

    Dec 22, 2010 ... This document explains the context and orientation of the IDRC's Globalization, Growth and Poverty (GGP) program initiative for the 2006-11 period, detailing the GGP program's objectives, research areas, cross-cutting themes, and programming approach.Download the PDF : Globalization, Growth and ...

  5. 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

  6. 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.

  7. Hanford Waste Vitrification Plant Quality Assurance Program description for high-level waste form development and qualification

    International Nuclear Information System (INIS)

    1993-08-01

    The Hanford Waste Vitrification Plant Project has been established to convert the high-level radioactive waste associated with nuclear defense production at the Hanford Site into a waste form suitable for disposal in a deep geologic repository. The Hanford Waste Vitrification Plant will mix processed radioactive waste with borosilicate material, then heat the mixture to its melting point (vitrification) to forin a glass-like substance that traps the radionuclides in the glass matrix upon cooling. The Hanford Waste Vitrification Plant Quality Assurance Program has been established to support the mission of the Hanford Waste Vitrification Plant. This Quality Assurance Program Description has been written to document the Hanford Waste Vitrification Plant Quality Assurance Program

  8. 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

  9. PSP Program close out documentation

    Energy Technology Data Exchange (ETDEWEB)

    Andringa, K.; Hootman, H.E.; Ferrara, A.S.; Smith, P.K.; Congdon, J.W.; Randolph, H.W.; Young, R.H.; Driggers, F.E.; Topp, S.V.

    1985-12-31

    In December 1982 DOE-SR directed SRL to study the feasibility and impact of a program to lower the U-236 content of the Highly Enriched Uranium (HEU) stockpile used as fuel for the SRP reactors. In response to this request SRL assessed four technologies, Atomic Vapor Laser Isotope Separation (AVLIS), Molecular Laser Isotope Separation (MLIS), Gas Centrifuge, and the Plasma Separation Process (PSP) for this purpose with the assistance of the Engineering Department. In April 1983 cost/benefit analyses for these processes, high spot cost estimates for production facilities, and process uncertainties were submitted to DOE-SR with a recommendation to proceed with the conceptual design and supporting development programs for a facility based on the use of the PSP process. The current program status for the PSP development program at SRL and the design and documentation of a production facility at SRP, referred to as the Fuel Improvement Demonstration Facility (FIDF), is described in this report.

  10. 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.

  11. 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

  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. Computer Program for Calculation of Complex Chemical Equilibrium Compositions and Applications II. Users Manual and Program Description. 2; Users Manual and Program Description

    Science.gov (United States)

    McBride, Bonnie J.; Gordon, Sanford

    1996-01-01

    This users manual is the second part of a two-part report describing the NASA Lewis CEA (Chemical Equilibrium with Applications) program. The program obtains chemical equilibrium compositions of complex mixtures with applications to several types of problems. The topics presented in this manual are: (1) details for preparing input data sets; (2) a description of output tables for various types of problems; (3) the overall modular organization of the program with information on how to make modifications; (4) a description of the function of each subroutine; (5) error messages and their significance; and (6) a number of examples that illustrate various types of problems handled by CEA and that cover many of the options available in both input and output. Seven appendixes give information on the thermodynamic and thermal transport data used in CEA; some information on common variables used in or generated by the equilibrium module; and output tables for 14 example problems. The CEA program was written in ANSI standard FORTRAN 77. CEA should work on any system with sufficient storage. There are about 6300 lines in the source code, which uses about 225 kilobytes of memory. The compiled program takes about 975 kilobytes.

  14. Source document for waste area groupings at Oak Ridge National Laboratory, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    Osborne, P.L.; Kuhaida, A.J., Jr.

    1996-09-01

    This document serves as a source document for Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) and other types of documents developed for and pertaining to Environmental Restoration (ER) Program activities at Oak Ridge National Laboratory (ORNL). It contains descriptions of the (1) regulatory requirements for the ORR ER Program, (2) Oak Ridge Reservation (ORR) ER Program, (3) ORNL site history and characterization, and (4) history and characterization of Waste Area Groupings (WAGS) 1-20. This document was created to save time, effort, and money for persons and organizations drafting documents for the ER Program and to improve consistency in the documents prepared for the program. By eliminating the repetitious use of selected information about the program, this document will help reduce the time and costs associated with producing program documents. By serving as a benchmark for selected information about the ER Program, this reference will help ensure that information presented in future documents is accurate and complete

  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. NRC/RSR Data Bank Program description

    International Nuclear Information System (INIS)

    Bankert, S.F.

    1979-01-01

    The United States Nuclear Regulatory Commission (NRC) has established the NRC/Reactor Safety Research (RSR) Data Bank Program to collect, store, and make available data from the many domestic and foreign water reactor safety research programs. Local direction of the program is provided by EG and G Idaho, Inc., at Idaho National Engineering Laboratory. The NRC/RSR Data Bank Program provides a central computer storage mechanism and access software for data to be used by code development and assessment groups in meeting the code and correlation needs of the nuclear industry. The administrative portion of the program provides data entry, documentation, and training and advisory services to users and the NRC. The NRC/RSR Data Bank Program and the capabilities of the data access software are described

  17. 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

  18. Standards for maintenance documentation of COSMOS programs

    International Nuclear Information System (INIS)

    Burstall, R.F.; Rickets, T.M.; Butland, A.T.D.

    1982-06-01

    The Compatible Open Shop Modular Operating Scheme (COSMOS) is used for fast reactor neutronics and subassembly distortion calculations in the UK. It provides database and databank facilities for this purpose. A large number of applications programs use these facilities. This report sets down the standards agreed for use in the preparation of maintenance documents for these programs. These standards have been developed as the result of experience with earlier more complicated standards. Some of the terminology used in this report is particular to COSMOS, but the general features of the standard may be useful to those responsible for other computer programs. (author)

  19. Planning, Conducting, and Documenting Data Analysis for Program Improvement

    Science.gov (United States)

    Winer, Abby; Taylor, Cornelia; Derrington, Taletha; Lucas, Anne

    2015-01-01

    This 2015 document was developed to help technical assistance (TA) providers and state staff define and limit the scope of data analysis for program improvement efforts, including the State Systemic Improvement Plan (SSIP); develop a plan for data analysis; document alternative hypotheses and additional analyses as they are generated; and…

  20. Regulatory research and support program for 1988/89 - project descriptions

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1988-03-15

    Information Bulletin, 1988. Project descriptions for the Regulatory Research and Support Program. This Information Bulletin contains a list of the projects with a brief description of each, and additional supporting information.

  1. Regulatory research and support program for 1988/89 - project descriptions

    International Nuclear Information System (INIS)

    1988-01-01

    Information Bulletin, 1988. Project descriptions for the Regulatory Research and Support Program. This Information Bulletin contains a list of the projects with a brief description of each, and additional supporting information

  2. Report on architecture description for the INFLO prototype.

    Science.gov (United States)

    2014-01-01

    This report documents the Architecture Description for the implementation of the Intelligent Network Flow Optimization : (INFLO) Prototype bundle within the Dynamic Mobility Applications (DMA) portion of the Connected Vehicle Program. The : intent is...

  3. Hanford site guide for preparing and maintaining generator group pollution prevention program documentation

    International Nuclear Information System (INIS)

    1995-12-01

    This manual provides the necessary guidance to contractor generator groups for developing and maintaining documentation of their pollution prevention (P2) program activities. Preparation of program documentation will demonstrate compliance with contractor and U.S. Department of Energy (DOE) requirements, as well as state and federal regulations. Contractor waste generator groups are no longer required to prepare and update facility waste minimization plans. Developing and maintaining program documentation replace this requirement

  4. 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

  5. Plutonium immobilization project development and testing technical project office quality assurance program description

    International Nuclear Information System (INIS)

    Gould, T.H.; MacLean, L.M.; Ziemba, J.M.

    1999-01-01

    The Plutonium Immobilization Project (PIP) is one of several fissile materials disposition projects managed by the Department of Energy (DOE) Office of Fissile Materials Disposition (OFMD). The PIP is expected to evolve from the current Development and Testing (D and T) effort, to design, to construction, and finally to operations. Overall management and technical management of the D and T effort resides at the Lead Laboratory, Lawrence Livermore National Laboratory (LLNL), through the LLNL Manager, Fissile Materials Disposition Program (FMDP). Day to day project activities are managed by the D and T Technical Project Office (TPO), which reports to the LLNL Manager, FMDP. The D and T TPO consists of the Technical Manager, the TPO Quality Assurance (QA) Program Manager, and TPO Planning and Support Staff. This Quality Assurance Program Description (QAPD) defines the QA policies and controls that will be implemented by these TPO personnel in their management of D and T activities. This QAPD is consistent with and responsive to the Department of Energy Fissile Materials Disposition Program Quality Assurance Requirements Document (FMDP QARD). As the Project and upper level requirement's documents evolve, this QAPD will be updated as necessary to accurately define and describe the QA Program and Management of the PIP. The TPO has a policy that all development and testing activities be planned, performed and assessed in accordance with its customer's requirements, needs and expectations, and with a commitment to excellence and continuous improvement. The TPO QAPD describes implementation requirements which, when completed, will ensure that the project development and testing activities conform to the appropriate QA requirements. For the program to be effective, the TPO QA Program Manager will ensure that each site participating in D and T activities has developed a QAPD, which meets the customer's requirements, and has a designated quality leader in place. These customer

  6. Description of work for routine groundwater sampling at the Environmental Restoration Disposal Facility

    International Nuclear Information System (INIS)

    Ford, B.H.

    1996-09-01

    This document provides a description of work and field implementation guidance for routine (post-baseline) groundwater monitoring sampling program at the Environmental Restoration Disposal Facility. The purpose of this program is to (1) meet the intent of the applicable or relevant and appropriate requirements; (2) document baseline groundwater conditions; (3) monitor those conditions for change; and (4) allow for modifications to groundwater sampling if required by the leachate management program

  7. Fossil energy program. Summary document

    Energy Technology Data Exchange (ETDEWEB)

    None

    1980-05-01

    This program summary document presents a comprehensive overview of the research, development, and demonstration (RD and D) activities that will be performed in FY 1981 by the Assistant Secretary for Fossil Energy (ASFE), US Department of Energy (DOE). The ASFE technology programs for the fossil resources of coal, petroleum (including oil shale) and gas have been established with the goal of making substantive contributions to the nation's future supply and efficienty use of energy. On April 29, 1977, the Administration submitted to Congress the National Energy Plan (NEP) and accompanying legislative proposals designed to establish a coherent energy policy structure for the United States. Congress passed the National Energy Act (NEA) on October 15, 1978, which allows implementation of the vital parts of the NEP. The NEP was supplemented by additional energy policy statements culminating in the President's address on July 15, 1979, presenting a program to further reduce dependence on imported petroleum. The passage of the NEA-related energy programs represent specific steps by the Administration and Congress to reorganize, redirect, and clarify the role of the Federal Government in the formulation and execution of national energy policy and programs. The energy technology RD and D prog4rams carried out by ASFE are an important part of the Federal Government's effort to provide the combination and amounts of energy resources needed to ensure national security and continued economic growth.

  8. ENDF/B-V utility programs: description and operating instructions

    International Nuclear Information System (INIS)

    McLaughlin, K.

    1984-03-01

    A description and operating instructions are supplied for the following ENDF/B-V Processing Programs: CHECKER, CRECT, STNDRD, FIZCON, PSYCHE, RESEND, INTER, INTEND, SUMRIZ, PLOTEF, LSTFCV, RIGEL. These programs can be obtained on magnetic tape, free of charge, from the IAEA Nuclear Data Section. (author)

  9. 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...

  10. 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

  11. 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

  12. 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.

  13. 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.

  14. 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.

  15. Technical Basis Document for PFP Area Monitoring Dosimetry Program

    CERN Document Server

    Cooper, J R

    2000-01-01

    This document describes the phantom dosimetry used for the PFP Area Monitoring program and establishes the basis for the Plutonium Finishing Plant's (PFP) area monitoring dosimetry program in accordance with the following requirements: Title 10, Code of Federal Regulations (CFR), part 835, ''Occupational Radiation Protection'' Part 835.403; Hanford Site Radiological Control Manual (HSRCM-1), Part 514; HNF-PRO-382, Area Dosimetry Program; and PNL-MA-842, Hanford External Dosimetry Technical Basis Manual.

  16. Technical Basis Document for PFP Area Monitoring Dosimetry Program

    International Nuclear Information System (INIS)

    COOPER, J.R.

    2000-01-01

    This document describes the phantom dosimetry used for the PFP Area Monitoring program and establishes the basis for the Plutonium Finishing Plant's (PFP) area monitoring dosimetry program in accordance with the following requirements: Title 10, Code of Federal Regulations (CFR), part 835, ''Occupational Radiation Protection'' Part 835.403; Hanford Site Radiological Control Manual (HSRCM-1), Part 514; HNF-PRO-382, Area Dosimetry Program; and PNL-MA-842, Hanford External Dosimetry Technical Basis Manual

  17. Hanford Waste Vitrification Plant Quality Assurance Program description for high-level waste form development and qualification. Revision 3, Part 2

    Energy Technology Data Exchange (ETDEWEB)

    1993-08-01

    The Hanford Waste Vitrification Plant Project has been established to convert the high-level radioactive waste associated with nuclear defense production at the Hanford Site into a waste form suitable for disposal in a deep geologic repository. The Hanford Waste Vitrification Plant will mix processed radioactive waste with borosilicate material, then heat the mixture to its melting point (vitrification) to forin a glass-like substance that traps the radionuclides in the glass matrix upon cooling. The Hanford Waste Vitrification Plant Quality Assurance Program has been established to support the mission of the Hanford Waste Vitrification Plant. This Quality Assurance Program Description has been written to document the Hanford Waste Vitrification Plant Quality Assurance Program.

  18. Technical Basis Document for PFP Area Monitoring Dosimetry Program

    Energy Technology Data Exchange (ETDEWEB)

    COOPER, J.R.

    2000-04-17

    This document describes the phantom dosimetry used for the PFP Area Monitoring program and establishes the basis for the Plutonium Finishing Plant's (PFP) area monitoring dosimetry program in accordance with the following requirements: Title 10, Code of Federal Regulations (CFR), part 835, ''Occupational Radiation Protection'' Part 835.403; Hanford Site Radiological Control Manual (HSRCM-1), Part 514; HNF-PRO-382, Area Dosimetry Program; and PNL-MA-842, Hanford External Dosimetry Technical Basis Manual.

  19. Descriptive study of external employee assistance program providers (EAP) in Japan.

    Science.gov (United States)

    Muto, Takashi; Haruyama, Yasuo; Higashi, Toshiaki

    2012-01-01

    The mental health problems of employees have become a major occupational health issue in Japan. External employee assistance program providers (EAP) have become important in mental health care for workers, but their activities are poorly documented. This descriptive study was undertaken to clarify the status and future tasks of EAP in Japan. The subjects were all EAP (n=27) registered in the Japanese Chapter of Employee Assistance Professionals Association. The questionnaire survey was conducted in January 2007. We received 13 replies, a response rate of 54.2%. Most EAP provided seminars, stress checks, stress management, counseling, and support for a return to work. The number of EAP contracted with small-scale enterprises was small. EAP communicated infrequently with companies. To promote the use of EAP, their advertising, education and training of staff, accumulation of scientific evidence, development of an official certification system for staff, and improvement of contents of EAP services were cited.

  20. Hanford Site Guide for Preparing and Maintaining Fenerator Group Pollution Prevention Program Documentation

    International Nuclear Information System (INIS)

    PLACE, B.G.

    1999-01-01

    This document provides guidance to generator groups for preparing and maintaining documentation of Pollution Prevention/Waste Minimization (P2/WMin) Program activities. The guidance is one of a hierarchical series that includes the Hanford Site Waste Minimization and Pollution Prevention Awareness Program Plan (DOE-RL, 1998a) and Prime Contractor implementation plans describing programs required by Resource Conservation and Recovery Act of 1976 (RCRA) 3002(b) and (300501) (RCRA and EPA, 1994). Documentation guidance for the following five P2/WMin elements are discussed: Fiscal Year (FY) Goals; Budget and Staffing; Waste Minimization (WMinn ) Assessments (WMAs); Pollution Prevention (P2) Reporting; WMin Certification

  1. 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

  2. HANFORD SITE SOLID WASTE MANAGEMENT ENVIRONMENTAL IMPACT STATEMENT TECHNICAL INFORMATION DOCUMENT [SEC 1 THRU 4

    International Nuclear Information System (INIS)

    FRITZ, L.L.

    2004-01-01

    This Technical Information Document (TID) provides engineering data to support DOE/EIS-0286, ''Hanford Site Solid (Radioactive and Hazardous) Waste Program Environmental Impact Statement''. Assumptions and waste volumes used to calculate engineering data are also provided in this document. This chapter provides a brief description of: the Solid Waste Management Program (including a description of waste types and known characteristics of waste covered under the program), the Hanford Site (including a general discussion of the operating areas), and the alternatives analyzed. The Hanford Site Solid Waste Management Program and DOE/EIS-0286 address solid radioactive waste types generated by various activities from both onsite and offsite generators. The Environmental Restoration (ER) waste management activities are not within the scope of DOE/EIS-0286 or this TID. Activities for processing and disposal of immobilized low-activity waste (ILAW) are not within the scope of the Solid Waste Management Program and this TID

  3. 75 FR 24718 - Guidance for Industry on Documenting Statistical Analysis Programs and Data Files; Availability

    Science.gov (United States)

    2010-05-05

    ...] Guidance for Industry on Documenting Statistical Analysis Programs and Data Files; Availability AGENCY... documenting statistical analyses and data files submitted to the Center for Veterinary Medicine (CVM) for the... on Documenting Statistical Analysis Programs and Data Files; Availability'' giving interested persons...

  4. 77 FR 48102 - Closed Captioning and Video Description of Video Programming

    Science.gov (United States)

    2012-08-13

    ... Captioning and Video Description of Video Programming AGENCY: Federal Communications Commission. [[Page 48103... show that providing captions on their programming would be economically burdensome. DATES: Effective...) establishing requirements for closed captioning on video programming to ensure access by persons with hearing...

  5. Hanford Site guide for preparing and maintaining generator group pollution prevention program documentation

    International Nuclear Information System (INIS)

    Place, B.G.

    1998-01-01

    This document provides guidance to generator groups for preparing and maintaining documentation of Pollution Prevention Waste Minimization (P2/WMin) Program activities. The guidance is one of a hierarchical series that includes the Hanford Site Waste Minimization and Pollution Prevention Awareness Program Plan (DOE-RL, 1998a) and Prime contractor implementation plans describing programs required by Resource Conservation and Recovery Act of 1976 (RCRA) 3002(b) and 3005(h) (RCRA and EPA, 1994). Documentation guidance for the following five P2/WMin elements are discussed: Fiscal Year (FY) Goals; Budget and Staffing; Waste Minimization (WMin) Assessments (WMAs); Quarterly Pollution Prevention (P2) Reporting WMin Certification

  6. Interface control document between Analytical Services and Solid Waste Disposal Division

    International Nuclear Information System (INIS)

    Venetz, T.J.

    1995-01-01

    This interface control document (ICD) between Analytical Services and Solid Waste Disposal (SWD) establishes a baseline description of the support needed and the wastes that will require management as part of the interface between the two divisions. It is important that each division has a clear understanding of the other division's expectations regarding levels and type of support needed. This ICD deals with the waste sampling support needed by SWD and the waste generated by the specified analytical laboratories. The baseline description of wastes includes waste volumes, characteristics and shipping schedules, which will be used to plan the proper support requirements. The laboratories included in this document are 222-S Laboratory Facility, the Waste Sampling and Characterization Facility (WSCF) and the Chemical Engineering Laboratory. These three facilities provide support to the entire site and are not associated with one major program/facility. The laboratories associated with major facilities or programs such as Engineering/Environmental Development Laboratory at K Basins Operation are not within the scope of this document

  7. Program MASTERCALC: an interactive computer program for radioanalytical computations. Description and operating instructions

    International Nuclear Information System (INIS)

    Goode, W.

    1980-10-01

    MASTERCALC is a computer program written to support radioanalytical computations in the Los Alamos Scientific Laboratory (LASL) Environmental Surveillance Group. Included in the program are routines for gross alpha and beta, 3 H, gross gamma, 90 Sr and alpha spectroscopic determinations. A description of MASTERCALC is presented and its source listing is included. Operating instructions and example computing sessions are given for each type of analysis

  8. Quality Assurance Requirements and Description

    International Nuclear Information System (INIS)

    Ram Murthy

    2002-01-01

    The Quality Assurance Requirements and Description (QARD) is the principal Quality Assurance (QA) document for the Civilian Radioactive Waste Management Program (Program). It establishes the minimum requirements for the QA program [INTRODUCTION :1p2s (NOT A REQUIREMENT)]. The QARD contains regulatory requirements and program commitments necessary for the development of an effective QA program [INTRODUCTION :1p3s (NOT A REQUIREMENT)]. Implementing documents must be based on, and be consistent with the QARD. The QARD applies to the following: (1) Acceptance of spent nuclear fuel and high-level waste. (2) Transport of spent nuclear fuel and high-level waste. (3) Storage of spent nuclear fuel through receipt of storage cask certification or a facility operating license. (4) Monitored Geologic Repository, including the site characterization activities [Exploratory Studies Facility (ESF) and surface based testing], through receipt of an operating license. (5) High-level waste form development through qualification, production, and acceptance. (6) Characterization of DOE spent nuclear fuel, and conditioning through acceptance of DOE spent nuclear fuel. Section 2.0, Quality Assurance Program, defines in greater detail criteria for determining work subject to the QARD

  9. Campus Partnerships Improve Impact Documentation of Nutrition Programs

    Science.gov (United States)

    Brinkman, Patricia

    2015-01-01

    Partnerships with other campus college units can provide ways of improving Extension's impact documentation. Nutrition programs have relied upon knowledge gained and people's self report of behavior change. Partnering with the College of Nursing, student nurses provided blood screenings during the pre and 6 month follow-up of a pilot heart risk…

  10. 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

  11. CANGEO program description and user's instruction

    International Nuclear Information System (INIS)

    Park, Joo Hwan; Jun, J. S.; Suk, H. C.; Hwang, D. H.; Yoo, Y. J.

    1997-10-01

    This is a report for the description and user's instruction of CANGEO (CANdu GEOmetry) program. CANGEO program is able to generate the geometry input for thermalhydraulic subchannel analysis of CANDU fuel channel. It is developed for the calculation of subchannel analysis of CANDU fuel channel. It is developed for the calculation of subchannel data for a complicated geometry such as a CANDU fuel channel. And this code can be applicable to a bundle eccentricity from pressure tube center to bundle center, pressure tube creep, rod ballooning, and any symmetric subchannel geometry required by thermalhydraulic subchannel analysis code. The report also describes the basic calculation method of subchannel geometry, including user's manual, input and output for a CANDU fuel channel loaded with 37-element fuel bundle. (author). 35 refs., 6 figs

  12. Description of mathematical models and computer programs

    International Nuclear Information System (INIS)

    1977-01-01

    The paper gives a description of mathematical models and computer programs for analysing possible strategies for spent fuel management, with emphasis on economic analysis. The computer programs developed, describe the material flows, facility construction schedules, capital investment schedules and operating costs for the facilities used in managing the spent fuel. The computer programs use a combination of simulation and optimization procedures for the economic analyses. Many of the fuel cycle steps (such as spent fuel discharges, storage at the reactor, and transport to the RFCC) are described in physical and economic terms through simulation modeling, while others (such as reprocessing plant size and commissioning schedules, interim storage facility commissioning schedules etc.) are subjected to economic optimization procedures to determine the approximate lowest-cost plans from among the available feasible alternatives

  13. Mississippi Curriculum Framework for Computer Information Systems Technology. Computer Information Systems Technology (Program CIP: 52.1201--Management Information Systems & Business Data). Computer Programming (Program CIP: 52.1201). Network Support (Program CIP: 52.1290--Computer Network Support Technology). Postsecondary Programs.

    Science.gov (United States)

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

    This document, which is intended for use by community and junior colleges throughout Mississippi, contains curriculum frameworks for two programs in the state's postsecondary-level computer information systems technology cluster: computer programming and network support. Presented in the introduction are program descriptions and suggested course…

  14. Simulation model for wind energy storage systems. Volume III. Program descriptions. [SIMWEST CODE

    Energy Technology Data Exchange (ETDEWEB)

    Warren, A.W.; Edsinger, R.W.; Burroughs, J.D.

    1977-08-01

    The effort developed a comprehensive computer program for the modeling of wind energy/storage systems utilizing any combination of five types of storage (pumped hydro, battery, thermal, flywheel and pneumatic). An acronym for the program is SIMWEST (Simulation Model for Wind Energy Storage). The level of detail of SIMWEST is consistent with a role of evaluating the economic feasibility as well as the general performance of wind energy systems. The software package consists of two basic programs and a library of system, environmental, and load components. Volume III, the SIMWEST program description contains program descriptions, flow charts and program listings for the SIMWEST Model Generation Program, the Simulation program, the File Maintenance program and the Printer Plotter program. Volume III generally would not be required by SIMWEST user.

  15. Environmental Compliance and Protection Program Description Oak Ridge, Tennessee

    Energy Technology Data Exchange (ETDEWEB)

    Bechtel Jacobs

    2009-02-26

    The objective of the Environmental Compliance and Protection (EC and P) Program Description (PD) is to establish minimum environmental compliance requirements and natural resources protection goals for the Bechtel Jacobs Company LLC (BJC) Oak Ridge Environmental Management Cleanup Contract (EMCC) Contract Number DE-AC05-98OR22700-M198. This PD establishes the work practices necessary to ensure protection of the environment during the performance of EMCC work activities on the US Department of Energy's (DOE's) Oak Ridge Reservation (ORR) in Oak Ridge, Tennessee, by BJC employees and subcontractor personnel. Both BJC and subcontractor personnel are required to implement this PD. A majority of the decontamination and demolition (D and D) activities and media (e.g., soil and groundwater) remediation response actions at DOE sites on the ORR are conducted under the authority of the Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA). CERCLA activities are governed by individual CERCLA decision documents (e.g., Record of Decision [ROD] or Action Memorandum) and according to requirements stated in the Federal Facility Agreement for the Oak Ridge Reservation (DOE 1992). Applicable or relevant and appropriate requirements (ARARs) for the selected remedy are the requirements for environmental remediation responses (e.g., removal actions and remedial actions) conducted under CERCLA.

  16. Defense transuranic waste program strategy document

    International Nuclear Information System (INIS)

    1982-07-01

    This document summarizes the strategy for managing transuranic (TRU) wastes generated in defense and research activities regulated by the US Department of Energy. It supercedes a document issued in July 1980. In addition to showing how current strategies of the Defense Transuranic Waste Program (DTWP) are consistent with the national objective of isolating radioactive wastes from the biosphere, this document includes information about the activities of the Transuranic Lead Organization (TLO). To explain how the DTWP strategy is implemented, this document also discusses how the TLO coordinates and integrates the six separate elements of the DTWP: (1) Waste Generation Site Activities, (2) Storage Site Activities, (3) Burial Site Activities, (4) Technology Development, (5) Transportation Development, and (6) Permanent Disposal. Storage practices for TRU wastes do not pose short-term hazards to public health and safety or to the environment. Isolation of TRU wastes in a deep-mined geologic repository is considered the most promising of the waste disposal alternatives available. This assessment is supported by the DOE Record of Decision to proceed with research and development work at the Waste Isolation Pilot Plant (WIPP) in southeastern New Mexico - a deep-mined geologic research and development project. In support of the WIPP research project and the permanent disposal of TRU waste, the DTWP strategy for the near term will concentrate on completion of procedures and the design and construction of all facilities necessary to certify newly-generated (NG) and stored TRU wastes for emplacement in the WIPP. In addition, the strategy involves evaluating alternatives for disposing of some transuranic wastes by methods which may allow for on-site disposal of these wastes and yet preserve adequate margins of safety to protect public health and the environment

  17. Standard Review Plan Maintenance Program implementing procedures document

    International Nuclear Information System (INIS)

    1996-11-01

    The implementing Procedures Document (IPD) was developed by the Inspection Program Projects Branch, Office of Nuclear Reactor Regulation, with assistance from Pacific Northwest National Laboratory, for the Standard Review Plan Maintenance Program (SRP-MP). The SRP-MP was established to maintain the Standard Review Plan (SRP) on an on-going basis. The IPD provides guidance, including an overall approach and procedures, for SRP-MP tasks. The objective of the IPD is to ensure that modifications to SRP need to reflect current NRC requirements and guidance are identified and that a consistent methodology is used to develop and revise SRP sections

  18. 13 CFR 108.10 - Description of the New Markets Venture Capital Program.

    Science.gov (United States)

    2010-01-01

    ... Venture Capital Program. 108.10 Section 108.10 Business Credit and Assistance SMALL BUSINESS ADMINISTRATION NEW MARKETS VENTURE CAPITAL (âNMVCâ) PROGRAM Introduction to Part 108 § 108.10 Description of the New Markets Venture Capital Program. The New Markets Venture Capital (“NMVC”) Program is a...

  19. 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

  20. Mississippi Curriculum Framework for Welding and Cutting Programs (Program CIP: 48.0508--Welder/Welding Technologist). Postsecondary Programs.

    Science.gov (United States)

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

    This document, which is intended for use by community and junior colleges throughout Mississippi, contains curriculum frameworks for the course sequences in the welding and cutting programs cluster. Presented in the introductory section are a description of the program and suggested course sequence. Section I lists baseline competencies, and…

  1. U-10Mo Baseline Fuel Fabrication Process Description

    Energy Technology Data Exchange (ETDEWEB)

    Hubbard, Lance R. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Arendt, Christina L. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Dye, Daniel F. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Clayton, Christopher K. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Lerchen, Megan E. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Lombardo, Nicholas J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Lavender, Curt A. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Zacher, Alan H. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

    2017-09-27

    This document provides a description of the U.S. High Power Research Reactor (USHPRR) low-enriched uranium (LEU) fuel fabrication process. This document is intended to be used in conjunction with the baseline process flow diagram (PFD) presented in Appendix A. The baseline PFD is used to document the fabrication process, communicate gaps in technology or manufacturing capabilities, convey alternatives under consideration, and as the basis for a dynamic simulation model of the fabrication process. The simulation model allows for the assessment of production rates, costs, and manufacturing requirements (manpower, fabrication space, numbers and types of equipment, etc.) throughout the lifecycle of the USHPRR program. This document, along with the accompanying PFD, is updated regularly

  2. Scheme Program Documentation Tools

    DEFF Research Database (Denmark)

    Nørmark, Kurt

    2004-01-01

    are separate and intended for different documentation purposes they are related to each other in several ways. Both tools are based on XML languages for tool setup and for documentation authoring. In addition, both tools rely on the LAML framework which---in a systematic way---makes an XML language available...... as named functions in Scheme. Finally, the Scheme Elucidator is able to integrate SchemeDoc resources as part of an internal documentation resource....

  3. FLUOR HANFORD SAFETY MANAGEMENT PROGRAMS

    Energy Technology Data Exchange (ETDEWEB)

    GARVIN, L. J.; JENSEN, M. A.

    2004-04-13

    This document summarizes safety management programs used within the scope of the ''Project Hanford Management Contract''. The document has been developed to meet the format and content requirements of DOE-STD-3009-94, ''Preparation Guide for US. Department of Energy Nonreactor Nuclear Facility Documented Safety Analyses''. This document provides summary descriptions of Fluor Hanford safety management programs, which Fluor Hanford nuclear facilities may reference and incorporate into their safety basis when producing facility- or activity-specific documented safety analyses (DSA). Facility- or activity-specific DSAs will identify any variances to the safety management programs described in this document and any specific attributes of these safety management programs that are important for controlling potentially hazardous conditions. In addition, facility- or activity-specific DSAs may identify unique additions to the safety management programs that are needed to control potentially hazardous conditions.

  4. 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

  5. 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)

  6. Integrated Data Collection Analysis (IDCA) Program: FY2011 Project Descriptions

    Energy Technology Data Exchange (ETDEWEB)

    Sandstrom, Mary M. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Brown, Geoffrey W. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Warner, Kirstin F. [Naval Surface Warfare Center (NSWC-IHD), Indian Head, MD (United States). Indian Head Division; Remmers, Daniel L. [Naval Surface Warfare Center (NSWC-IHD), Indian Head, MD (United States). Indian Head Division; Whinnery, LeRoy L. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Shelley, Timothy J. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Reyes, Jose A. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Hsu, Peter C. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Reynolds, John G. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

    2012-02-03

    This document provides brief descriptions of research topics for consideration by the IDCA for potential funding in funding in FY 2011. The topics include the utilization of the results from the Proficiency Test developed during FY 2010 to start populating the small-scale safety and thermal testing (SSST) Testing Compendium and revising results from methods modifications. Other research topics were also developed for FY 2011 from issues that arose in the Proficiency Test.

  7. Strategy and programs of the research on high-level and long-living radioactive wastes (by right of article L542 of the environment code from December 30, 1991 law). Conjuncture document

    International Nuclear Information System (INIS)

    2003-01-01

    This document gives, in a first part, a brief insight on the main results of the researches carried out in 2002 on the management of high-level and long-living radioactive wastes according to the three research ways defined by the December 30, 1991 law: separation-transmutation, disposal in deep geologic underground, wastes conditioning and storage. The second part of the document is an executive summary of the 2003 edition of the document 'strategy and programs of the researches on the management of high-level and long-living radioactive wastes - SPR 2003'. It presents the content of the different chapters: 1 - researches methodology and implementation of coordinated studies; 2 - researches status 10 years after the enforcement of the law; 3 - the main goals and steps to reach before the 2006 date-line; 4 - the description and analysis of the programs under consideration; 5 - the coordination between French programs; 6 - the international cooperation. (J.S.)

  8. FY 1987 program summary document: Office of Defense Waste and Transportation Management

    International Nuclear Information System (INIS)

    1987-04-01

    This document describes the Office of Defense Waste and Transportation Management (DWTM) Program as supported by the President's Fiscal Year (FY) 1987 Budget Request to Congress. It specifically addresses the program's organization, objectives, strategies, and plans for FY 1987

  9. Documentation of a Regional Aquifer Simulation Model RAQSIM, and a description of support programs applied in the Twin Platte - Middle Republican Study Area, Nebraska

    Science.gov (United States)

    Cady, R.E.; Peckenpaugh, J.M.

    1985-01-01

    RAQSIM, a generalized flow model of a groundwater system using finite-element methods, is documented to explain how it works and to demonstrate that it gives valid results. Three support programs that are used to compute recharge and discharge data required as input to RAQSIM are described. RAQSIM was developed to solve transient, two-dimensional, regional groundwater flow problems with isotropic or anisotropic conductance. The model can also simulate radially-symmetric flow to a well and steady-state flow. The mathematical basis, program structure, data input and output procedures, organization of data sets, and program features and options of RAQSIM are discussed. An example , containing listings of data and results and illustrating RAQSIM 's capabilities, is discussed in detail. Two test problems also are discussed comparing RAQSIM 's results with analytical procedures. The first support program described, the PET Program, uses solar radiation and other climatic data in the Jensen-Haise method to compute potential evapotranspiration. The second support program, the Soil-Water Program, uses output from the PET Program, soil characteristics, and the ratio of potential to actual evapotranspiration for each crop to compute infiltration, storage, and removal of water from the soil zone. The third program, the Recharge-Discharge Program, uses output from the Soil-Water Program together with other data to compute recharge and discharge from the groundwater flow system. For each support program, a program listing and examples of the data and results for the Twin Platte-Middle Republican study are provided. In addition, a brief discussion on how each program operates and on procedures for running and modifying these programs are presented. (Author 's abstract)

  10. 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

  11. The diffusion of the distance Entomology Master's Degree Program at the University of Nebraska Lincoln: A descriptive case study

    Science.gov (United States)

    Hubbell, Jody M.

    This study explored three selected phases of Rogers' (1995) Diffusion of Innovations Theory to examine the diffusion process of the distance Entomology Master's Degree program at the University of Nebraska, Lincoln. A qualitative descriptive case study approach incorporated semi-structured interviews with individuals involved in one or more of the three stages: Development, Implementation, and Institutionalization. Documents and archival evidence were used to triangulate findings. This research analyzed descriptions of the program as it moved from the Development, to the Implementation, and finally, the Institutionalization stages of diffusion. Each respective stage was examined through open and axial coding. Process coding identified themes common to two or more diffusion stages, and explored the evolution of themes from one diffusion stage to the next. At a time of significant budget constraints, many departments were faced with the possibility of merger or dissolution. The Entomology Master's Degree Program evolved from being an entrepreneurial means to prevent departmental dissolution to eventually being viewed as a model for the development of similar programs across this university and other institutions of higher education. During this evolution, the program was reinvented to meet the broader needs of industry and a global student market. One finding not consistent with Rogers' model was that smaller, rather than larger, departmental size contributed to the success of the program. Within this small department, faculty members were able to share their experiences and knowledge with each other on a regular basis, which promoted greater acceptance of the distance program. How quality and rigor may be defined and measured was a key issue in each respective stage. In this specific case, quality and rigor was initially a comparison of on-campus and distance course content and then moved to program-based assessment and measures of student outcomes such as job

  12. Mississippi Curriculum Framework for Banking & Finance Technology (Program CIP: 52.0803--Banking and Related Financial Programs, Other). Postsecondary Programs.

    Science.gov (United States)

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

    This document, which is intended for use by community and junior colleges throughout Mississippi, contains curriculum frameworks for the course sequences in the banking and finance technology program. Presented in the introduction are a program description and suggested course sequence. Section I is a curriculum guide consisting of outlines for…

  13. Program Management at the National Nuclear Security Administration Office of Defense Nuclear Security: A Review of Program Management Documents and Underlying Processes

    International Nuclear Information System (INIS)

    Madden, Michael S.

    2010-01-01

    The scope of this paper is to review the National Nuclear Security Administration Office of Defense Nuclear Security (DNS) program management documents and to examine the underlying processes. The purpose is to identify recommendations for improvement and to influence the rewrite of the DNS Program Management Plan (PMP) and the documentation supporting it. As a part of this process, over 40 documents required by DNS or its stakeholders were reviewed. In addition, approximately 12 other documents produced outside of DNS and its stakeholders were reviewed in an effort to identify best practices. The complete list of documents reviewed is provided as an attachment to this paper.

  14. 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.

  15. Documentation of SPECTROM-55: A finite element thermohydrogeological analysis program

    International Nuclear Information System (INIS)

    Osnes, J.D.; Ratigan, J.L.; Loken, M.C.; Parrish, D.K.

    1985-12-01

    SPECTROM-55 is a finite element computer program developed by RE/SPEC Inc. for analyses of coupled heat and fluid transfer through fully saturated porous media. The theoretical basis for the mathematical model, the implementation of the mathematical model into the computer code, the verification and validation efforts with the computer code, and the code support and continuing documentation are described in this document. The program is especially suited for analyses of the regional hydrogeology in the vicinity of a heat-generating nuclear waste repository. These applications typically involve forced and free convection in a ground-water flow system. The program provides transient or steady-state temperatures, pressures, and fluid velocities resulting from the application of a variety of initial and boundary conditions to bodies with complicated shapes. The boundary conditions include constant heat and fluid fluxes, convective heat transfer, constant temperature, and constant pressure. Initial temperatures and pressures can be specified. Composite systems of anisotropic materials, such as geologic strata, can be defined in either planar or axisymmetric configurations. Constant or varying volumetric heat generation, such as decaying heat generation from radioactive waste, can be specified

  16. 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…

  17. 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

  18. 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

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

    Science.gov (United States)

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

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

  20. 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

  1. Atmospheric Sciences Program summaries of research in FY 1993

    Energy Technology Data Exchange (ETDEWEB)

    1993-11-01

    This document describes the activities and products of the Atmospheric Science Program of the Environmental Sciences Division, Office of Health and Environmental Research, Office of Energy Research, in FY 1993. Each description contains the project`s title; three-year funding history; the contract period over which the funding applies; the name(s) of the principal investigator(s); the institution(s) conducting the projects; and the project`s objectives, products, approach, and results to date. Project descriptions are categorized within the report according to program areas: atmospheric chemistry, atmospheric dynamics, and support operations. Within these categories, the descriptions are ordered alphabetically by principal investigator. Each program area is preceded by a brief text that defines the program area, states its goals and objectives, lists principal research questions, and identifies program managers. Appendixes provide the addresses and telephone numbers of the principal investigators and define the acronyms used. This document has been indexed to aid the reader in locating research topics, participants, and research institutions in the text and the project descriptions. Comprehensive subject, principal investigator, and institution indexes are provided at the end of the text for this purpose. The comprehensive subject index includes keywords from the introduction and chapter texts in addition to those from the project descriptions.

  2. 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

  3. FURNACE; a toroidal geometry neutronic program system method description and users manual

    International Nuclear Information System (INIS)

    Verschuur, K.A.

    1984-12-01

    The FURNACE program system performs neutronic and photonic calculations in 3D toroidal geometry for application to fusion reactors. The geometry description is quite general, allowing any torus cross section and any neutron source density distribution for the plasma, as well as simple parametric representations of circular, elliptic and D-shaped tori and plasmas. The numerical method is based on an approximate transport model that produces results with sufficient accuracy for reactor-design purposes, at acceptable calculational costs. A short description is given of the numerical method, and a user manual for the programs of the system: FURNACE, ANISN-PT, LIBRA, TAPEMA and DRAWER is presented

  4. Mississippi Curriculum Framework for Welding (Program CIP: 48.0508--Welder/Welding Technologist). Secondary Programs.

    Science.gov (United States)

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

    This document, which reflects Mississippi's statutory requirement that instructional programs be based on core curricula and performance-based assessment, contains outlines of the instructional units required in local instructional management plans and daily lesson plans for welding I and II. Presented first are a program description and course…

  5. 46 CFR 176.620 - Description of the Alternative Hull Examination (AHE) Program for certain passenger vessels.

    Science.gov (United States)

    2010-10-01

    ... 46 Shipping 7 2010-10-01 2010-10-01 false Description of the Alternative Hull Examination (AHE... Hull and Tailshaft Examinations § 176.620 Description of the Alternative Hull Examination (AHE) Program for certain passenger vessels. The Alternative Hull Examination (AHE) Program provides you with an...

  6. 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

  7. 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....

  8. Resource programs: Draft Environmental Impact Statement Resource Programs

    International Nuclear Information System (INIS)

    1992-03-01

    Every two years, Bonneville Power Administration (BPA) prepares a Resource Program which identifies the resource actions BPA will take to meet its obligation to serve the forecasted power requirements of its customers. The Resource Program's Environmental Impact Statement (RPEIS) is a programmatic environmental document which will support decisions made in several future Resource Programs. Environmental documents tiered to the EIS may be prepared on a site-specific basis. The RPEIS includes a description of the environmental effects and mitigation for the various resource types available in order to evaluate the trade-offs among them. It also assesses the environmental impacts of adding thirteen alternative combinations of resources to the existing power system. This report contains the appendices to the RPEIS

  9. 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

  10. Process Evaluation for a Prison-based Substance Abuse Program.

    Science.gov (United States)

    Staton, Michele; Leukefeld, Carl; Logan, T. K.; Purvis, Rick

    2000-01-01

    Presents findings from a process evaluation conducted in a prison-based substance abuse program in Kentucky. Discusses key components in the program, including a detailed program description, modifications in planned treatment strategies, program documentation, and perspectives of staff and clients. Findings suggest that prison-based programs have…

  11. 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

  12. Strategic environmental safety inspection for the National disposal program. Description of the inspection volume. Documentation for the scoping team; Strategische Umweltpruefung zum Nationalen Entsorgungsprogramm. Beschreibung des Untersuchungsumfangs. Unterlage fuer den Scoping-Termin

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2015-01-06

    The Strategic environmental safety inspection for the National disposal program covers the following topics: Legal framework: determination of the requirement for an environmental inspection program, coordination of the scoping team into the overall context; environmental targets; approach for assessment and evaluation of environmental impact, description of the inspection targets for the strategic environmental inspection; consideration of alternatives.

  13. 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

  14. Technical baseline description for in situ vitrification laboratory test equipment

    International Nuclear Information System (INIS)

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

    1991-09-01

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

  15. Program strategy document for the nuclear materials. Transportation Technology Center (FY 80)

    International Nuclear Information System (INIS)

    Jefferson, R.M.

    1980-04-01

    The TTC's program is divided into four principal areas, Technology and Information Center, Systems Development, Technology, and Institutional Issues. These areas are broken into activities, elements, and subelements which are delineated in this document

  16. Oil program implementation plan FY 1996--2000

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-04-01

    This document reaffirms the US Department of Energy (DOE) Office of Fossil Energy commitment to implement the National Oil Research Program in a way to maximize assurance of energy security, economic growth, environmental protection, jobs, improved economic competitiveness, and improved US balance of trade. There are two sections and an appendix in this document. Section 1 is background information that guided its formulation and a summary of the Oil Program Implementation Plan. This summary includes mission statements, major program drivers, oil issues and trends, budget issues, customers/stakeholders, technology transfer, measures of program effectiveness, and benefits. Section 2 contains more detailed program descriptions for the eight technical areas and the NIPER infrastructure. The eight technical areas are reservoir characterization; extraction research; exploration, drilling, and risk-based decision management; analysis and planning; technology transfer; field demonstration projects; oil downstream operations; and environmental research. Each description contains an overview of the program, descriptions on main areas, a discussion of stakeholders, impacts, planned budget projections, projected schedules with Gantt charts, and measures of effectiveness. The appendix is a summary of comments from industry on an earlier draft of the plan. Although changes were made in response to the comments, many of the suggestions will be used as guidance for the FY 1997--2001 plan.

  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. 46 CFR 71.50-15 - Description of the Alternative Hull Examination (AHE) Program for certain passenger vessels.

    Science.gov (United States)

    2010-10-01

    ... 46 Shipping 3 2010-10-01 2010-10-01 false Description of the Alternative Hull Examination (AHE... Description of the Alternative Hull Examination (AHE) Program for certain passenger vessels. The Alternative Hull Examination (AHE) Program provides you with an alternative to a drydock examination by allowing...

  19. PROJECT ENGINEERING DATA MANAGEMENT AT AUTOMATED PREPARATION OF DESIGN DOCUMENTATION

    Directory of Open Access Journals (Sweden)

    A. V. Guryanov

    2017-01-01

    Full Text Available We have developed and realized instrumental means for automated support of end-to-end design process for design documentation on a product at the programming level. The proposed decision is based on processing of the engineering project data that are contained in interdependent design documents: tactical technical characteristics of products, data on the valuable metals contained in them, the list of components applied in a product and others. Processing of engineering data is based on their conversion to the form provided by requirements of industry standards for design documentation preparation. The general graph of the design documentation developed on a product is provided. The description of the developed software product is given. Automated preparation process of interdependent design documents is shown on the example of preparation of purchased products list. Results of work can be used in case of research and development activities on creation of perspective samples of ADP equipment.

  20. 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

  1. National Waste Terminal Storage Program: information management plan. Volume II. Plan description

    International Nuclear Information System (INIS)

    1977-05-01

    A comprehensive information management plan to provide for the systematic processing of large amounts of internally prepared and externally acquired documentation that will accrue to the Office of Waste Isolation (OWI) during the next decade is outlined. The Information Management Plan of the National Waste Terminal Storage (NWTS) Program is based on time proven procedures developed by government and industry for the requirements determination, acquisition, and the administration of documentation. The NWTS Information Management Plan is designed to establish the basis for the planning, development, implemenation, operation and maintenance of the NWTS Information Management System. This plan will help assure that documentation meets required quality standards and that each organization's needs are reflected when soliciting documentation from subcontractors. An example would be the Quality Assurance documentation requirement necessary to comply with eventual NRC licensing regulations. The provisions of the NWTS Information Management Plan will apply to all documentation from OWI contractors, subcontractors, and suppliers, and to OWI organizations for documentation prepared periodically for external dissemination

  2. Canadian safeguards research and development in support of the IAEA program document outlining the various tasks which comprise the program

    International Nuclear Information System (INIS)

    1985-12-01

    Canada has established a safeguards research and development program, the purpose of which is to supplement the resources of the International Atomic Energy Agency. The program of support is a coordinated effort for the development and application of safeguards techniques and instruments to facilities safeguarded by the IAEA. This document sets forth those tasks which comprise the program

  3. 'Only systems thinking can improve family planning program in Pakistan': A descriptive qualitative study.

    Science.gov (United States)

    Zafar, Saira; Shaikh, Babar Tasneem

    2014-12-01

    Family Planning (FP) program in Pakistan has been struggling to achieve the desired indicators. Despite a well-timed initiation of the program in late 50s, fertility decline has been sparingly slow. As a result, rapid population growth is impeding economic development in the country. A high population growth rate, the current fertility rate, a stagnant contraceptive prevalence rate and high unmet need remain challenging targets for population policies and FP programs. To accelerate the pace of FP programs and targets concerned, it is imperative to develop and adopt a holistic approach and strategy for plugging the gaps in various components of the health system: service delivery, information systems, drugs-supplies, technology and logistics, Human Resources (HRs), financing, and governance. Hence, World Health Organization (WHO) health systems building blocks present a practical framework for overall health system strengthening. This descriptive qualitative study, through 23 in-depth interviews, explored the factors related to the health system, and those responsible for a disappointing FP program in Pakistan. Provincial representatives from Population Welfare and Health departments, donor agencies and non-governmental organizations involved with FP programs were included in the study to document the perspective of all stakeholders. Content analysis was done manually to generate nodes, sub-nodes and themes. Performance of FP programs is not satisfactory as shown by the indicators, and these programs have not been able to deliver the desired outcomes. Interviewees agreed that inadequate prioritization given to the FP program by successive governments has led to this situation. There are issues with all health system areas, including governance, strategies, funding, financial management, service delivery systems, HRs, technology and logistic systems, and Management Information System (MIS); these have encumbered the pace of success of the program. All stakeholders

  4. WIPP documentation plan

    International Nuclear Information System (INIS)

    Plung, D.L.; Montgomery, T.T.; Glasstetter, S.R.

    1986-01-01

    In support of the programs at the Waste Isolation Pilot Plant (WIPP), the Publications and Procedures Section developed a documentation plan that provides an integrated document hierarchy; further, this plan affords several unique features: 1) the format for procedures minimizes the writing responsibilities of the technical staff and maximizes use of the writing and editing staff; 2) review cycles have been structured to expedite the processing of documents; and 3) the numbers of documents needed to support the program have been appreciably reduced

  5. Fission energy program of the U. S. Department of Energy

    Energy Technology Data Exchange (ETDEWEB)

    1978-06-01

    The document describes programs managed by the Program Director for Nuclear Energy, Department of Energy, and under the cognizance of the Committee on Science and Technology, United States House of Representatives. The major portion of the document is concerned with civilian nuclear power development, the policy for which has been established by the National Energy Plan of April 1977, but it also includes descriptions of the space applications and naval reactor programs.

  6. Fission energy program of the U.S. Department of Energy

    International Nuclear Information System (INIS)

    1978-06-01

    The document describes programs managed by the Program Director for Nuclear Energy, Department of Energy, and under the cognizance of the Committee on Science and Technology, United States House of Representatives. The major portion of the document is concerned with civilian nuclear power development, the policy for which has been established by the National Energy Plan of April 1977, but it also includes descriptions of the space applications and naval reactor programs

  7. Description of the thermoelastic/plastic computer program TEPCO. Memorandum report RSI-0040

    International Nuclear Information System (INIS)

    Pariseau, W.G.

    1975-01-01

    Presented is a description of the two-dimensional (plane strain, axial symmetry) thermoelastic/plastic computer program TEPCO used by RE/SPEC Inc. in conjunction with an investigation of rock mechanics of underground radioactive waste disposal

  8. Magnetic fusion program summary document

    International Nuclear Information System (INIS)

    1979-04-01

    This document outlines the current and planned research, development, and commercialization (RD and C) activities of the Offic of Fusion Energy under the Assistant Secretary for Energy Technology, US Department of Energy (DOE). The purpose of this document is to explain the Office of Fusion Energy's activities to Congress and its committees and to interested members of the public

  9. Farm-Level Effects of Soil Conservation and Commodity Policy Alternatives: Model and Data Documentation.

    Science.gov (United States)

    Sutton, John D.

    This report documents a profit-maximizing linear programming (LP) model of a farm typical of a major corn-soybean producing area in the Southern Michigan-Northern Indiana Drift Plain. Following an introduction, a complete description of the farm is provided. The next section presents the LP model, which is structured to help analyze after-tax…

  10. Evaluasi Program Mahasiswa Wirausaha (PMW) di Universitas Negeri Jakarta

    OpenAIRE

    Khiyari, Nuwrile Ard; Arum, Wahyu Sri Ambar; Zulaikha, Siti

    2017-01-01

    This research aims to give a description and information about EntrepreneurStudent Program (PMW) that has been held at Jakarta State University. This evaluationresearch uses Context, Input, Process and Product (CIPP) model with evaluativeapproach and descriptive method. Data were collected through observations, interviews,questionnaire, documentation study that have been done in Jakarta State University. Theresult of research shows Entrepreneur Student Program has been well done and met theev...

  11. 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

  12. Mississippi Curriculum Framework for Fashion Marketing Technology (Program CIP: 08.0101--Apparel and Accessories Mkt. Op., Gen.). Postsecondary Programs.

    Science.gov (United States)

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

    This document, which is intended for use by community and junior colleges throughout Mississippi, contains curriculum frameworks for the course sequences in the fashion marketing technology programs cluster. Presented in the introductory section are a description of the program and suggested course sequence. Section I lists baseline competencies,…

  13. NWTS waste package program plan. Volume I. Program strategy, description, and schedule

    International Nuclear Information System (INIS)

    1981-10-01

    This document describes the work planned for developing the technology to design, test and produce packages used for the long-term isolation of nuclear waste in deep geologic repositories. Waste forms considered include spent fuel and high-level waste. The testing and selection effort for barrier materials for radionuclide containment is described. The NWTS waste package program is a design-driven effort; waste package conceptual designs are used as input for preliminary designs, which are upgraded to a final design as materials and testing data become available. Performance assessment models are developed and validated. Milestones and a detailed schedule are given for the waste package development effort. Program logic networks defining work flow, interfaces among the NWTS Projects, and interrelationships of specific activities are presented. Detailed work elements are provided for the Waste Package Program Plan subtasks - design and development, waste form, barrier materials, and performance evaluation - for salt and basalt, host rocks for which the state of waste package knowledge and the corresponding data base are advanced

  14. AREVA - 2013 Reference document

    International Nuclear Information System (INIS)

    2014-01-01

    This Reference Document contains information on the AREVA group's objectives, prospects and development strategies, as well as estimates of the markets, market shares and competitive position of the AREVA group. Content: 1 - Person responsible for the Reference Document; 2 - Statutory auditors; 3 - Selected financial information; 4 - Description of major risks confronting the company; 5 - Information about the issuer; 6 - Business overview; 7 - Organizational structure; 8 - Property, plant and equipment; 9 - Situation and activities of the company and its subsidiaries; 10 - Capital resources; 11 - Research and development programs, patents and licenses; 12 - Trend information; 13 - Profit forecasts or estimates; 14 - Management and supervisory bodies; 15 - Compensation and benefits; 16 - Functioning of the management and supervisory bodies; 17 - Human resources information; 18 - Principal shareholders; 19 - Transactions with related parties; 20 - Financial information concerning assets, financial positions and financial performance; 21 - Additional information; 22 - Major contracts; 23 - Third party information, statements by experts and declarations of interest; 24 - Documents on display; 25 - Information on holdings; Appendix 1: report of the supervisory board chairman on the preparation and organization of the board's activities and internal control procedures; Appendix 2: statutory auditors' reports; Appendix 3: environmental report; Appendix 4: non-financial reporting methodology and independent third-party report on social, environmental and societal data; Appendix 5: ordinary and extraordinary general shareholders' meeting; Appendix 6: values charter; Appendix 7: table of concordance of the management report; glossaries

  15. 75 FR 38343 - High-Speed Intercity Passenger Rail (HSIPR) Program

    Science.gov (United States)

    2010-07-01

    ... notice. The initial draft of this pending guidance document will be open for public comment, and FRA will... Development Program Budget and Schedule Form is a Microsoft Excel document that supports the qualitative and...-defined reporting relationships, statements of functional responsibilities, job descriptions, and job...

  16. Two Models for Implementing Senior Mentor Programs in Academic Medical Settings

    Science.gov (United States)

    Corwin, Sara J.; Bates, Tovah; Cohan, Mary; Bragg, Dawn S.; Roberts, Ellen

    2007-01-01

    This paper compares two models of undergraduate geriatric medical education utilizing senior mentoring programs. Descriptive, comparative multiple-case study was employed analyzing program documents, archival records, and focus group data. Themes were compared for similarities and differences between the two program models. Findings indicate that…

  17. Data Science Programs in U.S. Higher Education: An Exploratory Content Analysis of Program Description, Curriculum Structure, and Course Focus

    Science.gov (United States)

    Tang, Rong; Sae-Lim, Watinee

    2016-01-01

    In this study, an exploratory content analysis of 30 randomly selected Data Science (DS) programs from eight disciplines revealed significant gaps in current DS education in the United States. The analysis centers on linguistic patterns of program descriptions, curriculum requirements, and DS course focus as pertaining to key skills and domain…

  18. ‘Only Systems Thinking Can Improve Family Planning Program in Pakistan’: A Descriptive Qualitative Study

    Directory of Open Access Journals (Sweden)

    Saira Zafar

    2014-12-01

    Full Text Available Background Family Planning (FP program in Pakistan has been struggling to achieve the desired indicators. Despite a well-timed initiation of the program in late 50s, fertility decline has been sparingly slow. As a result, rapid population growth is impeding economic development in the country. A high population growth rate, the current fertility rate, a stagnant contraceptive prevalence rate and high unmet need remain challenging targets for population policies and FP programs. To accelerate the pace of FP programs and targets concerned, it is imperative to develop and adopt a holistic approach and strategy for plugging the gaps in various components of the health system: service delivery, information systems, drugs-supplies, technology and logistics, Human Resources (HRs, financing, and governance. Hence, World Health Organization (WHO health systems building blocks present a practical framework for overall health system strengthening. Methods This descriptive qualitative study, through 23 in-depth interviews, explored the factors related to the health system, and those responsible for a disappointing FP program in Pakistan. Provincial representatives from Population Welfare and Health departments, donor agencies and non-governmental organizations involved with FP programs were included in the study to document the perspective of all stakeholders. Content analysis was done manually to generate nodes, sub-nodes and themes. Results Performance of FP programs is not satisfactory as shown by the indicators, and these programs have not been able to deliver the desired outcomes. Interviewees agreed that inadequate prioritization given to the FP program by successive governments has led to this situation. There are issues with all health system areas, including governance, strategies, funding, financial management, service delivery systems, HRs, technology and logistic systems, and Management Information System (MIS; these have encumbered the pace of

  19. DESCRIPTION OF THE TRITIUM-PRODUCING BURNABLE ABSORBER ROD FOR THE COMMERCIAL LIGHT WATER REACTOR TTQP-1-015 Rev 19

    Energy Technology Data Exchange (ETDEWEB)

    Burns, Kimberly A.; Love, Edward F.; Thornhill, Cheryl K.

    2012-02-01

    Tritium-producing burnable absorber rods (TPBARs) used in the U.S. Department of Energy’s Tritium Readiness Program are designed to produce tritium when placed in a Westinghouse or Framatome 17x17 fuel assembly and irradiated in a pressurized water reactor (PWR). This document provides an unclassified description of the current design baseline for the TPBARs. This design baseline is currently valid only for Watts Bar reactor production cores. A description of the Lead Use TPBARs will not be covered in the text of the document, but the applicable drawings, specifications and test plan will be included in the appropriate appendices.

  20. EPICS release 3.11.6 specific documentation -- Release notes for EPICS 3.11.6

    International Nuclear Information System (INIS)

    1994-01-01

    These notes cover the following: (1) directions for switching to production APS release R3.11.6; (2) unbundling of channel access clients; (3) access security; (4) channel access additions; synchronous time support; and (5) description of major differences between R3.11.3 and R3.11.6 Also included is a list of new and/or updated documentation for the program

  1. Materials program for magnetic fusion energy

    International Nuclear Information System (INIS)

    Zwilsky, K.M.; Cohen, M.M.; Finfgeld, C.R.; Reuther, T.C.

    1978-01-01

    The Magnetic Fusion Reactor Materials Program is currently operating at a level of $7.8M. The program is divided into four technical areas which cover both short and long term problems. These are: Alloy Development for Irradiation Performance, Damage Analysis and Fundamental Studies, Plasma-Materials Interaction, and Special Purpose Materials. A description of the program planning process, the continuing management structure, and the resulting documents is presented

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

    International Nuclear Information System (INIS)

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

    1997-04-01

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

  3. Software documentation for TRU certification program

    International Nuclear Information System (INIS)

    CLINTON, R.

    1999-01-01

    The document provides validation information for software used to support TRU operational activities. Calculations were performed using a spreadsheet application. This document provides information about the usage of the software application, Microsoft(reg s ign) Excel. Microsoft(reg s ign) Excel spreadsheets were used to perform specific calculations to determine the amount of containers to visually examine and to perform analyses on container head-gas data. Contained in this document are definitions of formulas and variables with relation to the Excel codes used. Also, a demonstration is provided using predetermined values to obtain predetermined results

  4. Standard Review Plan Update and Development Program. Implementing Procedures Document

    Energy Technology Data Exchange (ETDEWEB)

    1992-05-01

    This implementing procedures document (IPD) was prepared for use in implementing tasks under the standard review plan update and development program (SRP-UDP). The IPD provides comprehensive guidance and detailed procedures for SRP-UDP tasks. The IPD is mandatory for contractors performing work for the SRP-UDP. It is guidance for the staff. At the completion of the SRP-UDP, the IPD will be revised (to remove the UDP aspects) and will replace NRR Office Letter No. 800 as long-term maintenance procedures.

  5. 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

  6. 46 CFR 115.620 - Description of the Alternative Hull Examination (AHE) Program for certain passenger vessels.

    Science.gov (United States)

    2010-10-01

    ... 46 Shipping 4 2010-10-01 2010-10-01 false Description of the Alternative Hull Examination (AHE... ACCOMMODATIONS FOR MORE THAN 49 PASSENGERS INSPECTION AND CERTIFICATION Hull and Tailshaft Examinations § 115.620 Description of the Alternative Hull Examination (AHE) Program for certain passenger vessels. The Alternative...

  7. 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

  8. Software documentation and user's manual for fish-impingement sampling design and estimation method computer programs

    International Nuclear Information System (INIS)

    Murarka, I.P.; Bodeau, D.J.

    1977-11-01

    This report contains a description of three computer programs that implement the theory of sampling designs and the methods for estimating fish-impingement at the cooling-water intakes of nuclear power plants as described in companion report ANL/ES-60. Complete FORTRAN listings of these programs, named SAMPLE, ESTIMA, and SIZECO, are given and augmented with examples of how they are used

  9. Documentation and archiving of the Space Shuttle wind tunnel test data base. Volume 1: Background and description

    Science.gov (United States)

    Romere, Paul O.; Brown, Steve Wesley

    1995-01-01

    Development of the space shuttle necessitated an extensive wind tunnel test program, with the cooperation of all the major wind tunnels in the United States. The result was approximately 100,000 hours of space shuttle wind tunnel testing conducted for aerodynamics, heat transfer, and structural dynamics. The test results were converted into Chrysler DATAMAN computer program format to facilitate use by analysts, a very cost effective method of collecting the wind tunnel test results from many test facilities into one centralized location. This report provides final documentation of the space shuttle wind tunnel program. The two-volume set covers evolution of space shuttle aerodynamic configurations and gives wind tunnel test data, titles of wind tunnel data reports, sample data sets, and instructions for accessing the digital data base.

  10. 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

  11. 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

  12. BWR Full Integral Simulation Test (FIST) program: facility description report

    International Nuclear Information System (INIS)

    Stephens, A.G.

    1984-09-01

    A new boiling water reactor safety test facility (FIST, Full Integral Simulation Test) is described. It will be used to investigate small breaks and operational transients and to tie results from such tests to earlier large-break test results determined in the TLTA. The new facility's full height and prototypical components constitute a major scaling improvement over earlier test facilities. A heated feedwater system, permitting steady-state operation, and a large increase in the number of measurements are other significant improvements. The program background is outlined and program objectives defined. The design basis is presented together with a detailed, complete description of the facility and measurements to be made. An extensive component scaling analysis and prediction of performance are presented

  13. 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

  14. Documentation Panels Enhance Teacher Education Programs

    Science.gov (United States)

    Warash, Bobbie Gibson

    2005-01-01

    Documentation of children's projects is advantageous to their learning process and is also a good method for student teachers to observe the process of learning. Documentation panels are a unique way to help student teachers understand how children learn. Completing a panel requires a student teacher to think through a process. Teachers must learn…

  15. 77 FR 6113 - Video Programming and Accessibility Advisory Committee; Announcement of Date of Next Meeting

    Science.gov (United States)

    2012-02-07

    ... FEDERAL COMMUNICATIONS COMMISSION [DA 12-15] Video Programming and Accessibility Advisory.... SUMMARY: This document announces the next meeting of the Video Programming Accessibility Advisory... Commission regarding the provision of video description, access to emergency programming, and access to user...

  16. NASA software documentation standard software engineering program

    Science.gov (United States)

    1991-01-01

    The NASA Software Documentation Standard (hereinafter referred to as Standard) can be applied to the documentation of all NASA software. This Standard is limited to documentation format and content requirements. It does not mandate specific management, engineering, or assurance standards or techniques. This Standard defines the format and content of documentation for software acquisition, development, and sustaining engineering. Format requirements address where information shall be recorded and content requirements address what information shall be recorded. This Standard provides a framework to allow consistency of documentation across NASA and visibility into the completeness of project documentation. This basic framework consists of four major sections (or volumes). The Management Plan contains all planning and business aspects of a software project, including engineering and assurance planning. The Product Specification contains all technical engineering information, including software requirements and design. The Assurance and Test Procedures contains all technical assurance information, including Test, Quality Assurance (QA), and Verification and Validation (V&V). The Management, Engineering, and Assurance Reports is the library and/or listing of all project reports.

  17. Description and comparison of pharmacy technician training programs in the United States.

    Science.gov (United States)

    Anderson, Douglas C; Draime, Juanita A; Anderson, Timothy S

    2016-01-01

    To describe pharmacy technician training programs in the United States and to compare pharmacy technician program characteristics between programs with and without a pharmacist on faculty and between programs with different accreditation status. Descriptive, cross-sectional study. Not applicable. United States pharmacy technician programs. Not applicable. Student class size, faculty credentials, coursework components, program length, tuition rates, and admission criteria. Currently, there are more than 698 pharmacy technician programs across 1114 campuses, with complete data available for 216 programs. Programs varied widely in terms of class sizes, faculty credentials, and admission criteria. Programs with pharmacists on faculty were significantly less expensive than were those without pharmacists (P = 0.009). Accreditation had no impact on tuition prices. This is the first study of its kind to describe and characterize pharmacy technician training programs. There is relatively little control of technician training by the profession of pharmacy. The quality of these programs in terms of student outcomes is unknown, and it should be explored. Rigorous debate and discussion is needed regarding the future of pharmacy technician roles and the training required for those roles. Copyright © 2016 American Pharmacists Association®. Published by Elsevier Inc. All rights reserved.

  18. Plan for the large coil program

    International Nuclear Information System (INIS)

    Haubenreich, P.N.; Anderson, W.C.; Luton, J.N.; Thompson, P.B.

    1977-02-01

    This document has been prepared by the Large Coil Program (LCP) to make generally available the information that has been generated up to this point and to indicate the direction of future work. A summary of objectives, general strategy, and implementation of the LCP is given. Expanded descriptions are given of program content, technical requirements, selection of testing arrangements, tentative schedule and method of preliminary cost estimation

  19. Description of the Formerly Utilized Sites Remedial Action Program

    International Nuclear Information System (INIS)

    1980-09-01

    The background and the results to date of the Department of Energy program to identify and evaluate the radiological conditions at sites formerly utilized by the Corps of Engineers' Manhattan Engineer District (MED) and the US Atomic Energy Commission (AEC) are summarized. The sites of concern were federally, privately, and institutionally owned and were used primarily for research, processing, and storage of uranium and thorium ores, concentrates, or residues. Some sites were subsequently released for other purposes without radiological restriction. Surveys have been conducted since 1974 to document radiological conditions at such sites. Based on radiological surveys, sites are identified in this document that require, or are projected to require, remedial action to remove potential restrictions on the use of the property due to the presence of residual low-level radioactive contamination. Specific recommendations for each site will result from more detailed environmental and engineering surveys to be conducted at those sites and, if necessary, an environmental impact assessment or environmental impact statement will be prepared. Section 3.0 describes the current standards and guidelines now being used to conduct remedial actions. Current authority of the US Department of Energy (DOE) to proceed with remedial actions and the new authority required are summarized. A plan to implement the Formerly Utilized Sites Remedial Action Program (FUSRAP) in accordance with the new authority is presented, including the objectives, scope, general approach, and a summary schedule. Key issues affecting schedule and cost are discussed

  20. Description of the Formerly Utilized Sites Remedial Action Program

    Energy Technology Data Exchange (ETDEWEB)

    1980-09-01

    The background and the results to date of the Department of Energy program to identify and evaluate the radiological conditions at sites formerly utilized by the Corps of Engineers' Manhattan Engineer District (MED) and the US Atomic Energy Commission (AEC) are summarized. The sites of concern were federally, privately, and institutionally owned and were used primarily for research, processing, and storage of uranium and thorium ores, concentrates, or residues. Some sites were subsequently released for other purposes without radiological restriction. Surveys have been conducted since 1974 to document radiological conditions at such sites. Based on radiological surveys, sites are identified in this document that require, or are projected to require, remedial action to remove potential restrictions on the use of the property due to the presence of residual low-level radioactive contamination. Specific recommendations for each site will result from more detailed environmental and engineering surveys to be conducted at those sites and, if necessary, an environmental impact assessment or environmental impact statement will be prepared. Section 3.0 describes the current standards and guidelines now being used to conduct remedial actions. Current authority of the US Department of Energy (DOE) to proceed with remedial actions and the new authority required are summarized. A plan to implement the Formerly Utilized Sites Remedial Action Program (FUSRAP) in accordance with the new authority is presented, including the objectives, scope, general approach, and a summary schedule. Key issues affecting schedule and cost are discussed.

  1. 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.

  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. 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

  4. Quality Assurance Program description, Defense Waste Processing Facility (DWPF)

    International Nuclear Information System (INIS)

    Maslar, S.R.

    1992-01-01

    This document describes the Westinghouse Savannah River Company's (WSRC) Quality Assurance Program for Defense Waste Processing at the Savannah River Site (SRS). WSRC is the operating contractor for the US Department of Energy (DOE) at the SRS. The following objectives are achieved through developing and implementing the Quality Assurance Program: (1) Ensure that the attainment of quality (in accomplishing defense high-level waste processing objectives at the SRS) is at a level commensurate with the government's responsibility for protecting public health and safety, the environment, the public investment, and for efficiently and effectively using national resources. (2) Ensure that high-level waste from qualification and production activities conform to requirements defined by OCRWM. These activities include production processes, equipment, and services; and products that are planned, designed, procured, fabricated, installed, tested, operated, maintained, modified, or produced

  5. The Varieties of Programming Language Semantics (and Their Uses)

    DEFF Research Database (Denmark)

    Mosses, Peter David

    2001-01-01

    ; and regular expressions are extensively used for searching and transforming text. In contrast, formal semantic descriptions are widely regarded as being of interest only to theoreticians. This paper surveys the main frameworks available for describing the dynamic semantics of programming languages......Formal descriptions of syntax are quite popular: regular and context-free grammars have become accepted as useful for documenting the syntax of programming languages, as well as for generating efficient parsers; attribute grammars allow parsing to be linked with typechecking and code generation...

  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. Documenting Employee Conduct

    Science.gov (United States)

    Dalton, Jason

    2009-01-01

    One of the best ways for a child care program to lose an employment-related lawsuit is failure to document the performance of its employees. Documentation of an employee's performance can provide evidence of an employment-related decision such as discipline, promotion, or discharge. When properly implemented, documentation of employee performance…

  8. 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)

  9. Program information architecture/document hierarchy. [Information Management Systems, it's components and rationale

    Energy Technology Data Exchange (ETDEWEB)

    Woods, T.W.

    1991-09-01

    The Nuclear Waste Management System (NWMS) Management Systems Improvement Strategy (MSIS) (DOE 1990) requires that the information within the computer program and information management system be ordered into a precedence hierarchy for consistency. Therefore, the US Department of Energy (DOE). Office of Civilian Radioactive Waste Management (OCRWM) requested Westinghouse Hanford Company to develop a plan for NWMS program information which the MSIS calls a document hierarchy. This report provides the results of that effort and describes the management system as a program information architecture.'' 3 refs., 3 figs.

  10. Math Description Engine Software Development Kit

    Science.gov (United States)

    Shelton, Robert O.; Smith, Stephanie L.; Dexter, Dan E.; Hodgson, Terry R.

    2010-01-01

    The Math Description Engine Software Development Kit (MDE SDK) can be used by software developers to make computer-rendered graphs more accessible to blind and visually-impaired users. The MDE SDK generates alternative graph descriptions in two forms: textual descriptions and non-verbal sound renderings, or sonification. It also enables display of an animated trace of a graph sonification on a visual graph component, with color and line-thickness options for users having low vision or color-related impairments. A set of accessible graphical user interface widgets is provided for operation by end users and for control of accessible graph displays. Version 1.0 of the MDE SDK generates text descriptions for 2D graphs commonly seen in math and science curriculum (and practice). The mathematically rich text descriptions can also serve as a virtual math and science assistant for blind and sighted users, making graphs more accessible for everyone. The MDE SDK has a simple application programming interface (API) that makes it easy for programmers and Web-site developers to make graphs accessible with just a few lines of code. The source code is written in Java for cross-platform compatibility and to take advantage of Java s built-in support for building accessible software application interfaces. Compiled-library and NASA Open Source versions are available with API documentation and Programmer s Guide at http:/ / prim e.jsc.n asa. gov.

  11. 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  

  12. Texas geothermal R D and D program planning support document. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Davis, R.J.; Conover, M.F.; Keeney, R.C.; Personett, M.L.; Richmann, D.L.

    1981-08-28

    Program planning support was provided by; developing a geothermal RD and D program structure, characterizing the status of geothermal RD and D through review of literature and interaction with the geothermal research community, developing a candidate list of future Texas geothermal projects, and prioritizing the candidate projects based on appropriate evaluation criteria. The method used to perform this study and the results thereof are presented. Summary reviews of selected completed and ongoing projects and summary descriptions and evaluations of the candidate RD and D projects ar provided. A brief discussion emerging federal RD and D policies is presented. References and independent project rankings by three of the GRP members are included. (MHR)

  13. Technical basis document for internal dosimetry

    International Nuclear Information System (INIS)

    Hickman, D.P.

    1991-01-01

    This document provides the technical basis for the Chem-Nuclear Geotech (Geotech) internal dosimetry program. Geotech policy describes the intentions of the company in complying with radiation protection standards and the as low as reasonably achievable (ALARA) program. It uses this policy and applicable protection standards to derive acceptable methods and levels of bioassay to assure compliance. The models and computational methods used are described in detail within this document. FR-om these models, dose- conversion factors and derived limits are computed. These computations are then verified using existing documentation and verification information or by demonstration of the calculations used to obtain the dose-conversion factors and derived limits. Recommendations for methods of optimizing the internal dosimetry program to provide effective monitoring and dose assessment for workers are provided in the last section of this document. This document is intended to be used in establishing an accredited dosimetry program in accordance with expected Department of Energy Laboratory Accreditation Program (DOELAP) requirements for the selected radionuclides provided in this document, including uranium mill tailing mixtures. Additions and modifications to this document and procedures derived FR-om this document are expected in the future according to changes in standards and changes in programmatic mission

  14. Overview of Historical Earthquake Document Database in Japan and Future Development

    Science.gov (United States)

    Nishiyama, A.; Satake, K.

    2014-12-01

    In Japan, damage and disasters from historical large earthquakes have been documented and preserved. Compilation of historical earthquake documents started in the early 20th century and 33 volumes of historical document source books (about 27,000 pages) have been published. However, these source books are not effectively utilized for researchers due to a contamination of low-reliability historical records and a difficulty for keyword searching by characters and dates. To overcome these problems and to promote historical earthquake studies in Japan, construction of text database started in the 21 century. As for historical earthquakes from the beginning of the 7th century to the early 17th century, "Online Database of Historical Documents in Japanese Earthquakes and Eruptions in the Ancient and Medieval Ages" (Ishibashi, 2009) has been already constructed. They investigated the source books or original texts of historical literature, emended the descriptions, and assigned the reliability of each historical document on the basis of written age. Another database compiled the historical documents for seven damaging earthquakes occurred along the Sea of Japan coast in Honshu, central Japan in the Edo period (from the beginning of the 17th century to the middle of the 19th century) and constructed text database and seismic intensity data base. These are now publicized on the web (written only in Japanese). However, only about 9 % of the earthquake source books have been digitized so far. Therefore, we plan to digitize all of the remaining historical documents by the research-program which started in 2014. The specification of the data base will be similar for previous ones. We also plan to combine this database with liquefaction traces database, which will be constructed by other research program, by adding the location information described in historical documents. Constructed database would be utilized to estimate the distributions of seismic intensities and tsunami

  15. Documentation of Concurrent programs.

    Science.gov (United States)

    1983-07-01

    preparing the documentation formats, and Tom McDonald for preparing the supplemental materials and statistical analyses. 16 [ 1 -16- I j REFERENCES I Boehm...34*h (eeeeeotop to enter h, to IAmlOCSot land ,uoMXM to R&’T- kfC ’Cod At 1*1 ,lgo: 0) 4 O ~ en ttR .I SA’ tgOhegl that ’t to 40n. .hi &ren a ~ O toll s

  16. Forest Service programs, authorities, and relationships: A technical document supporting the 2000 USDA Forest Service RPA Assessment

    Science.gov (United States)

    Ervin G. Schuster; Michael A. Krebs

    2003-01-01

    The Forest and Rangeland Renewable Resources Planning Act (RPA) of 1974, as amended, directs the Forest Service to prepare and update a renewable resources assessment that would include "a description of Forest Service programs and responsibilities , their interrelationships, and the relationship of these programs and responsibilities to public and private...

  17. 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)

  18. 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.

  19. ERC Safety and Hygiene Programs functional organization structure and mission statement

    International Nuclear Information System (INIS)

    Coleman, S.R.

    2000-01-01

    This document provides a description of the functions, structure, commitments, and goals of the Environmental Restoration Contractor Safety and Hygiene Program. The current structure of the ERC Safety and Hygiene organization is described herein

  20. Environmental Restoration Remedial Action quality assurance requirements document

    International Nuclear Information System (INIS)

    1991-01-01

    This document defines the quality assurance requirements for the US Department of Energy-Richland Operations Office Environmental Restoration Remedial Action program at the Hanford Site. The Environmental Restoration Remedial Action program implements significant commitments made by the US Department of Energy in the Hanford Federal Facility Agreement and Consent Order entered into with the Washington State Department of Ecology and the US Environmental Protection Agency. This document combines quality assurance requirements from various source documents into one set of requirements for use by the US Department of Energy-Richland Operations Office and other Environmental Restoration Remedial Action program participants. This document will serve as the basis for developing Quality Assurance Program Plans and implementing procedures by the participants. The requirements of this document will be applied to activities affecting quality, using a graded approach based on the importance of the item, service, or activity to the program objectives. The Quality Assurance Program that will be established using this document as the basis, together with other program and technical documents, form an integrated management control system for conducting the Environmental Restoration Remedial Action program activities in a manner that provides safety and protects the environment and public health

  1. Sexual Orientation Topics in Elementary Teacher Preparation Programs in the USA

    Science.gov (United States)

    Jennings, Todd; Sherwin, Gary

    2008-01-01

    This investigation is a descriptive study documenting the inclusion of sexual orientation (gay and lesbian) topics in a sample of 65 public university elementary teacher preparation programs across the USA (representing the preparation of 14,000-19,000 new teachers annually). Findings indicate that only 55.6% of programs address sexual orientation…

  2. 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

  3. Hanford Waste Vitrification Plant Quality Assurance Program description for defense high-level waste form development and qualification

    International Nuclear Information System (INIS)

    Hand, R.L.

    1992-01-01

    This document describes the quality assurance (QA) program of the Hanford Waste Vitrification Plant (HWVP) Project. The purpose of the QA program is to control project activities in such a manner as to achieve the mission of the HWVP Project in a safe and reliable manner. A major aspect of the HWVP Project QA program is the control of activities that relate to high-level waste (HLW) form development and qualification. This document describes the program and planned actions the Westinghouse Hanford Company (Westinghouse Hanford) will implement to demonstrate and ensure that the HWVP Project meets the US Department of Energy (DOE) and ASME regulations. The actions for meeting the requirements of the Waste Acceptance Preliminary Specifications (WAPS) will be implemented under the HWVP product qualification program with the objective of ensuring that the HWVP and its processes comply with the WAPS established by the federal repository

  4. Development and implementation of documents control and records management system for KNPP units 5 and 6 modernization program

    International Nuclear Information System (INIS)

    Manchev, B.L.; Ilieva, M.; Nenkova, B. G. . E-mail of corresponding author: ilieva@riskeng.bg; Ilieva, M.)

    2005-01-01

    It was proposed to KNPP to develop and implement a Dcuments Control and Records Management System for an efficient and effective Configuration Management (CM) Program. It will provide reasonable assurance that consistency among design requirements, physical configuration and facility documentation is established and maintained during the Modernization Program and throughout the life of KNPP Units 5 and 6. The fully implemented CM Program will consider and track the modifications resulting from the Units 5 and 6 Modernization Program and will be consistent with internationally recognized principles and customized to fit within the KNPP organizational structure and philosophy (ANSI/NIRMA CM 1.0 - 2000, Configuration Management Of Nuclear Facilities). Development and implementation phase of Documents Control and Records Management System and SmartDoc information system, as well as ideas for further development are presented in this report. (author)

  5. 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.

  6. Seismic safety margin research program. Program plan, Revision II

    International Nuclear Information System (INIS)

    Smith, P.D.; Tokarz, F.J.; Bernreuter, D.L.; Cummings, G.E.; Chou, C.K.; Vagliente, V.N.; Johnson, J.J.; Dong, R.G.

    1978-01-01

    The document has been prepared pursuant to the second meeting of the Senior Research Review Group of the Seismic Safety Margin Research Program (SSMRP), which was held on June 15, 16, 1978. The major portion of the material contained in the document is descriptions of specific subtasks to be performed on the SSMRP. This is preceded by a brief discussion of the objective of the SSMRP and the approach to be used. Specific subtasks to be performed in Phase I of the SSMRP are as follows: (1) plant/site selection, (2) seismic input, (3) soil structure interaction, (4) structural building response, (5) structural sub-system response, (6) fragility, (7) system analysis, and (8) Phase II task definition

  7. Antimicrobial Exposure Assessment Task Force II (AEATF II) Volume 5: Governing Document for a Multi-Year Antimicrobial Chemical Exposure Monitoring Program (interim draft document with changes)

    Science.gov (United States)

    This document describes the overall scope of the AEATF II program, demonstrates the need for additional human exposure monitoring data and explains the proposed methodology for the exposure monitoring studies proposed for conduct by the AEATF II.

  8. Resource Programs : Draft Environmental Impact Statement, Volume 2, Appendices.

    Energy Technology Data Exchange (ETDEWEB)

    United States. Bonneville Power Administration.

    1992-03-01

    Every two years, Bonneville Power Administration (BPA) prepares a Resource Program which identifies the resource actions BPA will take to meet its obligation to serve the forecasted power requirements of its customers. The Resource Program`s Environmental Impact Statement (RPEIS) is a programmatic environmental document which will support decisions made in several future Resource Programs. Environmental documents tiered to the EIS may be prepared on a site-specific basis. The RPEIS includes a description of the environmental effects and mitigation for the various resource types available in order to evaluate the trade-offs among them. It also assesses the environmental impacts of adding thirteen alternative combinations of resources to the existing power system. This report contains the appendices to the RPEIS.

  9. Development of a Standardized Job Description for Healthcare Managers of Metabolic Syndrome Management Programs in Korean Community Health Centers

    Directory of Open Access Journals (Sweden)

    Youngjin Lee, RN, PhD

    2014-03-01

    Conclusion: A job description for healthcare managers may provide basic data essential for the development of a job training program for healthcare managers working in community health promotion programs.

  10. QA programme documentation

    International Nuclear Information System (INIS)

    Scheibelt, L.

    1980-01-01

    The present paper deals with the following topics: The need for a documented Q.A. program; Establishing a Q.A. program; Q.A. activities; Fundamental policies; Q.A. policies; Quality objectives Q.A. manual. (orig./RW)

  11. The Analysis of Heterogeneous Text Documents with the Help of the Computer Program NUD*IST

    Directory of Open Access Journals (Sweden)

    Christine Plaß

    2000-12-01

    Full Text Available On the basis of a current research project we discuss the use of the computer program NUD*IST for the analysis and archiving of qualitative documents. Our project examines the social evaluation of spectacular criminal offenses and we identify, digitize and analyze documents from the entire 20th century. Since public and scientific discourses are examined, the data of the project are extraordinarily heterogeneous: scientific publications, court records, newspaper reports, and administrative documents. We want to show how to transfer general questions into a systematic categorization with the assistance of NUD*IST. Apart from the functions, possibilities and limitations of the application of NUD*IST, concrete work procedures and difficulties encountered are described. URN: urn:nbn:de:0114-fqs0003211

  12. Registration document 2005; Document de reference 2005

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2005-07-01

    This reference document of Gaz de France provides information and data on the Group activities in 2005: financial informations, business, activities, equipments factories and real estate, trade, capital, organization charts, employment, contracts and research programs. (A.L.B.)

  13. 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

  14. 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.

  15. 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

  16. Oil and Gas R&D Programs

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-03-01

    This publication describes the major components of the research and development programs of the Department of Energy`s Office of Natural Gas and Petroleum Technology. These programs are commonly referred to collectively as the `Oil and Gas Program.` This document provides customers with a single source of information describing the details of the individual technology program components. This document reflects the results of a planning cycle that began in early 1996 with the development of a scenario analysis for the programs, followed by the development of the coordinated strategic plan. The technology program plans, which are the most recent products of the planning cycle, expand on the program descriptions presented in the coordinated strategic plan, and represent an initial effort to coordinate the Oil and Gas Program exploration and production programs and budgets. Each technology program plan includes a `roadmap` that summarizes the progress of the program to the present and indicates its future direction. The roadmaps describe the program drivers, vision, mission, strategies, and measures of success. Both the individual technology program plans and the strategic plan are dynamic and are intended to be updated regularly.

  17. Spent Nuclear Fuel Project Document Management Plan

    International Nuclear Information System (INIS)

    Connor, M.D.; Harizison, G.L.; Rice, W.C.

    1995-12-01

    The SNF Project Document Management Plan identifies and describes the currently available systems and processes for implementing and maintaining an effective document control and records management program. This program governs the methods by which documents are generated, released, distributed, maintained current, retired, and ultimately disposed

  18. 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

  19. 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.

  20. NRC review of Electric Power Research Institute's Advanced Light Reactor Utility Requirements Document - Program summary, Project No. 669

    International Nuclear Information System (INIS)

    1992-08-01

    The staff of the US Nuclear Regulatory Commission has prepared Volume 1 of a safety evaluation report (SER), ''NRC Review of Electric Power Research Institute's Advanced Light Water Reactor Utility Requirements Document -- Program Summary,'' to document the results of its review of the Electric Power Research Institute's ''Advanced Light Water Reactor Utility Requirements Document.'' This SER provides a discussion of the overall purpose and scope of the Requirements Document, the background of the staff's review, the review approach used by the staff, and a summary of the policy and technical issues raised by the staff during its review

  1. U.S. Department of Energy, Carlsbad Area Office quality assurance program document. Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-04-01

    Mission of the Carlsbad Area Office (CAO) is to protect human health and the environment by opening and operating the Waste Isolation Pilot Plant (WIPP) for safe disposal of TRU waste, and establishing an effective system for management of TRU waste from generation to disposal. To help in fulfilling this mission and to ensure that risks and environmental impacts are identified and minimized, and that safety, reliability, and performance are optimized, CAO`s policy is to establish and maintain an effective quality assurance (QA) program that supports compliance with applicable Federal, State, and local regulations, and DOE orders and requirements. This document establishes QA program requirements for all programs, projects, and activities sponsored by CAO.

  2. Description of CORSET: a computer program for quantitative x-ray fluorescence analysis

    International Nuclear Information System (INIS)

    Stohl, F.V.

    1980-08-01

    Quantitative x-ray fluorescence analysis requires a method of correcting for absorption and secondary fluorescence effects due to the sample matrix. The computer program CORSET carries out these corrections without requiring a knowledge of the spectral distribution of the x-ray source, and only requires one standard per element or one standard containing all the elements. Sandia's version of CORSET has been divided into three separate programs to fit Sandia's specific requirements for on-line analysis in a melt facility. The melt facility is used to fabricate new alloys with very variable compositions and requires very rapid analyses during a run. Therefore, the standards must be analyzed several days in advance. Program DAT1 is used to set up a permanent file consisting of all the data related to the standards. Program UNINT is used to set up a permanent file with the intensities, background counts and counting times of the unknowns. Program CORSET uses the files created in UNINT and DAT1 to carry out the analysis. This report contains descriptions, listings, and sample runs for these programs. The accuracy of the analyses carried out with these three programs is about 1 to 2% relative with an elemental concentration of about 10 wt %

  3. MAVL wastes containers functional demonstration and associated tests program

    International Nuclear Information System (INIS)

    Templier, J.C.

    2002-01-01

    In the framework of studies on the MAVL wastes, the CEA develops containers for middle time wastes storage. This program aims to realize a ''B wastes containers'' demonstrator. A demonstrator is a container, parts of a container or samples which must validate the tests. This document presents the state of the study in the following three chapters: functions description, base data and design choices; presentation of the functional demonstrators; demonstration tests description. (A.L.B.)

  4. Applications for electronic documents

    International Nuclear Information System (INIS)

    Beitel, G.A.

    1995-01-01

    This paper discusses the application of electronic media to documents, specifically Safety Analysis Reports (SARs), prepared for Environmental Restoration and Waste Management (ER ampersand WM) programs being conducted for the Department of Energy (DOE) at the Idaho National Engineering Laboratory (INEL). Efforts are underway to upgrade our document system using electronic format. To satisfy external requirements (DOE, State, and Federal), ER ampersand WM programs generate a complement of internal requirements documents including a SAR and Technical Safety Requirements along with procedures and training materials. Of interest, is the volume of information and the difficulty in handling it. A recently prepared ER ampersand WM SAR consists of 1,000 pages of text and graphics; supporting references add 10,000 pages. Other programmatic requirements documents consist of an estimated 5,000 pages plus references

  5. 40 CFR 51.362 - Motorist compliance enforcement program oversight.

    Science.gov (United States)

    2010-07-01

    ... deviate from established requirements, or in the case of non-government entities that process... registrations; and (10) The prevention of fraudulent procurement or use of inspection documents by controlling... measurements. (c) SIP requirements. The SIP shall include a description of enforcement program oversight and...

  6. 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)

  7. Department of Energy WindSentinel Loan Program Description

    Energy Technology Data Exchange (ETDEWEB)

    Shaw, William J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Sturges, Mark H. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

    2016-12-01

    The U.S. Department of Energy (DOE) currently owns two AXYS WindSentinel buoys that collect a comprehensive set of meteorological and oceanographic data to support resource characterization for wind energy offshore. The two buoys were delivered to DOE’s Pacific Northwest National Laboratory (PNNL) in September, 2014. After acceptance testing and initial performance testing and evaluation at PNNL’s Marine Sciences Laboratory in Sequim, Washington, the buoys have been deployed off the U.S. East Coast. One buoy was deployed approximately 42 km east of Virginia Beach, Virginia from December, 2014 through June, 2016. The second buoy was deployed approximately 5 km off Atlantic City, New Jersey in November, 2015. Data from the buoys are available to the public. Interested parties can create an account and log in to http://offshoreweb.pnnl.gov. In response to a number of inquiries and unsolicited proposals, DOE’s Wind Energy Technologies Office is implementing a program, to be managed by PNNL, to lend the buoys to qualified parties for the purpose of acquiring wind resource characterization data in areas of interest for offshore wind energy development. This document describes the buoys, the scope of the loans, the process of how borrowers will be selected, and the schedule for implementation of this program, including completing current deployments.

  8. Mississippi Curriculum Framework for Medical Radiologic Technology (Radiography) (CIP: 51.0907--Medical Radiologic Technology). Postsecondary Programs.

    Science.gov (United States)

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

    This document, which is intended for use by community and junior colleges throughout Mississippi, contains curriculum frameworks for the course sequences in the radiologic technology program. Presented in the introductory section are a description of the program and suggested course sequence. Section I lists baseline competencies for the program,…

  9. 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)

  10. Planning Document for an NBSR Conversion Safety Analysis Report

    Energy Technology Data Exchange (ETDEWEB)

    Diamond D. J.; Baek J.; Hanson, A.L.; Cheng, L-Y.; Brown, N.; Cuadra, A.

    2013-09-25

    The NIST Center for Neutron Research (NCNR) is a reactor-laboratory complex providing the National Institute of Standards and Technology (NIST) and the nation with a world-class facility for the performance of neutron-based research. The heart of this facility is the National Bureau of Standards Reactor (NBSR). The NBSR is a heavy water moderated and cooled reactor operating at 20 MW. It is fueled with high-enriched uranium (HEU) fuel elements. A Global Threat Reduction Initiative (GTRI) program is underway to convert the reactor to low-enriched uranium (LEU) fuel. This program includes the qualification of the proposed fuel, uranium and molybdenum alloy foil clad in an aluminum alloy, and the development of the fabrication techniques. This report is a planning document for the conversion Safety Analysis Report (SAR) that would be submitted to, and approved by, the Nuclear Regulatory Commission (NRC) before the reactor could be converted.This report follows the recommended format and content from the NRC codified in NUREG-1537, “Guidelines for Preparing and Reviewing Applications for the Licensing of Non-power Reactors,” Chapter 18, “Highly Enriched to Low-Enriched Uranium Conversions.” The emphasis herein is on the SAR chapters that require significant changes as a result of conversion, primarily Chapter 4, Reactor Description, and Chapter 13, Safety Analysis. The document provides information on the proposed design for the LEU fuel elements and identifies what information is still missing. This document is intended to assist ongoing fuel development efforts, and to provide a platform for the development of the final conversion SAR. This report contributes directly to the reactor conversion pillar of the GTRI program, but also acts as a boundary condition for the fuel development and fuel fabrication pillars.

  11. Apparatus-Program Complexes Processing and Creation of Essentially non-Format Documents on the Basis of Technology Auto-Adaptive Fonts

    Directory of Open Access Journals (Sweden)

    E. G. Andrianova

    2014-01-01

    Full Text Available The need to translate paper documents into electronic form demanded a development of methods and algorithms for automatic processing systems and web publishing unformatted graphic documents of on-line libraries. Translation of scanned images into modern formats of electronic documents using OCR programmes faces serious difficulties. These difficulties are connected with the standardization set of fonts and design of printed documents. There is also a need to maintain the original form of electronic format of such documents. The article discusses the possibility for building an extensible adaptive dictionary of graphic objects, which constitute unformatted graphics documents. Dictionary automatically adjusted as graphics processing and accumulation of statistical information for each new document. This adaptive extensible dictionary of graphic letters, fonts, and other objects of automated particular document processing is called "auto-adaptive font", and a set of its application methods is named "auto-adaptive font technology."Based on the theory of estimation algorithms, a mathematical model is designed. It allows us to represent all objects of unformatted graphic document in a unified manner to build a feature vector for each object, and evaluate a similarity of these objects in the selected metric. The algorithm of the adaptive models of graphic images is developed and a criterion for combining similar properties in one element to build an auto-adaptive font is offered thus allowing us to build a software core of hardware-software complex for processing the unformatted graphic documents. A standard block diagram of hardware-software complex is developed to process the unformatted graphic documents. The article presents a description of all the blocks of this complex, including document processing station and its interaction with the web server of publishing electronic documents.

  12. Program plan for evaluation of the Ferrocyanide Waste Tank safety issue at the Hanford Site

    International Nuclear Information System (INIS)

    Borsheim, G.L.; Meacham, J.E.; Cash, R.J.; Dukelow, G.T.

    1994-03-01

    This document describes the background, priorities, strategy and logic, and task descriptions for the Ferrocyanide Waste Tank Safety Program. The Ferrocyanide Safety Program was established in 1990 to provide resolution of a major safety issue identified for 24 high-level radioactive waste tanks at the Hanford Site

  13. DOE Defense Program (DP) safety programs. Final report, Task 003

    International Nuclear Information System (INIS)

    1998-01-01

    The overall objective of the work on Task 003 of Subcontract 9-X52-W7423-1 was to provide LANL with support to the DOE Defense Program (DP) Safety Programs. The effort included the identification of appropriate safety requirements, the refinement of a DP-specific Safety Analysis Report (SAR) Format and Content Guide (FCG) and Comprehensive Review Plan (CRP), incorporation of graded approach instructions into the guidance, and the development of a safety analysis methodologies document. All tasks which were assigned under this Task Order were completed. Descriptions of the objectives of each task and effort performed to complete each objective is provided here

  14. Technical basis document for internal dosimetry

    CERN Document Server

    Hickman, D P

    1991-01-01

    This document provides the technical basis for the Chem-Nuclear Geotech (Geotech) internal dosimetry program. Geotech policy describes the intentions of the company in complying with radiation protection standards and the as low as reasonably achievable (ALARA) program. It uses this policy and applicable protection standards to derive acceptable methods and levels of bioassay to assure compliance. The models and computational methods used are described in detail within this document. FR-om these models, dose- conversion factors and derived limits are computed. These computations are then verified using existing documentation and verification information or by demonstration of the calculations used to obtain the dose-conversion factors and derived limits. Recommendations for methods of optimizing the internal dosimetry program to provide effective monitoring and dose assessment for workers are provided in the last section of this document. This document is intended to be used in establishing an accredited dosi...

  15. Uranium accountability for ATR fuel fabrication. Part I. A description of the existing system

    International Nuclear Information System (INIS)

    Dolan, C.A.; Nieschmidt, E.B.; Vegors, S.H. Jr.; Wagner, E.P. Jr.

    1977-06-01

    An evaluation of the materials accountability program at the Atomics International fuel fabrication facility in Canoga Park, California, with regard to the fabrication of highly enriched uranium fuel for the Advanced Test Reactor is presented. An analysis is given of the existing standards program, the existing measurements program and the existing statistical analysis procedures. In addition a short discussion is given of our evaluation of the safeguards procedures at Atomics International together with suggestions for possible modifications and improvements. Appendices of this report contain a rather complete description of the Atomics International plant and the flow of highly enriched uranium through the plant as well as the principal documents used for material accountability records

  16. Hanford Site grundwater protection management program

    International Nuclear Information System (INIS)

    1989-10-01

    Groundwater protection has emerged over the past few years as a national priority that has been promulgated in a variety of environmental regulations at both the state and federal level. In order to effectively coordinate and ensure compliance with applicable regulations, the US Department of Energy (DOE) requires all DOE facilities to prepare separate groundwater protection program descriptions and plans (groundwater activities were formerly included as a subpart of environmental protection programs). This document is for the Hanford Site located in the state of Washington. The DOE Order specifies that the groundwater protection management program cover the following general topical areas: (1) documentation of the groundwater regime, (2) design and implementation of a groundwater monitoring program to support resource management and comply with applicable laws and regulations, (3) a management program for groundwater protection and remediation, (4) a summary and identification of areas that may be contaminated with hazardous waste, (5) strategies for controlling these sources, (6) a remedial action program, and (7) decontamination and decommissioning and related remedial action requirements. 14 refs., 19 figs., 2 tabs

  17. US Department of Energy Oak Ridge Field Office Environmental Restoration Program review

    International Nuclear Information System (INIS)

    1992-05-01

    This document summarizes the baselined FY 1993 Department of Energy Oak Ridge Field Office (DOE-OR) Environmental Restoration Program task priorities, budgets, and associated abbreviated task descriptions. Also included is a description of the approach utilized to establish priorities for the FY 1993 and FY 1994 budget process. Abbreviated task descriptions for FY 1994 are also included in priority listing. These FY 1994 tasks form the basis for the Activity Data Sheets prepared for DOE-OR that were submitted in May 1992

  18. Mississippi Curriculum Framework for Dental Hygiene Technology (Program CIP: 51.0602--Dental Hygienist). Postsecondary Education.

    Science.gov (United States)

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

    This document, which is intended for use by community and junior colleges throughout Mississippi, contains curriculum frameworks for the course sequences in the dental hygiene technology program. Presented in the introductory section are a description of the program and suggested course sequence. Section I lists baseline competencies. Section II…

  19. Savannah River Interim Waste Management Program Plan - FY 1986

    International Nuclear Information System (INIS)

    1985-09-01

    This document provides the program plan as requested by the Savannah River Operations Office of the Department of Energy. The plan was developed to provide a working knowledge of the nature and extent of the interim waste management programs being undertaken by Savannah River (SR) contractors for the Fiscal Year 1986. In addition, the document projects activities for several years beyond 1986 to adequately plan for safe handling and storage of radioactive wastes generated at Savannah River and for developing technology for improved management of low-level solid wastes. A revised plan will be issued prior to the beginning of the first quarter of each fiscal year. In this document, work descriptions and milestone schedules are current as of the date of publication. Budgets are based on available information as of May 1985

  20. Savannah River Interim Waste Management Program plan, FY-1987

    International Nuclear Information System (INIS)

    1986-09-01

    This document provides the program plan as requested by the Savannah River Operations office of the Department of Energy. The plan was developed to provide a working knowledge of the nature and extent of the interim waste management programs being undertaken by Savannah River (SR) contractors for the Fiscal Year 1987. In addition, the document projects activities for several years beyond 1987 to adequately plan for safe handling and storage of radioactive wastes generated at Savannah River and for developing technology for improved management of low-level solid wastes. A revised plan will be issued prior to the beginning of the first quarter of each fiscal year. In this document, work descriptions and milestone schedules are current as of the date of publication. Budgets are based on available information as of June 1986

  1. 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.

  2. 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

  3. Instructions for submittal and control of FFTF design documents and design related documentation

    International Nuclear Information System (INIS)

    Grush, R.E.

    1976-10-01

    This document provides the system and requirements for management of FFTF technical data prepared by Westinghouse Hanford (HEDL), and design contractors, the construction contractor and lower tier equipment suppliers. Included in this document are provisions for the review, approval, release, change control, and accounting of FFTF design disclosure and base documentation. Also included are provisions for submittal of other design related documents for review and approval consistent with applicable requirements of RDT-Standard F 2-2, ''Quality Assurance Program Requirements.''

  4. 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

  5. A Descriptive Analysis of the Use of Twitter by Emergency Medicine Residency Programs.

    Science.gov (United States)

    Diller, David; Yarris, Lalena M

    2018-02-01

    Twitter is increasingly recognized as an instructional tool by the emergency medicine (EM) community. In 2012, the Council of Residency Directors in Emergency Medicine (CORD) recommended that EM residency programs' Twitter accounts be managed solely by faculty. To date, little has been published regarding the patterns of Twitter use by EM residency programs. We analyzed current patterns in Twitter use among EM residency programs with accounts and assessed conformance with CORD recommendations. In this mixed methods study, a 6-question, anonymous survey was distributed via e-mail using SurveyMonkey. In addition, a Twitter-based search was conducted, and the public profiles of EM residency programs' Twitter accounts were analyzed. We calculated descriptive statistics and performed a qualitative analysis on the data. Of 168 Accreditation Council for Graduate Medical Education-accredited EM programs, 88 programs (52%) responded. Of those programs, 58% (51 of 88) reported having a program-level Twitter account. Residents served as content managers for those accounts in the majority of survey respondents (61%, 28 of 46). Most programs did not publicly disclose the identity or position of their Twitter content manager. We found a wide variety of applications for Twitter, with EM programs most frequently using Twitter for educational and promotional purposes. There is significant variability in the numbers of followers for EM programs' Twitter accounts. Applications and usage among EM residency programs are varied, and are frequently not consistent with current CORD recommendations.

  6. Assessment of the Business Administration and Business Management Programs.

    Science.gov (United States)

    Forestieri, Kathleen; Karlen, Janice; Coiro, Robert; Gabriel, Theodore; Leff, Elaine; Silverman, Barry; Wertheimer, David

    This document presents City University of New York LaGuardia Community College's Department of Accounting and Managerial Studies assessment of its business and administration and business management programs report, and includes the following items: (1) a description of the mission and goals of the Department of Accounting and Managerial Studies;…

  7. OCRWM baseline management procedure for document identifiers

    International Nuclear Information System (INIS)

    1993-03-01

    This procedure establishes a uniform numbering system (document identifier) for all Program and project technical, cost, and schedule baselines, and selected management and procurement documents developed for and controlled by the Office of Civilian Radioactive Waste Management (OCRWM) for the Civilian Radioactive Waste Management System (CRWMS). The document identifier defined in this procedure is structured to ensure that the relational integrity between configuration items (CIs) and their associated documentation and software is maintained, traceable, categorical, and retrievable for the life of the program

  8. Development of a standardized job description for healthcare managers of metabolic syndrome management programs in Korean community health centers.

    Science.gov (United States)

    Lee, Youngjin; Choo, Jina; Cho, Jeonghyun; Kim, So-Nam; Lee, Hye-Eun; Yoon, Seok-Jun; Seomun, GyeongAe

    2014-03-01

    This study aimed to develop a job description for healthcare managers of metabolic syndrome management programs using task analysis. Exploratory research was performed by using the Developing a Curriculum method, the Intervention Wheel model, and focus group discussions. Subsequently, we conducted a survey of 215 healthcare workers from 25 community health centers to verify that the job description we created was accurate. We defined the role of healthcare managers. Next, we elucidated the tasks of healthcare managers and performed needs analysis to examine the frequency, importance, and difficulty of each of their duties. Finally, we verified that our job description was accurate. Based on the 8 duties, 30 tasks, and 44 task elements assigned to healthcare managers, we found that the healthcare managers functioned both as team coordinators responsible for providing multidisciplinary health services and nurse specialists providing health promotion services. In terms of importance and difficulty of tasks performed by the healthcare managers, which were measured using a determinant coefficient, the highest-ranked task was planning social marketing (15.4), while the lowest-ranked task was managing human resources (9.9). A job description for healthcare managers may provide basic data essential for the development of a job training program for healthcare managers working in community health promotion programs. Copyright © 2014. Published by Elsevier B.V.

  9. 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.…

  10. TWRS configuration management requirement source document

    International Nuclear Information System (INIS)

    Vann, J.M.

    1997-01-01

    The TWRS Configuration Management (CM) Requirement Source document prescribes CM as a basic product life-cycle function by which work and activities are conducted or accomplished. This document serves as the requirements basis for the TWRS CM program. The objective of the TWRS CM program is to establish consistency among requirements, physical/functional configuration, information, and documentation for TWRS and TWRS products, and to maintain this consistency throughout the life-cycle of TWRS and the product, particularly as changes are being made

  11. Mississippi Curriculum Framework for Diesel Equipment Technology (CIP: 47.0605--Diesel Engine Mechanic & Repairer). Postsecondary Programs.

    Science.gov (United States)

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

    This document, which is intended for use by community and junior colleges throughout Mississippi, contains curriculum frameworks for the course sequences in the diesel equipment technology programs cluster. Presented in the introductory section are a description of the program and suggested course sequence. Section I lists baseline competencies,…

  12. Pre-WIPP in-situ experiments in salt. Part I. Executive summary. Part II. Program description

    Energy Technology Data Exchange (ETDEWEB)

    Sattler, A.R.; Hunter, T.O.

    1979-08-01

    This document presents plans for in-situ experiments in a specific location in southeastern New Mexico. Schedule and facility design were based on features of a representative local potash mine and on contract negotiations with mine owners. Subsequent WIPP program uncertainties have required a delay in the implementation of the activities discussed here; however, the relative schedule for various activities are appropriate for future planning. The document represents a matrix of in-situ activities to address relevant technical issues prior to the availability of a bedded salt repository.

  13. Pre-WIPP in-situ experiments in salt. Part I. Executive summary. Part II. Program description

    International Nuclear Information System (INIS)

    Sattler, A.R.; Hunter, T.O.

    1979-08-01

    This document presents plans for in-situ experiments in a specific location in southeastern New Mexico. Schedule and facility design were based on features of a representative local potash mine and on contract negotiations with mine owners. Subsequent WIPP program uncertainties have required a delay in the implementation of the activities discussed here; however, the relative schedule for various activities are appropriate for future planning. The document represents a matrix of in-situ activities to address relevant technical issues prior to the availability of a bedded salt repository

  14. 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

  15. Office of Civilian Radioactive Waste Management Program Cost and Schedule Baseline

    International Nuclear Information System (INIS)

    1992-09-01

    The purpose of this document is to establish quantitative expressions of proposed costs and schedule to serve as a basis for measurement of program performance. It identifies the components of the Program Cost and Schedule Baseline (PCSB) that will be subject to change control by the Executive (Level 0) and Program (Level 1) Change Control Boards (CCBS) and establishes their baseline values. This document also details PCSB reporting, monitoring, and corrective action requirements. The Program technical baseline contained in the Waste Management System Description (WMSD), the Waste Management System Requirements (WMSR), and the Physical System Requirements documents provide the technical basis for the PCSB. Changes to the PCSB will be approved by the Pregrain Change Control Board (PCCB)In addition to the PCCB, the Energy System Acquisition Advisory Board Baseline CCB (ESAAB BCCB) will perform control functions relating to Total Project Cost (TPC) and major schedule milestones for the Yucca Mountain Site Characterization Project and the Monitored Retrievable Storage (MRS) Project

  16. 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.

  17. 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

  18. 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

  19. 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…

  20. Spent fuel receipt and lag storage facility for the spent fuel handling and packaging program

    International Nuclear Information System (INIS)

    Black, J.E.; King, F.D.

    1979-01-01

    Savannah River Laboratory (SRL) is participating in the Spent Fuel Handling and Packaging Program for retrievable, near-surface storage of spent light water reactor (LWR) fuel. One of SRL's responsibilities is to provide a technical description of the wet fuel receipt and lag storage part of the Spent Fuel Handling and Packaging (SFHP) facility. This document is the required technical description

  1. 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.

  2. Radioactivity standards distribution program, 1978--1979. Interim report, 1978--1979

    International Nuclear Information System (INIS)

    Ziegler, L.H.

    1978-06-01

    A program for the distribution of calibrated radioactive samples, as one function of EPA's quality assurance program for environmental radiation measurements, is described. Included is a discussion of the objectives of the distribution program and a description of the preparation, availability, and distribution of calibrated radioactive samples. Instructions and application forms are included for laboratories desiring to participate in the program. This document is not a research report. It is designed for use by personnel of laboratories participating or desiring to participate in the Radioactivity Standards Distribution Program, which is a part of the U.S. Environmental Protection Agency's quality assurance program

  3. Computer automation of continuous-flow analyzers for trace constituents in water. Volume 4. Description of program segments. Part 3. TAASTART

    International Nuclear Information System (INIS)

    Crawford, R.W.

    1979-01-01

    This report describes TAASTART, the third program in the series of programs necessary in automating the Technicon AutoAnalyzer. Included is a flow chart that illustrates the program logic and a description of each section and subroutine. In addition, all arrays, variables and strings are listed and defined, and a sample program listing with a complete list of symbols and references is provided

  4. NASIS data base management system - IBM 360/370 OS MVT implementation. 4: Program design specifications

    Science.gov (United States)

    1973-01-01

    The design specifications for the programs and modules within the NASA Aerospace Safety Information System (NASIS) are presented. The purpose of the design specifications is to standardize the preparation of the specifications and to guide the program design. Each major functional module within the system is a separate entity for documentation purposes. The design specifications contain a description of, and specifications for, all detail processing which occurs in the module. Sub-modules, reference tables, and data sets which are common to several modules are documented separately.

  5. A summary description of the flammable gas tank safety program

    International Nuclear Information System (INIS)

    Johnson, G.D.; Sherwood, D.J.

    1994-10-01

    Radioactive liquid waste may produce hydrogen as result of the interaction of gamma radiation and water. If the waste contains organic chelating agents, additional hydrogen as well as nitrous oxide and ammonia may be produced by thermal and radiolytic decomposition of these organics. Several high-level radioactive liquid waste storage tanks, located underground at the Hanford Site in Washington State, are on a Flammable Gas Watch List. Some contain waste that produces and retains gases until large quantities of gas are released rapidly to the tank vapor space. Tanks nearly-filled to capacity have relatively little vapor space; therefore if the waste suddenly releases a large amount of hydrogen and nitrous oxide, a flammable gas mixture could result. The most notable example of a Hanford waste tank with a flammable gas problem is tank 241-SY-101. Upon occasion waste stored in this tank has released enough flammable gas to burn if an ignition source had been present inside of the tank. Several, other Hanford waste tanks exhibit similar behavior although to a lesser magnitude. Because this behavior was hot adequately-addressed in safety analysis reports for the Hanford Tank Farms, an unreviewed safety question was declared, and in 1990 the Flammable Gas Tank Safety Program was established to address this problem. The purposes of the program are a follows: (1) Provide safety documents to fill gaps in the safety analysis reports, and (2) Resolve the safety issue by acquiring knowledge about gas retention and release from radioactive liquid waste and developing mitigation technology. This document provides the general logic and work activities required to resolve the unreviewed safety question and the safety issue of flammable gas mixtures in radioactive liquid waste storage tanks

  6. MODLP program description: A program for solving linear optimal hydraulic control of groundwater contamination based on MODFLOW simulation. Version 1.0

    International Nuclear Information System (INIS)

    Ahlfeld, D.P.; Dougherty, D.E.

    1994-11-01

    MODLP is a computational tool that may help design capture zones for controlling the movement of contaminated groundwater. It creates and solves linear optimization programs that contain constraints on hydraulic head or head differences in a groundwater system. The groundwater domain is represented by USGS MODFLOW groundwater flow simulation model. This document describes the general structure of the computer program, MODLP, the types of constraints that may be imposed, detailed input instructions, interpretation of the output, and the interaction with the MODFLOW simulation kernel

  7. 78 FR 40421 - Inquiry Regarding Video Description in Video Programming Distributed on Television and on the...

    Science.gov (United States)

    2013-07-05

    ... description services for television are provided on a secondary audio stream, and typically a consumer can... box. The Commission recently adopted rules requiring apparatus that is designed to receive, play back, or record video programming transmitted simultaneously with sound to make secondary audio streams...

  8. Program plan for the resolution of tank vapor issues

    International Nuclear Information System (INIS)

    Osborne, J.W.

    1992-09-01

    The purpose of this document is to provide a detailed description of the priorities, logic, work breakdown structure (WBS), task descriptions, and program milestones required for the resolution of tank vapor issues associated with the single-shell tanks (SST) and double-shell tanks (DST). The primary objective of this plan is to determine whether a health (personnel exposure) and/or safety (flammability) hazard exists. This plan is focused upon one waste tank, 241-C-103, but contains all elements required to bring the vapor issues to resolution

  9. 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

  10. 77 FR 11785 - Energy Conservation Program: Public Meeting and Availability of the Framework Document for High...

    Science.gov (United States)

    2012-02-28

    ... standards for high-intensity discharge (HID) lamps. Accordingly, DOE will hold a public meeting to discuss..._standards/commercial/high_intensity_discharge_lamps.html . DATES: The Department will hold a public meeting... Technologies Program, Mailstop EE-2J, Framework Document for High-Intensity Discharge Lamps, EERE-2010-BT-STD...

  11. Land reclamation program description

    Energy Technology Data Exchange (ETDEWEB)

    None

    1977-05-01

    The Land Reclamation Program will address the need for coordinated applied and basic research into the physical and ecological problems of land reclamation, and advance the development of cost-effective techniques for reclaiming and rehabilitating mined coal land to productive end uses. The purpose of this new program is to conduct integrated research and development projects focused on near- and long-term reclamation problems in all major U.S. coal resource regions including Alaska and to coordinate, evaluate, and disseminate the results of related studies conducted at other research institutions. The activities of the Land Reclamation Laboratory program will involve close cooperation with industry and focus on establishing a comprehensive field and laboratory effort. Research demonstration sites will be established throughout the United States to address regional and site-specific problems. Close cooperation with related efforts at academic institutions and other agencies, to transfer pertinent information and avoid duplication of effort, will be a primary goal of the program. The major effort will focus on the complete coal extraction/reclamation cycle where necessary to develop solutions to ameliorating the environmental impacts of coal development. A long-range comprehensive national reclamation program will be established that can schedule and prioritize research activities in all of the major coal regions. A fully integrated data management system will be developed to store and manage relevant environmental and land use data. Nine research demonstration sites have been identified.

  12. Resource Programs: Final Environmental Impact Statement

    International Nuclear Information System (INIS)

    1993-02-01

    Every two years, BA prepares a Resource Program, which identifies the resource actions BA will take to meet its obligation to serve the forecasted power requirements of its customers. The Resource Programs Environmental Impact Statement (RPEIS) is a programmatic environmental document that will support decisions made in several future Resource Programs. Environmental documents tiered to this EIS may be prepared on a site-specific basis. The RPEIS includes a description of the environmental effects and mitigation for the various resource types available in order to evaluate the trade-offs among them. It also assesses the environmental impacts of adding thirteen alternative combinations of resources to the existing power system. The alternatives represent the range of actions BA could take to meet its load obligations. Each of the alternatives allows BA to meet the almost 5,000 average megawatt load increase that could occur with high load growth, or an equivalent need for resources caused by a combination of load growth and any future loss of resources

  13. GENIE-V3 concepts document

    International Nuclear Information System (INIS)

    Moreton-Smith, C.M.

    1990-01-01

    The GENIE data analysis program is a program used for analysis of data from the ISIS neutron scattering instruments. The current version, GENIE-V2, is now being re-written to provide a much more powerful data analysis system for the next major version of the program, GENIE-V3. The purpose of this ''Concepts Document'' is to establish a frame of reference within which to discuss the development of GENIE-V3. It does not seek to define everything which will be implemented in the new version of the GENIE program. A substantial amount of design effort has been expended to produce a plausible design for the language and operation of GENIE-V3. Having said this, this is in no way a complete specification. Several features (although intended for any working version of GENIE-V3) have not been documented here, hopefully though, nothing material has been left out. To keep this document to a reasonable length, commands which can be written using GENIE-V3 are omitted. (author)

  14. 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

  15. REBUILD AMERICA PROGRAM SCOPE OF WORK

    Energy Technology Data Exchange (ETDEWEB)

    Jeffrey Brown; Bruce Exstrum

    2004-12-01

    This report summarizes the activities carried out by Aspen Systems Corporation in support of the Department of Energy's Rebuild America program during the period from October 9, 1999 to October 31, 2004. These activities were in accordance with the Scope of Work contained in a GSA MOBIS schedule task order issued by the National Energy Technology Laboratory. This report includes descriptions of activities and results in the following areas: deployment/delivery model; program and project results; program representative support activities; technical assistance; web site development and operation; business/strategic partners; and training/workshop activities. The report includes conclusions and recommendations. Five source documents are also provided as appendices.

  16. 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.

  17. Savannah River Waste Management Program Plan - FY 1982

    International Nuclear Information System (INIS)

    1981-12-01

    This document provides the program plan as requested by the Savannah River Operations Office of the Department of Energy. The plan was developed to provide a working knowledge of the nature and extent of the waste management programs being undertaken by Savannah River (SR) contractors for the Fiscal Year 1982. In addition, the document projects activities for several years beyond 1982 to adequately plan for safe handling and storage of radioactive wastes generated at Savannah River, for developing technology to immobilize high-level radioactive wastes generated and stored at SR, and for developing technology for improved management of low-level solid wastes. A revised plan will be issued prior to the beginning of the first quarter of each fiscal year. In this document, work descriptions and milestone schedules are current as of the date of publication. Budgets are based on available information as of October 1, 1981

  18. The Advancement of Public Awareness, Concerning TRU Waste Characterization, Using a Virtual Document

    International Nuclear Information System (INIS)

    West, T. B.; Burns, T. P.; Estill, W. G.; Riggs, M. J.; Taggart, D. P.; Punjak, W. A.

    2002-01-01

    Building public trust and confidence through openness is a goal of the DOE Carlsbad Field Office for the Waste Isolation Pilot Plant (WIPP). The objective of the virtual document described in this paper is to give the public an overview of the waste characterization steps, an understanding of how waste characterization instrumentation works, and the type and amount of data generated from a batch of drums. The document is intended to be published on a web page and/or distributed at public meetings on CDs. Users may gain as much information as they desire regarding the transuranic (TRU) waste characterization program, starting at the highest level requirements (drivers) and progressing to more and more detail regarding how the requirements are met. Included are links to: drivers (which include laws, permits and DOE Orders); various characterization steps required for transportation and disposal under WIPP's Hazardous Waste Facility Permit; physical/chemical basis for each characterization method; types of data produced; and quality assurance process that accompanies each measurement. Examples of each type of characterization method in use across the DOE complex are included. The original skeleton of the document was constructed in a PowerPoint presentation and included descriptions of each section of the waste characterization program. This original document had a brief overview of Acceptable Knowledge, Non-Destructive Examination, Non-Destructive Assay, Small Quantity sites, and the National Certification Team. A student intern was assigned the project of converting the document to a virtual format and to discuss each subject in depth. The resulting product is a fully functional virtual document that works in a web browser and functions like a web page. All documents that were referenced, linked to, or associated, are included on the virtual document's CD. WIPP has been engaged in a variety of Hazardous Waste Facility Permit modification activities. During the

  19. Water Resources Research Grant Program project descriptions, fiscal year 1987

    Science.gov (United States)

    ,

    1987-01-01

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

  20. Assessment of the Accounting and Joint Accounting/Computer Information Systems Programs.

    Science.gov (United States)

    Appiah, John; Cernigliaro, James; Davis, Jeffrey; Gordon, Millicent; Richards, Yves; Santamaria, Fernando; Siegel, Annette; Lytle, Namy; Wharton, Patrick

    This document presents City University of New York LaGuardia Community College's Department of Accounting and Managerial Studies assessment of its accounting and joint accounting/computer information systems programs report, and includes the following items: (1) description of the mission and goals of the Department of Accounting and Managerial…

  1. Hanford Site waste minimization and pollution prevention awareness program plan

    International Nuclear Information System (INIS)

    Place, B.G.

    1998-01-01

    This plan, which is required by US Department of Energy (DOE) Order 5400. 1, provides waste minimization and pollution prevention guidance for all Hanford Site contractors. The plan is primary in a hierarchical series that includes the Hanford Site Waste Minimization and Pollution Prevention Awareness Program Plan, Prime contractor implementation plans, and the Hanford Site Guide for Preparing and Maintaining Generator Group Pollution Prevention Program Documentation (DOE-RL, 1997a) describing programs required by Resource Conservation and Recovery Act of 1976 (RCRA) 3002(b) and 3005(h) (RCRA and EPA, 1994). Items discussed include the pollution prevention policy and regulatory background, organizational structure, the major objectives and goals of Hanford Site's pollution prevention program, and an itemized description of the Hanford Site pollution prevention program. The document also includes US Department of Energy, Richland Operations Office's (RL's) statement of policy on pollution prevention as well as a listing of regulatory drivers that require a pollution prevention program

  2. 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

  3. Hanford Site Groundwater Protection Management Program: Revision 1

    International Nuclear Information System (INIS)

    1993-11-01

    Groundwater protection is a national priority that is promulgated in a variety of environmental regulations at local, state, and federal levels. To effectively coordinate and ensure compliance with applicable regulations, the US Department of Energy has issued DOE Order 5400.1 (now under revision) that requires all US Department of Energy facilities to prepare separate groundwater protection program descriptions and plans. This document describes the Groundwater Protection Management Program for the Hanford Site located in the state of Washington. DOE Order 5400.1 specifies that the Groundwater Protection Management Program cover the following general topical areas: (1) documentation of the groundwater regime, (2) design and implementation of a groundwater monitoring program to support resource management and comply with applicable laws and regulations, (3) a management program for groundwater protection and remediation, (4) a summary and identification of areas that may be contaminated with hazardous waste, (5) strategies for controlling these sources, (6) a remedial action program, and (7) decontamination and decommissioning and related remedial action requirements. Many of the above elements are covered by existing programs at the Hanford Site; thus, one of the primary purposes of this document is to provide a framework for coordination of existing groundwater protection activities. Additionally, it describes how information needs are identified and can be incorporated into existing or proposed new programs. The Groundwater Protection Management Program provides the general scope, philosophy, and strategies for groundwater protection/management at the Hanford Site. Subtier documents provide the detailed plans for implementing groundwater-related activities and programs. Related schedule and budget information are provided in the 5-year plan for environmental restoration and waste management at the Hanford Site

  4. Employee assistance programs: history and program description.

    Science.gov (United States)

    Gilbert, B

    1994-10-01

    1. The history and development of Employee Assistance Programs (EAPs) can be traced back to the 1800s. There are currently over 10,000 EAPs in the United States. 2. Standards for program accreditation and counselor certification have been established for EAPs. The "core technology of Employee Assistance Programs" includes identification of behavioural problems based on job performance issues, expert consultation with supervisors, appropriate use of constructive confrontation, microlinkages with treatment providers and resources, macrolinkages between providers, resources, and work organizations, focus on substance abuse, and evaluation of employee success based on job performance. 3. Some EAPs take a broad brush approach, and incorporate health promotion and managed care functions.

  5. Firebird-III program description

    International Nuclear Information System (INIS)

    Lin, M.R.; Prawirosochardjo, S.; Rennick, D.F.; Wessman, E.; Blain, R.J.D.; Wilson, J.M.

    1979-09-01

    The FIREBIRD-III digital computer program is a general network code developed primarily for predicting the thermalhydraulic behaviour of CANDU power reactors during a postulated loss-of-coolant accident and the subsequent emergency coolant injection. Because of its flexibility, the code can also be used to solve a large variety of general two-phase flow problems. This report describes the thermalhydraulic models and the computation methods used in the program

  6. Manufacturing Math Classes: An Instructional Program Guide for Manufacturing Workers.

    Science.gov (United States)

    McBride, Pamela G.; And Others

    This program guide documents a manufacturing job family curriculum that develops competence in generic work force education skills through three courses: Reading Rulers, Charts, and Gauges and Math for Manufacturing Workers I and II. An annotated table of contents lists a brief description of the questions answered in each section. An introduction…

  7. Abstracts of computer programs and data libraries pertaining to photon production data

    Energy Technology Data Exchange (ETDEWEB)

    White, J.E.; Manneschmidt, J.B.; Finch, S.Y.; Dickens, J.K.

    1998-06-01

    Abstracts, or descriptions, of computer programs and data libraries pertaining to Photon Production Data (Measurements, Evaluations and Calculations) maintained in the collections of the Radiation Safety Information Computational Center, Oak Ridge, Tennessee USA and at the OECD/NEA Data Bank, Paris, are collected in this document.

  8. Abstracts of computer programs and data libraries pertaining to photon production data

    International Nuclear Information System (INIS)

    White, J.E.; Manneschmidt, J.B.; Finch, S.Y.; Dickens, J.K.

    1998-01-01

    Abstracts, or descriptions, of computer programs and data libraries pertaining to Photon Production Data (Measurements, Evaluations and Calculations) maintained in the collections of the Radiation Safety Information Computational Center, Oak Ridge, Tennessee USA and at the OECD/NEA Data Bank, Paris, are collected in this document

  9. Reading and Writing as Academic Literacy in EAP Program of Indonesian Leaners

    Science.gov (United States)

    Solikhah, Imroatus

    2015-01-01

    This study investigates academic literacy imposed in reading and writing for academic purposes in the EAP program. This study uses descriptive design elaborating data from curriculum documents and interviews. Involving 45 participants from IAIN Surakarta and Veteran University, data were analyzed using constant-comparison and inductive analysis…

  10. Savannah River interim waste management program plan: FY 1984. Revision 1

    International Nuclear Information System (INIS)

    1983-10-01

    This document provides the program plan as requested by the Savannah River Operations Office of the Department of Energy. The plan was developed to provide a working knowledge of the nature and extent of the interim waste management programs being undertaken by Savannah River (SR) contractors for the Fiscal Year 1984. In addition, the document projects activities for several years beyond 1984 to adequately plan for safe handling and storage of radioactive wastes generated at Savannah River and for developing technology for improved management of low-level solid wastes. A revised plan will be issued prior to the beginning of the first quarter of each fiscal year. In this document, work descriptions and milestone schedules are current as of the date of publication. Budgets are based on available information as of June 1983

  11. Recommended HSE-7 documents hierarchy

    International Nuclear Information System (INIS)

    Klein, R.B.; Jennrich, E.A.; Lund, D.M.; Danna, J.G.; Davis, K.D.; Rutz, A.C.

    1990-01-01

    This report recommends a hierarchy of waste management documents at Los Alamos National Laboratory (LANL or ''Laboratory''). The hierarchy addresses documents that are required to plan, implement, and document waste management programs at Los Alamos. These documents will enable the waste management group and the six sections contained within that group to satisfy requirements that are imposed upon them by the US Department of Energy (DOE), DOE Albuquerque Operations, US Environmental Protection Agency, various State of New Mexico agencies, and Laboratory management

  12. Respiratory Protection Program. Programmatic description

    Energy Technology Data Exchange (ETDEWEB)

    Brooks, J.M.; Porter, W.E.

    1986-03-01

    The ORNL Respirator Program is designed to provide employees with devices which afford maximum protection with minimum inconvenience and discomfort. Teamwork is essential since a comprehensive program involves the Medical Department, the Industrial Hygiene Department, Radiation and Safety Surveys, the Operations Division, Quality Assurance and Inspection, and the Fire Department. The purpose of this manual is to describe in detail the ORNL Respirator Program. Included are discussions of the following elements: quality assurance, selection, fit-testing, maintenance and issue, certified breathing air for self-contained breathing apparatus, inspection, program surveillance, available devices, and standard operating procedures. As program modifications develop and improvements are made, periodic revisions may be necessary. The Industrial Hygiene Department will perform this task on an ''as required'' basis.

  13. 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

  14. 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.

  15. RIMS Program Description.

    Science.gov (United States)

    Kraepelien, Hans

    Computer routines for the translation of teacher-prepared mark sense forms to magnetic tape are described. The program, Receiving IMS (RIMS), is part of the Southwest Regional Laboratory's (SWRL) Instructional Management System (IMS). It accepts mark sense sheets from remotely located Xerox 660 scanner copiers and/or IMS update information from…

  16. Documentation for the viscoplastic and creep program

    DEFF Research Database (Denmark)

    Bellini, Anna

    2004-01-01

    of this workpackage is to simulate creep behavior of aluminum cast samples subjected to high temperature. In this document a two-state variables unified model is applied in order to simulate creep behavior and time-dependent metallurgical changes. The fundamental assumption of the unified theory is that creep...... is run using the material data obtained through the mentioned experimental study. The results obtained for the simulation of tensile tests and of creep tests are compared with experimental curves, showing a good agreement. Moreover, the document describes the results obtained during the first...... is quite stable and convergence can be reached also with big time steps. Keywords: Viscoplasticity, creep, unified constitutive model, aluminum, high temperature....

  17. 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.

  18. 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

  19. 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

  20. Program Plan: field radionuclide migration studies in Climax granite

    International Nuclear Information System (INIS)

    Isherwood, D.; Raber, E.; Coles, D.; Stone, R.

    1980-01-01

    This Program Plan describes the field radionuclide migration studies we plan to conduct in the Climax granite at the Nevada Test Site. Laboratory support studies are included to help us understand the geochemical and hydrologic processes involved in the field. The Program Plan begins with background information (Section 1) on how this program fits into the National Waste Terminal Storage Program Plan and discusses the needs for field studies of this type. The objectives stated in Section 2 are in direct response to these needs, particularly the need to determine whether laboratory studies accurately reflect actual field conditions and the need for field testing to provide a data base for verification of hydrologic and mass transport models. The technical scope (Section 3) provides a work breakdown structure that integrates the various activities and establishes a base for the technical approach described in Section 4. Our approach combines an interactive system of field and laboratory migration experiments with the use of hydrologic models for pre-test predictions and data interpretation. Section 5 on program interfaces identifies how information will be transferred to other related DOE projects. A schedule of activities and major milestones (Section 6) and the budget necessary to meet the project objectives (Section 7) are included in the Program Plan. Sections 8 and 9 contain brief descriptions of how the technical and program controls will be established and maintained and an outline of our quality assurance program. This program plan is an initial planning document and provides a general description of activities. An Engineering Test Plan containing detailed experimental test plans, an instrumentation plan and equipment design drawings will be published as a separate document

  1. The Nordic nuclear safety program 1994-1997. Project handbook

    International Nuclear Information System (INIS)

    1997-06-01

    This is a new revision of the handbook for administrators of the Nordic reactor safety program NKS. The most important administrative functions in project management are described, which should secure a uniform management approach in all the projects. The description of the organizational scheme of the NKS and distribution of responsibilities is followed by examples of various administrative routines and document forms. In the annex the names and addresses of the staff involved in administration of the NKS program are listed. (EG)

  2. 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.

  3. MAPLE-II. A program for plotting fault trees

    International Nuclear Information System (INIS)

    Poucet, A.; Van Den Muyzenberg, C.L.

    1987-01-01

    The MAPLE II code is an improved version of the MAPLE program for plotting fault trees. MAPLE II has added features which make it a versatile tool for drawing large and complex logic trees. The code is developed as part of a package for computer aided fault tree construction and analysis in which it is integrated and used as a documentation tool. However the MAPLE II code can be used as a separate program which uses as input a structure function of a tree and a description of the events and gates which make up the tree. This report includes a short description of the code and of its features. Moreover it contains the how-to-use and some indications for implementing the code and for adapting it to different graphics systems

  4. Waterborne Release Monitoring and Surveillance Programs at the Savannah River Site

    Energy Technology Data Exchange (ETDEWEB)

    Blanchard, A.

    1999-03-26

    This report documents the liquid release environmental compliance programs currently in place at the Savannah river Site (SRS). Included are descriptions of stream monitoring programs, which measure chemical parameters and radionuclides in site streams and the Savannah river and test representative biological communities within the streams for chemical and radiological uptake. This report also explains the field sampling and analytical capabilities that are available at SRS during both normal and emergency conditions.

  5. Waterborne Release Monitoring and Surveillance Programs at the Savannah River Site

    International Nuclear Information System (INIS)

    Blanchard, A.

    1999-01-01

    This report documents the liquid release environmental compliance programs currently in place at the Savannah river Site (SRS). Included are descriptions of stream monitoring programs, which measure chemical parameters and radionuclides in site streams and the Savannah river and test representative biological communities within the streams for chemical and radiological uptake. This report also explains the field sampling and analytical capabilities that are available at SRS during both normal and emergency conditions

  6. 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

  7. 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.

  8. 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.

  9. 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

  10. 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

  11. User Guide and Documentation for Five MODFLOW Ground-Water Modeling Utility Programs

    Science.gov (United States)

    Banta, Edward R.; Paschke, Suzanne S.; Litke, David W.

    2008-01-01

    This report documents five utility programs designed for use in conjunction with ground-water flow models developed with the U.S. Geological Survey's MODFLOW ground-water modeling program. One program extracts calculated flow values from one model for use as input to another model. The other four programs extract model input or output arrays from one model and make them available in a form that can be used to generate an ArcGIS raster data set. The resulting raster data sets may be useful for visual display of the data or for further geographic data processing. The utility program GRID2GRIDFLOW reads a MODFLOW binary output file of cell-by-cell flow terms for one (source) model grid and converts the flow values to input flow values for a different (target) model grid. The spatial and temporal discretization of the two models may differ. The four other utilities extract selected 2-dimensional data arrays in MODFLOW input and output files and write them to text files that can be imported into an ArcGIS geographic information system raster format. These four utilities require that the model cells be square and aligned with the projected coordinate system in which the model grid is defined. The four raster-conversion utilities are * CBC2RASTER, which extracts selected stress-package flow data from a MODFLOW binary output file of cell-by-cell flows; * DIS2RASTER, which extracts cell-elevation data from a MODFLOW Discretization file; * MFBIN2RASTER, which extracts array data from a MODFLOW binary output file of head or drawdown; and * MULT2RASTER, which extracts array data from a MODFLOW Multiplier file.

  12. 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

  13. Document Models

    Directory of Open Access Journals (Sweden)

    A.A. Malykh

    2017-08-01

    Full Text Available In this paper, the concept of locally simple models is considered. Locally simple models are arbitrarily complex models built from relatively simple components. A lot of practically important domains of discourse can be described as locally simple models, for example, business models of enterprises and companies. Up to now, research in human reasoning automation has been mainly concentrated around the most intellectually intensive activities, such as automated theorem proving. On the other hand, the retailer business model is formed from ”jobs”, and each ”job” can be modelled and automated more or less easily. At the same time, the whole retailer model as an integrated system is extremely complex. In this paper, we offer a variant of the mathematical definition of a locally simple model. This definition is intended for modelling a wide range of domains. Therefore, we also must take into account the perceptual and psychological issues. Logic is elitist, and if we want to attract to our models as many people as possible, we need to hide this elitism behind some metaphor, to which ’ordinary’ people are accustomed. As such a metaphor, we use the concept of a document, so our locally simple models are called document models. Document models are built in the paradigm of semantic programming. This allows us to achieve another important goal - to make the documentary models executable. Executable models are models that can act as practical information systems in the described domain of discourse. Thus, if our model is executable, then programming becomes redundant. The direct use of a model, instead of its programming coding, brings important advantages, for example, a drastic cost reduction for development and maintenance. Moreover, since the model is well and sound, and not dissolved within programming modules, we can directly apply AI tools, in particular, machine learning. This significantly expands the possibilities for automation and

  14. Computer automation of continuous-flow analyzers for trace constituents in water. Volume 4. Description of program segments. Part 2. TAAINRE

    International Nuclear Information System (INIS)

    Crawford, R.W.

    1979-01-01

    TAAINRE, the second program in the series of programs necessary in automating the Technicon AutoAnalyzer, is presented. A flow chart and sequence list that describes and illustrates the function of each logical group of coding, and a description of the contents and function of each section and subroutine in the program is included. In addition, all arrays, strings, and variables are listed and defined, and a sample program listing with a complete list of symbols and references provided

  15. Computer automation of continuous-flow analyzers for trace constituents in water. Volume 4. Description of program segments. Part 1. TAAIN

    International Nuclear Information System (INIS)

    Crawford, R.W.

    1979-01-01

    This report describes TAAIN, the first program in the series of programs necessary in automating the Technicon AutoAnalyzer. A flow chart and sequence list that describes and illustrates each logical group of coding, and a description of the contents and functions of each section and subroutine in the program is included. In addition, all arrays, strings, and variables are listed and defined, and a sample program listing with a complete list of symbols and references is provided

  16. The development of AECB regulatory documents

    International Nuclear Information System (INIS)

    Joyce, M.

    1981-01-01

    This document describes the Atomic Energy Control Board's (AECB) approach to the development and preparation of regulatory documents. The principal factors that have shaped the AECB'a regulatory approach are identified as background to the evolution of regulatory documents as are a number of current influences that affect the present and future development of these documents. Also described are the process by which regulatory documents are prepared and published and the points of contact between this process and the Canadian Standards Association program for nuclear standards. (author)

  17. Inclusion of Students with Special Education Needs in French as a Second Language Programs: A Review of Canadian Policy and Resource Documents

    Science.gov (United States)

    Muhling, Stefanie; Mady, Callie

    2017-01-01

    This article describes a document analysis of policy and resource documents pertaining to inclusion of students with special education needs (SSEN) in Canadian French as a Second Language (FSL) programs. By recognizing gaps and acknowledging advancements, we aim to inform current implementation and future development of inclusive policy. Document…

  18. Registration document 2005

    International Nuclear Information System (INIS)

    2005-01-01

    This reference document of Gaz de France provides information and data on the Group activities in 2005: financial informations, business, activities, equipments factories and real estate, trade, capital, organization charts, employment, contracts and research programs. (A.L.B.)

  19. Title I of the Higher Education Act of 1965: Evaluation of the Present Program: Recommendations for the Future.

    Science.gov (United States)

    Whipple, James B.

    In this document, which points out weaknesses in evaluation procedures and offers a new approach to the subject, it is suggested that in the area of the United States studied, the Title 1 program is drifting without direction, leadership, or system. This makes evaluation impossible. Evaluation is sometimes a description of a program and often…

  20. Local and regional space heating models. Documentation. Pt. 1 and 2. Oertliche und regionale Energieversorgungskonzepte fuer Niedertemperaturen. Dokumentation des Arbeitsprogramms. T. 1 und 2

    Energy Technology Data Exchange (ETDEWEB)

    Fuerboeck, M; Elsenberger, U

    1988-01-01

    The documentation focuses on the statistical presentation of the structure and flow of the program on local and regional space heating models, the development of a regional model typology for documentation, the description of energy model steps, and the discussion of first experiences gained in the practical application of models. The program is based on 25 planned studies of quarters, communities, and regions in the Federal Republic of Germany. Their equal spatial distribution plotted in a general map is in good correspondence with the requirement of making planned studies of the main settlement, demand, supply, and organization structures. Apart from the town construction, settlement and construction planning basis the methodical studies intend to supply methodical planning vehicles. With secondary importance given to practical application, the program aims at developing and testing a suitable methodical tool for the development and application of supply models. Cabinet decided the program to be given the character of a research program. The practical application of research results is in charge of the competent energy boards and local decision makers. (orig./UA).

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

    Science.gov (United States)

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

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

  2. User experience and compatibility in documentation standards. Summary

    International Nuclear Information System (INIS)

    Maskewitz, B.F.

    1982-01-01

    Existing guidelines for documentation of scientific computer programs or data libraries are reviewed, and the essential elements for facilitating exchange of the software are outlined. Selected case studies are made in which accepted standards were followed from the programming stage through documentation, and an analysis of user experience

  3. Automated Generation of Technical Documentation and Provenance for Reproducible Research

    Science.gov (United States)

    Jolly, B.; Medyckyj-Scott, D.; Spiekermann, R.; Ausseil, A. G.

    2017-12-01

    Data provenance and detailed technical documentation are essential components of high-quality reproducible research, however are often only partially addressed during a research project. Recording and maintaining this information during the course of a project can be a difficult task to get right as it is a time consuming and often boring process for the researchers involved. As a result, provenance records and technical documentation provided alongside research results can be incomplete or may not be completely consistent with the actual processes followed. While providing access to the data and code used by the original researchers goes some way toward enabling reproducibility, this does not count as, or replace, data provenance. Additionally, this can be a poor substitute for good technical documentation and is often more difficult for a third-party to understand - particularly if they do not understand the programming language(s) used. We present and discuss a tool built from the ground up for the production of well-documented and reproducible spatial datasets that are created by applying a series of classification rules to a number of input layers. The internal model of the classification rules required by the tool to process the input data is exploited to also produce technical documentation and provenance records with minimal additional user input. Available provenance records that accompany input datasets are incorporated into those that describe the current process. As a result, each time a new iteration of the analysis is performed the documentation and provenance records are re-generated to provide an accurate description of the exact process followed. The generic nature of this tool, and the lessons learned during its creation, have wider application to other fields where the production of derivative datasets must be done in an open, defensible, and reproducible way.

  4. 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.

  5. 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.

  6. Gentilly - 2 NGS ALARA program

    International Nuclear Information System (INIS)

    Rheaume, Michel R.

    1998-01-01

    This is a slide-based oral presentation given to the COG/IAEA: Fifth technical committee meeting on 'Exchange of operating experience of pressurized heavy water reactors' held in Mangalia, Romania on 7-10 September 1998. The operation experience of Gentilly -1 and Gentilly - 2 nuclear power stations is summarized. The radiation protection philosophy is addressed, the orange/yellow/green RP qualifications are explained and the ALARA Program objectives are described. The criteria used to develop the Gentilly - 2 station ALARA Program are presented. The program is based on: strong Hydro Quebec commitments, organization (responsibilities well defined); ALARA Committee; tools; procedures; good documentation. Description of the program is given then in details. Measures for dose and radioactive sources reduction are presented. Collective doses recorded at Gentilly - 2 between 1984 and 1997 are plotted and figures are given in a table

  7. 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

  8. PFP MICON DCS computer software documentation

    Energy Technology Data Exchange (ETDEWEB)

    Silvan, G.R.

    1996-03-26

    This document contains the complete printout of the MICON A/S system configuration used in the Plutonium Finishing Plant. The document is divided into several volumes. Volume 1 covers the workstation display and configuration. All other volumes contain the controller configurations, or programs.

  9. PFP MICON DCS computer software documentation

    International Nuclear Information System (INIS)

    Silvan, G.R.

    1996-01-01

    This document contains the complete printout of the MICON A/S system configuration used in the Plutonium Finishing Plant. The document is divided into several volumes. Volume 1 covers the workstation display and configuration. All other volumes contain the controller configurations, or programs

  10. 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)

  11. POSSIBILITIES OF CREATIVE URBAN DEVELOPMENT AND CREATIVE FUTURE OF BUDAPEST ACCORDING TO THE NEW PROGRAMMING REGULATIONS AND DOCUMENTS

    OpenAIRE

    Szilágyi, Anna

    2013-01-01

    In the next programming period, starting in 2014, European cities face the challenge to become SMART cities focusing on sustainability, competitiveness and liveability. Does culture play a key role in this process, and if so, is the European Union aware of its importance? Do programming documents for the next period for Budapest express a recognizable will of the decision makers to transform the city to a Central-European creative capital? In my study, I examine the concepts and regulations o...

  12. 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…

  13. 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

  14. 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

  15. AGRIS: Description of computer programs

    International Nuclear Information System (INIS)

    Schmid, H.; Schallaboeck, G.

    1976-01-01

    The set of computer programs used at the AGRIS (Agricultural Information System) Input Unit at the IAEA, Vienna, Austria to process the AGRIS computer-readable data is described. The processing flow is illustrated. The configuration of the IAEA's computer, a list of error messages generated by the computer, the EBCDIC code table extended for AGRIS and INIS, the AGRIS-6 bit code, the work sheet format, and job control listings are included as appendixes. The programs are written for an IBM 370, model 145, operating system OS or VS, and require a 130K partition. The programming languages are PL/1 (F-compiler) and Assembler

  16. 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.

  17. 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

  18. NACHOS: a finite element computer program for incompressible flow problems. Part I. Theoretical background

    International Nuclear Information System (INIS)

    Gartling, D.K.

    1978-04-01

    The theoretical background for the finite element computer program, NACHOS, is presented in detail. The NACHOS code is designed for the two-dimensional analysis of viscous incompressible fluid flows, including the effects of heat transfer. A general description of the fluid/thermal boundary value problems treated by the program is described. The finite element method and the associated numerical methods used in the NACHOS code are also presented. Instructions for use of the program are documented in SAND77-1334

  19. Description of a medical writing rotation for a postgraduate pharmacy residency program.

    Science.gov (United States)

    Brown, Jamie N; Tiemann, Kelsey A; Ostroff, Jared L

    2014-04-01

    To provide a description of a pharmacy residency rotation dedicated to medical writing developed at a tertiary care academic medical center. Contribution to the medical literature is an important component of professional pharmacy practice, and there are many benefits seen by practitioners actively involved in scholarly activities. Residency programs have an opportunity to expand beyond the standard roles of postgraduate pharmacist training but rarely is there formal instruction on medical writing skills or are scholarship opportunities provided to residents. In order to address this deficiency, a residency program may consider the implementation of a formal Medical Writing rotation. This rotation is designed to introduce the resident to medical writing through active discussion on medical writing foundational topics, engage the resident in a collaborative review of a manuscript submitted to a peer-reviewed professional journal, and support the resident in the design and composition of manuscript of publishable quality. A structured Medical Writing rotation during a pharmacy resident's training can help develop the skills necessary to promote scholarly activities and foster resident interest in future pursuit of professional medical writing.

  20. Hanford Waste Vitrification Plant quality assurance program description for defense high-level waste form development and qualification

    International Nuclear Information System (INIS)

    Hand, R.L.

    1990-12-01

    The US Department of Energy-Office of Civilian Radioactive Waste Management has been designated the national high-level waste repository licensee and the recipient for the canistered waste forms. The Office of Waste Operations executes overall responsibility for producing the canistered waste form. The Hanford Waste Vitrification Plant Project, as part of the waste form producer organization, consists of a vertical relationship. Overall control is provided by the US Department of Energy-Environmental Restoration and Waste Management Headquarters; with the US Department of Energy-Office of Waste Operations; the US Department of Energy- Headquarters/Vitrification Project Branch; the US Department of Energy-Richland Operations Office/Vitrification Project Office; and the Westinghouse Hanford Company, operations and engineering contractor. This document has been prepared in response to direction from the US Department of Energy-Office of Civilian Radioactive Waste Management through the US Department of Energy-Richland Operations Office for a quality assurance program that meets the requirements of the US Department of Energy. This document provides guidance and direction for implementing a quality assurance program that applies to the Hanford Waste Vitrification Plant Project. The Hanford Waste Vitrification Plant Project management commits to implementing the quality assurance program activities; reviewing the program periodically, and revising it as necessary to keep it current and effective. 12 refs., 6 figs., 1 tab

  1. DITTY - a computer program for calculating population dose integrated over ten thousand years

    International Nuclear Information System (INIS)

    Napier, B.A.; Peloquin, R.A.; Strenge, D.L.

    1986-03-01

    The computer program DITTY (Dose Integrated Over Ten Thousand Years) was developed to determine the collective dose from long term nuclear waste disposal sites resulting from the ground-water pathways. DITTY estimates the time integral of collective dose over a ten-thousand-year period for time-variant radionuclide releases to surface waters, wells, or the atmosphere. This document includes the following information on DITTY: a description of the mathematical models, program designs, data file requirements, input preparation, output interpretations, sample problems, and program-generated diagnostic messages

  2. 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)

  3. Proceedings of the second Department Of Energy Defense Programs waste reduction workshop

    International Nuclear Information System (INIS)

    1989-04-01

    The second waste reduction workshop was held at the Rocky Flats Plant (RFP). The objective of this workshop was to exchange specific information (successes and failures) on education and training programs for waste reduction. Each facility was asked to provide a description of their programs to include information on formal, informal, and planned employee training programs; employee incentive programs; pamphlets, posters, books, magazines, communications, and publicity; procurement control and awareness in minimizing hazardous materials; housekeeping successes; waste minimization surveys; and implementation successes and failures. This document contains copies of the demonstrations and not the text of the presentations

  4. 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.

  5. 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

  6. Modular Integrated Stackable Layers (MISL) MI_MSP430A Board Design Document (BDD)

    Science.gov (United States)

    Yim, Hester

    2013-01-01

    This is a board-level design document for Modular Integrated Stackable Layers (MISL) MI_MSP430A board (PIN MSP430F5438A). The Board Design Document (BDD) contains the description, features of microcontroller, electrical and mechanical design, and drawings.

  7. 文件物件模型及其在XML文件處理之應用 Document Object Model and Its Application on XML Document Processing

    Directory of Open Access Journals (Sweden)

    Sinn-cheng Lin

    2001-06-01

    Full Text Available 無Document Object Model (DOM is an application-programming interface that can be applied to process XML documents. It defines the logical structure, the accessing interfaces and the operation methods for the document. In the DOM, an original document is mapped to a tree structure. Therefore ，the computer program can easily traverse the tree manipulate the nodes in the tree. In this paper, the fundamental models, definitions and specifications of DOM are surveyed. Then we create an experimenta1 system of DOM called XML On-Line Parser. The front-end of the system is built by the Web-based user interface for the XML document input and the parsed result output. On the other hand, the back-end of the system is built by an ASP program, which transforms the original document to DOM tree for document manipulation. This on-line system can be linked with a general-purpose web browser to check the well-formedness and the validity of the XML documents.

  8. Standards for Documenting Finite‐Fault Earthquake Rupture Models

    KAUST Repository

    Mai, Paul Martin

    2016-04-06

    In this article, we propose standards for documenting and disseminating finite‐fault earthquake rupture models, and related data and metadata. A comprehensive documentation of the rupture models, a detailed description of the data processing steps, and facilitating the access to the actual data that went into the earthquake source inversion are required to promote follow‐up research and to ensure interoperability, transparency, and reproducibility of the published slip‐inversion solutions. We suggest a formatting scheme that describes the kinematic rupture process in an unambiguous way to support subsequent research. We also provide guidelines on how to document the data, metadata, and data processing. The proposed standards and formats represent a first step to establishing best practices for comprehensively documenting input and output of finite‐fault earthquake source studies.

  9. Standards for Documenting Finite‐Fault Earthquake Rupture Models

    KAUST Repository

    Mai, Paul Martin; Shearer, Peter; Ampuero, Jean‐Paul; Lay, Thorne

    2016-01-01

    In this article, we propose standards for documenting and disseminating finite‐fault earthquake rupture models, and related data and metadata. A comprehensive documentation of the rupture models, a detailed description of the data processing steps, and facilitating the access to the actual data that went into the earthquake source inversion are required to promote follow‐up research and to ensure interoperability, transparency, and reproducibility of the published slip‐inversion solutions. We suggest a formatting scheme that describes the kinematic rupture process in an unambiguous way to support subsequent research. We also provide guidelines on how to document the data, metadata, and data processing. The proposed standards and formats represent a first step to establishing best practices for comprehensively documenting input and output of finite‐fault earthquake source studies.

  10. 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...

  11. CORECOOL, model description of the programme

    International Nuclear Information System (INIS)

    Andersen, J.G.M.; Abel-Larsen, H.

    1978-11-01

    CORECOOL, Convection and Radiation Emergency Cooling, is a model for the two-phase flow and heat transfer in a fuel element during the core heat-up phase following a loss of coolant accident. The model for the two-phase flow is based on a solution of the conservation equations with a separate description of the two phases and thermodynamic non-equilibrium. The flow-regimes considered are drop flow and film flow. The heat transfer consists of convection, sputtering and radiation heat transfer. The documentation of CORECOOL consists of four parts: I) model description, II) programme description (COMMERCIAL), III) users guide (COMMERCIAL) IV) verification (COMMERCIAL). CORECOOL is a joint project between Risoe National Laboratory Denmark and General Electric Company, San Jose, USA. (author)

  12. 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

  13. Hanford Site existing irradiated fuel storage facilities description

    Energy Technology Data Exchange (ETDEWEB)

    Willis, W.L.

    1995-01-11

    This document describes facilities at the Hanford Site which are currently storing spent nuclear fuels. The descriptions provide a basis for the no-action alternatives of ongoing and planned National Environmental Protection Act reviews.

  14. 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...

  15. Computer hardware description languages - A tutorial

    Science.gov (United States)

    Shiva, S. G.

    1979-01-01

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

  16. EP1000 passive plant description

    International Nuclear Information System (INIS)

    Saiu, G.

    1999-01-01

    In 1994, a group of European Utilities, together with Westinghouse and its Industrial Partner GENESI (an Italian consortium including ANSALDO and FIAT), initiated a program designated EPP (European Passive Plant) to evaluate Westinghouse Passive Nuclear Plant Technology for application in Europe. In Phase I of the European Passive Plant Program which was completed in 1996, a 1000 MWe passive plant reference design (EP1000) was established which conforms to the European Utility Requirements (EUR) and is expected to meet the European Safety Authorities requirements. Phase 2 of the program was initiated in 1997 with the objective of developing the Nuclear Island design details and performing supporting analyses to start development of Safety Case Report (SCR) for submittal to European Licensing Authorities. The first part of Phase 2, 'Design Definition' phase (Phase 2A) will be completed at the end of 1998, the main efforts being design definition of key systems and structures, development of the Nuclear Island layout, and performing preliminary safety analyses to support design efforts. The second part, 'Phase 2B', includes both the analyses and evaluations required to demonstrate the adequacy of the design, and to support the preparation of Safety Case Report. The second part of Phase 2 of the program will start at the beginning of 1999 and will be completed in the 2001. Incorporation of the EUR has been a key design requirement for the EP1000 from the beginning of the program. Detailed design solutions to meet the EUR have been defined and the safety approach has also been developed based on the EUR guidelines. This paper integrates and updates the plant description reported in the IAEA TECDOC-968. The most significant developments of the EP1000 plant design during Phase 2A of the EPP program are described and reference is made to the key design requirements set by the EUR Rev. B document. (author)

  17. 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

  18. 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...

  19. Multi-year strategic plan for the Atmospheric Studies in Complex Terrain: ASCOT program

    International Nuclear Information System (INIS)

    1992-06-01

    The Atmospheric Studies in Complex Terrain (ASCOT) program was developed by the Office of Health and Environmental Research of the Office of Energy Research in the Department of Energy (DOE). The program was originally designed to study atmospheric process in regions of complex terrain and the impact of energy sources on air quality in those regions. The ASCOT program has been the principal atmospheric boundary layer research program of DOE. This document contains a description of the ASCOT program's objectives over the next five years and beyond, placing them in the context of current and anticipated needs of DOE and initiatives described in the National Energy Strategy

  20. ANALYZED FACTORS THAT LEADS TO THE BALANCED SCORECARD NURSING CARE DOCUMENTATION AT RUMAH SAKIT JIWA MENUR SURABAYA

    Directory of Open Access Journals (Sweden)

    Yuli Anggraini

    2017-04-01

    Full Text Available Introduction: Nursing documentation is an important aspect of nursing practice so that should be assessed comprehensively. The objective of the study was to analyze the causing factor of nursing care documentation at Rumah Sakit Jiwa Menur Surabaya through balanced scorecard. Method: This research was an analytical descriptive conducted out on January 2010 at Rumah Sakit Jiwa Menur Surabaya that measured nursing care documentation through four perspectives of balanced scorecard by distributing quisioner to 55 nurses and 69 customers (patient families using inclusion criteria, and holding personal interview to 3 structural offi cial, 2 functional official, and 6 ward supervisors. Data of nurse education, percentage of trained nurse was gained by checklist. Data were analyzed using content analysis to fi nd the causing factor of nursing documentation within balanced scorecard. Result: The result showed that financial, internal business processes, and learning and growth perspectives had causal relationship with nursing care documentation at Rumah Sakit Jiwa Menur Surabaya, but customer perspective didn’t have direct causal relationship with it. Discussion: It can be concluded that impractical nursing documentation form especially in dimension of time on assessment, implementation, and evaluation, and comprehension on assessment, absence of physical nursing standards, limited knowledge on nursing documentation evoked by absence of inhouse training about nursing documentation, ineffective supervision and audit were factors which affecting nursing documentation at Rumah Sakit Jiwa Menur Surabaya. The researcher recommended that the hospital manager should modificate the nursing documentation form using NIC & NOC of NANDA and computerized system, compose physical nursing standards, carry out advanced nursing education and inhouse training about nursing care documentation, improve supervision program, and nursing documentation audit.

  1. "I Like to Plan Events": A Document Analysis of Essays Written by Applicants to a Public Relations Program

    Science.gov (United States)

    Taylor, Ronald E.

    2016-01-01

    A document analysis of 249 essays written during a 5-year period by applicants to a public relations program at a major state university in the southeast suggests that there are enduring reasons why students choose to major in public relations. Public relations is described as a major that allows for and encourages creative expression and that…

  2. LCS Content Document Application

    Science.gov (United States)

    Hochstadt, Jake

    2011-01-01

    My project at KSC during my spring 2011 internship was to develop a Ruby on Rails application to manage Content Documents..A Content Document is a collection of documents and information that describes what software is installed on a Launch Control System Computer. It's important for us to make sure the tools we use everyday are secure, up-to-date, and properly licensed. Previously, keeping track of the information was done by Excel and Word files between different personnel. The goal of the new application is to be able to manage and access the Content Documents through a single database backed web application. Our LCS team will benefit greatly with this app. Admin's will be able to login securely to keep track and update the software installed on each computer in a timely manner. We also included exportability such as attaching additional documents that can be downloaded from the web application. The finished application will ease the process of managing Content Documents while streamlining the procedure. Ruby on Rails is a very powerful programming language and I am grateful to have the opportunity to build this application.

  3. LANL Environmental ALARA Program Status Report for CY 2016

    Energy Technology Data Exchange (ETDEWEB)

    Whicker, Jeffrey Jay [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Mcnaughton, Michael [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Ruedig, Elizabeth [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2017-02-24

    Los Alamos National Laboratory (LANL) ensures that radiation exposures to members of the public and the environment from LANL operations, past and present, are below regulatory thresholds and are as low as reasonably achievable (ALARA) through compliance with DOE Order 458.1 Radiation Protection for the Public and the Environment, and LANL Policy 412 Environmental Radiation Protection (LANL2016a). In 2007, a finding (RL.2-F-1) and observation (RL.2-0-1) in the NNSA/ LASO report, September 2007, Release of Property (Land) Containing Residual Radioactive Material Self-Assessment Report, indicated that LANL had no policy or documented process in place for the release of property containing residual radioactive material. In response, LANL developed PD410, Los Alamos National Laboratory Environmental ALARA Program. The most recent version of this document became effective in 2014 (LANL 2014a). The document provides program authorities, responsibilities, descriptions, processes, and thresholds for conducting qualitative and quantitative ALARA analyses for prospective and actual radiation exposures to the public and t o the environment resulting from DOE activities conducted on the LANL site.

  4. Quality Assurance Program Plan (QAPP) Waste Management Project

    Energy Technology Data Exchange (ETDEWEB)

    VOLKMAN, D.D.

    1999-10-27

    This document is the Quality Assurance Program Plan (QAPP) for Waste Management Federal Services of Hanford, Inc. (WMH), that implements the requirements of the Project Hanford Management Contract (PHMC), HNF-MP-599, Project Hanford Quality Assurance Program Description (QAPD) document, and the Hanford Federal Facility Agreement with Consent Order (Tri-Party Agreement), Sections 6.5 and 7.8. WHM is responsible for the treatment, storage, and disposal of liquid and solid wastes generated at the Hanford Site as well as those wastes received from other US Department of Energy (DOE) and non-DOE sites. WMH operations include the Low-Level Burial Grounds, Central Waste Complex (a mixed-waste storage complex), a nonradioactive dangerous waste storage facility, the Transuranic Storage Facility, T Plant, Waste Receiving and Processing Facility, 200 Area Liquid Effluent Facility, 200 Area Treated Effluent Disposal Facility, the Liquid Effluent Retention Facility, the 242-A Evaporator, 300 Area Treatment Effluent Disposal Facility, the 340 Facility (a radioactive liquid waste handling facility), 222-S Laboratory, the Waste Sampling and Characterization Facility, and the Hanford TRU Waste Program.

  5. 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

  6. Clean Coal Technology Demonstration Program: Program Update 1998

    Energy Technology Data Exchange (ETDEWEB)

    Assistant Secretary for Fossil Energy

    1999-03-01

    Annual report on the Clean Coal Technology Demonstration Program (CCT Program). The report address the role of the CCT Program, implementation, funding and costs, accomplishments, project descriptions, legislative history, program history, environmental aspects, and project contacts. The project descriptions describe the technology and provides a brief summary of the demonstration results.

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

    International Nuclear Information System (INIS)

    1995-01-01

    This large document provides a catalog of the location of large numbers of reports pertaining to the charge of the Presidential Advisory Committee on Human Radiation Research and is arranged as a series of appendices. Titles of the appendices are Appendix A- Records at the Washington National Records Center Reviewed in Whole or Part by DoD Personnel or Advisory Committee Staff; Appendix B- Brief Descriptions of Records Accessions in the Advisory Committee on Human Radiation Experiments (ACHRE) Research Document Collection; Appendix C- Bibliography of Secondary Sources Used by ACHRE; Appendix D- Brief Descriptions of Human Radiation Experiments Identified by ACHRE, and Indexes; Appendix E- Documents Cited in the ACHRE Final Report and other Separately Described Materials from the ACHRE Document Collection; Appendix F- Schedule of Advisory Committee Meetings and Meeting Documentation; and Appendix G- Technology Note

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-01-01

    This large document provides a catalog of the location of large numbers of reports pertaining to the charge of the Presidential Advisory Committee on Human Radiation Research and is arranged as a series of appendices. Titles of the appendices are Appendix A- Records at the Washington National Records Center Reviewed in Whole or Part by DoD Personnel or Advisory Committee Staff; Appendix B- Brief Descriptions of Records Accessions in the Advisory Committee on Human Radiation Experiments (ACHRE) Research Document Collection; Appendix C- Bibliography of Secondary Sources Used by ACHRE; Appendix D- Brief Descriptions of Human Radiation Experiments Identified by ACHRE, and Indexes; Appendix E- Documents Cited in the ACHRE Final Report and other Separately Described Materials from the ACHRE Document Collection; Appendix F- Schedule of Advisory Committee Meetings and Meeting Documentation; and Appendix G- Technology Note.

  9. "In Our Corner": A Qualitative Descriptive Study of Patient Engagement in a Community-Based Care Coordination Program.

    Science.gov (United States)

    Sefcik, Justine S; Petrovsky, Darina; Streur, Megan; Toles, Mark; O'Connor, Melissa; Ulrich, Connie M; Marcantonio, Sherry; Coburn, Ken; Naylor, Mary D; Moriarty, Helene

    2018-03-01

    The purpose of this study was to explore participants' experience in the Health Quality Partners (HQP) Care Coordination Program that contributed to their continued engagement. Older adults with multiple chronic conditions often have limited engagement in health care services and face fragmented health care delivery. This can lead to increased risk for disability, mortality, poor quality of life, and increased health care utilization. A qualitative descriptive design with two focus groups was conducted with a total of 20 older adults enrolled in HQP's Care Coordination Program. Conventional content analysis was the analytical technique. The overarching theme resulting from the analysis was "in our corner," with subthemes "opportunities to learn and socialize" and "dedicated nurses," suggesting that these are the primary contributing factors to engagement in HQP's Care Coordination Program. Study findings suggest that nurses play an integral role in patient engagement among older adults enrolled in a care coordination program.

  10. Quality Assurance Program Description

    Energy Technology Data Exchange (ETDEWEB)

    Halford, Vaughn Edward [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Ryder, Ann Marie [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2017-07-01

    Effective May 1, 2017, led by a new executive leadership team, Sandia began operating within a new organizational structure. National Technology and Engineering Solutions of Sandia (Sandia’s) Quality Assurance Program (QAP) was established to assign responsibilities and authorities, define workflow policies and requirements, and provide for the performance and assessment of work.

  11. R&D PROPOSAL FOR THE NATIONAL MUON ACCELERATOR PROGRAM

    OpenAIRE

    Zisman, Michael S.

    2011-01-01

    This document contains a description of a multi-year national R&D program aimed at completing a Design Feasibility Study (DFS) for a Muon Collider and, with international participation, a Reference Design Report (RDR) for a muon-based Neutrino Factory. It also includes the supporting component development and experimental efforts that will inform the design studies and permit an initial down-selection of candidate technologies for the ionization cooling and acceleration systems. We intend to ...

  12. 42 CFR 420.303 - HHS criteria for requesting books, documents, and records.

    Science.gov (United States)

    2010-10-01

    ... 42 Public Health 3 2010-10-01 2010-10-01 false HHS criteria for requesting books, documents, and... HEALTH AND HUMAN SERVICES (CONTINUED) MEDICARE PROGRAM PROGRAM INTEGRITY: MEDICARE Access to Books, Documents, and Records of Subcontractors § 420.303 HHS criteria for requesting books, documents, and records...

  13. 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. ...

  14. 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

  15. 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

  16. Title list of documents made publicly available

    International Nuclear Information System (INIS)

    1991-01-01

    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 docketed material associated with civilian nuclear power plants and other uses of radioactive materials and nondocketed material received and generated by NRC pertinent to its role as a regulatory agency. 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 though the Department of Energy publication Power Reactor Docket Information, last published in January 1979

  17. 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.

  18. International Nuclear Model. Volume 3. Program description. Appendix A-H (Part 1)

    International Nuclear Information System (INIS)

    Andress, D.

    1985-01-01

    The International Nuclear Model (INM) is a comprehensive model of the commercial nuclear power industry. It simulates economic decisions for reactor deployment and fuel management decisions based on an input set of technical, economic and scenario parameters. The technical parameters include reactor operating characteristics, fuel cycle timing and mass loss factors, and enrichment tails assays. Economic parameters include fuel cycle costs, financial data, and tax alternatives. INM has a broad range of scenario options covering, for example, process constraints, interregional activities, reprocessing, and fuel management selection. INM reports reactor deployment schedules, electricity generation, and fuel cycle requirements and costs. It also has specialized reports for extended burnup and permanent disposal. This volume contains appendices A through H including a description of subroutines and the Fortran listing of the program

  19. Description of the detailed Functional Architecture of the Frequency and Voltage control solution (functional and information layer)

    DEFF Research Database (Denmark)

    Caerts, Chris; Rikos, Evangelos; Syed, Mazheruddin

    2017-01-01

    This D4.2 document provides the description of the detailed functional architecture of the selected solutions that will be implemented and tested. This is documented by combining a function-based IEC 62559 Use Case description with an SGAM mapping of these functions and the interactions among...... these functions on the Function and Information layer....

  20. 49 CFR 237.155 - Documents and records.

    Science.gov (United States)

    2010-10-01

    ..., DEPARTMENT OF TRANSPORTATION BRIDGE SAFETY STANDARDS Documentation, Records, and Audits of Bridge Management Programs § 237.155 Documents and records. Each track owner required to implement a bridge management... protected by a security system that incorporates a user identity and password, or a comparable method, to...

  1. Jake Garn Mission Simulator and Training Facility, Building 5, Historical Documentation

    Science.gov (United States)

    Slovinac, Trish; Deming, Joan

    2010-01-01

    astronaut training facility. 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 5 and how it supported the SSP; and a physical description of the structure. In addition, photographs documenting the construction and historical use of Building 5 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 also provided.

  2. 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

  3. ROOT Reference Documentation

    CERN Document Server

    Fuakye, Eric Gyabeng

    2017-01-01

    A ROOT Reference Documentation has been implemented to generate all the lists of libraries needed for each ROOT class. Doxygen has no option to generate or add the lists of libraries for each ROOT class. Therefore shell scripting and a basic C++ program was employed to import the lists of libraries needed by each ROOT class.

  4. Doctoral Theses from Nursing Postgraduate Programs in Brazil and their Association with the Millennium Development Goals

    OpenAIRE

    Rosalina Aparecida Partezani Rodrigues; Maria Lúcia do Carmo Cruz Robazzi; Alacoque Lorenzini Erdmann; Josicélia Dumet Fernandes; Alba Lucia Bottura Leite de Barros; Flávia Regina Souza Ramos

    2015-01-01

    OBJECTIVES: The Millennium Development Goals are centered around combatting poverty and other social evils all over the world. Thus, this study seeks to identify the Millennium Development Goals as an object of study in theses from Postgraduate Nursing Programs in Brazil scoring 5 (national excellence) and 6 or 7 (international excellence), and evaluate the association between the score for the program and achieving the Millennium Development Goals. METHOD: Exploratory descriptive document re...

  5. User's manual for elegant Program Version 12.4, Manual Version 1

    International Nuclear Information System (INIS)

    Borland, M.

    1993-01-01

    Elegant stands for ''Electron Generation and Tracking,'' a somewhat out-of-date description of a fully 6D accelerator program that now does much more than generate particle distributions and track them elegant, written entirely in the C programming language, uses a variant of the MAD input format to describe accelerators, which may be either transport lines, circular machines, or a combination thereof. Program execution is driven by commands in a namelist format. This document describes the features available in elegant, listing the commands and their arguments. The differences between elegant and MAD formats for describing accelerators are listed. A series of examples of elegant input and output are given. Finally, appendices are included describing the post-processing programs

  6. Blood pressure documentation in the emergency department

    Science.gov (United States)

    Daniel, Ana Carolina Queiroz Godoy; Machado, Juliana Pereira; Veiga, Eugenia Velludo

    2017-01-01

    ABSTRACT Objective To analyze the frequency of blood pressure documentation performed by nursing professionals in an emergency department. Methods This is a cross-sectional, observational, descriptive, and analytical study, which included medical records of adult patients admitted to the observation ward of an emergency department, between March and May 2014. Data were obtained through a collection instrument divided into three parts: patient identification, triage data, and blood pressure documentation. For statistical analysis, Pearson’s correlation coefficient was used, with a significance level of α<0.05. Results One hundred fifty-seven records and 430 blood pressure measurements were analyzed with an average of three measurements per patient. Of these measures, 46.5% were abnormal. The mean time from admission to documentation of the first blood pressure measurement was 2.5 minutes, with 42 minutes between subsequent measures. There is no correlation between the systolic blood pressure values and the mean time interval between blood pressure documentations: 0.173 (p=0.031). Conclusion The present study found no correlation between frequency of blood pressure documentation and blood pressure values. The frequency of blood pressure documentation increased according to the severity of the patient and decreased during the length of stay in the emergency department. PMID:28444085

  7. Repository-Based Software Engineering Program: Working Program Management Plan

    Science.gov (United States)

    1993-01-01

    Repository-Based Software Engineering Program (RBSE) is a National Aeronautics and Space Administration (NASA) sponsored program dedicated to introducing and supporting common, effective approaches to software engineering practices. The process of conceiving, designing, building, and maintaining software systems by using existing software assets that are stored in a specialized operational reuse library or repository, accessible to system designers, is the foundation of the program. In addition to operating a software repository, RBSE promotes (1) software engineering technology transfer, (2) academic and instructional support of reuse programs, (3) the use of common software engineering standards and practices, (4) software reuse technology research, and (5) interoperability between reuse libraries. This Program Management Plan (PMP) is intended to communicate program goals and objectives, describe major work areas, and define a management report and control process. This process will assist the Program Manager, University of Houston at Clear Lake (UHCL) in tracking work progress and describing major program activities to NASA management. The goal of this PMP is to make managing the RBSE program a relatively easy process that improves the work of all team members. The PMP describes work areas addressed and work efforts being accomplished by the program; however, it is not intended as a complete description of the program. Its focus is on providing management tools and management processes for monitoring, evaluating, and administering the program; and it includes schedules for charting milestones and deliveries of program products. The PMP was developed by soliciting and obtaining guidance from appropriate program participants, analyzing program management guidance, and reviewing related program management documents.

  8. Status of maintenance in the US nuclear power industry 1985. Volume 2. Description of programs and practices

    International Nuclear Information System (INIS)

    1986-06-01

    This report documents a review of the status of maintenance programs and practices in the US commercial nuclear power industry. The purpose of this review is to establish a baselines reference for evaluating the effectiveness of future industry activities in maintenance. Two methods used to collect progammatic data. First, a Maintenance Review Protocol was used during site visits to eight selected power plants to collect in-depth maintenance program information. Second, a Maintenance Questionnaire was filled out by NRC Resident Inspectors regarding maintenance programs at their plant. The protocol and questionnaire contained items regarding five broad categories of maintenance: (1) organization and administration, (2) facilities and equipment, (3) procedures, (4) personnel, and (5) work control. The study found that there is wide variability in industry maintenance programs. However, the industry is currently undergoing changes in maintenance practices, and adherence to INPO and NUMARC guidance in maintenance may bring about more systematically developed program practices

  9. 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.

  10. Clean Coal Technology Demonstration Program: Program Update 2001

    Energy Technology Data Exchange (ETDEWEB)

    Assistant Secretary for Fossil Energy

    2002-07-30

    Annual report on the Clean Coal Technology Demonstration Program (CCT Program). The report address the role of the CCT Program, implementation, funding and costs, accomplishments, project descriptions, legislative history, program history, environmental aspects, and project contacts. The project descriptions describe the technology and provides a brief summary of the demonstration results. Also includes Power Plant Improvement Initiative Projects.

  11. Quality improvement in documentation of postoperative care nursing using computer-based medical records

    DEFF Research Database (Denmark)

    Olsen, Susanne Winther

    2013-01-01

    on the template with quantitative data showed satisfactory documentation of postoperative care nursing in 67% (18% to 92%; mean [min-max]) of the scores. The template for documentation using qualitative descriptions was used by 63% of the nurses, but the keywords were used to a varying degree, that is, from 0......Postanesthesia nursing should be documented with high quality. The purpose of this retrospective case-based study on 49 patients was to analyze the quality of postoperative documentation in the two existing templates and, based on this audit, to suggest a new template for documentation. The audit...

  12. 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

  13. 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

  14. INTRA/Mod3.2. Manual and code description. Volume 2 - User's manual

    International Nuclear Information System (INIS)

    Andersson, Jenny; Edlund, O.; Hermann, J.; Johansson, Lise-Lotte

    1999-01-01

    The INTRA Manual consists of two volumes. Volume I of the manual is a thorough description of the code INTRA, the physical modelling of INTRA and the ruling numerics, and volume II, the User's Manual is an input description. This document, the User's Manual, Volume II, contains a detailed description of how to use INTRA, how to set up an input file, how to run INTRA and also post-processing

  15. Title list of documents made publicly available, October 1--31, 1993

    International Nuclear Information System (INIS)

    1993-12-01

    This document is a monthly publication containing descriptions of information received and generated by the US Nuclear Regulatory Commission (NRC). This information docketed material associated with civilian nuclear power plants and other uses of radioactive materials, and 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 of Enclosures to Principal Documents

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

    International Nuclear Information System (INIS)

    1995-01-01

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

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

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-01-01

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

  18. 6 CFR 13.20 - Disclosure of Documents.

    Science.gov (United States)

    2010-01-01

    ... 6 Domestic Security 1 2010-01-01 2010-01-01 false Disclosure of Documents. 13.20 Section 13.20 Domestic Security DEPARTMENT OF HOMELAND SECURITY, OFFICE OF THE SECRETARY PROGRAM FRAUD CIVIL REMEDIES § 13.20 Disclosure of Documents. (a) Upon written request to the Reviewing Official, the Defendant may...

  19. 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

  20. 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

  1. Radiological control FY 1995 site support program plan WBS 6.7.2.4

    International Nuclear Information System (INIS)

    1994-09-01

    The 1995 Site Support Program Plan (SSPP) brings year planning and execution year planning into a single document. The plan presented consists of the following four major sections: Overview and Introduction - Health physics has been renamed Radiological Control (RadCon) with the role of protecting workers, the public and the environment from the harmful effects of radiation resulting from the DOE Hanford Site Operations; Cost Baselines which contains cost, technical and schedule baselines; Execution Year work Plan - cost summaries and detailed descriptions of the work to be done; Appendix - including brief description of other project activities directly coupled to RadCon

  2. Radiological control FY 1995 site support program plan WBS 6.7.2.4

    Energy Technology Data Exchange (ETDEWEB)

    1994-09-01

    The 1995 Site Support Program Plan (SSPP) brings year planning and execution year planning into a single document. The plan presented consists of the following four major sections: Overview and Introduction - Health physics has been renamed Radiological Control (RadCon) with the role of protecting workers, the public and the environment from the harmful effects of radiation resulting from the DOE Hanford Site Operations; Cost Baselines which contains cost, technical and schedule baselines; Execution Year work Plan - cost summaries and detailed descriptions of the work to be done; Appendix - including brief description of other project activities directly coupled to RadCon.

  3. Semantic Metadata for Heterogeneous Spatial Planning Documents

    Science.gov (United States)

    Iwaniak, A.; Kaczmarek, I.; Łukowicz, J.; Strzelecki, M.; Coetzee, S.; Paluszyński, W.

    2016-09-01

    Spatial planning documents contain information about the principles and rights of land use in different zones of a local authority. They are the basis for administrative decision making in support of sustainable development. In Poland these documents are published on the Web according to a prescribed non-extendable XML schema, designed for optimum presentation to humans in HTML web pages. There is no document standard, and limited functionality exists for adding references to external resources. The text in these documents is discoverable and searchable by general-purpose web search engines, but the semantics of the content cannot be discovered or queried. The spatial information in these documents is geographically referenced but not machine-readable. Major manual efforts are required to integrate such heterogeneous spatial planning documents from various local authorities for analysis, scenario planning and decision support. This article presents results of an implementation using machine-readable semantic metadata to identify relationships among regulations in the text, spatial objects in the drawings and links to external resources. A spatial planning ontology was used to annotate different sections of spatial planning documents with semantic metadata in the Resource Description Framework in Attributes (RDFa). The semantic interpretation of the content, links between document elements and links to external resources were embedded in XHTML pages. An example and use case from the spatial planning domain in Poland is presented to evaluate its efficiency and applicability. The solution enables the automated integration of spatial planning documents from multiple local authorities to assist decision makers with understanding and interpreting spatial planning information. The approach is equally applicable to legal documents from other countries and domains, such as cultural heritage and environmental management.

  4. 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

  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. CDIO Projects in Civil Engineering Study Program at DTU

    DEFF Research Database (Denmark)

    Krogsbøll, Anette; Simonsen, Claus; Christensen, Jørgen Erik

    2011-01-01

    or a design build project on each of the first four semesters. In this paper the four projects in the civil engineering study program are described along with a brief description of the entire study program. The aim is to provide additional information and documentation to accompany an exposition where......In 2008 all Bachelor of engineering study programs at the Technical University of Denmark (DTU) have been adopted to the “Conceive – Design – Implement – Operate” approach. As part of the necessary changes it was decided that all seven study programs should have a cross disciplinary project...... students present their projects. Learning outcomes, training and assessment of personal, professional and social engineering skills are described from a project point of view. Progression of engineering skills is discussed from a study program perspective. The interrelation between the various elements...

  8. Multi-Year Program Plan - Building Regulatory Programs

    Energy Technology Data Exchange (ETDEWEB)

    none,

    2010-10-01

    This document presents DOE’s multi-year plan for the three components of the Buildings Regulatory Program: Appliance and Equipment Efficiency Standards, ENERGY STAR, and the Building Energy Codes Program. This document summarizes the history of these programs, the mission and goals of the programs, pertinent statutory requirements, and DOE’s 5-year plan for moving forward.

  9. 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.

  10. Savannah River Site Interim Waste Management Program Plan FY 1991--1992

    Energy Technology Data Exchange (ETDEWEB)

    Chavis, D.M.

    1992-05-01

    The primary purpose of the Waste Management Program Plan is to provide an annual report of how Waste Management's operations are conducted, what facilities are being used to manage wastes, what forces are acting to change current waste management systems, and what plans are in store for the coming fiscal year. In addition, this document projects activities for several years beyond the coming fiscal year in order to adequately plan for safe handling, storage, and disposal of radioactive wastes generated at the Savannah River Site and for developing technology for improved management of wastes. In this document, work descriptions and milestone schedules are current as of December 1991.

  11. Savannah River Site Interim Waste Management Program Plan FY 1991--1992

    Energy Technology Data Exchange (ETDEWEB)

    Chavis, D.M.

    1992-05-01

    The primary purpose of the Waste Management Program Plan is to provide an annual report of how Waste Management`s operations are conducted, what facilities are being used to manage wastes, what forces are acting to change current waste management systems, and what plans are in store for the coming fiscal year. In addition, this document projects activities for several years beyond the coming fiscal year in order to adequately plan for safe handling, storage, and disposal of radioactive wastes generated at the Savannah River Site and for developing technology for improved management of wastes. In this document, work descriptions and milestone schedules are current as of December 1991.

  12. Savannah River Site Interim Waste Management Program Plan FY 1991--1992

    International Nuclear Information System (INIS)

    Chavis, D.M.

    1992-05-01

    The primary purpose of the Waste Management Program Plan is to provide an annual report of how Waste Management's operations are conducted, what facilities are being used to manage wastes, what forces are acting to change current waste management systems, and what plans are in store for the coming fiscal year. In addition, this document projects activities for several years beyond the coming fiscal year in order to adequately plan for safe handling, storage, and disposal of radioactive wastes generated at the Savannah River Site and for developing technology for improved management of wastes. In this document, work descriptions and milestone schedules are current as of December 1991

  13. 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)

  14. National NIF Diagnostic Program Fiscal Year 2002 Second Quarter Report

    International Nuclear Information System (INIS)

    MacGowan, B

    2002-01-01

    Since October 2001 the development of the facility diagnostics for NIF has been funded by the NIF Director through the National NIF Diagnostic Program (NNDP). The current emphasis of the NNDP is on diagnostics for the early NIF quad scheduled to be available for experiment commissioning in FY03. During the past six months the NNDP has set in place processes for funding diagnostics, developing requirements for diagnostics, design reviews and monthly status reporting. Those processes are described in an interim management plan for diagnostics (National NIF Diagnostic Program Interim Plan, NIF-008 13 15, April 2002) and a draft Program Execution Plan (Program Execution Plan for the National NlF Diagnostic Program, NIF-0072083, October 2001) and documents cited therein. Work has been funded at Lawrence Livermore National Laboratory (LLNL), Los Alamos National Laboratory (LANL), Naval Research Laboratory (NRL), Sandia National Laboratories (SNL), Bechtel Nevada at Los Alamos and Santa Barbara. There are no major technical risks with the early diagnostics. The main concerns relate to integration of the diagnostics into the facility, all such issues are being worked. This report is organized to show the schedule and budget status and a summary of Change Control Board actions for the past six months. The following sections then provide short descriptions of the status of each diagnostic. Where design reviews or requirements documents are cited, the documents are available on the Diagnostics file server or on request

  15. Minimally invasive semantification of light weight service descriptions

    NARCIS (Netherlands)

    Musyaffa, Fathoni A.; Halilaj, Lavdim; Siebes, Ronald; Orlandi, Fabrizio; Auer, Soren

    2016-01-01

    Unification and automation of RESTful web services' documentation and descriptions is currently receiving increasing attention. The open-source OpenAPI Specification (formerly known as Swagger) has become core of this effort and has been adopted by a number of major companies. It allows the

  16. 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...

  17. Second Line of Defense Spares Program

    Energy Technology Data Exchange (ETDEWEB)

    Henderson, Dale L.; Holmes, Aimee E.; Muller, George; Mercier, Theresa M.; Brigantic, Robert T.; Perkins, Casey J.; Cooley, Scott K.; Thorsen, Darlene E.

    2012-11-20

    During Fiscal Year 2012, a team from the Pacific Northwest National Laboratory (PNNL) conducted an assessment and analysis of the Second Line of Defense (SLD) Sustainability spare parts program. Spare parts management touches many aspects of the SLD Sustainability Program including contracting and integration of Local Maintenance Providers (LMP), equipment vendors, analyses and metrics on program performance, system state of health, and maintenance practices. Standardized spares management will provide better data for decisions during site transition phase and will facilitate transition to host country sustainability ownership. The effort was coordinated with related SLD Sustainability Program initiatives, including a configuration items baselining initiative, a metrics initiative, and a maintenance initiative. The spares study has also led to pilot programs for sourcing alternatives that include regional intermediate inventories and partnering agreements that leverage existing supply chains. Many partners from the SLD Sustainability program contributed to and were consulted in the course of the study. This document provides a description of the findings, recommendations, and implemented solutions that have resulted from the study.

  18. Adaptive Algorithms for Automated Processing of Document Images

    Science.gov (United States)

    2011-01-01

    ABSTRACT Title of dissertation: ADAPTIVE ALGORITHMS FOR AUTOMATED PROCESSING OF DOCUMENT IMAGES Mudit Agrawal, Doctor of Philosophy, 2011...2011 4. TITLE AND SUBTITLE Adaptive Algorithms for Automated Processing of Document Images 5a. CONTRACT NUMBER 5b. GRANT NUMBER 5c. PROGRAM...ALGORITHMS FOR AUTOMATED PROCESSING OF DOCUMENT IMAGES by Mudit Agrawal Dissertation submitted to the Faculty of the Graduate School of the University

  19. Title list of documents made publicly available May 1--31, 1991

    International Nuclear Information System (INIS)

    1991-07-01

    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

  20. Title list of documents made publicly available. Volume 17, No. 1

    International Nuclear Information System (INIS)

    1995-03-01

    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 of enclosures to principal documents

  1. Title list of documents made publicly available: April 1-30, 1987

    International Nuclear Information System (INIS)

    1987-06-01

    This document is a monthly publication containing descriptions of 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. The following indexes are included: Personal Author Index, Corporate Author Index, Report Number Index, and Cross Reference to Principal Documents Index

  2. Title list of documents made publicly available, January 1--31, 1994

    International Nuclear Information System (INIS)

    1994-03-01

    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 regulator agency. The following indexes are included: Personal Author, Corporate Source, Report Number, and Cross Reference of Enclosures to Principal Documents

  3. Title list of documents made publicly available, February 1--28, 1993

    International Nuclear Information System (INIS)

    1993-04-01

    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 of Enclosures to Principal Documents

  4. Title list of documents made publicly available, May 1--31, 1993

    International Nuclear Information System (INIS)

    1993-07-01

    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 material 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 of Enclosures to Principal Documents

  5. Title list of documents made publicly available, January 1--31, 1993

    International Nuclear Information System (INIS)

    1993-03-01

    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 of Enclosures to Principal Documents

  6. Title List of Documents Made Publicly Available, March 1--31, 1992

    International Nuclear Information System (INIS)

    1992-05-01

    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 of Enclosures to Principal Documents

  7. Title List of documents made publicly available, September 1--30, 1993

    International Nuclear Information System (INIS)

    1993-11-01

    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 of Enclosures to Principals Documents

  8. Title list of documents made publicly available, November 1--30, 1993

    International Nuclear Information System (INIS)

    1994-01-01

    This document is a monthly publication containing descriptions of information received and generated by the US Nuclear Regulatory Commission (NRC). Ills 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 of Enclosures to Principal Documents

  9. Title list of documents made publicly available, July 1-31, 1986

    International Nuclear Information System (INIS)

    1986-09-01

    This document is a monthly publication containing descriptions of 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. The following indexes are included: Personal Author Index, Corporate Source Index, Report Number Index, and Cross Reference to Principal Documents Index

  10. Title list of documents made publicly available, March 1-31, 1988

    International Nuclear Information System (INIS)

    1988-05-01

    This document is a monthly publication containing descriptions of 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. The following indexes are included: Personal Author Index, Corporate Author Index, Report Number Index, and Cross Reference to Principal Documents Index

  11. Title list of documents made publicly available, July 1--31, 1991

    International Nuclear Information System (INIS)

    1991-09-01

    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

  12. Title list of documents made publicly available, November 1--30, 1991

    International Nuclear Information System (INIS)

    1992-01-01

    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 of Enclosures to Principal Documents

  13. Title list of documents made publicly available, October 1--31, 1992

    International Nuclear Information System (INIS)

    1992-12-01

    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 of Enclosures to Principal documents

  14. Title list of documents made publicly available, November 1--30, 1992

    International Nuclear Information System (INIS)

    1993-01-01

    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 of Enclosures to Principal Documents

  15. Title list of documents made publicly available. Volume 17, No. 10

    International Nuclear Information System (INIS)

    1995-12-01

    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 of Enclosures to Principal Documents

  16. Title list of documents made publicly available, March 1--31, 1994

    International Nuclear Information System (INIS)

    1994-05-01

    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 used 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 of Enclosures to Principal Documents

  17. Title list of documents made publicly available, July 1--21, 1993

    International Nuclear Information System (INIS)

    1993-09-01

    This document is a monthly publication containing descriptions of information received and generated by the US Nuclear Regulatory commission (NRC). This information includes: Docketed material associated with civilian nuclear power plants and other uses of radioactive materials, and 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 of Enclosures to Principal Documents

  18. Title list of documents made publicly available, December 1--31, 1992

    International Nuclear Information System (INIS)

    1993-02-01

    This document is a monthly publication containing descriptions of information received and generated by the US Nuclear Regulatory Commission (NRC). This information includes docketed material associated with civilian nuclear power plants and other uses of radioactive materials and 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 of Enclosures to Principal Documents

  19. Title list of documents made publicly available, June 1--30, 1993

    International Nuclear Information System (INIS)

    1993-08-01

    This document is a monthly publication containing descriptions of information received and generated by the US Nuclear Regulatory Commission (NRC). This information includes docketed material associated with civilian nuclear power plants and other uses of radioactive materials, and 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 of Enclosures to Principal Documents

  20. Title list of documents made publicly available, September 1--30, 1992

    International Nuclear Information System (INIS)

    1992-11-01

    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 of Enclosures to Principal Documents

  1. Title list of documents made publicly available: March 1-31, 1987

    International Nuclear Information System (INIS)

    1987-05-01

    This document is a monthly publication containing descriptions of 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. The following indexes are included: Personal Author Index, Corporate Author Index, Report Number Index, and Cross Reference to Principal Documents Index

  2. Title list of documents made publicly available, February 1--29, 1992

    International Nuclear Information System (INIS)

    1992-04-01

    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 of Enclosures to Principal Documents

  3. Title list of documents made publicly available: September 1--30, 1988

    International Nuclear Information System (INIS)

    1988-11-01

    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

  4. Title list of documents made publicly available, October 1-31, 1986

    International Nuclear Information System (INIS)

    1986-12-01

    This document is a monthly publication containing descriptions of 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. The following indexes are included: Personal Author Index, Corporate Source Index, Report Number Index, and Cross Reference to Principal Documents Index

  5. Title list of documents made publicly available, October 1--31, 1991

    International Nuclear Information System (INIS)

    1991-12-01

    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 of enclosures to Principal Documents

  6. Title list of documents made publicly available, March 1--31, 1991

    International Nuclear Information System (INIS)

    1991-05-01

    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

  7. Title list of documents made publicly available, July 1-31, 1987

    International Nuclear Information System (INIS)

    1987-09-01

    This document is a monthly publication containing descriptions of 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. The following indexes are included: Personal Author Index, Corporate Author Index, Report Number Index, and Cross Reference to Principal Documents Index

  8. Title list of documents made publicly available: June 1-30, 1987

    International Nuclear Information System (INIS)

    1987-08-01

    This document is a monthly publication containing descriptions of 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. The following indexes are included: Personal Author Index, Corporate Author Index, Report Number Index, and Cross Reference to Principal Documents Index

  9. Title list of documents made publicly available, June 1--30, 1991

    International Nuclear Information System (INIS)

    1991-08-01

    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

  10. Title list of documents made publicly available, April 1--30, 1992

    International Nuclear Information System (INIS)

    1992-06-01

    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 of Enclosures to Principal Documents

  11. Title list of documents made publicly available, August 1--31, 1992

    International Nuclear Information System (INIS)

    1992-10-01

    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 of Enclosures to Principal Documents

  12. Title list of documents made publicly available, April 1--30, 1993

    International Nuclear Information System (INIS)

    1993-06-01

    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 of Enclosures to Principal Documents

  13. Title list of documents made publicly available, November 1-30, 1986

    International Nuclear Information System (INIS)

    1987-01-01

    This document is a monthly publication containing description of 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. The following indexes are included: Personal Author Index, Corporate Source Index, Report Number Index, and Cross Reference to Principal Documents Index

  14. Title list of documents made publicly available, December 1--31, 1991

    International Nuclear Information System (INIS)

    1992-02-01

    This document is a monthly 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 of Enclosures to Principal Documents

  15. Title list of documents made publicly available. Volume 17, No. 10

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-12-01

    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 of Enclosures to Principal Documents.

  16. Title list of documents made publicly available, August 1--31, 1991

    International Nuclear Information System (INIS)

    1991-10-01

    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

  17. Title list of documents made publicly available, August 1--31, 1993

    International Nuclear Information System (INIS)

    1993-10-01

    This document is a monthly publication containing descriptions of information received and generated by the US Nuclear Regulatory commission (NRC). This information includes docketed material associated with civilian nuclear power plants and other uses of radioactive materials, and 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 of Enclosures to Principal Documents

  18. Title list of documents made publicly available: February 1-28, 1987

    International Nuclear Information System (INIS)

    1987-04-01

    This document is a monthly publication containing descriptions of 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. The following indexes are included: Personal Author Index, Corporate Author Index, Report Number Index, and Cross Reference to Principal Documents Index

  19. Title list of documents made publicly available. Volume 17, No. 1

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-03-01

    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 of enclosures to principal documents.

  20. Title list of documents made publicly available, June 1--30, 1989

    International Nuclear Information System (INIS)

    1989-08-01

    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

  1. A retrospective quality assessment of pre-hospital emergency medical documentation in motor vehicle accidents in south-eastern Norway

    Directory of Open Access Journals (Sweden)

    Staff Trine

    2011-03-01

    Full Text Available Abstract Background Few studies have evaluated pre-hospital documentation quality. We retrospectively assessed emergency medical service (EMS documentation of key logistic, physiologic, and mechanistic variables in motor vehicle accidents (MVAs. Methods Records from police, Emergency Medical Communication Centers (EMCC, ground and air ambulances were retrospectively collected for 189 MVAs involving 392 patients. Documentation of Glasgow Coma Scale (GCS, respiratory rate (RR, and systolic blood pressure (SBP was classified as exact values, RTS categories, clinical descriptions enabling post-hoc inference of RTS categories, or missing. The distribution of values of exact versus inferred RTS categories were compared (Chi-square test for trend. Results 25% of ground and 11% of air ambulance records were unretrieveable. Patient name, birth date, and transport destination was documented in >96% of ambulance records and 81% of EMCC reports. Only 54% of patient encounter times were transmitted to the EMCC, but 77% were documented in ground and 96% in air ambulance records. Ground ambulance records documented exact values of GCS in 48% and SBP in 53% of cases, exact RR in 10%, and RR RTS categories in 54%. Clinical descriptions made post-hoc inference of RTS categories possible in another 49% of cases for GCS, 26% for RR, and 20% for SBP. Air ambulance records documented exact values of GCS in 89% and SBP in 84% of cases, exact RR in 7% and RR RTS categories in 80%. Overall, for lower RTS categories of GCS, RR and SBP the proportion of actual documented values to inferred values increased (All: p Conclusion EMS documentation of logistic and mechanistic variables was adequate. Patient physiology was frequently documented only as descriptive text. Our finding indicates a need for improved procedures, training, and tools for EMS documentation. Documentation is in itself a quality criterion for appropriate care and is crucial to trauma research.

  2. Descriptive documentation for New Mexico uranium milling model

    International Nuclear Information System (INIS)

    Bonem, G.; Livevano, R.J.

    1981-01-01

    The New Mexico Uranium Milling Model is a linear programming model. It can demonstrate how cost minimizing management can reduce the costs of milling uranium subject to a series of environmental, resource, and technological constraints. For example, if 15,000 tons were the targeted level of milling output, the model would provide the minimum cost of this production level, given certain levels of environmental, fuel, water, and technological constraints. The model was developed to allow state policymakers to assess the uranium industry from various standpoints. Through the use of the model, state policymakers can determine the effects of air and water discharge standards and limited capital availability on: milling costs of production; uses of electricity, fuel, and water; and levels of air and water emissions. The model covers the following: process technologies which are acid leach and carbonate leach; raw materials mix; air and water discharges; residual treatment process; and plant types

  3. Interim report for documentation of computer programs for crude oil profile analysis. [Codes, CV, CRULE, CPR, CIMPACT, ENT ADJ, REF VOLS, CIMP PRT, C MODEL, C PRINT

    Energy Technology Data Exchange (ETDEWEB)

    This report is summarizing the findings and documenting the programs developed by Economic Regulatory Administration (ERA) for the Crude Oil Profile Analysis. Based on a variety of estimates and assumptions from different sources, ERA developed a series of computer programs which generate a 24-month projection of the crude oil production in each of the price categories. AVANTE International Systems Corporation is contracted to provide an organized documentation for all of these data base, assumptions, estimation rationale and computing procedures.

  4. 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.

  5. 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.

  6. 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

  7. Structure and drafting of safeguards regulatory documents

    International Nuclear Information System (INIS)

    Cole, R.J.; Bennett, C.A.; Edelhertz, H.; Wood, M.T.; Brown, R.J.; Roberts, F.P.

    1977-09-01

    This study develops hypothesis about the relation between the structure and drafting of safeguards regulatory documents and the ability of document users to understand and implement them in a way that reflects the intent and requirements of the NRC. Four decisions are needed to improve communication: (1) Should improvement of safeguards regulatory documents as communication instruments be an explicit NRC program. (2) What specific methods of communication should be the focus of improvement efforts. (3) What actions to improve communications are feasible and desirable. (4) How should the NRC divide its available effort and resources among desirable actions in order to provide the most effective communication through regulatory documents. This volume contains: introduction, conceptual bases, legal requirements, targets, choice of documents, preparation of documents, readability, and further study of recommended changes in structure and drafting

  8. INTRA/Mod3.2. Manual and Code Description. Volume I - Physical Modelling

    International Nuclear Information System (INIS)

    Andersson, Jenny; Edlund, O.; Hermann, J.; Johansson, Lise-Lotte

    1999-01-01

    The INTRA Manual consists of two volumes. Volume I of the manual is a thorough description of the code INTRA, the Physical modelling of INTRA and the ruling numerical methods and volume II, the User's Manual is an input description. This document, the Physical modelling of INTRA, contains code characteristics, integration methods and applications

  9. INTRA/Mod3.2. Manual and Code Description. Volume I - Physical Modelling

    Energy Technology Data Exchange (ETDEWEB)

    Andersson, Jenny; Edlund, O; Hermann, J; Johansson, Lise-Lotte

    1999-01-01

    The INTRA Manual consists of two volumes. Volume I of the manual is a thorough description of the code INTRA, the Physical modelling of INTRA and the ruling numerical methods and volume II, the User`s Manual is an input description. This document, the Physical modelling of INTRA, contains code characteristics, integration methods and applications

  10. YALINA facility a sub-critical Accelerator- Driven System (ADS) for nuclear energy research facility description and an overview of the research program (1997-2008).

    Energy Technology Data Exchange (ETDEWEB)

    Gohar, Y.; Smith, D. L.; Nuclear Engineering Division

    2010-04-28

    The YALINA facility is a zero-power, sub-critical assembly driven by a conventional neutron generator. It was conceived, constructed, and put into operation at the Radiation Physics and Chemistry Problems Institute of the National Academy of Sciences of Belarus located in Minsk-Sosny, Belarus. This facility was conceived for the purpose of investigating the static and dynamic neutronics properties of accelerator driven sub-critical systems, and to serve as a neutron source for investigating the properties of nuclear reactions, in particular transmutation reactions involving minor-actinide nuclei. This report provides a detailed description of this facility and documents the progress of research carried out there during a period of approximately a decade since the facility was conceived and built until the end of 2008. During its history of development and operation to date (1997-2008), the YALINA facility has hosted several foreign groups that worked with the resident staff as collaborators. The participation of Argonne National Laboratory in the YALINA research programs commenced in 2005. For obvious reasons, special emphasis is placed in this report on the work at YALINA facility that has involved Argonne's participation. Attention is given here to the experimental program at YALINA facility as well as to analytical investigations aimed at validating codes and computational procedures and at providing a better understanding of the physics and operational behavior of the YALINA facility in particular, and ADS systems in general, during the period 1997-2008.

  11. Subsurface Conditions Description of the B and BX and BY Waste Management Area

    Energy Technology Data Exchange (ETDEWEB)

    WOOD, M.I.

    2000-03-13

    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-B, -BX, and -BY 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.

  12. Subsurface Conditions Description of the B and BX and BY Waste Management Area

    International Nuclear Information System (INIS)

    WOOD, M.I.

    2000-01-01

    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-B, -BX, and -BY 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. 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

  14. 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.

  15. A Typed Text Retrieval Query Language for XML Documents.

    Science.gov (United States)

    Colazzo, Dario; Sartiani, Carlo; Albano, Antonio; Manghi, Paolo; Ghelli, Giorgio; Lini, Luca; Paoli, Michele

    2002-01-01

    Discussion of XML focuses on a description of Tequyla-TX, a typed text retrieval query language for XML documents that can search on both content and structures. Highlights include motivations; numerous examples; word-based and char-based searches; tag-dependent full-text searches; text normalization; query algebra; data models and term language;…

  16. 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.

  17. [Programs for optimizing the use of antibiotics (PROA) in Spanish hospitals: GEIH-SEIMC, SEFH and SEMPSPH consensus document].

    Science.gov (United States)

    Rodríguez-Baño, Jesús; Paño-Pardo, José Ramón; Alvarez-Rocha, Luis; Asensio, Angel; Calbo, Esther; Cercenado, Emilia; Cisneros, José Miguel; Cobo, Javier; Delgado, Olga; Garnacho-Montero, José; Grau, Santiago; Horcajada, Juan Pablo; Hornero, Ana; Murillas-Angoiti, Javier; Oliver, Antonio; Padilla, Belén; Pasquau, Juan; Pujol, Miquel; Ruiz-Garbajosa, Patricia; San Juan, Rafael; Sierra, Rafael

    2012-01-01

    The antimicrobial agents are unique drugs for several reasons. First, their efficacy is higher than other drugs in terms of reduction of morbidity and mortality. Also, antibiotics are the only group of drugs associated with ecological effects, because their administration may contribute to the emergence and spread of microbial resistance. Finally, they are used by almost all medical specialties. Appropriate use of antimicrobials is very complex because of the important advances in the management of infectious diseases and the spread of antibiotic resistance. Thus, the implementation of programs for optimizing the use of antibiotics in hospitals (called PROA in this document) is necessary. This consensus document defines the objectives of the PROA (namely, to improve the clinical results of patients with infections, to minimise the adverse events associated to the use of antimicrobials including the emergence and spread of antibiotic resistance, and to ensure the use of the most cost-efficacious treatments), and provides recommendations for the implementation of these programs in Spanish hospitals. The key aspects of the recommendations are as follows. Multidisciplinary antibiotic teams should be formed, under the auspices of the Infection Committees. The PROA need to be considered as part of institutional programs and the strategic objectives of the hospital. The PROA should include specific objectives based on measurable indicators, and activities aimed at improving the use of antimicrobials, mainly through educational activities and interventions based more on training activities directed to prescribers than just on restrictive measures. Copyright © 2011 Elsevier España, S.L. All rights reserved.

  18. SEMANTIC METADATA FOR HETEROGENEOUS SPATIAL PLANNING DOCUMENTS

    Directory of Open Access Journals (Sweden)

    A. Iwaniak

    2016-09-01

    Full Text Available Spatial planning documents contain information about the principles and rights of land use in different zones of a local authority. They are the basis for administrative decision making in support of sustainable development. In Poland these documents are published on the Web according to a prescribed non-extendable XML schema, designed for optimum presentation to humans in HTML web pages. There is no document standard, and limited functionality exists for adding references to external resources. The text in these documents is discoverable and searchable by general-purpose web search engines, but the semantics of the content cannot be discovered or queried. The spatial information in these documents is geographically referenced but not machine-readable. Major manual efforts are required to integrate such heterogeneous spatial planning documents from various local authorities for analysis, scenario planning and decision support. This article presents results of an implementation using machine-readable semantic metadata to identify relationships among regulations in the text, spatial objects in the drawings and links to external resources. A spatial planning ontology was used to annotate different sections of spatial planning documents with semantic metadata in the Resource Description Framework in Attributes (RDFa. The semantic interpretation of the content, links between document elements and links to external resources were embedded in XHTML pages. An example and use case from the spatial planning domain in Poland is presented to evaluate its efficiency and applicability. The solution enables the automated integration of spatial planning documents from multiple local authorities to assist decision makers with understanding and interpreting spatial planning information. The approach is equally applicable to legal documents from other countries and domains, such as cultural heritage and environmental management.

  19. Guidance documents relating to landfills and contaminants

    Energy Technology Data Exchange (ETDEWEB)

    Schomaker, N.B.; Zunt, D.A.

    1990-01-01

    The Environmental Protection Agency is developing and updating a series of Technical Guidance Documents to provide best engineering control technology to meet the needs of the Resource Conservation and Recovery Act (RCRA) and the Comprehensive Environmental Response Compensation and Liability Act (CERCLA), respectively. These documents are the compilation of the research efforts to date relating to containment of pollutants from waste disposal to the land as relates to residuals management. The specific areas of research being conducted under the RCRA land disposal program relates to laboratory, pilot and field validation studies in cover systems, waste leaching and solidification, liner systems and disposal facility evaluation. The specific areas of research being conducted under the CERCLA uncontrolled waste sites (Superfund) program relate to in situ treatment, solidification/stabilization for treating hazardous waste, combustion technologies, best demonstrated available technology (BDAT), on-site treatment technologies, emerging biosystems, expert systems, personnel health protection equipment, and site and situation assessment. The Guidance Documents are intended to assist both the regulated community and the permitting authorities, as well as the Program Offices, and Regions, as well as the states and other interested parties, with the latest information relevant to waste management.

  20. MDEP Generic Common Position No DICWG-05. Common position on the treatment of hardware description language (HDL) programmed devices for use in nuclear safety systems

    International Nuclear Information System (INIS)

    2013-01-01

    Following other industries, the nuclear industry developed increasing interest in the use of programmable logic components that are implemented using hardware description language (HDL) such as such as FPGAs, CPLDs or ASICs. HDL programmed devices (HPD) has both characteristics of software and hardware. Therefore applications using HPDs has many similarities with the traditional software (in particular the design may be affected by errors) and characteristics of traditional electronic design (e.g. electronic-level timing and electrical issues). However, due to the unique nature of HPDs, there exist several differences between HPDs and traditional software. Some key differences include: - HPDs use parallel processing with dedicated hardware for each function instead of executing instructions sequentially as in the case of traditional software. - Safety critical software uses imperative languages which specify each instruction of the program whereas HPDs use declarative languages. - The target of software is a microprocessor, which guarantees properties such as memory consistency after each instruction. Such properties are not inherent in HPDs and thus the design process needs different steps to build and guarantee behavioural properties. - Translation of the HDL description to bit-streams in HPDs is much more involved than the translation of source code to binary in software compilation. In the HPD case, this process is not fully automatic, and therefore designer must guide the tools, which may result in undetectable errors. The Digital Instrumentation and Controls Working Group (DICWG) has agreed that a common position on this topic is warranted given the increase of use of Digital I and C in new reactor designs, its safety implications, and the need to develop a common understanding from the perspectives of regulatory authorities. This action follows the DICWG examination of the regulatory requirements of the participating members and of relevant industry

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