WorldWideScience

Sample records for repository project office

  1. Office of Crystalline Repository Development FY 83 technical project plan

    International Nuclear Information System (INIS)

    1983-03-01

    The technical plan for FY 83 activities of the Office of Crystalline Repository Development is presented in detail. Crystalline Rock Project objectives are discussed in relation to the National Waste Terminal storage (NWTS) program. The plan is in full compliance with requirements mandated by the Nuclear Waste Policy Act of 1982. Implementation will comply with the requirements and criteria set forth in the Nuclear Regulatory Commission regulations (10 CFR 60) and the Environmental Protection Agency standard (40 CFR 191). Technical approaches and the related milestones and schedules are presented for each of the Level 3 NWTS work Breakdown Structure Tasks. These are: Systems, Waste Package, Site, Repository, Regulatory and Institutional, Test Facilities and Excavations, Land Acquisition, and Program Management

  2. Statement of J.O. Neff, Manager, Salt Repository Project Office, Department of Energy

    International Nuclear Information System (INIS)

    Anon.

    1987-01-01

    My name is Jeff Neff and I am the Manager of the US Department of Energy's Salt Repository Project Office, now located in Hereford, Texas. The responsibilities of my office are to manage the day-to-day activities of the site suitability investigations of the designated nine-square-mile site located in Deaf Smith County, near Hereford in the Texas Panhandle. The location is indicated on several of the attachments. My remarks will be divided into five categories: (1) a brief history of how the Deaf Smith County site was designated; (2) a review of major issues for the Texas site and how these are expected to be resolved during site characterization; (3) a summary of major institutional issues; (4) a summary of consultation and cooperation activities with the State of Texas, through its Nuclear Waste Programs Office; and (5) highlights of current and past interactions with local governmental officials and the public in the Panhandle

  3. Bibliography of studies for the Salt Repository Project Office of the Civilian Radioactive Waste Management Program, April 1978-May 1986

    International Nuclear Information System (INIS)

    1986-10-01

    DOE/CH/10140-05 is an annotated bibliography of approved reports that have been produced for the US Department of Energy Salt Repository Project Office of the Civilian Radioactive Waste Management Program since April 1978. This document is intended for use by the US Department of Energy, State and local officials, the US Nuclear Regulatory Commission, contractors to the Office of Nuclear Waste Isolation, concerned citizens, and others who need a comprehensive listing of reports related to a nuclear waste repository in salt. This document consists of a main report listing, appendixes with Work Breakdown Structure lists, and a topical index

  4. Bibliography of studies for the Salt Repository Project Office of the Civilian Radioactive Waste Management Program, April 1978-December 1986

    International Nuclear Information System (INIS)

    1987-06-01

    This document is an annotated bibliography of approved reports that have been produced for the US Department of Energy Salt Repository Project Office of the Civilian Radioactive Waste Management Program since April 1978. This document is intended for use by the US Department of Energy, State and local officials, the US Nuclear Regulatory Commission, contractors to the Office of Nuclear Waste Isolation, concerned citizens, and others who need a comprehensive listing of reports related to a nuclear waste repository in salt. This document consists of a main report listing, appendixes with Work Breakdown Structure lists, and a topical index

  5. Office of Geologic Repositories quality assurance plan for high-level radioactive waste repositories

    International Nuclear Information System (INIS)

    1986-08-01

    This document sets forth geologic repository program-wide quality assurance program requirements and defines management's quality assurance responsibilities for the Office of Geologic Repositories and its projects. (LM)

  6. Nye County Nuclear Waste Repository Project Office independent scientific investigations program annual report, May 1997 - April 1998

    International Nuclear Information System (INIS)

    1998-07-01

    This annual summary report, prepared by the Nye County Nuclear Waste Repository Project Office (NWRPO), summarizes the activities that were performed during the period from May 1, 1997 to April 30, 1998. These activities were conducted in support of the Independent Scientific Investigation Program (ISIP) of Nye County at the Yucca Mountain Site (YMS). The Nye County NWRPO is responsible for protecting the health and safety of the Nye County residents. NWRPO's on-site representative is responsible for designing and implementing the Independent Scientific Investigation Program (ISIP). Major objectives of the ISIP include: Investigating key issues related to conceptual design and performance of the repository that can have major impact on human health, safety, and the environment; identifying areas not being addressed adequately by the Department of Energy (DOE). Nye County has identified several key scientific issues of concern that may affect repository design and performance which were not being adequately addressed by DOE. Nye County has been conducting its own independent study to evaluate the significance of these issues. This report summarizes the results of monitoring from two boreholes and the Exploratory Studies Facility (ESF) tunnel that have been instrumented by Nye County since March and April of 1995. The preliminary data and interpretations presented in this report do not constitute and should not be considered as the official position of Nye County. The ISIP presently includes borehole and tunnel instrumentation, monitoring, data analysis, and numerical modeling activities to address the concerns of Nye County

  7. Nye County Nuclear Waste Repository Project Office independent scientific investigations program annual report, May 1997--April 1998

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-07-01

    This annual summary report, prepared by the Nye County Nuclear Waste Repository Project Office (NWRPO), summarizes the activities that were performed during the period from May 1, 1997 to April 30, 1998. These activities were conducted in support of the Independent Scientific Investigation Program (ISIP) of Nye County at the Yucca Mountain Site (YMS). The Nye County NWRPO is responsible for protecting the health and safety of the Nye County residents. NWRPO`s on-site representative is responsible for designing and implementing the Independent Scientific Investigation Program (ISIP). Major objectives of the ISIP include: Investigating key issues related to conceptual design and performance of the repository that can have major impact on human health, safety, and the environment; identifying areas not being addressed adequately by the Department of Energy (DOE). Nye County has identified several key scientific issues of concern that may affect repository design and performance which were not being adequately addressed by DOE. Nye County has been conducting its own independent study to evaluate the significance of these issues. This report summarizes the results of monitoring from two boreholes and the Exploratory Studies Facility (ESF) tunnel that have been instrumented by Nye County since March and April of 1995. The preliminary data and interpretations presented in this report do not constitute and should not be considered as the official position of Nye County. The ISIP presently includes borehole and tunnel instrumentation, monitoring, data analysis, and numerical modeling activities to address the concerns of Nye County.

  8. Nye County nuclear waste repository project office independent scientific investigations program. Summary annual report, May 1996--April 1997

    International Nuclear Information System (INIS)

    1997-05-01

    This annual summary report, prepared by Multimedia Environmental Technology, Inc. (MET) on behalf of Nye County Nuclear Waste Project Office, summarizes the activities that were performed during the period from May 1, 1996 to April 30, 1997. These activities were conducted in support of the Independent Scientific Investigation Program (ISIP) of Nye County at the Yucca Mountain Site (YMS). The Nye County NWRPO is responsible for protecting the health and safety of the Nye County residents. NWRPO's on-site representative is responsible for designing and implementing the Independent Scientific Investigation Program (ISIP). Major objectives of the ISIP include: (1) Investigating key issues related to conceptual design and performance of the repository that can have major impact on human health, safety, and the environment. (2) Identifying areas not being addressed adequately by DOE Nye County has identified several key scientific issues of concern that may affect repository design and performance which were not being adequately addressed by DOE. Nye County has been conducting its own independent study to evaluate the significance of these issues

  9. Station, local, and public participation plan, Salt Repository Project Office, Deaf Smith County, Texas: Draft

    International Nuclear Information System (INIS)

    1987-12-01

    The purpose of the SRPO State, Local, and Public Participation Plan is to provide an ''umbrella'' document for the ongoing and planned institutional involvement. One of the major goals is to develop project-specific outreach and participation programs based on input received from interested parties. DOE's commitment to interaction and information programs is to be demonstrated by conducting activities in an open environment, listening to and understanding the concerns of interested parties, actively involving affected parties in the program, executing faithfully the intent of Congress expressed through the NWPA, and providing equitable treatment for all affected parties. 1 fig., 2 tabs

  10. Crystalline Repository Project. Technical progress report, October 1982-March 1983

    International Nuclear Information System (INIS)

    1985-01-01

    This document reports the progress being made periodically on the development of a geologic repository in crystalline rock for the permanent disposal of high-level nuclear waste. The reporting elements are arranged by the work breakdown structure so that related studies are presented together. The studies are reported by the Office of Crystalline Respository Development (OCRD), a prime contractor of the US Department of Energy Repository Project Office. The studies include work by other prime contractors and by subcontractors to OCRD

  11. Sample management implementation plan: Salt Repository Project

    International Nuclear Information System (INIS)

    1987-01-01

    The purpose of the Sample Management Implementation Plan is to define management controls and building requirements for handling materials collected during the site characterization of the Deaf Smith County, Texas, site. This work will be conducted for the US Department of Energy Salt Repository Project Office (SRPO). The plan provides for controls mandated by the US Nuclear Regulatory Commission and the US Environmental Protection Agency. Salt Repository Project (SRP) Sample Management will interface with program participants who request, collect, and test samples. SRP Sample Management will be responsible for the following: (1) preparing samples; (2) ensuring documentation control; (3) providing for uniform forms, labels, data formats, and transportation and storage requirements; and (4) identifying sample specifications to ensure sample quality. The SRP Sample Management Facility will be operated under a set of procedures that will impact numerous program participants. Requesters of samples will be responsible for definition of requirements in advance of collection. Sample requests for field activities will be approved by the SRPO, aided by an advisory group, the SRP Sample Allocation Committee. This document details the staffing, building, storage, and transportation requirements for establishing an SRP Sample Management Facility. Materials to be managed in the facility include rock core and rock discontinuities, soils, fluids, biota, air particulates, cultural artifacts, and crop and food stuffs. 39 refs., 3 figs., 11 tabs

  12. Crystalline Repository Project: Technical progress report for the period October 1, 1982--May 28, 1986

    International Nuclear Information System (INIS)

    1988-11-01

    This document reports the progress made on the development of a second geologic repository in crystalline rocks during the duration of the Crystalline Repository Project from its inception in October 1982 to its termination in May 1986. The reporting elements are arranged by the work breakdown structure so that related studies are presented together. The studies are reported by the Office of Waste Technology Development (OWTD), successor to the Office of Crystalline Repository Development. OWTD is a prime contractor of the US Department of Energy (DOE) Repository Technology Program Office, itself the successor to the Crystalline Repository Project Office. The studies include work by other DOE prime contractors and by contractors to the Office of Crystalline Repository Development. 151 refs

  13. The Sellafield repository project information programme

    Energy Technology Data Exchange (ETDEWEB)

    Curd, P J [United Kingdom Nirex Limited (United Kingdom)

    1993-07-01

    The Sellafield Repository Project Information programme has been guided by formal research and by feedback through members of the team. Progress has been made and a significant majority of local people support the project and feel it will benefit the area. (author)

  14. The Sellafield repository project information programme

    International Nuclear Information System (INIS)

    Curd, P.J.

    1993-01-01

    The Sellafield Repository Project Information programme has been guided by formal research and by feedback through members of the team. Progress has been made and a significant majority of local people support the project and feel it will benefit the area. (author)

  15. Strategic management of HLW repository projects

    International Nuclear Information System (INIS)

    Bartlett, J.W.

    1984-01-01

    This paper suggests an approach to strategic management of HLW repository projects based on the premise that a primary objective of project activities is resolution of issues. The approach would be implemented by establishing an issues management function with responsibility to define the issues agenda, develop and apply the tools for assessing progress toward issue resolution, and develop the issue resolution criteria. A principal merit of the approach is that it provides a defensible rationale for project plans and activities. It also helps avoid unnecessary costs and schedule delays, and it helps assure coordination between project functions that share responsibilities for issue resolution

  16. Salt repository project closeout status report

    International Nuclear Information System (INIS)

    1988-06-01

    This report provides an overview of the scope and status of the US Department of Energy (DOE's) Salt Repository Project (SRP) at the time when the project was terminated by the Nuclear Waste Policy Amendments Act of 1987. The report reviews the 10-year program of siting a geologic repository for high-level nuclear waste in rock salt formations. Its purpose is to aid persons interested in the information developed during the course of this effort. Each area is briefly described and the major items of information are noted. This report, the three salt Environmental Assessments, and the Site Characterization Plan are the suggested starting points for any search of the literature and information developed by the program participants. Prior to termination, DOE was preparing to characterize three candidate sites for the first mined geologic repository for the permanent disposal of high-level nuclear waste. The sites were in Nevada, a site in volcanic tuff; Texas, a site in bedded salt (halite); and Washington, a site in basalt. These sites, identified by the screening process described in Chapter 3, were selected from the nine potentially acceptable sites shown on Figure I-1. These sites were identified in accordance with provisions of the Nuclear Waste Policy Act of 1982. 196 refs., 21 figs., 11 tabs

  17. Salt Repository Project Waste Package Program Plan: Draft

    International Nuclear Information System (INIS)

    Carr, J.A.; Cunnane, J.C.

    1986-01-01

    Under the direction of the Office of Civilian Radioactive Waste Management (OCRWM) created within the DOE by direction of the Nuclear Waste Policy Act of 1982 (NWPA), the mission of the Salt Repository Project (SRP) is to provide for the development of a candidate salt repository for disposal of high-level radioactive waste (HLW) and spent reactor fuel in a manner that fully protects the health and safety of the public and the quality of the environment. In consideration of the program needs and requirements discussed above, the SRP has decided to develop and issue this SRP Waste Package Program Plan. This document is intended to outline how the SRP plans to develop the waste package design and to show, with reasonable assurance, that the developed design will satisfy applicable requirements/performance objectives. 44 refs., 16 figs., 16 tabs

  18. SRP [Salt Repository Project] configuration management plan

    International Nuclear Information System (INIS)

    1987-01-01

    This configuration management plan describes the organization, policies, and procedures that will be used on the Salt Repository Project (SRP) to implement the configuration management disciplines and controls. Configuration management is a part of baseline management. Baseline management is defined in the SRP Baseline Procedures Notebook and also includes cost and schedule baselines. Configuration management is a discipline applying technical and administrative direction and surveillance to identify and document the functional and physical characteristics of an item, to control changes to those characteristics, to record and report change processing and implementation status, and to audit the results. Configuration management is designed as a project management tool to determine and control baselines, and ensure and document all components of a project interface both physically and functionally. The purpose is to ensure that the product acquired satisfies the project's technical and operational requirements, and that the technical requirements are clearly defined and controlled throughout the development and acquisition process. 5 figs

  19. 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)

  20. 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)

  1. Salt Repository Project transportation program plan

    International Nuclear Information System (INIS)

    Fisher, R.L.; Greenberg, A.H.; Anderson, T.L.; Yates, K.R.

    1987-01-01

    The Salt Repository Project (SRP) has the responsibility to develop a comprehensive transportation program plan (TrPP) that treats the transportation of workers, supplies, and high-level radioactive waste to the site and the transportation of salt, low-level, and transuranic wastes from the site. The TrPP has developed a systematic approach to transportation which is directed towards satisfying statutes, regulations, and directives and is guided by a hierarchy of specific functional requirements, strategies, plans, and reports. The TrPP identifies and develops the planning process for transportation-related studies and provides guidance to staff in performing and documenting these activities. The TrPP also includes an explanation of the responsibilities of the organizational elements involved in these transportation studies. Several of the report chapters relate to identifying routes for transporting nuclear waste to the site. These include a chapter on identifying an access corridor for a new rail route leading to the site, identifying and evaluating emergency-response preparedness capabilities along candidate routes in the state, and identifying alternative routes from the state border, ports, or in-state reactors to the site. The TrPP also includes plans for identifying salt disposal routes and a discussion of repository/transportation interface requirements. 89 refs., 6 figs

  2. Salt Repository Project: FY 85 technical project plan

    International Nuclear Information System (INIS)

    1985-07-01

    The FY 85 technical plan for the Salt Repository Project is briefly presented. The objectives of the project in relation to the Civilian Radioactive Waste Management Program are discussed, and the technical activities directed toward accomplishing these objectives are detailed. A budget is presented for each of the Level 2 work breakdown structure tasks (Systems, Waste Package, Site, Repository, Regulatory and Institutional, Exploratory Shaft, Test Facilities, Land Acquisition, and Project Management) in the various sections. An overall description, current status, and planned activities are presented for each of the subtasks which make up the above-mentioned Level 2 tasks. A strategy diagram and a master schedule are included and each of the milestones is also listed chronologically in the sections

  3. Salt repository project: Technical progress report for the quarter 1 April--30 June 1987

    International Nuclear Information System (INIS)

    1987-01-01

    This document reports the progress being made each quarter on the development of a geologic repository in salt for the permanent disposal of high-level nuclear waste. The reporting elements are arranged by the work breakdown structure so that related studies are presented together. The studies are reported by the Office of Nuclear Waste Isolation, a prime contractor of the US Department of Energy (DOE) Salt Repository Project Office. The studies include work by other DOE prime contractors and by contractors to the Office of Nuclear Waste Isolation

  4. Salt Repository Project technical progress report for the quarter 1 January--31 March 1987

    International Nuclear Information System (INIS)

    1988-03-01

    This document reports the progress being made each quarter on the development of a geologic repository in salt for the permanent disposal of high-level nuclear waste. The reporting elements are arranged by the work breakdown structure so that related studies are presented together. The studies are reported by the Office of Nuclear Waste Isolation, a prime contractor of the US Department of energy (DOE) Salt Repository Project Office. The studies include work by other DOE prime contractors and by contractors to the Office of Nuclear Waste Isolation. 23 refs., 1 fig

  5. United States Crystalline Repository Project - key research areas

    International Nuclear Information System (INIS)

    Patera, E.S.

    1986-01-01

    The Crystalline Repository Project is responsible for siting the second high-level nuclear waste repository in crystalline rock for the US Department of Energy. A methodology is being developed to define data and information needs and a way to evaluate that information. The areas of research the Crystalline Repository Project is involved in include fluid flow in a fractured network, coupled thermal, chemical and flow processes and cooperation in other nations and OECD research programs

  6. Salt Repository Project. FY-84 technical project plan

    International Nuclear Information System (INIS)

    1984-08-01

    The FY 84 technical plans for the Salt Repository Project (SRP) are briefly presented. The objectives of the project in relation to the Civilian Radioactive Waste Management (CRWM) program are discused and the technical activities directed toward accomplishing these objectives are detailed. A budget is presented for each of the Level 2 Work Breakdown Structure Tasks (Systems, Waste Package, Site, Repository, Regulatory and Institutional, Test Facilities, Exploratory Shaft, Land Acquisition, and Program Management) in an appendix. An overall description, current status, and planned activities are presented for each of the subtasks which make up the above-mentioned Level 2 tasks. Milestones and their definitions for the plan year, as well as milestones for the outyears are also presented at this same subtask level for each subtask

  7. Tunnel Boring Machine for nuclear waste repository research project

    International Nuclear Information System (INIS)

    Janzon, H.A.

    1994-01-01

    A description is presented of a Tunnel Boring Machine and its intended use on a research project underway in Sweden for demonstrating and testing methods for rock investigation at a suitable depth for a deep repository for nuclear waste

  8. Office of Geologic Repositories program baseline procedures notebook (OGR/B-1)

    International Nuclear Information System (INIS)

    1986-06-01

    Baseline management is typically applied to aid in the internal control of a program by providing consistent programmatic direction, control, and surveillance to an evolving system development. This fundamental concept of internal program control involves the establishment of a baseline to serve as a point of departure for consistent technical program coordination and to control subsequent changes from that baseline. The existence of a program-authorized baseline ensures that all participants are working to the same ground rules. Baseline management also ensures that, once the baseline is defined, changes are assessed and approved by a process which ensures adequate consideration of overall program impact. Baseline management also includes the consideration of examptions from the baseline. The process of baseline management continues through all the phases of an evolving system development program. As the Program proceeds, there will be a progressive increase in the data contained in the baseline documentation. Baseline management has been selected as a management technique to aid in the internal control of the Office of Geologic Repositories (OGR) program. Specifically, an OGR Program Baseline, including technical and programmatic requirements, is used for program control of the four Mined Geologic Disposal System field projects, i.e., Basalt Waste Isolation Project, Nevada Nuclear Waste Storage Investigation, Salt Repository Project and Crystalline Repository Project. This OGR Program Baseline Procedures Notebook provides a description of the baseline mwanagement concept, establishes the OGR Program baseline itself, and provides procedures to be followed for controlling changes to that baseline. The notebook has a controlled distribution and will be updated as required

  9. Preliminary waste acceptance requirements - Konrad repository project

    International Nuclear Information System (INIS)

    Brennecke, P.W.; Warnecke, E.H.

    1991-01-01

    In Germany, the planned Konrad repository is proposed for the disposal of all types of radioactive wastes whose thermal influence upon the host rock is negligible. The Bundesamt fuer Strahlenschutz has established Preliminary Waste Acceptance Requirements (as of April 1990) for this facility. The respective requirements were developed on the basis of the results of site-specific safety assessments. They include general requirements on the waste packages to be disposed of as well as more specific requirements on the waste forms, the packaging and the radionuclide inventory per waste package. In addition, the delivery of waste packages was regulated. An outline of the structure and the elements of the Preliminary Waste Acceptance Requirements of April 1990 is given including comments on their legal status. (Author)

  10. ERG [Engineering Review Group] review of the SRP [Salt Repository Project] salt irradiation effects program: Technical report

    International Nuclear Information System (INIS)

    Clark, D.E.

    1986-11-01

    The Engineering Review Group (ERG) was established by the Office of Nuclear Waste Isolation (ONWI) to help evaluate engineering-related issues in the US Department of Energy's nuclear waste repository program. The August 1985 meeting of the ERG reviewed the Salt Repository Project (SRP) salt irradiation effects program. This report documents the ERG's comments and recommendations on these subjects and the ONWI response to the specific points raised by the ERG

  11. Optimized application of systems engineering to nuclear waste repository projects

    International Nuclear Information System (INIS)

    Miskimin, P.A.; Shepard, M.

    1986-01-01

    The purpose of this presentation is to describe a fully optimized application of systems engineering methods and philosophy to the management of a large nuclear waste repository project. Knowledge gained from actual experience with the use of the systems approach on two repository projects is incorporated in the material presented. The projects are currently evaluating the isolation performance of different geologic settings and are in different phases of maturity. Systems engineering methods were applied by the principal author at the Waste Isolation Pilot Plant (WIPP) in the form of a functional analysis. At the Basalt Waste Isolation Project (BWIP), the authors assisted the intergrating contractor with the development and application of systems engineering methods. Based on this experience and that acquired from other waste management projects, an optimized plan for applying systems engineering techniques was developed. The plan encompasses the following aspects: project organization, developing and defining requirements, assigning work responsibilities, evaluating system performance, quality assurance, controlling changes, enhancing licensability, optimizing project performance, and addressing regulatory issues. This information is presented in the form of a roadmap for the practical application of system engineering principles to a nuclear waste repository project

  12. Area recommendation report for the crystalline repository project: An evaluation

    International Nuclear Information System (INIS)

    Beck, J.E.; Lowe, H.; Yurkovich, S.P.

    1986-01-01

    An evaluation is given of DOE's recommendation of the Elk River complex in North Carolina for siting the second repository. Twelve recommendations are made including a strong suggestion that the Cherokee Tribe appeal both through political and legal avenues for inclusion as an affected area primarily due to projected impacts upon economy and public health as a consequence of the potential for reduced tourism

  13. The Ec prototype repository project: implications of assessments for refining repository design

    International Nuclear Information System (INIS)

    Svemar, C.

    2004-01-01

    The most important issue in the evaluation of the repository performance is the long term safety of the repository. Analyses for this issue focuses on the 'steady state' conditions which start at the time when the repository has been saturated and the groundwater table returned to its normal level. The bentonite buffer around the canisters is saturated and homogeneous, and the canister is located exactly in the centre of the buffer. The backfill in the tunnel has been saturated as well and fills the earlier open spaces in the tunnel completely. The task of the activities taking places prior to the start of the 'steady state' conditions, like excavation, deposition, backfilling and sealing, with due consideration to the processes a consequences they may cause in the long run, is to provide for these 'ideal' conditions, as close as possible. While studying these activities in detail it has become obvious that development of methods and techniques needs to be carefully addressed before the decision is made on how to apply them in the repository. One general finding is that the situation in engineering of details is not that much different from the situation in geological characterisation of a site in detail; one more detail of engineering and the consequences it brings often complicates the situation rather than supports the solution prioritized so far. Many of the practical issues have been studied in the Prototype Repository project in the AEspoe Hard Rock Laboratory (Pusch et al., 2000). The Prototype Repository consists of two sections with four respectively two deposition holes with bentonite buffer and canister, the latter holding electrical heaters. The sections are separated by a concrete plug, and the whole test is to be separated from the rest of the laboratory by an outer plug. The project has two objectives: 1. To demonstrate the integrated function of tile deep repository components under realistic conditions and to compare results with models and

  14. A web-based repository of surgical simulator projects.

    Science.gov (United States)

    Leskovský, Peter; Harders, Matthias; Székely, Gábor

    2006-01-01

    The use of computer-based surgical simulators for training of prospective surgeons has been a topic of research for more than a decade. As a result, a large number of academic projects have been carried out, and a growing number of commercial products are available on the market. Keeping track of all these endeavors for established groups as well as for newly started projects can be quite arduous. Gathering information on existing methods, already traveled research paths, and problems encountered is a time consuming task. To alleviate this situation, we have established a modifiable online repository of existing projects. It contains detailed information about a large number of simulator projects gathered from web pages, papers and personal communication. The database is modifiable (with password protected sections) and also allows for a simple statistical analysis of the collected data. For further information, the surgical repository web page can be found at www.virtualsurgery.vision.ee.ethz.ch.

  15. Salt Repository Project shaft design guide: Revision 0

    International Nuclear Information System (INIS)

    1987-12-01

    The Salt Repository Project (SRP) Shaft Design Guide (SDG) and the accompanying SRP Input to Seismic Design define the basic approach for developing appropriate shaft designs for a high-level nuclear waste repository in salt at a proposed site in Deaf Smith County, Texas. The SDG is based on current mining industry standards and practices enhanced to meet the special needs of an underground nuclear waste repository. It provides a common approach for design of both the exploratory and repository shafts. The SDG defines shaft lining and material concepts and presents methods for calculating the loads and displacements that will be imposed on lining structures. It also presents the methodology and formulae for sizing lining components. The SDG directs the shaft designer to sources of geoscience and seismic design data for the Deaf Smith County, Texas repository site. In addition, the SDG describes methods for confirming shaft lining design by means of computer analysis, and it discusses performance monitoring needs that must be considered in the design. 113 refs., 18 figs., 14 tabs

  16. Croatian repository construction project - present status and main obstacles

    International Nuclear Information System (INIS)

    Kucar Dragicevic, S.; Subasic, D.; Schaller, A.; Lokner, V.; Cerskov Klika, M.

    1999-01-01

    Croatia has been preparing backgrounds for the construction of the repository for low and intermediate radioactive waste on its territory, almost for a decade, now. In the name of Hrvtaska elektroprivreda, the co-owner of the NE Krsko, APO has been co-ordinating and organising numerous activities and projects during that time period. Siting process, safety assessment, disposal technology and repository design and public acceptance issues are the main fields of activities. The overall status of the project at the moment, including the overview of the present status of the main four aspects of activities, will be presented. Relatively, big and important progress made on the project work out during the last two years, as well as the main obstacles we were faced with during that time period, will be discussed.(author)

  17. Repository-relevant testing applied to the Yucca Mountain Project

    International Nuclear Information System (INIS)

    Bates, J.K.; Gerding, T.J.; Veleckis, E.

    1989-04-01

    A repository environment poses a challenge to developing a testing program because of the diverse nature of conditions that may exist at a given time during the life of the repository. A starting point is to identify whether any potential waste-water contact modes are particularly deleterious to the waste form performance, and whether any interactions between materials present in the waste package environment need to be accounted for during modeling the waste form reaction. The Unsaturated Test method in one approach that has been developed by the Yucca Mountain Project (YMP) to investigate the above issues, and a description of results that have been obtained during the testing of glass and unirradiated UO 2 are the subject of this report. 10 refs., 7 figs., 4 tabs

  18. SKI SITE-94, deep repository performance assessment project, summary

    International Nuclear Information System (INIS)

    1999-01-01

    SITE-94 is a comprehensive performance assessment exercise for a hypothetical repository for spent nuclear fuel at a real site in Sweden. SITE-94 was carried out to develop the capability and tools to enable Swedish Nuclear Power Inspectorate (SKI) to review fully the proposals for a deep repository which are expected to be made by the Swedish Nuclear Fuel and Waste Management Company, SKB (the implementor). Sweden is one of the leading countries in the research and development of geological disposal of radioactive waste. The developed methodology for performance assessment has attracted interests from other countries. The Summary of the main report of the SITE-94 project is translated here into Japanese to allow to make the information on the methodology and the related issues available among Japanese concerned. (author)

  19. The FORGE (Fate Of Repository Gases) pan European project

    International Nuclear Information System (INIS)

    Shaw, Richard

    2010-01-01

    Document available in extended abstract form only. Full text of publication follows: The multiple barrier concept is the cornerstone of all proposed schemes for underground disposal of radioactive wastes. The concept invokes a series of barriers, both engineered and natural, between the waste and the surface. Achieving this concept is the primary objective of all disposal programmes, from site appraisal and characterisation to repository design and construction. However, the performance of the repository as a whole (waste, buffer, engineering disturbed zone, host rock), and in particular its gas transport properties, are still poorly understood. Issues still to be adequately examined that relate to understanding basic processes include: dilational versus visco-capillary flow mechanisms; long-term integrity of seals, in particular gas flow along contacts; role of the EDZ as a conduit for preferential flow; laboratory to field up-scaling. Understanding gas generation and migration is thus vital in the quantitative assessment of repositories and is the focus of the research in this proposal for an integrated, multidisciplinary project. The FORGE project is a pan-European project with links to international radioactive waste management organisations, regulators and academia, specifically designed to tackle the key research issues associated with the generation and movement of repository gasses with partners from 24 organisations in 12 European countries. It is supported by funding under the European Commission FP7 Euratom programme and runs from 2009 to 2013. Of particular importance are the long-term performance of bentonite buffers, plastic clays, indurated mud-rocks and crystalline formations. Further experimental data are required to reduce uncertainty relating to the quantitative treatment of gas in performance assessment. FORGE will address these issues through a series of laboratory and field-scale experiments, including the development of new methods for up

  20. Rhode Island crystalline repository project: Technical progress report, 1984-1986

    International Nuclear Information System (INIS)

    1986-01-01

    A Nuclear Waste Fund established by the Nuclear Waste Policy Act of 1982 provided financial support to the State of Rhode Island for its participation in the high-level radioactive waste repository siting program. In 1984, the Office of the Governor set up a multidisciplinary Project Review Team consisting of staff from three State agencies and the University of Rhode Island. Members of the Review Team attended several meetings throughout the reporting period to voice their concerns about siting directly to the US Department of Energy (DOE). Written comments were also submitted on draft plans and reports. Many of Rhode Island's recommendations in these comments were later adopted. In May, 1986, Secretary of Energy John Herrington announced the suspension of the crystalline repository siting program. The remainder of the year was spent monitoring litigation challenging that decision and pending legislation. Administrative phase-down of the program was essentially complete by the close of the calendar year

  1. Radioactive waste isolation in salt: special advisory report on the status of the Office of Nuclear Waste Isolation's plans for repository performance assessment

    International Nuclear Information System (INIS)

    Ditmars, J.D.; Walbridge, E.W.; Rote, D.M.; Harrison, W.; Herzenberg, C.L.

    1983-10-01

    Repository performance assessment is analysis that identifies events and processes that might affect a repository system for isolation of radioactive waste, examines their effects on barriers to waste migration, and estimates the probabilities of their occurrence and their consequences. In 1983 Battelle Memorial Institute's Office of Nuclear Waste Isolation (ONWI) prepared two plans - one for performance assessment for a waste repository in salt and one for verification and validation of performance assessment technology. At the request of the US Department of Energy's Salt Repository Project Office (SRPO), Argonne National Laboratory reviewed those plans and prepared this report to advise SRPO of specific areas where ONWI's plans for performance assessment might be improved. This report presents a framework for repository performance assessment that clearly identifies the relationships among the disposal problems, the processes underlying the problems, the tools for assessment (computer codes), and the data. In particular, the relationships among important processes and 26 model codes available to ONWI are indicated. A common suggestion for computer code verification and validation is the need for specific and unambiguous documentation of the results of performance assessment activities. A major portion of this report consists of status summaries of 27 model codes indicated as potentially useful by ONWI. The code summaries focus on three main areas: (1) the code's purpose, capabilities, and limitations; (2) status of the elements of documentation and review essential for code verification and validation; and (3) proposed application of the code for performance assessment of salt repository systems. 15 references, 6 figures, 4 tables

  2. Performance assessment plans and methods for the Salt Repository Project

    International Nuclear Information System (INIS)

    1984-08-01

    This document presents the preliminary plans and anticipated methods of the Salt Repository Project (SRP) for assessing the postclosure and radiological aspects of preclosure performance of a nuclear waste repository in salt. This plan is intended to be revised on an annual basis. The emphasis in this preliminary effort is on the method of conceptually dividing the system into three subsystems (the very near field, the near field, and the far field) and applying models to analyze the behavior of each subsystem and its individual components. The next revision will contain more detailed plans being developed as part of Site Characterization Plan (SCP) activities. After a brief system description, this plan presents the performance targets which have been established for nuclear waste repositories by regulatory agencies (Chapter 3). The SRP approach to modeling, including sensitivity and uncertainty techniques is then presented (Chapter 4). This is followed by a discussion of scenario analysis (Chapter 5), a presentation of preliminary data needs as anticipated by the SRP (Chapter 6), and a presentation of the SRP approach to postclosure assessment of the very near field, the near field, and the far field (Chapters 7, 8, and 9, respectively). Preclosure radiological assessment is discussed in Chapter 10. Chapter 11 presents the SRP approach to code verification and validation. Finally, the Appendix lists all computer codes anticipated for use in performance assessments. The list of codes will be updated as plans are revised

  3. Salt Repository Project waste emplacement mode decision paper: Revison 1

    International Nuclear Information System (INIS)

    1987-08-01

    This paper provides a recommendation as to the mode of waste emplacement to be used as the current basis for site characterization activity for the Deaf Smith County, Texas, high level nuclear waste repository site. It also presents a plan for implementing the recommendation so as to provide a high level of confidence in the project's success. Since evaluations of high-level waste disposal in geologic repositories began in the 1950s, most studies emplacement in salt formations employed the vertical orientation for emplacing waste packages in boreholes in the floor of the underground facility. This orientation was used in trials at Project Salt Vault in the 1960s. The Waste Isolation Pilot Plant (WIPP) has recently settled on a combination of vertical and horizontal modes for various waste types. This paper analyzes the information available and develops a project position upon which to base current site characterization activities. The position recommended is that the SRP should continue to use the vertical waste emplacement mode as the reference design and to carry the horizontal mode as a ''passive'' alternative. This position was developed based upon the conclusions of a decision analysis, risk assessment, and cost/schedule impact assessment. 52 refs., 6 figs., 1 tab

  4. Valorization of a repository in an added value project

    International Nuclear Information System (INIS)

    Van Hove, E.

    2004-01-01

    Professor of Sociology (retired), spoke of the valorization of a repository in an added value project. He pointed out that though local stakeholders may lack technical expertise, they consider their personal interests very carefully and projects affecting such interests are taken quite personally. This provides caution but also opportunity for such projects to be conducted in ways that can help, though not guarantee, better acceptance by local stakeholders. Professor Van Hove mentioned three attributes. First, while engineering projects tend to be thought of as mono-functional (e.g. dispose of waste), building flexibility into the project to reflect the interests of the local stakeholders can measurably improve Stakeholder satisfaction. What the implementer may see as a single-purpose project may indeed provide additional, desirable capabilities to a creative local population. Second, while engineering projects, particularly waste management projects are often designed and built in uninteresting, utilitarian ways, a more creative design and implementation can add a sense of enjoyment and pride on the part of the local stakeholders. And third, while engineering projects are often conducted a manner closed to their environment, a more transparent, inclusive process may draw local stakeholders more intimately into the project. All of these features can help by providing inviting borders, by valuing the beauty and aesthetic dimension of the project and by building the project so that it has an appropriate place in the memory of society. Professor Van Hove emphasised that people show great ingenuity in adapting uses and functions beyond those originally intended. The extent to which local stakeholders can help provide the vision and then the reality of such waste management projects can significantly improve their sense of ownership of the project and their ultimate acceptance. (author)

  5. Systems engineering management plan for the Salt Repository Project

    International Nuclear Information System (INIS)

    Neff, J.O.

    1986-08-01

    This document presents the plan for using systems engineering in conducting and managing the technical work of the Salt Repository Project (SRP) of the US Department of Energy's Civilian Radioactive Waste Management Program. The need for preparing a Systems Engineering Management Plan (SEMP) is traced back to relevant DOE directives. These directives are interpreted as SRP requirements in the context of the Mined Geologic Disposal System. The strategy for conducting systems engineering on the SRP, including the role of the systems engineering process, is then described. The SEMP also designates who in the project organization will be responsible for carrying out the activities. Finally, the management tools that are used to implement the systems engineering process, including associated documentation on the SRP, are described

  6. SKI SITE-94. Deep Repository Performance Assessment Project. Summary

    International Nuclear Information System (INIS)

    1997-02-01

    The function of SITE-94 is to provide the Swedish Nuclear Power Inspectorate (SKI) with the capacity and supporting knowledge needed for reviewing the Swedish nuclear industry's R and D programs and for reviewing license applications, as stipulated in Swedish legislation. The report is structured as a Performance Assessment exercise needed for input to decisions regarding repository safety, but the SITE-94 is neither a safety assessment nor a model for future assessments to be undertaken by the prospective licensee. The specific project objectives of SITE-94 comprise site evaluation, performance assessment methodology, canister integrity and radionuclide release and transport calculations. The main report (SKI-R--96-36) gives a detailed description of the many inter-related studies undertaken as part of the research project, while the present report presents a condensed summary of the main report. 46 refs

  7. DSN Aperture Enhancement Project Office

    Science.gov (United States)

    Marina, Miguel

    2012-01-01

    All contracts are underway for antennas, associated facilities modifications and new transmitters. High risk CPI 100kW klystron and JPL high power uplink microwave components have been designed, prototyped and successfully tested at GDSCC to support the 80kW transmitter implementation and testing at vendor facility. Open issues, which might affect project delivery date, have plans in place or are being created, to maintain DSS-35 Operational Date. There are no known open issues that affect performance. Overall good progress has been made in all areas (procurements, contracts, design and development) and the project is confident that DSS-35 & 36 antennas and the three 80kW Uplink systems will be delivered according to plan.

  8. Environmental Audit of the Grand Junction Projects Office

    Energy Technology Data Exchange (ETDEWEB)

    1991-08-01

    The Grand Junction Projects Office (GJPO) is located in Mesa County, Colorado, immediately south and west of the Grand Junction city limits. The US Atomic Energy Commission (AEC) established the Colorado Raw Materials Office at the present-day Grand Junction Projects Office in 1947, to aid in the development of a viable domestic uranium industry. Activities at the site included sampling uranium concentrate; pilot-plant milling research, including testing and processing of uranium ores; and operation of a uranium mill pilot plant from 1954 to 1958. The last shipment of uranium concentrate was sent from GJPO in January, 1975. Since that time the site has been utilized to support various DOE programs, such as the former National Uranium Resource Evaluation (NURE) Program, the Uranium Mill Tailings Remedial Action Project (UMTRAP), the Surplus Facilities Management Program (SFMP), and the Technical Measurements Center (TMC). All known contamination at GJPO is believed to be the result of the past uranium milling, analyses, and storage activities. Hazards associated with the wastes impounded at GJPO include surface and ground-water contamination and potential radon and gamma-radiation exposure. This report documents the results of the Baseline Environmental Audit conducted at Grand Junction Projects Office (GJPO) located in Grand Junction, Colorado. The Grand Junction Baseline Environmental Audit was conducted from May 28 to June 12, 1991, by the Office of Environmental Audit (EH-24). This Audit evaluated environmental programs and activities at GJPO, as well as GJPO activities at the State-Owned Temporary Repository. 4 figs., 12 tabs.

  9. Environmental Audit of the Grand Junction Projects Office

    International Nuclear Information System (INIS)

    1991-08-01

    The Grand Junction Projects Office (GJPO) is located in Mesa County, Colorado, immediately south and west of the Grand Junction city limits. The US Atomic Energy Commission (AEC) established the Colorado Raw Materials Office at the present-day Grand Junction Projects Office in 1947, to aid in the development of a viable domestic uranium industry. Activities at the site included sampling uranium concentrate; pilot-plant milling research, including testing and processing of uranium ores; and operation of a uranium mill pilot plant from 1954 to 1958. The last shipment of uranium concentrate was sent from GJPO in January, 1975. Since that time the site has been utilized to support various DOE programs, such as the former National Uranium Resource Evaluation (NURE) Program, the Uranium Mill Tailings Remedial Action Project (UMTRAP), the Surplus Facilities Management Program (SFMP), and the Technical Measurements Center (TMC). All known contamination at GJPO is believed to be the result of the past uranium milling, analyses, and storage activities. Hazards associated with the wastes impounded at GJPO include surface and ground-water contamination and potential radon and gamma-radiation exposure. This report documents the results of the Baseline Environmental Audit conducted at Grand Junction Projects Office (GJPO) located in Grand Junction, Colorado. The Grand Junction Baseline Environmental Audit was conducted from May 28 to June 12, 1991, by the Office of Environmental Audit (EH-24). This Audit evaluated environmental programs and activities at GJPO, as well as GJPO activities at the State-Owned Temporary Repository. 4 figs., 12 tabs

  10. Offsite testing in support of the Salt Repository Project

    International Nuclear Information System (INIS)

    Kalia, H.N.

    1987-04-01

    This report presents a rationale and recommendation to perform an offsite testing program in support of the Salt Repository Project. The investigation to be performed primarily consists of qualifying test methods and procedures, qualifying personnel-training procedures, evaluating test instruments and selected equipment, and obtaining mining and production equipment performance-related information. The key objective of these activities is to develop capabilities to be used at the exploratory shaft facility (ESF). The ESF is to be excavated at the Deaf Smith County site to characterize the salt site for the construction of a repository used to isolate radioactive waste from the biosphere. The bulk of the offsite testing work will be performed at Avery Island Salt Mine at New Iberia, Lousiana. Additional knowledge will be obtained by exchanging technical information either as participants or as observers at the Waste Isolation Pilot Plant (WIPP) site and the Asse Mine in the Federal Republic of Germany (FRG). It is estimated that the offsite testing program will cost approximately $9.3 million over 4 fiscal years. 14 refs., 1 fig., 8 tabs

  11. The ESDRED project: Engineering studies and demonstration of repository designs

    International Nuclear Information System (INIS)

    Verstricht, J.

    2009-01-01

    The construction, operation and closure of a deep geological repository for spent fuel and long-lived radioactive waste in clay involves specific technologies. The demonstration of these techniques at an industrial scale is being carried out in the frame of a technological integrated project within the sixth Framework Programme of EURATOM. The Belgian design for high level waste disposal is based on the so-called Supercontainer concept. Within this concept, the waste is encased in a carbon steel overpack, which is consequently fitted into a 70 cm thick concrete shell, in its turn enveloped by a stainless steel liner. A Supercontainer measures about 2 m in diameter. In the design of the repository, the Supercontainers will be emplaced, one after the other, in disposal galleries. The space between the Supercontainers and the gallery lining needs to be filled up with a solid material. The most essential function of this component, referred to as backfill, is to prevent a collapse of the gallery. A secondary function is to limit the presence of free oxygen, to limit corrosion. In the ESDRED project EIG EURIDICE, together with SCK-CEN and ONDRAF/NIRAS, investigates technologies to apply the backfill. After testing two techniques to apply the backfill in 2007 at limited scale (unite with granular material and grouting with backfill mortar), grouting was selected as the preferred technique. This technique then should be tested at full-scale (30 m long mock-up). First, a full-scale structure needs to built, including an extensive instrumentation programme. In addition, the logistical needs to ensure a continuous backfill operation have to be worked out. The objective is to have the almost 100 m 3 backfilled in 4 hours

  12. Repository seal materials performance for a SALT Repository Project 5-year code/model development plan: Draft

    International Nuclear Information System (INIS)

    1987-06-01

    This document describes an integrated laboratory testing and model development effort for the seal system for a high-level nuclear waste repository in salt. The testing and modeling efforts are designed to determine seal material response in the repository environment, to provide models of seal system components for performance assessment, and to assist in the development of seal system designs. A code/model development and performance analysis program will be performed to predict the short- and long-term response of seal materials and seal components. The results from these analyses will be used to support the material testing activities on this contract and to support performance assessment activities that are conducted in other parts of the Salt Repository Project (SRP). 48 refs., 15 figs., 4 tabs

  13. Response to state comments on the draft regional characterization reports for the Crystalline Repository Project

    International Nuclear Information System (INIS)

    1984-11-01

    In May, 1983, the US Department of Energy (DOE) Crystalline Repository Project Office (CPO) issued six draft Regional Characterization Reports (RCRs) for review and comment to the 17 Crystalline States comprising the Northeastern, Southeastern, and North Central crystalline regions. Comment letters were received from 13 of the 17 states. The more than 2000 comments generally focused on the quality and content of the characterization reports and on their intended use in region-to-area screening. These comments were paraphrased and grouped into 23 subjects within the following four topical areas: (1) General and Programmatic; (2) Geologic; (3) Environmental and Socioeconomic; and (4) Editorial. This document provides responses to the comments submitted by the states

  14. Annotated outline for the SCP conceptual design report: Office of Geologic Repositories

    International Nuclear Information System (INIS)

    1987-06-01

    The Nuclear Waste Policy Act of 1982 (NWPA) requires that site characterization plans (SCPs) be submitted to the Nuclear Regulatory Commission (NRC), affected States and Indian tribes, and the general public for review and comment prior to the sinking of shafts at a candidate repository site. The SCP is also required by the NRC licensing procedures for the disposal of high-level waste. An Annotated Outline (AO) for Site Characterization Plans (OGR/B-5) has been prepared to provide DOE's standard format and guidance for preparation of SCPs. Consistent with the AO for SCPs. Chapter 6 of the SCP is to provide the requirements and references the media-specific design data base, describe the current design concepts, and discuss design information needs. In order to develop this design information, the Office of Geologic Repositories program is planning a SCP conceptual design phase as part of the overall repository design process. This phase is the first step in the design process, and the result and design can be expected to change as the program moves through the site characterization phase. The Annotated Outline which follows provides the standard format and guidance for the preparation of the SCP Conceptual Design Reports. It is considered to meet the intent of NRC's proposed Generic Technical Position philosophy contained therein. The SCP Conceptual Design Report will be the primary basis for preparation of Chapter 6 of the SCP and will be stand-alone reference document for the SCP. Appendix 1 to this Annotated Outline provides a correlation between Chapter 6 of the SCP and SCP Conceptual Design Report for the information purposes

  15. Office of Geologic Repositories issues hierarchy for a mined geologic disposal system

    International Nuclear Information System (INIS)

    1987-08-01

    The Nuclear Regulatory Commission (NRC) has indicated that the identification of the issues that must be resolved to complete licensing assessments of site and design suitability is an important step in the licensing process. The issues hierarchy developed by the Office of Geologic Repositories (OGR) for the mined geologic disposal system (MGDS) are based on the issues-hierarchy concept presented in the Mission Plan. Specific questions are encompassed by the general issue statements in the OGR issues hierarchy. The OGR issues hierarchy is limited to the issues related to the siting and licensing requirements of applicable federal regulations and does not address the requirements of other regulations, functional or operating requirements for the MGDS, or requirements for the integration and the design/operational efficiency of the MGDS. 4 figs

  16. Salt Repository Project transportation system interface requirements: Transportation system/repository receiving facility interface requirements

    International Nuclear Information System (INIS)

    Smith, L.A.; Insalaco, J.W.; Trainer, T.A.

    1988-01-01

    This report is a preliminary review of the interface between the transportation system and the repository receiving facility for a nuclear waste mined geologic disposal system in salt. Criteria for generic cask and facility designs are developed. These criteria are derived by examining the interfaces that occur as a result of the operations needed to receive nuclear waste at a repository. These criteria provide the basis for design of a safe, operable, practical nuclear waste receiving facility. The processing functions required to move the shipping unit from the gate into the unloading area and back to the gate for dispatch are described. Criteria for a generic receiving facility are discussed but no specific facility design is presented or evaluated. The criteria are stated in general terms to allow application to a wide variety of cask and facility designs. 9 refs., 6 figs., 4 tabs

  17. [Earth Science Technology Office's Computational Technologies Project

    Science.gov (United States)

    Fischer, James (Technical Monitor); Merkey, Phillip

    2005-01-01

    This grant supported the effort to characterize the problem domain of the Earth Science Technology Office's Computational Technologies Project, to engage the Beowulf Cluster Computing Community as well as the High Performance Computing Research Community so that we can predict the applicability of said technologies to the scientific community represented by the CT project and formulate long term strategies to provide the computational resources necessary to attain the anticipated scientific objectives of the CT project. Specifically, the goal of the evaluation effort is to use the information gathered over the course of the Round-3 investigations to quantify the trends in scientific expectations, the algorithmic requirements and capabilities of high-performance computers to satisfy this anticipated need.

  18. National Unmanned Aircraft Systems Project Office

    Science.gov (United States)

    Goplen, Susan E.; Sloan, Jeff L.

    2015-01-01

    The U.S. Geological Survey (USGS) National Unmanned Aircraft Systems (UAS) Project Office leads the implementation of UAS technology in the Department of the Interior (DOI). Our mission is to support the transition of UAS into DOI as a new cost-effective tool for collecting remote-sensing data to monitor environmental conditions, respond to natural hazards, recognize the consequences and benefits of land and climate change and conduct wildlife inventories. The USGS is teaming with all DOI agencies and academia as well as local, State, and Tribal governments with guidance from the Federal Aviation Administration and the DOI Office of Aviation Services (OAS) to lead the safe, efficient, costeffective and leading-edge adoption of UAS technology into the scientific research and operational activities of the DOI.

  19. State of Nevada, Agency for Nuclear Projects/Nuclear Waste Project Office narrative report, January 1992

    International Nuclear Information System (INIS)

    1992-01-01

    The Agency for Nuclear Projects/Nuclear Waste Project Office (NWPO) is the State of Nevada agency designated by State law to monitor and oversee US Department of Energy (DOE) activities relative to the possible siting, construction, operation and closure of a high-level nuclear waste repository at Yucca Mountain and to carry out the State of Nevada's responsibilities under the Nuclear Waste Policy Act of 1982. During the reporting period the NWPO continued to work toward the five objectives designed to implement the Agency's oversight responsibilities: (1) Assure that the health and safety of Nevada's citizens are adequately protected with regard to any federal high-level radioactive waste program within the State; (2) Take the responsibilities and perform the duties of the State of Nevada as described in the Nuclear Waste Policy Act of 1982 (Public Law 97-425) and the Nuclear Waste Policy Amendments Act of 1987; (3) Advise the Governor, the State Commission on Nuclear Projects and the Nevada State Legislature on matters concerning the potential disposal of high-level radioactive waste in the State; (4) Work closely and consult with affected local governments and State agencies; (5) Monitor and evaluate federal planning and activities regarding high-level radioactive waste disposal. Plan and conduct independent State studies regarding the proposed repository

  20. Statistical methods for mechanistic model validation: Salt Repository Project

    International Nuclear Information System (INIS)

    Eggett, D.L.

    1988-07-01

    As part of the Department of Energy's Salt Repository Program, Pacific Northwest Laboratory (PNL) is studying the emplacement of nuclear waste containers in a salt repository. One objective of the SRP program is to develop an overall waste package component model which adequately describes such phenomena as container corrosion, waste form leaching, spent fuel degradation, etc., which are possible in the salt repository environment. The form of this model will be proposed, based on scientific principles and relevant salt repository conditions with supporting data. The model will be used to predict the future characteristics of the near field environment. This involves several different submodels such as the amount of time it takes a brine solution to contact a canister in the repository, how long it takes a canister to corrode and expose its contents to the brine, the leach rate of the contents of the canister, etc. These submodels are often tested in a laboratory and should be statistically validated (in this context, validate means to demonstrate that the model adequately describes the data) before they can be incorporated into the waste package component model. This report describes statistical methods for validating these models. 13 refs., 1 fig., 3 tabs

  1. Agency for Nuclear Projects/Nuclear Waste Project Office final progress report

    International Nuclear Information System (INIS)

    1992-01-01

    The Nevada Agency for Nuclear Projects/Nuclear Waste Project Office (NWPO) was formally established by Executive Policy in 1983 following passage of the federal Nuclear Waste Policy Act of 1982 (Act). That Act provides for the systematic siting, construction, operation, and closure of high-level radioactive defense and research by-products and other forms of high-level radioactive waste from around the country which will be stored at such repositories. In 1985 the Nevada legislature formally established the NWPO as a distinct and statutorily authorized agency to provide support to the Governor and State Legislature on matters concerning the high-level nuclear waste programs. The NWPO utilized a small, central staff supplemented by contractual services for needed technical and specialized expertise in order to provide high quality oversight and monitoring of federal activities, to conduct necessary independent studies, and to avoid unnecessary duplication of efforts. This report summarizes the results of this ongoing program to ensure that risks to the environment and to human safety are minimized. It includes findings in the areas of hydrogeology, geology, quality assurance activities, repository engineering, legislature participation, socioeconomic affects, risk assessments, monitoring programs, public information dissemination, and transportation activities. The bulk of the reporting deals with the Yucca Mountain facility

  2. Salt Repository Project input to seismic design: Revision 0

    International Nuclear Information System (INIS)

    1987-12-01

    The Salt Repository Program (SRP) Input to Seismic Design (ISD) documents the assumptions, rationale, approaches, judgments, and analyses that support the development of seismic-specific data and information to be used for shaft design in accordance with the SRP Shaft Design Guide (SDG). The contents of this document are divided into four subject areas: (1) seismic assessment, (2) stratigraphy and material properties for seismic design, (3) development of seismic design parameters, and (4) host media stability. These four subject areas have been developed considering expected conditions at a proposed site in Deaf Smith County, Texas. The ISD should be used only in conjunction with seismic design of the exploratory and repository shafts. Seismic design considerations relating to surface facilities are not addressed in this document. 54 refs., 55 figs., 18 tabs

  3. Repository relevant testing applied to the Yucca Mountain Project

    International Nuclear Information System (INIS)

    Bates, J.K.; Woodland, A.B.; Wronkiewicz, D.J.; Cunnane, J.C.

    1990-10-01

    The tuff beds of Yucca Mountain, Nevada, are currently being investigated as a site for the disposal of high-level nuclear waste in an underground repository. If this site is found suitable, the repository would be located in the unsaturated zone above the water table, and a description of the site and the methodology of assessing the performance of the repository are described in the Site Characterization Plan (SCP). While many factors are accounted for during performance assessment, an important input parameter is the degradation behavior of the waste forms, which may be either spent fuel or reprocessed waste contained in a borosilicate glass matrix. To develop the necessary waste form degradation input, the waste package environment needs to be identified. This environment will change as the waste decays and also is a function of the repository design which has not yet been finalized. At the present time, an exact description of the waste package environment is not available. The SCP does provide an initial description of conditions that can be used to guide waste form evaluation. However, considerable uncertainty exists concerning the conditions under which waste form degradation and radionuclide release may occur after the waste package containment barriers are finally breached. The release conditions that are considered to be plausible include (1) a open-quotes bathtubclose quotes condition in which the waste becomes fully or partially submerged in water that enters the breached container and accumulates to fill the container up to the level of the breach opening, (2) a open-quotes wet dripclose quotes or open-quotes trickle throughclose quotes condition in which the waste form is exposed to dripping water that enters through the top and exits the bottom of a container with multiple holes, and (3) a open-quotes dryclose quotes condition in which the waste form is exposed to a humid air environment

  4. A comparison of project participants and extension officers ...

    African Journals Online (AJOL)

    The study examined the perception of project participants and extension officers regarding marketing of agricultural produce in agricultural projects in the North West Province. The objective of the study was primarily to compare the perceptions of project participants and extension officers. When establishing a project, ...

  5. 48 CFR 2052.215-71 - Project officer authority.

    Science.gov (United States)

    2010-10-01

    ... directive whatever. (d) All technical directions must be issued in writing by the project officer or must be... advise the contractor in writing that, in the contracting officer's opinion, the technical direction is... subject to the technical direction of the NRC project officer. The term technical direction is defined to...

  6. Technical progress report: Rhode Island crystalline repository project, calendar year 1985

    International Nuclear Information System (INIS)

    Vild, B.F.

    1985-01-01

    A Nuclear Waste Fund established by the Nuclear Waste Policy Act of 1982 provides financial support to affected states to participate in the high-level radioactive waste repository siting program of the US Department of Energy. In Rhode Island, that function is performed by a multidisciplinary Project Review Team consisting of staff from three State agencies. Members of the Review Team attended several meetings in 1985 to voice their concerns directly to DOE. Written comments were also submitted on draft plans and reports. Among the issues raised were inconsistencies in the geologic and environmental data used to screen potential repository sites, the role of Monitored Retrievable Storage (MRS) in the repository program, and regulations regarding the transportation and storage of nuclear waste. The Review Team also began work on a public information booklet describing the repository program in nontechnical terms. That booklet will be distributed widely upon completion

  7. SemanticOrganizer: A Customizable Semantic Repository for Distributed NASA Project Teams

    Science.gov (United States)

    Keller, Richard M.; Berrios, Daniel C.; Carvalho, Robert E.; Hall, David R.; Rich, Stephen J.; Sturken, Ian B.; Swanson, Keith J.; Wolfe, Shawn R.

    2004-01-01

    SemanticOrganizer is a collaborative knowledge management system designed to support distributed NASA projects, including diverse teams of scientists, engineers, and accident investigators. The system provides a customizable, semantically structured information repository that stores work products relevant to multiple projects of differing types. SemanticOrganizer is one of the earliest and largest semantic web applications deployed at NASA to date, and has been used in diverse contexts ranging from the investigation of Space Shuttle Columbia's accident to the search for life on other planets. Although the underlying repository employs a single unified ontology, access control and ontology customization mechanisms make the repository contents appear different for each project team. This paper describes SemanticOrganizer, its customization facilities, and a sampling of its applications. The paper also summarizes some key lessons learned from building and fielding a successful semantic web application across a wide-ranging set of domains with diverse users.

  8. Massachusetts Crystalline Repository Project. Progress report, December 31, 1985

    International Nuclear Information System (INIS)

    1985-01-01

    Project activities which have been undertaken include the following: review and comment on OCRD projects reports; review of pertinent DOE, NRC, EPA, and DOT quidelines and regulations; review of reports and maps released by the federal project group and contractors; attendance at DOE workshops and conferences; implementation of state-specific research activities; interaction with representatives of federal agencies and other participating states; and interface with media, state officials and legislators, and interested citizens

  9. Project Guarantee 1985. Repository for high-level radioactive waste: construction and operation

    International Nuclear Information System (INIS)

    Anon.

    1985-01-01

    An engineering project study aimed at demonstrating the feasibility of constructing a deep repository for high-level waste (Type C repository) has been carried out; the study is based on a model data-set representing typical geological and rock mechanical conditions as found outside the so-called Permocarboniferous basin in the regions under investigation by Nagra in Cantons Aargau, Schaffhausen, Solothurn and Zuerich. The repository is intended for disposal of high-level waste and any intermediate-level waste from re-processing in which the concentration of long-lived alpha-emitters exceeds the permissible limits set for a Type B repository. Final disposal of high-level waste is in subterranean, horizontally mined tunnels and of intermediate-level waste in underground vertical silos. The repository is intended to accomodate a total of around 6'000 HWL-cylinders (gross volume of around 1'200 m3) and around 10'000 m3 of intermediate-level waste. The total excavated volume is around 1'100'000 m3 and a construction time for the whole repository (up to the beginning of emplacement) of around 15 years is expected. For the estimated 50-year emplacement operations, a working team of around 60 people will be needed and a team of around 160 for the simultaneous tunnelling operations and auxiliary work. The project described in the present report permits the conclusion that construction of a repository for high-level radioactive waste and, if necessary, spent fuel-rods is feasible with present-day technology

  10. Project Guarantee 1985. Repository for low- and intermediate-level radioactive waste: construction and operation

    International Nuclear Information System (INIS)

    Anon.

    1985-01-01

    A constructional engineering project study aimed at clarification of the feasibility of a repository for low- and intermediate-level radioactive waste (type B repository) has been carried out; the study is based on a model data-set derived from the geological, rock mechanical and topographical characterictics of one of Nagra's planned exploration areas. Final storage is effected in subterranean rock caverns accessed by horizontal tunnel. The reception area also is sited below the surface. Storage is conceived in such a way that, after closure of the repository, maintenance and supervision can be dispensed with and a guarantee of high long-term safety can nevertheless be provided. The envisaged repository consists of an entry tunnel for road vehicles and a reception area with a series of caverns for receiving waste, for additional technical facilities and for the production of the concrete back-fill material. The connecting tunnel is serviced by a tunnel railway and the actual repository area consists of several storage caverns. The repository is intended to accomodate a total of 200'000 m3 of solidified low- and intermediate-level waste. Valanginian marl is assumed as the host rock, although it would also be basically possible to house the proposed installations in other host rocks. The excavated material will total around 1'000'000 m3. The construction time for the whole installation is estimated as about 7 years and a working team of around 30 people will be required for the estimated 60-year operational duration. The project described in the present report justifies the conclusion that construction of a repository for low-and intermediate-level radioactive waste is feasible with present-day technology. This conclusion takes into consideration quantitative and operational constraints as well as geological and hydrogeological data relevant to constructional engineering. The latter are derived from a model data-set based on a specific locality

  11. Lower Sioux Indian Community Repository Research Project: Final report

    International Nuclear Information System (INIS)

    O'Brien, L.; Farmer, D.; Lewis, S.

    1988-01-01

    The Upper and Lower Sioux Communities have undertaken a review of the geotechnical aspects of the Department of Energy (DOE) program document entitled Draft Area Recommendation Report (DARR). The DARR recommends twenty sites be retained for continued consideration as a possible location for the second high-level nuclear waste repository. Of these twenty sites, twelve are designated as Potentially Acceptable Sites (PAS), and eight are designated as candidate areas to serve as /open quotes/back-ups/close quotes/ to the PAS's. It is understood there are no current plans to investigate any of the eight candidate areas. It is distressing to the Upper and Lower Sioux Communities that the DOE intends to hold these eight sites in reserve. We do not feel it is appropriate to identify /open quotes/reserve/close quotes/ sites which could be elevated to a PAS at any time during the area phase of investigation. The following chapters in this report provide a summary of the specific procedural and technical problems noted in the screening methodology; and describe our concerns over the selection of NC-13 and NC-14 as reserve sites. Also included are the specific comments recorded by our technical subcontractors as they examined the DARR for us. 10 refs

  12. The Age-ility Project (Phase 1): Structural and functional imaging and electrophysiological data repository

    NARCIS (Netherlands)

    Karayanidis, F.; Keuken, M.C.; Wong, A.; Rennie, J.L.; de Hollander, G.; Cooper, P.S.; Fulham, W.R.; Lenroot, R.; Parsons, M.; Philips, N.; Michie, P.T.; Forstmann, B.U.

    2015-01-01

    Our understanding of the complex interplay between structural and functional organisation of brain networks is being advanced by the development of novel multi-modal analyses approaches. The Age-ility Project (Phase 1) data repository offers open access to structural MRI, diffusion MRI, and

  13. Census of Institutional Repositories in the United States: MIRACLE Project Research Findings. CLIR Publication No. 140

    Science.gov (United States)

    Markey, Karen; Rieh, Soo Young; St. Jean, Beth; Kim, Jihyun; Yakel, Elizabeth

    2007-01-01

    In this report, the authors describe results of a nationwide census of institutional repositories in U.S. academic institutions. The census is one of several activities of the MIRACLE Project, an Institute of Museum and Library Services (IMLS)-funded research program based at the University of Michigan. The acronym MIRACLE means "Making…

  14. Performance analysis for waste repositories in the nordic countries. Report for project AFA-1.2

    Energy Technology Data Exchange (ETDEWEB)

    Vuori, S. [VTT Energy (Finland); Broden, K. [Studsvik RadWaste AB (Sweden); Carugati, S.; Brodersen, K. [Forskningscenter Risoe (Denmark); Walderhaug, T. [Icelandic Radiation Protection Institute (Iceland); Helgason, J. [Ekra Geological Consulting (Iceland); Sneve, M.; Hornkjoel, S. [Norwegian Radiation Protection (Norway); Backe, S. [IFE (Norway)

    1997-02-01

    The Nordic Nuclear Safety Research (NKS) project (AFA-1) focused on safety in the final disposal of long-lived low and medium level radioactive waste and its sub project (AFA-1.2), where this report has been produced, is dealing with the performance analysis of the engineered barrier system (near-field) of the repositories for low-and medium level wastes. The topic intentionally excludes the discussion of the characteristics of the geological host medium. Therefore a more generic discussion of the features of performance analysis is possible independent of the fact that different host media are considered in the Nordic countries. The different waste management systems existing and planned in the Nordic countries are shortly described in the report. In the report main emphasis is paid on the general repositories. Some of the phenomena and interactions relevant for a generic type of repository are discussed as well. Among the different approaches for the development of scenarios for safety and performance analyses one particular method - the Rock Engineering System (RES) - was chosen to be demonstratively tested in a brainstorming session, where the possible interactions and their safety significance were discussed employing a simplified and generic Nordic repository system as the reference system. As an overall impression, the AFA-project group concludes that the use of the RES approach is very easy to learn even during a short discussion session. The use of different ways to indicate the safety significance of various interactions in a graphical user interface increases the clarity. Within the project a simple software application was developed employing a generally available spread sheet programme. The developed tool allows an easy opportunity to link the cell specific comments readily available for the `reader` of the obtained results. A short review of the performance analyses carried out in the Nordic countries for actual projects concerning repositories for

  15. Performance analysis for waste repositories in the nordic countries. Report for project AFA-1.2

    International Nuclear Information System (INIS)

    Vuori, S.; Broden, K.; Carugati, S.; Brodersen, K.; Walderhaug, T.; Helgason, J.; Sneve, M.; Hornkjoel, S.; Backe, S.

    1997-02-01

    The Nordic Nuclear Safety Research (NKS) project (AFA-1) focused on safety in the final disposal of long-lived low and medium level radioactive waste and its sub project (AFA-1.2), where this report has been produced, is dealing with the performance analysis of the engineered barrier system (near-field) of the repositories for low-and medium level wastes. The topic intentionally excludes the discussion of the characteristics of the geological host medium. Therefore a more generic discussion of the features of performance analysis is possible independent of the fact that different host media are considered in the Nordic countries. The different waste management systems existing and planned in the Nordic countries are shortly described in the report. In the report main emphasis is paid on the general repositories. Some of the phenomena and interactions relevant for a generic type of repository are discussed as well. Among the different approaches for the development of scenarios for safety and performance analyses one particular method - the Rock Engineering System (RES) - was chosen to be demonstratively tested in a brainstorming session, where the possible interactions and their safety significance were discussed employing a simplified and generic Nordic repository system as the reference system. As an overall impression, the AFA-project group concludes that the use of the RES approach is very easy to learn even during a short discussion session. The use of different ways to indicate the safety significance of various interactions in a graphical user interface increases the clarity. Within the project a simple software application was developed employing a generally available spread sheet programme. The developed tool allows an easy opportunity to link the cell specific comments readily available for the 'reader' of the obtained results. A short review of the performance analyses carried out in the Nordic countries for actual projects concerning repositories for

  16. Project Guarantee 1985. Final repository for high-level radioactive wastes: The system of safety barriers

    International Nuclear Information System (INIS)

    Anon.

    1985-01-01

    Final disposal of radioactive waste involves preventing the waste from returning from the repository location into the biosphere by means of successively arranged containment measures known as safety barriers. In the present volume NGB 85-04 of the series of reports for Project 'Guarantee' 1985, the safety barrier system for the type C repository for high-level waste is described. The barrier parameters which are relevant for safety analysis are quantified and associated error limits and data scatter are given. The aim of the report is to give a summary documentation of the safety analysis input data and their scientific background. For secure containment of radioactive waste safety barriers are used which effectively limit the release of radioactive material from the repository (release barriers) and effectively retard the entry of the original radioactive material into the biosphere (time barriers). Safety barriers take the form of both technically constructed containment measures and the siting of the repository in suitable geological formations. The technical safety barrier system in the case of high-level waste comprises: the waste solidification matrix (borosilicate glass), massive steel canisters, encasement of the waste canisters, encasement of the waste canisters in highly compacted bentonite, sealing of vacant storage space and access routes on repository closure. The natural geological safety barriers - the host rock and overlying formations provide sufficiently long deep groundwater flow times from the repository location to the earth's surface and for additional lengthening of radionuclide migration times by means of various chemical and physical retardation mechanisms. The stability of the geological formations is so great that hydrogeological system is protected for a sufficient length of time from deterioration caused, in particular, by erosion. Observations in the final section of the report indicate that input data for the type C repository safety

  17. Project JADE. Long-term function and safety. Comparison of repository systems

    International Nuclear Information System (INIS)

    Birgersson, Lars; Pers, K.; Wiborgh, M.

    2001-12-01

    A comparison of the KBS-3 V(ertical deposition), KBS-3 H(orizontal deposition) and MLH repository systems with regard to the long-term repository performance and the radionuclide migration is presented in the report. Several differences between the repository systems have been identified. The differences are mainly related to the: distance between canister and backfilled tunnels, excavated rock volumes, deposition hole direction. The overall conclusion is that the differences are in general quite small with regard to the repository function and safety. None of the differences are of such importance for the long-term repository performance and radionuclide migration that they discriminate any of the repository systems. The differences between the two KBS-3 systems are small. Based on this study, there is no reason to change from the reference system KBS-3 V to KBS-3 H. MLH has the potential to be a very robust system, especially in a long-term perspective. However, the MLH system will require extensive research, development, and analysis before it will be as confident as the reference repository system, KBS-3 V. Although the MLH and KBS-3 H systems are in some ways favourable compared to the reference system KBS-3 V, the overall conclusion is that the KBS-3 V system is still a very attractive system. A major advantage with KBS-3 V is that it is by far the most investigated and developed system. The JADE-project was initiated in 1996, and the main part of the study was carried out during 1997 and 1998. The JADE study is consequently based on presumptions that were valid a few years ago. Some of these presumptions have been modified since then. The new presumptions are however not judged to change the overall conclusions

  18. Demonstrating the sealing of a deep geologic repository: the RECAP project

    International Nuclear Information System (INIS)

    Kuzyk, G.W.; Dixon, D.A.; Martino, J.B.; Kozak, E.T.; Bilinsky, D.M.; Thompson, P.M.

    2006-01-01

    Atomic Energy of Canada Limited (AECL) has operated an Underground Research Laboratory (URL) for twenty-three years (1982-2005). The URL was designed and constructed to carry out in situ geotechnical R and D needed for the Canadian Nuclear Fuel Waste Management program. The facility is now being closed, the final of several phases that have included siting, site evaluation, construction and operation. The closure phase presents a unique opportunity to develop and demonstrate the methodologies needed for closure and site restoration of a deep geologic repository for used nuclear fuel. A wealth of technical background and characterization data, dating back to before the first excavation work was carried out, are available to support closure activities. A number of closure-related activities are being proposed as part of a REpository Closure And Post-closure (RECAP) project. The RECAP project is proposed to include demonstrations of shaft and borehole sealing and monitoring as well as fracture sealing (grouting), room closure and monitoring system decommissioning, all activities that would occur when closing an actual repository. In addition to the closure-related activities, the RECAP project could provide a unique opportunity to conduct intrusion-monitoring demonstrations as part of a repository safeguards demonstration. (author)

  19. Institutional repository in communication: the REPOSCOM project implemented in the digital libraries federation of communication science

    Directory of Open Access Journals (Sweden)

    Sueli Mara Soares Pinto Ferreira

    2007-01-01

    Full Text Available Considering the conceptualization, characterization and context of the institutional repositories (IR this paper discuss the procedures, policies and strategies delineated to the implementation of IR in a research environment. The object of discussion is the project called Reposcom - Institutional Repository of Intercom (Brazilian Society of Interdisciplinary Studies of Communication – which is part of a broader project managed by the Portcom – Information Network in Communication Sciences of Countries of Portuguese Language – and called Digital Libraries Federation in the Communication Sciences. Aiming to share the knowledge and experience acquired with the implementation of the Reposcom, this paper describes its work activities, the decisions made, the customization of the software DSpace (the technological solution and the initial results achieved with the project.

  20. Repository simulation model: Final report

    International Nuclear Information System (INIS)

    1988-03-01

    This report documents the application of computer simulation for the design analysis of the nuclear waste repository's waste handling and packaging operations. The Salt Repository Simulation Model was used to evaluate design alternatives during the conceptual design phase of the Salt Repository Project. Code development and verification was performed by the Office of Nuclear Waste Isolation (ONWL). The focus of this report is to relate the experience gained during the development and application of the Salt Repository Simulation Model to future repository design phases. Design of the repository's waste handling and packaging systems will require sophisticated analysis tools to evaluate complex operational and logistical design alternatives. Selection of these design alternatives in the Advanced Conceptual Design (ACD) and License Application Design (LAD) phases must be supported by analysis to demonstrate that the repository design will cost effectively meet DOE's mandated emplacement schedule and that uncertainties in the performance of the repository's systems have been objectively evaluated. Computer simulation of repository operations will provide future repository designers with data and insights that no other analytical form of analysis can provide. 6 refs., 10 figs

  1. Report on draft Area Recommendation Report for the Crystalline Repository Project

    International Nuclear Information System (INIS)

    1987-01-01

    The draft Area Recommendation Report for the Crystalline Repository Project (ARR) is one product which is part and parcel of a process which was established by Congress and implemented by the Department of Energy. Congress, by enacting the Nuclear Waste Policy Act of 1982 (NWPA), Published Law 97-425, 96 stat 2201, 42 USC 10101, directed the Department of Energy to establish a national program which would provide for the development of repositories for the disposal of high-level radioactive waste and spent nuclear fuel, The NWPA requires, among other things, that affected Tribes and States be provided the opportunity to participate fully in the development of proposed repositories. The Fond du Lac Tribe is an affected tribe whose proprietary interests will be impacted by the Crystalline Repository Project as identified in the draft ARR. The draft ARR does not meet the obligations of the NWPA, the Treaties of 1837 and 1842 or the Trust Responsibility to Indian Tribes. The NWPA required participation by affected tribes, of which the Fond du Lac Band of Lake Superior Chippewa is included. This exclusion has placed in question the validity of the initial CRP process and does not adequately protect the interest of the Fond du Lac Band. Further study is required to fully appreciate the total affect that the Fond du Lac Bands interest may have on this report

  2. MRS system study for the repository: Yucca Mountain Site Characterization Project

    International Nuclear Information System (INIS)

    Sinagra, T.A.; Harig, R.

    1990-12-01

    The US Department of Energy (DOE), Office of Civilian Radioactive Waste Management (OCRWM), has initiated a waste management system study to identify the impacts of the presence or absence of a monitored retrievable storage facility (hereinafter referred to as ''MRS'') on system costs and program schedules. To support this study, life-cycle cost estimates and construction schedules have been prepared for the surface and underground facilities and operations of a geologic nuclear waste repository at Yucca Mountain, Nye County, Nevada. Nine different operating scenarios (cases) have been identified by OCRWM for inclusion in this study. For each case, the following items are determined: the repository design and construction costs, operating costs, closure and decommissioning costs, required staffing, construction schedules, uncertainties associated with the costs and schedules, and shipping cask and disposal container throughputs. 6 refs., 83 figs., 57 tabs

  3. MRS system study for the repository: Yucca Mountain Site Characterization Project

    International Nuclear Information System (INIS)

    Sinagra, T.A.; Harig, R.

    1990-12-01

    The US Department of Energy (DOE), Office of Civilian Radioactive Waste Management (OCRWM), has initiated a waste management system study to identify the impacts of the presence or absence of a monitored retrievable storage facility (hereinafter referred to as ''MRS'') on system costs and program schedules. To support this study, life-cycle cost estimates and construction schedules have been prepared for the surface and underground facilities and operations geologic nuclear waste repository at Yucca Mountain, Nye County, Nevada. Nine different operating scenarios (cases) have been identified by OCRWM for inclusion in this study. For each case, the following items are determined: the repository design and construction costs, operating costs, closure and decommissioning costs, required staffing, construction schedules, uncertainties associated with the costs and schedules, and shipping cask and disposal container throughputs. This document contains A-D

  4. Radioactive waste isolation in salt: peer review of the Office of Nuclear Waste Isolation's reports on preferred repository sites within the Palo Duro Basin, Texas

    International Nuclear Information System (INIS)

    Fenster, D.; Edgar, D.; Gonzales, S.; Domenico, P.; Harrison, W.; Engelder, T.; Tisue, M.

    1984-04-01

    Documents are being submitted to the Salt Repository Project Office (SRPO) of the US Department of Energy (DOE) by Battelle Memorial Institute's Office of Nuclear Waste Isolation (ONWI) to satisfy milestones of the Salt Repository Project of the Civilian Radioactive Waste Management Program. Some of these documents are being reviewed by multidisciplinary groups of peers to ensure DOE of their adequacy and credibility. Adequacy of documents refers to their ability to meet the standards of the US Nuclear Regulatory Commission, as enunciated in 10 CFR 60, and the requirements of the National Environmental Policy Act and the Nuclear Waste Policy Act of 1982. Credibility of documents refers to the validity of the assumptions, methods, and conclusions, as well as to the completeness of coverage. This report summarizes Argonne's review of ONWI's two-volume draft report entitled Identification of Preferred Sites within the Palo Duro Basin: Vol. 1 - Palo Duro Location A, and Vol. 2 - Palo Duro Location B, dated January 1984. Argonne was requested by DOE to review these documents on January 17 and 24, 1984 (see App. A). The review procedure involved obtaining written comments on the reports from three members of Argonne's core peer review staff and three extramural experts in related research areas. The peer review panel met at Argonne on February 6, 1984, and reviewer comments were integrated into this report by the review session chairman, with the assistance of Argonne's core peer review staff. All of the peer review panelists concurred in the way in which their comments were represented in this report (see App. B). A letter report and a draft of this report were sent to SRPO on February 10, 1984, and April 17, 1984, respectively. 5 references

  5. The new Wallula CO2 project may revive the old Columbia River Basalt (western USA) nuclear-waste repository project

    Science.gov (United States)

    Schwartz, Michael O.

    2018-02-01

    A novel CO2 sequestration project at Wallula, Washington, USA, makes ample use of the geoscientific data collection of the old nuclear waste repository project at the Hanford Site nearby. Both projects target the Columbia River Basalt (CRB). The new publicity for the old project comes at a time when the approach to high-level nuclear waste disposal has undergone fundamental changes. The emphasis now is on a technical barrier that is chemically compatible with the host rock. In the ideal case, the waste container is in thermodynamic equilibrium with the host-rock groundwater regime. The CRB groundwater has what it takes to represent the ideal case.

  6. Leadership Behaviors In Project Design Offices

    OpenAIRE

    Kasapoğlu, Esin

    2011-01-01

    Leadership may be defined as the ability to collect a group of people around definite objectives and the achievement of said objectives. An architectural design team needs a leader, and in this paper, the owner of the office is the formal leader. Leadership behaviors of employer architects are directly related to the performance of the design team; therefore, effective leadership is key to a successful design process. Data were collected through a questionnaire on leadership behaviors that wa...

  7. Nuclear Waste Facing the Test of Time: The Case of the French Deep Geological Repository Project.

    Science.gov (United States)

    Poirot-Delpech, Sophie; Raineau, Laurence

    2016-12-01

    The purpose of this article is to consider the socio-anthropological issues raised by the deep geological repository project for high-level, long-lived nuclear waste. It is based on fieldwork at a candidate site for a deep storage project in eastern France, where an underground laboratory has been studying the feasibility of the project since 1999. A project of this nature, based on the possibility of very long containment (hundreds of thousands of years, if not longer), involves a singular form of time. By linking project performance to geology's very long timescale, the project attempts "jump" in time, focusing on a far distant future, without understanding it in terms of generations. But these future generations remain measurements of time on the surface, where the issue of remembering or forgetting the repository comes to the fore. The nuclear waste geological storage project raises questions that neither politicians nor scientists, nor civil society, have ever confronted before. This project attempts to address a problem that exists on a very long timescale, which involves our responsibility toward generations in the far future.

  8. Project JADE. Comparison of repository systems. Executive summary of results

    International Nuclear Information System (INIS)

    Sandstedt, H.; Pers, K.; Birgersson, Lars; Ageskog, L.; Munier, R.

    2001-12-01

    not be studied further. The JADE-project was initiated in 1996, and the main part of the study was carried out during 1997 and 1998. This report is published in 2001. The JADE study is consequently based on presumptions that were valid a few years ago. Some of these presumptions have been modified since then. The new presumptions are, however, not judged to change the overall conclusions

  9. Massachusetts' participation in the US Department of Energy's Crystalline Repository Project: Final report

    International Nuclear Information System (INIS)

    1986-12-01

    The purpose of this report is to review activities of the Crystalline Rock Project in Massachusetts, the context in which it arose, and the implications and possibilities of future federal policy decisions on the siting of a high-level waste repository in a crystalline rock body. Although Massachusetts has been eliminated from consideration, there are still issues of concern to be resolved regarding the potential impacts upon Massachusetts if a site were ever to be chosen in New England

  10. Massachusetts' participation in the US Department of Energy's Crystalline Repository Project: Final report

    International Nuclear Information System (INIS)

    Dukakis, M.S.; Johnston, P.W.; Walker, B. Jr.

    1986-12-01

    The purpose of this report is to review activities of the Crystalline Rock Project (CRP) in Massachusetts, the context in which it arose, and the implications and possibilities of future federal policy decisions on the siting of a HLW repository in a crystalline rock body. Although Massachusetts has been eliminated from consideration, there are still issues of concern to be resolved regarding the potential impacts upon Massachusetts if a site were ever to be chosen in New England

  11. The function of packing materials in a high-level nuclear waste repository and some candidate materials: Salt Repository Project

    International Nuclear Information System (INIS)

    Bunnell, L.R.; Shade, J.W.

    1987-03-01

    Packing materials should be included in waste package design for a high-level nuclear waste repository in salt. A packing material barrier would increase confidence in the waste package by alleviating possible shortcomings in the present design and prolonging confinement capabilities. Packing materials have been studied for uses in other geologic repositories; appropriately chosen, they would enhance the confinement capabilities of salt repository waste packages in several ways. Benefits of packing materials include retarding or chemically modifying brines to reduce corrosion of the waste package, providing good thermal conductivity between the waste package and host rock, retarding or absorbing radionuclides, and reducing the massiveness of the waste package. These benefits are available at low percentage of total repository cost, if the packing material is properly chosen and used. Several candidate materials are being considered, including oxides, hydroxides, silicates, cement-based mixtures, and clay mixtures. 18 refs

  12. Project Guarantee 1985. Final repository for low- and intermediate level radioactive wastes: Safety report

    International Nuclear Information System (INIS)

    Anon.

    1985-01-01

    Storage of radioactive waste must delay the return of radionuclides to the biosphere for a long period of time and must maintain the release rates at a sufficiently low level for all time. This is achieved with the aid of a series of safety barriers which consist, on the one hand, of technical barriers in the repository and, on the other hand , of natural geological barriers as they occur at the repository location. In order to assess the efficiency of the barriers, the working methods of the technical barriers and the host rock must be understood. This understanding is transferred into quantitative models in order to calculate the safety of the repository. The individual barriers and the methods used to modelling their functions were described in volume NGB 85-07 of the Project Guarantee 1985 report series and the data necessary for modelling were given. The models and data are used in the safety analysis, the results of which are contained in the present report. Safety considerations show that models are available in Switzerland which allow, in principle, an assessment of the long-term behaviour of a repository for low- and intermediate-level waste. The evaluation of earlier studies and experimental work, suitable laboratory measurements and results from field research enable compilation of a representative data-set so that the requirements for quantitative statements on safety of final disposal are met from this side also. The safety calculations show that the radiation doses calculated for a base case scenario with realistic/conservative parameter values are negligibly low. Also, radiation doses which are clearly under the protection standard of 10 mrem per year result for conservative values and the cumulation of several conservative assumptions. Even assuming exposure of the repository by erosion, a radiotoxicity of the soil formed results which is under natural values

  13. Project Alternative Systems Study - PASS. Analysis of performance and long-term safety of repository concepts

    International Nuclear Information System (INIS)

    Birgersson, L.; Skagius, K.; Wiborgh, M.; Widen, H.

    1992-09-01

    This study is part of the Project on Alternative Systems Study, PASS, with the overall aim to perform a technical/economical ranking of alternative repository concepts and canisters for the final storage of spent nuclear fuel. The comparison should in the first stage separately assess technology in construction and operation, long-term performance and safety, and costs. Three of the repository concepts are assumed to be located at a depth of approximately 500 m in the host rock, KBS-3, Very Long Holes (VLH) and Medium Long Holes (MLH). In the KBS-3 concept the canisters are deposited in vertical deposition holes in a system of parallel storage tunnels. In the VLH concept larger canisters are deposited in long horizontal tunnels. The MLH concept, is an evolution of the two other concepts, with KBS-3 type canisters deposited in horizontal tunnels. Smaller canisters are to be deposited in deep bore holes at a depth between 2000 to 4000 m in the Very Deep Holes (VDH) concept. In all concepts the canisters will be surrounded by a bentonite buffer. The aim of the present study is to analyze and compare the performance and long-term safety of the repository concepts. Only a qualitative comparison of the concepts is made as no calculations of radionuclide releases or dose to man have been performed. The ranking of the repository concepts was carried out by comparing the VDH, VLH and MLH concept with the KBS-3 concept. The performance and long-term safety of the repositories located at 500 m level will be based on a multiple barrier system and the predictions for the concepts will involve similar uncertainties. (54 refs.)

  14. Technical support for GEIS: radioactive waste isolation in geologic formations. Volume 2. Commercial waste forms, packaging and projections for preconceptual repository design studies

    International Nuclear Information System (INIS)

    1978-04-01

    This volume, Y/OWI/TM-36/2, ''Commercial Waste Forms, Packaging and Projections for Preconceptual Repository Design Studies,'' is one of a 23-volume series, ''Technical Support for GEIS: Radioactive Waste Isolation in Geologic Formations,'' Y/OWI/TM-36, which supplements the ''Contribution to Draft Generic Environmental Impact Statement on Commercial Waste Management: Radioactive Waste Isolation in Geologic Formations,'' Y/OWI/TM-44. The series provides a more complete technical basis for the preconceptual designs, resource requirements, and environmental source terms associated with isolating commercial LWR wastes in underground repositories in salt, granite, shale and basalt. Wastes are considered from three fuel cycles: uranium and plutonium recycling, no recycling of spent fuel and uranium-only recycling. This volume contains the data base for waste forms, packages, and projections from the commercial waste defined by the Office of Waste Isolation in ''Nuclear Waste Projections and Source Term Data for FY 1977,'' Y/OWI/TM-34. Also, as an alternative data base for repository design and analysis, waste forms, packages, and projections for commercial waste defined by Battelle Pacific Northwest Laboratory (BPNL) have been included. This data base consists of a reference case for use in the alternative design study and a definition of combustible wastes for use in mine fire and hydrogen generation analyses

  15. Technical support for GEIS: radioactive waste isolation in geologic formations. Volume 2. Commercial waste forms, packaging and projections for preconceptual repository design studies

    Energy Technology Data Exchange (ETDEWEB)

    1978-04-01

    This volume, Y/OWI/TM-36/2, ''Commercial Waste Forms, Packaging and Projections for Preconceptual Repository Design Studies,'' is one of a 23-volume series, ''Technical Support for GEIS: Radioactive Waste Isolation in Geologic Formations,'' Y/OWI/TM-36, which supplements the ''Contribution to Draft Generic Environmental Impact Statement on Commercial Waste Management: Radioactive Waste Isolation in Geologic Formations,'' Y/OWI/TM-44. The series provides a more complete technical basis for the preconceptual designs, resource requirements, and environmental source terms associated with isolating commercial LWR wastes in underground repositories in salt, granite, shale and basalt. Wastes are considered from three fuel cycles: uranium and plutonium recycling, no recycling of spent fuel and uranium-only recycling. This volume contains the data base for waste forms, packages, and projections from the commercial waste defined by the Office of Waste Isolation in ''Nuclear Waste Projections and Source Term Data for FY 1977,'' Y/OWI/TM-34. Also, as an alternative data base for repository design and analysis, waste forms, packages, and projections for commercial waste defined by Battelle Pacific Northwest Laboratory (BPNL) have been included. This data base consists of a reference case for use in the alternative design study and a definition of combustible wastes for use in mine fire and hydrogen generation analyses.

  16. Rhode Island crystalline repository siting project: Technical progress report, Calendar year 1986

    International Nuclear Information System (INIS)

    Vild, B.

    1987-01-01

    A Nuclear Waste Fund established by the Nuclear Waste Policy Act of 1982 provides financial support to affected states to participate in the high-level radioactive waste repository siting program of the US Department of Energy. In Rhode Island, that function was performed by a multidisciplinary Project Review Team consisting of staff from three State agencies. Members of the Review Team attended several meetings in 1986 to discuss mutual concerns with Federal, State and Tribal officials. Comments were developed on DOE's Draft Area Recommendation Report. Members of the Review Team also testified at a public hearing in Providence on the Draft ARR, and developed and distributed a public information booklet. In May, Secretary of Energy John Herrington announced the suspension of the crystalline repository siting program. The remainder of the year was spent monitoring litigation challenging that decision and pending legislation. Administrative phase-down of the program was essentially complete by the close of the calendar year

  17. The Poco de Caldas project: Natural analogues of processes in a radioactive waste repository

    International Nuclear Information System (INIS)

    Chapman, N.A.; McKinley, I.G.; Shea, M.E.; Smellie, J.A.T.

    1993-01-01

    The safe disposal of radioactive wastes by burial in deep geologic formations requires long-term predictions of the future behavior of the wastes nd their engineered repository. Such predictions can be tested by evaluating processes analogous to those which will occur in a repository, which have been long active in the natural geochemical environment. The title project is a comprehensive study of two ore deposits in Minas Gerais, Brasil, aimed at looking at uranium and thorium series radionuclide and rare earth element mobility, the development and movement of redox fronts, and the nature of natural groundwater colloids. A multidisciplinary team of experts from 27 laboratories carried out a fully integrated study of the geology, geomorphology, hydrogeology, geochemistry, hydrochemistry and geomicrobiology of the two sited for nearly four years. This book contains 20 papers covering the detailed findings, with particular emphasis on their significance for radioactive waste disposal, especially on the use of the data in testing models of radionuclide movement

  18. The SeaView EarthCube project: Lessons Learned from Integrating Across Repositories

    Science.gov (United States)

    Diggs, S. C.; Stocks, K. I.; Arko, R. A.; Kinkade, D.; Shepherd, A.; Olson, C. J.; Pham, A.

    2017-12-01

    SeaView is an NSF-funded EarthCube Integrative Activity Project working with 5 existing data repositories* to provide oceanographers with highly integrated thematic data collections in user-requested formats. The project has three complementary goals: Supporting Scientists: SeaView targets scientists' need for easy access to data of interest that are ready to import into their preferred tool. Strengthening Repositories: By integrating data from multiple repositories for science use, SeaView is helping the ocean data repositories align their data and processes and make ocean data more accessible and easily integrated. Informing EarthCube (earthcube.org): SeaView's experience as an integration demonstration can inform the larger NSF EarthCube architecture and design effort. The challenges faced in this small-scale effort are informative to geosciences cyberinfrastructure more generally. Here we focus on the lessons learned that may inform other data facilities and integrative architecture projects. (The SeaView data collections will be presented at the Ocean Sciences 2018 meeting.) One example is the importance of shared semantics, with persistent identifiers, for key integration elements across the data sets (e.g. cruise, parameter, and project/program.) These must allow for revision through time and should have an agreed authority or process for resolving conflicts: aligning identifiers and correcting errors were time consuming and often required both deep domain knowledge and "back end" knowledge of the data facilities. Another example is the need for robust provenance, and tools that support automated or semi-automated data transform pipelines that capture provenance. Multiple copies and versions of data are now flowing into repositories, and onward to long-term archives such as NOAA NCEI and umbrella portals such as DataONE. Exact copies can be identified with hashes (for those that have the skills), but it can be painfully difficult to understand the processing

  19. Project Guarantee 1985. Radioactive wastes: Properties and allocation to final repository types

    International Nuclear Information System (INIS)

    Anon.

    1985-01-01

    An overview of waste-specific data, as input into constructional engineering studies and safety analyses of Project Guarantee, is presented which describes the activity inventory of the radioactive waste to be disposed of, classified according to origin, the quantitative spezifications of the waste, the concept of classifying waste into appropriate categories, grouping into major categories and distribution of these between the different repository types, and finally, control measures which ensure observance of the specifications of the waste to be disposed of. It is expedient, for conceptional considerations and for the operational phase of the repository, to split the waste up into several suitably specified waste categories according to the practical aspects of origin and conditioning. This can be done in such a way that the waste within a specific category is sufficiently homogeneous with regard to its radiological properties and chemical composition for the requirements of safety analysis. The present volume contains base-data for around 30 waste types. Two waste types are documented with more detailed data as an example of the practicability of the comprehensive waste characterisation contained in reference report NTB 84-47. It is shown that waste-specific data which go into safety analysis and constructional engineering project studies are available in an appropriate degree of detail. The method of distributing the waste between repositories with differing degrees of protection and procedures for controlling adherence to admission specifications are developed and documented. It can be ensured that no waste with an impermissibly high radiotoxicity level will later be emplaced in a repository for low- and intermediate-level waste

  20. 48 CFR 301.607-78 - Contracting Officer designation of a Program/Project Manager as the Contracting Officer's...

    Science.gov (United States)

    2010-10-01

    ... designation of a Program/Project Manager as the Contracting Officer's Technical Representative. 301.607-78... Contracting Officer designation of a Program/Project Manager as the Contracting Officer's Technical... acquisition. However, for those individuals serving as a Program or Project Manager under a FAC-P/PM...

  1. Experimental conditions and monitoring items of the prototype repository project (PRP). Research document

    International Nuclear Information System (INIS)

    Sugita, Yutaka; Ito, Akira; Kawakami, Susumu

    2003-03-01

    Various experiments are ongoing in the underground research facility 'the Hard Rock Laboratory (HRL)' of SKB in Sweden for the geological disposal of the high-level radioactive waste. International joint project Prototype Repository Project (PRP) is one of the experiments in the HRL which has some engineered barrier systems and to study the coupled behavior happening in and around the engineered barrier system. JNC has joined this international joint project PRP to obtain the information of the coupled behavior on such systematic engineered barrier system and to apply the JNC's coupled THMC analytical code to the prediction and back analysis of the PRP. The analytical code will be verified through these analyses in this project. JNC can apply the verified analytical code to assess the coupled behavior in Japan. This report summarizes the experimental conditions and monitoring items of the PRP. (author)

  2. Region-to-area screening methodology for the Crystalline Repository Project

    International Nuclear Information System (INIS)

    1985-04-01

    The purpose of this document is to describe the Crystalline Repository Project's (CRP) process for region-to-area screening of exposed and near-surface crystalline rock bodies in the three regions of the conterminous United States where crystalline rock is being evaluated as a potential host for the second nuclear waste repository (i.e., in the North Central, Northeastern, and Southeastern Regions). This document indicates how the US Department of Energy's (DOE) General Guidelines for the Recommendation of Sites for Nuclear Waste Repositories (10 CFR 960) were used to select and apply factors and variables for the region-to-area screening, explains how these factors and variable are to be applied in the region-to-area screening, and indicates how this methodology relates to the decision process leading to the selection of candidate areas. A brief general discussion of the screening process from the national survey through area screening and site recommendation is presented. This discussion sets the scene for detailed discussions which follow concerning the region-to-area screening process, the guidance provided by the DOE Siting Guidelines for establishing disqualifying factors and variables for screening, and application of the disqualifying factors and variables in the screening process. This document is complementary to the regional geologic and environmental characterization reports to be issued in the summer of 1985 as final documents. These reports will contain the geologic and environmental data base that will be used in conjunction with the methodology to conduct region-to-area screening

  3. Salt Repository Project site study plan for seismographic monitoring: Revision 1

    International Nuclear Information System (INIS)

    1987-01-01

    This site study plan describes the seismographic monitoring activities to be conducted during the early stages of Site Characterization at the Deaf Smith County site, Texas. The field programs has been designed to provide data useful in addressing information/data needs resulting from Federal/State/local regulatory requirements and repository program requirements. Sixteen new and three relocated seismographic stations will be added to the now existing network of 13 stations for a total of 32 stations in the network. The areal extent is being expanded and selected regions covered more densely to provide more accurate monitoring and location of microearthquakes. More sophisticated instruments are being used at selected locations to allow for more detailed analysis. A few seismographs are being installed at depth to provide a limited 3-D monitoring network in the area of the repository. The Salt Repository Project (SRP) Networks specify the schedule under which the program will operate. The Technique Field Services Contractor (TFSC) is responsible for conducting the field program. Data will be handled and reported in accordance with established SRP procedures. A quality assurance program will be utilized to assure that activities affecting quality are performed correctly and that appropriate documentation is maintained. 32 refs., 11 figs., 4 tabs

  4. Radioactive waste isolation in salt: peer review of the Office of Nuclear Waste Isolation's report on Functional Design Criteria for a Repository for High-Level Radioactive Waste

    International Nuclear Information System (INIS)

    Hambley, D.F.; Russell, J.E.; Busch, J.S.; Harrison, W.; Edgar, D.E.; Tisue, M.W.

    1984-08-01

    This report summarizes Argonne's review of the Office of Nuclear Waste Isolation's (ONWI's) draft report entitled Functional Design Criteria for High-Level Nuclear Waste Repository in Salt, dated January 23, 1984. Recommendations are given for improving the ONWI draft report

  5. Spent fuel stability under repository conditions - final report of the european project

    International Nuclear Information System (INIS)

    Poinssot, Ch.; Ferry, C.; Kelm, M.; Cavedon, J.M.; Corbel, C.; Jegou, Ch.; Lovera, P.; Miserque, F.; Poulesquen, A.; Grambow, B.; Andriambololona, Z.; Martinez-Esparza, A.; Kelm, M.; Loida, A.; Rondinella, V.; Wegen, D.; Spahiu, K.; Johnson, L.; Cachoir, Ch.; Lemmens, K.; Quinones, J.; Bruno, J.; Christensen, H.; Grambow, B.; Pablo, J. de

    2005-01-01

    This report is the final report of the European Project 'Spent Fuel Stability under Repository Conditions' (FIKW-CT-2001-00192 SFS) funded by the European Commission from Nov.2000 to Oct.2004. Gathering the work performed by 13 partners from 6 countries, it aims to specifically focus on the spent nuclear fuel long term alteration in deep repository and the subsequent radionuclides release rate as a function of time. This report synthesised the wide experimental work performed within this project and enlightens the major outcomes, which can be summarised as follow: - A new model for defining the Instant Release Fraction was developed in order to consider the potential fuel evolution before the water penetrates the canister. Quantitative assessment has been produced and shows a significant contribution to the long term dose; - Based on new experimental data, kinetic radiolytic scheme have been upgraded and are used to determine the amount of oxidants produced at the fuel/water interface; - The existence of a dose threshold below which the water radiolysis does not influence the fuel alteration has been demonstrated and occurs between 3.5 and 33 MBq.g UO21. Above the threshold, the fuel alteration rates is directly related to the dose rate. - Hydrogen was experimentally demonstrated to be an efficient oxidants scavenger preventing therefore the fuel oxidation. Molecular mechanism still need to be understood. - Finally, a new Matrix Alteration Model integrating most of the SFS results (apart of the hydrogen effect) has been developed and used to assess the fuel long tern stability in representative conditions of deep repository in salt, clay-rock and granite. The breadth of the results and the significance of the conclusions testify of the success of the collaboration within the project. (authors)

  6. Salt Repository Project: Waste Package Program (WPP) modeling activiteis: FY 1984 annual report

    International Nuclear Information System (INIS)

    Kuhn, W.L.; Simonson, S.A.; Pulsipher, B.A.

    1987-03-01

    The Pacific Northwest Laboratory (PNL) is supporting the US Department of Energy's (DOE) Salt Repository Project (SRP) through its Waste Package Program (WPP). During FY 1984, the WPP continued its program of waste package component development and interactions testing and application of the resulting data base to develop predictive models describing waste package degradation and radionuclide release. Within the WPP, the Modeling Task (Task 04 during FY 1984) was conducted to interpret the tests in such a way that scientifically defensible models can be developed for use in qualification of the waste package

  7. Salt Repository Project site study plan for background environmental radioactivity: Revision 1

    International Nuclear Information System (INIS)

    1987-12-01

    The Site Study Plan for Background Environmental Radioactivity describes a field program consisting of an initial radiological survey and a radiological sampling program. The field program includes measurement of direct radiation and collection and analysis of background radioactivity samples of air, precipitation, soil, water, milk, pasture grass, food crops, meat, poultry, game, and eggs. The plan describes for each study the need for the study, the study design, data management, and use, schedule of proposed activities, and quality assurance requirements. These studies will provide data needed to satisfy requirements contained in, or derived from, the Salt Repository Project Requirements Document. 43 refs., 10 figs., 7 tabs

  8. European indoor air quality audit project in 56 office buildings

    NARCIS (Netherlands)

    Bluyssen, P.M.; Oliveira Fernandes, E. de; Groes, L.; Clausen, G.H.; Fanger, F.O.; Valbjorn, O.; Bernhard, C.A.; Roulet, C.A.

    1996-01-01

    A European project started at the end of 1992, in which, in addition to current methods, trained sensory panels were used to investigate office buildings all over Europe. The main aim of this EC-Audit was to develop assessment procedures and guid-ance on ventilation and source control, to help

  9. Co-operation between Slovenia and Croatia in the low- and intermediate level radioactive waste repository project

    International Nuclear Information System (INIS)

    Schaller, A.; Lokner, V.; Subasic, D.; Zeleznik, N.; Mele, I.; Tomse, P.

    2001-01-01

    The paper describes the LILW repository project development in Slovenia and Croatia from the viewpoint of co-operation of national agencies for radioactive waste management - ARAO in Slovenia and APO in Croatia. The project performance, as well as the co-operation itself, are based on the fact that NPP Krsko, sited in Slovenia, is the joint venture facility of both countries, which are consequently obliged to find a proper solution for final disposal of operational and decommissioning radioactive waste generated by the plant. The main aspects of the project development in both countries, such as LILW repository site selection and characterisation, development of repository conceptual design, performance assessment/safety analysis procedures and public participation, are presented in the paper. Based on separate descriptions of the project development in Slovenia and Croatia respectively, the main aspects of co-operation between ARAO and APO are elaborated.(author)

  10. The technical and economical optimization of the French geological repository project - 59275

    International Nuclear Information System (INIS)

    Raffard, Rodolphe; Labalette, Thibaud

    2012-01-01

    Document available in abstract form only. Full text of publication follows: The French Act of 28 June 2006 made the choice of reversible geological repository for long term management of high level and long-lived intermediate level waste. Andra is in charge of designing, building and operating the future industrial repository Cigeo. Current major issues consist in preparing the application to be examined in 2015, planning the construction so that operation would start in 2025 and optimizing the design on both technical and economical points of view. The Dossier 2005 -provided by Andra prior to the 2006 Act- established the feasibility of the project, especially towards compliance with safety and reversibility. Design options were presented at that time with the objective of demonstrating feasibility without ruling out possibilities of further optimization. Along with the scientific and technical review of Dossier 2005, a number of design optimization topics were identified in 2006. Working groups involved Andra's specialists as well as external experts. A particular attention was given to (i) the industrial experience of waste producers and (ii) the characteristics of the clay layer investigated in the Meuse/Haute-Marne Underground Research Laboratory. The 2006 optimization topics were prioritized taking into account their economical impact and the development plan of the project

  11. Final status of the salt repository project waste package program experimental database

    International Nuclear Information System (INIS)

    Thornton, B.M.; Reimus, P.W.

    1988-03-01

    This report describes the final status of the Salt Repository Project Waste Package Program Experimental Database. The data base serves as a clearinghouse for all data collected within the Waste Package Program (WPP) and its predecessor programs at Pacific Northwest Laboratory (PNL). The database was maintained using RS/1 database management software. Documented assurance that the entries in the database were consistent with experimental records was provided by having each experimentalist inspect the entries and signify that they were in agreement with the records. The inspection and signoff were done per PNL technical procedures. Data for which it was impossible to obtain the experimentalist's inspection and signature were segregated from the rest of the database, although they could still be accessed by WPP staff. The WPPED contains two groups of subdirectories. One group contains data taken prior to the installation of quality assurance procedures at PNL. The other group of subdirectories contains data taken under the NQA-1 procedures since their installation in April 1985. As part of closeout activities in the Salt Repository Project, the WPP database has been archived onto magnetic media. The data in the database are available by request on magnetic media or in hardcopy form. 2 refs

  12. JSS project phase 4: Experimental and modelling studies of HLW glass dissolution in repository environments

    International Nuclear Information System (INIS)

    1987-10-01

    A goal of the JSS project was to develop a scientific basis for understanding the effects of waste package components, groundwater chemistry, and other repository conditions on glass dissolution behaviour, and to develop and refine a model for the processes governing glass dissolution. The fourth phase of the project, which was performed by the Hahn-Meitner-Institut, Berlin, FRG, dealt specifically with model development and application. Phase 4 also adressed whether basaltic glasses could serve as natural analogues for nuclear waste glasses, thus providing a means to test the capability of the model for long-term predictions. Additional experiments were performed in order to complete the data base necessary to model interactions between the glass and bentonite and between glass and steel corrosion products. More data on temperature, S/V, and pH dependence of the glass/water reaction were also collected. In this report, the data acquired during phase 4 are presented and discussed. (orig./DG)

  13. Salt Repository Project site study plan for stratigraphic boreholes: Revision 1, December 18, 1987

    International Nuclear Information System (INIS)

    1987-01-01

    This site study describes the Stratigraphic Boreholes field work to be conducted during the early stages of Site Characterization at the Deaf Smith County, Texas site. The field program has been designed to provide data useful in addressing information/data needs resulting from Federal/State/local regulations, and repository program requirements. Four Stratigraphic Holes will be drilled near the perimeter of the site to document the subsurface geologic conditions in that area and to provide data necessary for design and construction of the Exploratory Shaft Facilities. Continuous samples will be recovered from the ground surface to the total depth of each sell. Geophysical well logs will provide additional coverage of the stratigraphic section. In-situ down hole testing will include short term hydrologic tests and hydraulic fracture tests to provide information on deep groundwater characteristics and regional stress patterns, respectively. Field methods/tests are chosen that provide the best or only means of obtaining the required data. The Salt Repository Project (SRP) Networks specify the schedule which the program will operate. The Technical Services Contractor is responsible for conducting the field program of drilling and testing. Samples and data will be handled and reported in accordance with established SRP procedures. A quality assurance program will be utilized to assure that activities affecting quality are performed correctly and that the appropriate documentation is maintained. 30 refs., 13 figs., 4 tabs

  14. DOE Contribution to the 2015 US CLIVAR Project Office Budget

    Energy Technology Data Exchange (ETDEWEB)

    DeWeaver, Eric [National Science Foundation (NSF), Washington, DC (United States); Patterson, Michael [US CLIVAR Project Office (USCPO),Washington DC (United States)

    2017-05-10

    The primary goal of the US Climate Variability and Predictability (CLIVAR) Project Office is to enable science community planning and implementation of research to understand and predict climate variability and change on intraseasonal-to-centennial timescales, through observations and modeling with emphasis on the role of the ocean and its interaction with other elements of the Earth system, and to serve the climate community and society through the coordination and facilitation of research on outstanding climate questions.

  15. UMTRA Project Office quality assurance program plan. Revision 6

    International Nuclear Information System (INIS)

    1994-09-01

    The Uranium Mill Tailings Remedial Action (UMTRA) Project was established to accomplish remedial actions at inactive uranium mill tailings sites. The UMTRA Project's mission is to stabilize and control the residual radioactive materials at designated sites in a safe and environmentally sound manner so as to minimize or eliminate radiation health hazards to the public. Because these efforts may involve possible risks to public health and safety, a quality assurance (QA) program that conforms to the applicable criteria has been established to control the quality of the work. This document, the Quality Assurance Program Plan (QAPP), brings into one document the essential criteria to be applied on a selective basis, depending upon the nature of the activity being conducted, and describes how those criteria shall be applied to the UMTRA Project. QA requirements contained in this QAPP shall apply to all personnel, processes, and activities, including planning, scheduling, and cost control, performed by the UMTRA Project Office and its contractors

  16. The Age-ility Project (Phase 1): Structural and functional imaging and electrophysiological data repository.

    Science.gov (United States)

    Karayanidis, Frini; Keuken, Max C; Wong, Aaron; Rennie, Jaime L; de Hollander, Gilles; Cooper, Patrick S; Ross Fulham, W; Lenroot, Rhoshel; Parsons, Mark; Phillips, Natalie; Michie, Patricia T; Forstmann, Birte U

    2016-01-01

    Our understanding of the complex interplay between structural and functional organisation of brain networks is being advanced by the development of novel multi-modal analyses approaches. The Age-ility Project (Phase 1) data repository offers open access to structural MRI, diffusion MRI, and resting-state fMRI scans, as well as resting-state EEG recorded from the same community participants (n=131, 15-35 y, 66 male). Raw imaging and electrophysiological data as well as essential demographics are made available via the NITRC website. All data have been reviewed for artifacts using a rigorous quality control protocol and detailed case notes are provided. Copyright © 2015. Published by Elsevier Inc.

  17. Tectonic risk forecasting through expert elicitation for geological repositories: the TOPAZ project

    Energy Technology Data Exchange (ETDEWEB)

    Goto, Junichi [NUMO, Tokyo (Japan); Kawamura, Hideki [Obayashi Corporation, Tokyo (Japan); Chapman, Neil [MCM Consulting, Baden (Switzerland)

    2013-07-01

    This paper describes the development of a probabilistic methodology for the evaluation of tectonic hazards to geological repositories in Japan. The approach is a development of NUMO's ITM methodology, which produced probabilistic hazard maps for volcanism and rock deformation for periods up to about 100,000 years in a set of Case Studies that covered a large area of the country. To address potential regulatory requirements, the TOPAZ project has extended the ITM methodology to look into the period between 100,000 and 1 million years, where significant uncertainties begin to emerge about the tectonic framework within which quantitative forecasting can be made. Part of this methodology extension has been to adopt expert elicitation techniques to capture differing expert views as a means of addressing such uncertainties. This paper briefly outlines progress in this development work to date. (authors)

  18. Tectonic risk forecasting through expert elicitation for geological repositories: the TOPAZ project

    International Nuclear Information System (INIS)

    Goto, Junichi; Kawamura, Hideki; Chapman, Neil

    2013-01-01

    This paper describes the development of a probabilistic methodology for the evaluation of tectonic hazards to geological repositories in Japan. The approach is a development of NUMO's ITM methodology, which produced probabilistic hazard maps for volcanism and rock deformation for periods up to about 100,000 years in a set of Case Studies that covered a large area of the country. To address potential regulatory requirements, the TOPAZ project has extended the ITM methodology to look into the period between 100,000 and 1 million years, where significant uncertainties begin to emerge about the tectonic framework within which quantitative forecasting can be made. Part of this methodology extension has been to adopt expert elicitation techniques to capture differing expert views as a means of addressing such uncertainties. This paper briefly outlines progress in this development work to date. (authors)

  19. Salt repository project site study plan for water resources: Revision 1

    International Nuclear Information System (INIS)

    1987-12-01

    The Site Study Plan for Water Resources describes a field program consisting of surface-water and ground-water characterization. The surface-water studies will determine the drainage basin characteristics (i.e., topography, soils, land use), hydrometeorology, runoff to streams and playas, and surface-water quality (i.e., offsite pollution sources in playa lakes and in streams). The environmental ground-water studies will focus on ground-water quality characterization. The site study plan describes for each study the need for the study, study design, data management and use, schedule of proposed activities, and quality assurance. These studies will provide data needed to satisfy requirements contained in, or derived from, the Salt Repository Projects Requirements Document. 78 refs., 8 figs., 5 tabs

  20. Site study plan for Playa investigations, Deaf Smith County, Texas: Salt Repository Project

    International Nuclear Information System (INIS)

    1987-01-01

    This plan defines the purpose and objectives of the Playa Investigation Study, presents a plan of work to provide the information necessary to resolve issues, and discusses the rationale for test method selection. The required information will be obtained from existing well drilling records, describing and testing of soil and rock samples recovered from project test holes, geophysical well logs, seismic surveys, and shallow test pits excavated at ground surface. There have been numerous, often conflicting, theories presented to explain the origin(s) of the playas of the Texas High Plains. The primary purpose of this study is to establish if existing playas and playa alignments are related to deeper subsurface structure, such as faulting or salt dissolution, the potential for future playa development, and the significance of existing and/or future playas on siting a repository in Deaf Smith County, Texas. 11 refs

  1. Monitoring as component for the decision making in final repository projects; Monitoring als Baustein fuer die Entscheidungsfindung in Endlagerprojekten

    Energy Technology Data Exchange (ETDEWEB)

    Kallenbach-Herbert, Beate; Alt, Stefan [Oeko-Institut e.V., Darmstadt (Germany)

    2012-12-15

    The monitoring in final radioactive waste repositories is performed by continuous or repeated measurements of technical and geologic parameters during long time periods. The collected data serve manifold purposes. The central focus is to provide fundamental information for the decision between and within the three phases of a final repository project. This means that monitoring is not only the sum of technical surveillance measures. Monitoring is also important for several sociopolitical decisions, for instance in case of closure of the repository. The article discusses possible objectives and shows the relevant technical aspects that are used deduce the requirements for an integrated monitoring concept. It is shown that a monitoring concept should be developed early enough involving all groups that are concerned by the waste disposal project.

  2. Office of River Protection: Simplifying Project management tools

    International Nuclear Information System (INIS)

    TAYLOR, D.G.

    2000-01-01

    The primary approach to the effort was to form a multi-organizational team comprised of federal and contractor staff to develop and implement the necessary tools and systems to manage the project. In late 1999 the DOE Manager of the Office of River Protection formed the Project Integration Office to achieve the objective of managing the efforts as a single project. The first major task, and the foundation upon which to base the development of all other tools, was the establishment of a single baseline of activities. However, defining a single scope schedule and cost was a difficult matter indeed. Work scopes were available throughout the project, but the level of detail and the integration of the activities existed primarily between working groups and individuals and not on a project-wide basis. This creates a situation where technical needs, logic flaws, resource balancing, and other similar integration needs are not elevated for management attention and resolution. It should be noted that probably 90% of the interface issues were known and being addressed. The key is simplifying the process and providing tangible assurance that the other 10% does not contain issues that can delay the project. Fortunately all of the contractors employed a common scheduling tool, which served as the basis for first communicating and then integrating baseline activities. Utilizing a powerful computer-based scheduling tool, it was soon possible to integrate the various schedules after the following was accomplished: Establishment of a scheduling specification (standardized input, coding, and approach to logic); and Clearly defined project assumptions

  3. Project Manager Performance and the Decision to Backsource the Project Management Office

    Science.gov (United States)

    Lively, William R.

    2014-01-01

    This paper reviews a management decision of an Information Technology Outsource (ITO) provider to backshore the management oversight of its Project Management Office (PMO) after only one year of offshore operations. Governance is a term used in project management to refer to management oversight. The review is a quantitative analysis of existing…

  4. SKI SITE-94. Deep Repository Performance Assessment Project Volume I and II

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-12-01

    The function of SITE-94 is to provide the Swedish Nuclear Power Inspectorate (SKI) with the capacity and supporting knowledge needed for reviewing the Swedish nuclear industry`s R and D programs and for reviewing license applications, as stipulated in Swedish legislation. The report is structured as a Performance Assessment exercise needed for input to decisions regarding repository safety, but the SITE-94 is not a safety assessment or a model for future assessments to be undertaken by the prospective licensee. The specific project objectives of SITE-94 comprise site evaluation, performance assessment methodology, canister integrity and radionuclide release and transport calculations. The report gives a detailed description of the many inter-related studies undertaken as part of the research project. As a general conclusion it is noted that the SITE-94 project has significantly advanced SKI`s capability of reviewing performance assessments and has led to the development of a tool-kit for carrying out assessment calculations, both in terms of numerical and scoping analyses. The study has highlighted a number of key issues for safety assessment (and consequently for disposal system design): Canister performance; Derived parameters of geosphere retention properties; Spatial variability of groundwater flow and geochemistry of migration paths; Time dependency (more emphasis on transient, time-dependent processes); Buffer evolution over long time. 488 refs.

  5. SKI SITE-94. Deep Repository Performance Assessment Project Volume I and II

    International Nuclear Information System (INIS)

    1996-12-01

    The function of SITE-94 is to provide the Swedish Nuclear Power Inspectorate (SKI) with the capacity and supporting knowledge needed for reviewing the Swedish nuclear industry's R and D programs and for reviewing license applications, as stipulated in Swedish legislation. The report is structured as a Performance Assessment exercise needed for input to decisions regarding repository safety, but the SITE-94 is not a safety assessment or a model for future assessments to be undertaken by the prospective licensee. The specific project objectives of SITE-94 comprise site evaluation, performance assessment methodology, canister integrity and radionuclide release and transport calculations. The report gives a detailed description of the many inter-related studies undertaken as part of the research project. As a general conclusion it is noted that the SITE-94 project has significantly advanced SKI's capability of reviewing performance assessments and has led to the development of a tool-kit for carrying out assessment calculations, both in terms of numerical and scoping analyses. The study has highlighted a number of key issues for safety assessment (and consequently for disposal system design): Canister performance; Derived parameters of geosphere retention properties; Spatial variability of groundwater flow and geochemistry of migration paths; Time dependency (more emphasis on transient, time-dependent processes); Buffer evolution over long time. 488 refs

  6. Preliminary on-surface experiments for backfilling a HLW repository: the ESDRED project

    International Nuclear Information System (INIS)

    Bastiaens, W.

    2007-01-01

    ESDRED is a technological integrated project within the context of the Sixth Framework Program of EURATOM. The project aims to demonstrate the technical feasibility at an industrial scale of specific technologies related to the construction, operation and closure of a deep geological repository for spent fuel and long-lived radioactive waste. The Belgian design for high level waste disposal is based on the so-called Supercontainer concept. Within this concept, the waste is encased in a carbon steel overpack, which is consequently fitted into a 70 cm thick concrete shell, in its turn enveloped by a stainless steel liner. A Supercontainer measures about 2 m in diameter. In the design of the repository, the Supercontainers will be emplaced, one after the other, in disposal galleries. The space between the Supercontainers and the gallery lining needs to be filled up with a solid material. The most essential function of this component, referred to as backfill, is to prevent a collapse of the gallery. A secondary function is to limit the presence of free oxygen, to limit corrosion. In the ESDRED project EIG EURIDICE, together with SCK-CEN and ONDRAF/NIRAS, investigates technologies to apply the backfill. Two options to apply the backfill were investigated within the ESDRED project: fill the gap with a granular material and backfill the gap with a grout. The prime operational target will be to achieve a 100 percent filling of the gap. A wide variety of materials was tested. A number of considerations regarding long-term safety and operational feasibility impose constraints on the backfill component:it should preserve the corrosion-protective environment established by the Supercontainer; it should not act as a thermal isolator; it should not introduce organic materials that can give rise to the formation of migration-enhancing complexes between radionuclides and soluble organic compounds; it should be feasible to construct at a sufficiently high rate; the strength of the

  7. Engaging Researchers with the World's First Scholarly Arts Repositories: Ten Years after the UK's Kultur Project

    Science.gov (United States)

    Meece, Stephanie; Robinson, Amy; Gramstadt, Marie-Therese

    2017-01-01

    Open access institutional repositories can be ill-equipped to manage the complexity of research outputs from departments of fine arts, media, drama, music, cultural heritage, and the creative arts in general. The U.K.-based Kultur project was funded to create a flexible multimedia repository model using EPrints software. The project launched the…

  8. SKB's Project SAFE for the SFR 1 Repository. A Review by Consultants to SKI

    International Nuclear Information System (INIS)

    Chapman, N.A.; Maul, P.R.; Robinson, P.C.; Savage, D.

    2002-06-01

    The SFR 1 repository used for final disposal of low- and intermediate level radioactive waste produced by the Swedish nuclear power programme, industry, medicine and research. In 1992 it was granted a full-scale operating permit following additional reporting on long-term safety aspects by SKB, including the first in-depth safety assessment in 1991. It was stipulated as part of the full-scale licence for SFR 1 that a revised safety assessment should be carried out by SKB at least every ten years during the continued operation of the facility. The first 10-year SKB re-evaluation, called 'Project SAFE', was submitted to the regulators in 2001. The review of Project SAFE presented in this report is the culmination of several years' work with SKI including: 1. The extension and application of SKI's 'systems' approach to set up a description of the SFR 1 repository using Process Influence Diagrams (PIDs). 2. Participation in the development of a flexible Performance Assessment (PA) software tool (the AMBER code) that enables time-dependent analyses to be made of system behaviour. 3. Use of the PID database to explore, from first principles, issues that are likely to be important in the safety performance of SFR 1 and thereby to identify topics to be explored by PA modelling. 4. Peer review of the main SKB Project SAFE supporting documentation to evaluate quality, completeness and the implications of the results. 5. An independent PA exercise, using the AMBER code. 6. A review of an English translation of Section 5 of SKB's Project SAFE Final Safety Report. The present report covers only items 3 to 6, and a separate report provides a more detailed description of item 5. As a result of this review, the key issues that the regulatory authorities will need to address when reviewing SKB's safety case for SFR 1 have been identified as: 1. There is no clear statement of SKB's overall safety concept for SFR 1. It is therefore difficult to judge the results of the PA against

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

    International Nuclear Information System (INIS)

    1986-01-01

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

  10. Risk management in the project of implantation of the repository for low and intermediate level radioactive waste

    International Nuclear Information System (INIS)

    Borssatto, Maria de Fatima B.; Tello, Cledola Cassia O. de; Uemura, George

    2011-01-01

    Project RBMN is part of the Brazilian solution for the storage of radioactive waste generated by the activities of nuclear energy in Brazil. The aim of RBMN is to implement the National Repository to dispose the low and intermediate-level radioactive waste. Risk is a characteristic of all projects, and it is originated from uncertainties, assumptions and the environment of execution of the project. Risk management is the way to monitor systematically these uncertainties and a guaranty that the goals of the project will be attained. A specific methodology for the risk management of the Project RBMN is under development, which integrates models and processes for identification and analysis of risks, reactions, monitoring, control and planning of risk management. This methodology is fundamental and will be of primordial importance for future generations who will be responsible for the operation at final stages, closure and institutional control during the post-closure of the repository. It will provide greater safety to executed processes and safeguarding risks and specific solutions for this enterprise, guaranteeing the safety of the repository in its life cycle, which has a foreseen duration of at least three hundred years. The aim of this paper is to present the preliminary analysis of the opportunities, threats, strong points and weak points identified up to now, that will provide support to implement risk management procedures. The methodology will be based on the PMBOK R - Project Management Board of Knowledge - and will take into consideration the best practices for project management.(author)

  11. Compliance status summaries for federal and state statutory directives that apply to the Salt Repository Project at the Deaf Smith County Site, Texas

    International Nuclear Information System (INIS)

    1986-07-01

    This document contains statutory summaries, checklists of compliance requirements, status summaries, and lists of information needs for the environmental and health and safety statutory directives at Federal and State levels that apply to the Salt Repository Project at the Deaf Smith County Site, Texas. Statutes that apply in general to any repository project but not specifically to the Deaf Smith are not included. The information herein supplements the Salt Repository Project Statutory Compliance Plan and the Salt Repository Project Permitting Management Plan by providing lengthy details on statutory directives, compliance requirements, information needs, and the overall status of the environmental and health and safety compliance program for the Salt Repository Project at the Deaf Smith County Site, Texas

  12. Project characteristics monitoring report: BWIP (Basalt Waste Isolation Program) repository project

    Energy Technology Data Exchange (ETDEWEB)

    Friedli, E.A.; Herborn, D.I.; Taylor, C.D.; Tomlinson, K.M.

    1988-03-01

    This monitoring report has been prepared to show compliance with provisions of the Nuclear Waste Policy Act of 1982 (NWPA) and to provide local and state government agencies with information concerning the Basalt Waste Isolation Program (BWIP). This report contains data for the time period May 26, 1986 to February 1988. The data include employment figures, salaries, project purchases, taxes and fees paid, worker survey results, and project closedown personal interview summaries. This information has become particularly important since the decision in December 1987 to stop all BWIP activities except those for site reclamation. The Nuclear Waste Policy Amendments Act of 1987 requires nonreclamation work at the Hanford Site to stop as of March 22, 1988. 7 refs., 6 figs., 28 tabs.

  13. Project characteristics monitoring report: BWIP [Basalt Waste Isolation Program] repository project

    International Nuclear Information System (INIS)

    Friedli, E.A.; Herborn, D.I.; Taylor, C.D.; Tomlinson, K.M.

    1988-03-01

    This monitoring report has been prepared to show compliance with provisions of the Nuclear Waste Policy Act of 1982 (NWPA) and to provide local and state government agencies with information concerning the Basalt Waste Isolation Program (BWIP). This report contains data for the time period May 26, 1986 to February 1988. The data include employment figures, salaries, project purchases, taxes and fees paid, worker survey results, and project closedown personal interview summaries. This information has become particularly important since the decision in December 1987 to stop all BWIP activities except those for site reclamation. The Nuclear Waste Policy Amendments Act of 1987 requires nonreclamation work at the Hanford Site to stop as of March 22, 1988. 7 refs., 6 figs., 28 tabs

  14. Redox processes in the safety case of deep geological repositories of radioactive wastes. Contribution of the European RECOSY Collaborative Project

    International Nuclear Information System (INIS)

    Duro, L.; Bruno, J.; Grivé, M.; Montoya, V.; Kienzler, B.; Altmaier, M.; Buckau, G.

    2014-01-01

    Highlights: • The RECOSY project produced results relevant for the Safety Case of nuclear disposal. • We classify the safety related features where RECOSY has contributed. • Redox processes effect the retention of radionuclides in all repository subsystems. - Abstract: Redox processes influence key geochemical characteristics controlling radionuclide behaviour in the near and far field of a nuclear waste repository. A sound understanding of redox related processes is therefore of high importance for developing a Safety Case, the collection of scientific, technical, administrative and managerial arguments and evidence in support of the safety of a disposal facility. This manuscript presents the contribution of the specific research on redox processes achieved within the EURATOM Collaborative Project RECOSY (REdox phenomena COntrolling SYstems) to the Safety Case of nuclear waste disposal facilities. Main objectives of RECOSY were related to the improved understanding of redox phenomena controlling the long-term release or retention of radionuclides in nuclear waste disposal and providing tools to apply the results to Performance Assessment and the Safety Case. The research developed during the project covered aspects of the near-field and the far-field aspects of the repository, including studies relevant for the rock formations considered in Europe as suitable for hosting an underground repository for radioactive wastes. It is the intention of this paper to highlight in which way the results obtained from RECOSY can feed the scientific process understanding needed for the stepwise development of the Safety Case associated with deep geological disposal of radioactive wastes

  15. Estimation of expenses for low and intermediate level radioactive waste repository project in Croatia up to site license acquisition

    International Nuclear Information System (INIS)

    Schaller, A.; Lokner, V.; Subasic, D.

    2003-01-01

    The expenses needed for development of low- and intermediate level radioactive waste (LILW) repository project in Croatia include: (a) preliminary activities, (b) preparatory activities, and (c) preparing of environmental impact study. The first group of expenses are referring to the project leading activities, project plan updating, build-up of required infrastructure, preparing of licensing documentation, site investigations, data acquisition programme, pre-operational radio-ecological monitoring, modelling, safety analysis (first iteration) and public related activities. Preparatory activities are referring to purchasing of land for repository and preparatory activities for carrying out of on-site investigations, while third group of expenses are related to preparation and validation of Environmental impact study. It was found out that about 50 % of total expenses refer to build-up of infrastructure. Additional 25 % finances are related to radio-ecological monitoring, site investigations and development of calculations and models, while remaining 25 % of total estimated sum is expected to be spent for repository safety assessment, public relations, purchasing and preparing the on-site terrain for construction, etc. It was calculated 607 EUR per m3 of LILW to be needed up to site license acquisition. According to the world-wide practice, by extrapolating of additional expenses necessary for construction of the repository and acquisition of operational license, it comes out the cost of 1.723 EUR per m3 of LILW for shallow-ground and 2.412 EUR per m3 of LILW for tunnel repository. The estimated expenses for Croatia are within the span of expenses for the same purpose in the countries considered. Expected duration of the project performance up to acquisition of the site license is 4 years and 3 months. (author)

  16. Community interviews task report: Working draft: BWIP [Basalt Waste Isolation Project] Repository Project

    International Nuclear Information System (INIS)

    Bolton, P.A.

    1987-11-01

    The socioeconomic program for the Basalt Waste Isolation Project (BWIP) requires the collection of information about economic, social and cultural conditions, demographic, housing and settlement patterns, and the provision of public services and facilities in order to monitor and assess the impacts of the project on the study area. Much of the information needed by the socioeconomic program is compiled, maintained, and used by officials or staff members of local, regional, state, or tribal agencies or organizations. Because much of this information is prepared for internal use, the documents are often not published or advertised and it can be difficult for researchers to identify many obscure, yet useful, sources of information. In order to identify and gain access to this information, it is often most efficient to talk directly with officials and staff members of pertinent agencies or organizations who may have knowledge of these documents or who may have useful information themselves. Consequently, interviews in the study communities with persons knowledgeable about the socioeconomic or sociocultural characteristics of the area constitute an important source of data for the socioeconomic program. In addition to identifying various data sources, these interviews provide a mechanism for understanding and interpreting those data. Knowledge of specific local conditions is often necessary to correctly interpret quantitative data. The purpose of this paper is to summarize the objectives of the community interviews task and the general methods that will be used in conducting the community interviews. 3 refs

  17. Operational procedures for receiving, packaging, emplacing, and retrieving high-level and transuranic waste in a geologic repository in TUFF

    International Nuclear Information System (INIS)

    Dennis, A.W.; Mulkin, R.

    1984-01-01

    The Nevada Nuclear Waste Storage Investigations Project, directed by the Nevada Operations Office of the Department of Energy, is currently developing conceptual designs for a commercial nuclear waste repository. In this paper, the preliminary repository operating plans are identified and the proposed repository waste inventory is discussed. The receipt rates for truck and rail car shipments of waste are determined as are the required repository waste emplacement rates

  18. The projected environmental impacts of transportation of radioactive material to the first United States repository site

    International Nuclear Information System (INIS)

    Cashwell, J.W.; Neuhauser, K.S.; Reardon, P.C.; McNair, G.W.

    1987-01-01

    The relative national environmental impacts of transporting spent fuel and other nuclear wastes to each of 9 candidate repository sites in the United States were analyzed for the 26-year period of repository operation. Two scenarios were examined for each repository: 1) shipment of 5-year-old spent fuel and Defence High-Level Waste (DHLW) directly from their points of origin to a repository (reference case); and 2) shipment of 5-year-old spent fuel to a Monitored Retrievable Storage (MRS) facility and shipment (by dedicated rail) of 10-year-old consolidated spent fuel from the MRS to a repository. Transport by either all truck or all rail from the points of origin were analyzed as bounding cases. The computational system used to analyze these impacts included the WASTES II logistics code and the RADTRAN III risk analysis code. The radiological risks for the reference case increased as the total shipment miles to a repository increased for truck; the risks also increased with mileage for rail but at a lower rate. For the MRS scenario the differences between repository sites were less pronounced for both modal options, because of the reduction in total shipment miles possible with the large dedicated rail casks. All the risks reported are small in comparison to the radiological risks due to 'natural background'

  19. A scoping review of online repositories of quality improvement projects, interventions and initiatives in healthcare.

    Science.gov (United States)

    Bytautas, Jessica P; Gheihman, Galina; Dobrow, Mark J

    2017-04-01

    Quality improvement (QI) is becoming an important focal point for health systems. There is increasing interest among health system stakeholders to learn from and share experiences on the use of QI methods and approaches in their work. Yet there are few easily accessible, online repositories dedicated to documenting QI activity. We conducted a scoping review of publicly available, web-based QI repositories to (i) identify current approaches to sharing information on QI practices; (ii) categorise these approaches based on hosting, scope and size, content acquisition and eligibility, content format and search, and evaluation and engagement characteristics; and (iii) review evaluations of the design, usefulness and impact of their online QI practice repositories. The search strategy consisted of traditional database and grey literature searches, as well as expert consultation, with the ultimate aim of identifying and describing QI repositories of practices undertaken in a healthcare context. We identified 13 QI repositories and found substantial variation across the five categories. The QI repositories used different terminology (eg, practices vs case studies) and approaches to content acquisition, and varied in terms of primary areas of focus. All provided some means for organising content according to categories or themes and most provided at least rudimentary keyword search functionality. Notably, none of the QI repositories included evaluations of their impact. With growing interest in sharing and spreading best practices and increasing reliance on QI as a key contributor to health system performance, the role of QI repositories is likely to expand. Designing future QI repositories based on knowledge of the range and type of features available is an important starting point for improving their usefulness and impact. Published by the BMJ Publishing Group Limited. For permission to use (where not already granted under a licence) please go to http://www.bmj.com/company/products-services/rights-and-licensing/.

  20. Modern Project: monitoring developments for safe repository operation and staged closure

    International Nuclear Information System (INIS)

    Mayer, S.; Ouchhi, S.; Verstricht, J.; Maurer, H.; Breen, B.

    2010-01-01

    Document available in extended abstract form only. In a first part, the overall objectives of the MoDeRn project (Monitoring Developments for safe Repository operation and stage closure project) are presented. MoDeRn is a four year (2009-2013) collaborative project co-funded under the 7. Framework Program for Nuclear Research and Training (EURATOM). It involves 17 organizations responsible for research into radioactive waste management in the European Union, United States, Japan and Switzerland, with partners with extensive experience in monitoring activities in underground research laboratories (URL); as well as research institutes and universities with substantial experience in research on socio-technical interactions and public and stakeholder engagement. An overview of the project work packages and of their interdependencies is given. The successful implementation of a repository program for radioactive waste relies on both the technical aspects of a sound safety strategy and scientific and engineering excellence as well as on social aspects such as stakeholder acceptance and confidence. Monitoring is considered key in serving both technical and social objectives. It is not only essential to underpin the technical safety strategy and quality of the engineering, but it can also be an important tool for public communication, contributing to public understanding of and confidence in the repository behaviour. By inclusion of specific national contexts of waste management programs in different countries, the MoDeRn project aims at providing a reference framework for development and implementation of monitoring activities. This will be achieved by stakeholder engagement during all identifiable phases of the radioactive waste disposal process. Thus, site characterisation, construction, operation and staged closure, as well as post-closure institutional control phases have to be addressed. MoDeRn considers different host rock types, such as salt, tuff, crystalline rock

  1. Region-to-area screening methodology for the crystalline repository project

    International Nuclear Information System (INIS)

    1984-08-01

    The ''Nuclear Waste Policy Act of 1982'' (NWPA), enacted January 7, 1983 as Public Law 97-425, confirmed the responsibility of the US Department of Energy (DOE) for management of high-level radioactive waste. The NWPA directed the DOE to provide safe facilities for isolation of high-level radioactive waste from the environment in federally owned and federally licensed repositories. To achieve the goals of providing licensed repositories for high-level radioactive waste, a technical program has been developed by the DOE to meet all relevant radiological protection criteria and other requirements. By March 1987, the NWPA requires the DOE to recommend to the President a single site, chosen from five nominated sites for construction of the first repository. Rock types being considered as potential hosts for the first repository include salt, basalt, and tuff. The NWPA also requires the DOE to select three candidate sites, chosen from five nominated sites to be recommended to the President by July 1989, as possible locations for the second repository. Potential host rock types for the second federal repository will include crystalline rock. This document outlines the methodology for region-to-area screening of exposed crystalline rock bodies for suitability as sites for further study. 17 refs., 14 figs., 2 tabs

  2. Engineering feasibility for the fabrication and emplacement of cementitious repository materials: results from the EC-ESDRED project

    International Nuclear Information System (INIS)

    Alonso, Maria Cruz; Garcia-Sineriz, Jose Luis

    2012-01-01

    Maria Cruz Alonso of the Spanish National Research Council gave a presentation that summarised relevant findings on cementitious materials from the EC ESDRED (Engineering Studies and Demonstration of Repository Designs) Project. Concrete will be used for different purposes during the construction of geologic repositories for radioactive waste. These purposes include grouting, tunnel and drift lining, and tunnel plugging and sealing. Although some of the concrete may be removed before repository closure, a significant amount of concrete will remain in the repository. An important concern regarding the use of cementitious materials in geologic repositories for HLW and spent fuel is their interaction with the bentonite buffer, backfill material, and the host rock close to the repository near-field. For this reason, the ESDRED project has developed a low-pH concrete formulation as an alternative to standard ordinary Portland cement (OPC) concrete formulations with the aim of reducing the interaction of the cementitious materials with the near-field components. The main functional requirement required in the development of the low-pH material was a pore fluid pH < 11, which is considered acceptable for preventing or reducing the alteration of the bentonite EBS. Other functional requirements considered in the development of the low-pH concrete were: - Hydraulic conductivity. - Mechanical properties. - Durability. - Workability and pumpability. - Slumping. - Peak hydration temperature. - Thermal conductivity. - Use of organic components. - Use of other products. The development of the low-pH concrete involved laboratory work, as well as field testing at the Aespoe underground research laboratory (URL) in Sweden, and in the Grimsel URL and at the Hagerbach site in Switzerland. The ESDRED project demonstrated that low-pH cements can be formulated and used for production of concrete plugs and rock support. OPC can be used as the cement included in low-pH blends, but at least

  3. Appendix VI: KHNP staffing plan of construction site office: ULCHIN 5 and 6 construction project (ROK)

    International Nuclear Information System (INIS)

    2008-01-01

    KHNP, as an owner/operator organization, is responsible for all project activities including design, procurement, construction, and commissioning, for Korea's nuclear power plant (NPP) construction projects. Four separate functional offices of KHNP are set up to complete the construction management work. These offices are (1) home office, (2) field construction office, (3) field quality assurance office, and (4) field startup/commissioning office. This paper presents a staffing plan for the field construction office starting initial project implementation to final turnover to operations stages. It is recognized that the plan may not be applicable to other utility situations in terms of project management of site activity depending upon how the overall project contract is structured

  4. Report of early site suitability evaluation of the potential repository site at Yucca Mountain, Nevada; Yucca Mountain Site Characterization Project

    Energy Technology Data Exchange (ETDEWEB)

    Younker, J.L.; Andrews, W.B.; Fasano, G.A.; Herrington, C.C.; Mattson, S.R.; Murray, R.C. [Science Applications International Corp., Las Vegas, NV (United States); Ballou, L.B.; Revelli, M.A. [Lawrence Livermore National Lab., CA (United States); Ducharme, A.R.; Shephard, L.E. [Sandia National Labs., Albuquerque, NM (United States); Dudley, W.W.; Hoxie, D.T. [Geological Survey, Denver, CO (United States); Herbst, R.J.; Patera, E.A. [Los Alamos National Lab., NM (United States); Judd, B.R. [Decision Analysis Co., Portola Valley, CA (United States); Docka, J.A.; Rickertsen, L.D. [Weston Technical Associates, Washington, DC (United States)

    1992-01-01

    This study evaluated the technical suitability of Yucca Mountain, Nevada, as a potential site for a mined geologic repository for the permanent disposal of radioactive waste. The evaluation was conducted primarily to determine early in the site characterization program if there are any features or conditions at the site that indicate it is unsuitable for repository development. A secondary purpose was to determine the status of knowledge in the major technical areas that affect the suitability of the site. This early site suitability evaluation (ESSE) was conducted by a team of technical personnel at the request of the Associate Director of the US Department of Energy (DOE) Office of Geologic Disposal, a unit within the DOE`s Office of Civilian Radioactive Waste Management. The Yucca Mountain site has been the subject of such evaluations for over a decade. In 1983, the site was evaluated as part of a screening process to identify potentially acceptable sites. The site was evaluated in greater detail and found suitable for site characterization as part of the Environmental Assessment (EA) (DOE, 1986) required by the Nuclear Waste Policy Act of 1982 (NWPA). Additional site data were compiled during the preparation of the Site Characterization Plan (SCP) (DOE, 1988a). This early site suitability evaluation has considered information that was used in preparing both-documents, along with recent information obtained since the EA and SCP were published. This body of information is referred to in this report as ``current information`` or ``available evidence.``

  5. Repository sealing concepts for the Nevada nuclear waste storage Investigations Project

    International Nuclear Information System (INIS)

    Fernandez, J.A.; Freshley, M.D.

    1984-08-01

    This report describes concepts for sealing a nuclear waste repository in an unsaturated tuff environment. The repository site under consideration is Yucca Mountain, which is on and adjacent to the Nevada Test Site. The hydrogeology of Yucca Mountain, preliminary repository concepts, functional requirements and performance criteria for sealing, federal and state regulations, and hydrological calculations are considered in developing the sealing concepts. Water flow through the unsaturated zone is expected to be small and generally vertically downward with some potential to occur through discrete fault and fracture zones. These assumptions are used in developing sealing concepts for shafts, ramps, and boreholes. Sealing of discrete, water-producing faults and fracture zones encountered in horizontal emplacement holes and in access and emplacement drifts is also described. 49 references, 21 figures, 6 tables

  6. Critical review of the draft Area Recommendation Report and region-to-area screening methodology for the Crystalline Repository Project

    International Nuclear Information System (INIS)

    1986-01-01

    Two documents related to the Crystalline Repository Project have been reviewed. Comments and concerns related to the review of the ''Region-To-Area Screening Methodology'' and the ''Draft Area Recommendation Report'' are presented. These comments will be considered in preparation of the Final Area Recommendation Report, which will serve to formally identify potentially acceptable sites for a second repository in crystalline rock. Following a detailed review of the aforementioned documents, it is concluded that the identification of proposed potentially acceptable sites in the Draft Area Recommendation Report is based on questionable screening methodology and often incomplete data. As a result, ''favorable characteristics'' that are ascribed to each of the proposed potentially acceptable sites are, in many cases, misleading

  7. Using the project management office to connect the dots between projects and strategy.

    Science.gov (United States)

    Phan, Jacqueline

    2015-03-01

    Project management is recognized as an essential skill required for healthcare leadership and as a result, Project Management Offices (PMOs) in healthcare organizations have become commonplace. When PMOs are well suited and fit to their organization, they are being valued for their ability to support appropriate trade-offs between investments, capacity, and quality. This article provides an overview of healthcare PMOs and advocates for elevating the role of the healthcare PMO from a monitoring and reporting function to a leader and the engine for strategic change within an organization. © 2015 The Canadian College of Health Leaders.

  8. Microbial Influence on the Performance of Subsurface, Salt-Based Radioactive Waste Repositories. An Evaluation Based on Microbial Ecology, Bioenergetics and Projected Repository Conditions

    International Nuclear Information System (INIS)

    Swanson, J.S.; Reed, D.T.; Cherkouk, A.; Arnold, T.; Meleshyn, A.; Patterson, Russ

    2018-01-01

    For the past several decades, the Nuclear Energy Agency Salt Club has been supporting and overseeing the characterisation of rock salt as a potential host rock for deep geological repositories. This extensive evaluation of deep geological settings is aimed at determining - through a multidisciplinary approach - whether specific sites are suitable for radioactive waste disposal. Studying the microbiology of granite, basalt, tuff, and clay formations in both Europe and the United States has been an important part of this investigation, and much has been learnt about the potential influence of microorganisms on repository performance, as well as about deep subsurface microbiology in general. Some uncertainty remains, however, around the effects of microorganisms on salt-based repository performance. Using available information on the microbial ecology of hyper-saline environments, the bioenergetics of survival under high ionic strength conditions and studies related to repository microbiology, this report summarises the potential role of microorganisms in salt-based radioactive waste repositories

  9. Low Emissions Alternative Power (LEAP) Project Office Business Team of the Aeropropulsion Research Program Office (ARPO) Org. 0140

    Science.gov (United States)

    Buttler, Jennifer A.

    2004-01-01

    The program for which I am working at this summer is Propulsion and Power/Low Emissions Alternative Power (P&P/LEAP). It invests in a fundamental TRL 1-6 research and technology portfolio that will enable the future of: Alternative fuels and/or alternative propulsion systems, non-combustion (electric) propulsion systems. P&P/LEAP will identify and capitalize on the highest potential concepts generated both internal and external to the Agency. During my 2004 summer at NASA Glenn Research Center, I worked with my mentor Barbara Mader, in the Project Office with the Business Team completing various tasks for the project and personnel. The LEAP project is a highly matrixed organization. The Project Office is responsible for the goals advocacy and dollar (budget) of the LEAP project. The objectives of the LEAP Project are to discover new energy sources and develop unconventional engines and power systems directed towards greatly reduced emissions, enable new vehicle concepts for public mobility, new science missions and national security. The Propulsion and PowerLow Emissions Alternative Power directly supports the environmental, mobility, national security objectives of the Vehicle Systems Program and the Aeronautics Technology Theme. Technology deliverables include the demonstration through integrated ground tests, a constant volume combustor in an engine system, and UAV/small transport aircraft all electric power system. My mentor serves as a key member of the management team for the Aeropropulsion Research Program Office (ARPO). She has represented the office on numerous occasions, and is a member of a number of center-wide panels/teams, such as the Space management Committee and is chair to the Business Process Consolidation Team. She is responsible for the overall coordination of resources for the Propulsion and Power Project - from advocacy to implementation. The goal for my summer at NASA was to document processes and archive program documents from the past

  10. Iterative performance assessments as a regulatory tool for evaluating repository safety: How experiences from SKI Project-90 were used in formulating the new performance assessment project SITE-94

    International Nuclear Information System (INIS)

    Andersson, J.

    1993-01-01

    The Swedish Nuclear Power Inspectorate, SKI, regulatory research program has to prepare for the process of licensing a repository for spent nuclear fuel, by building up the necessary knowledge and review capacity. SKIs main strategy for meeting this demand is to develop an independent performance assessment capability. SKIs first own performance assessment project, Project-90, was completed in 1991 and is now followed by a new project, SITE-94. SITE-94 is based on conclusions reached within Project-90. An independent review of Project-90, carried out by a NEA team of experts, has also contributed to the formation of the project. Another important reason for the project is that the implementing organization in Sweden, SKB, has proposed to submit an application to start detailed investigation of a repository candidate site around 1997. SITE-94 is a performance assessment of a hypothetical repository at a real site. The main objective of the project is to determine how site specific data should be assimilated into the performance assessment process, and to evaluate how uncertainties inherent in site characterization will influence performance assessment results. This will be addressed by exploring multiple interpretations, conceptual models, and parameters consistent with the site data. The site evaluation will strive for consistency between geological, hydrological, rock mechanical, and geochemical descriptions. Other important elements of SITE-94 are the development of a practical and defensible methodology for defining, constructing and analyzing scenarios, the development of approaches for treatment of uncertainties, evaluation of canister integrity, and the development and application of an appropriate quality assurance plan for performance assessments

  11. Project Guarantee 1985. Final repository for high-level radioactive wastes: Safety report

    International Nuclear Information System (INIS)

    Anon.

    1985-01-01

    Disposal of radioactive was involves preventing releases to the biosphere for a long period of time and subsequently limiting the magnitude of releases by means of a series of safety barriers: the waste solidification matrix (borosilicate glass), massive steel canisters in highly compacted bentonite, sealing of void spacer and access routes on repository closure. The geological barriers are formed by the crystalline bed-rock and the overlying sedimentary layers. In order to perform a safety assessment the behaviour of these technical barriers and of the host rock must be understood and this understanding must be translated into quantitative models which allow calculation of repository performance. For the particular case of a Swiss repository, the main criterion is the individual dose limit of 10 mrem/year, which is given in the safety guidelines of the Swiss authorities. The procedure for the safety analysis involves examination of all scenarios which could give rise to radionuclide release from the repository. Qualitative considerations of both the magnitude of their consequences and their likelihood are used in order to identify a restricted number of scenarios for quantitative analysis

  12. The Community project on engineering aspects of backfilling and sealing of radioactive waste repositories

    International Nuclear Information System (INIS)

    Lake, L.M.; Bennett, A.

    1987-01-01

    This report summarizes the work carried out under CEC contracts about engineering aspects of backfilling and sealing of radioactive waste repositories, for the time period 1983-84. It complements a previous report (ref. EUR 9283) on the same topic, this latter covering the period 1980-82

  13. The Listening and Spoken Language Data Repository: Design and Project Overview

    Science.gov (United States)

    Bradham, Tamala S.; Fonnesbeck, Christopher; Toll, Alice; Hecht, Barbara F.

    2018-01-01

    Purpose: The purpose of the Listening and Spoken Language Data Repository (LSL-DR) was to address a critical need for a systemwide outcome data-monitoring program for the development of listening and spoken language skills in highly specialized educational programs for children with hearing loss highlighted in Goal 3b of the 2007 Joint Committee…

  14. Projected environmental impacts of radioactive material transportation to the first US repository site

    International Nuclear Information System (INIS)

    Neuhauser, K.S.; Cashwell, J.W.; Reardon, P.C.; Ostmeyer, R.M.; McNair, G.W.

    1986-01-01

    This paper discusses the relative national environmental impacts of transporting nuclear wastes to each of the nine candidate repository sites in the United States. Several of the potential sites are closely clustered and, for the purpose of distance and routing calculations, are treated as a single location. These are: Cypress Creek Dome and Richton Dome in Mississippi (Gulf Interior Region), Deaf Smith County and Swisher County sites in Texas (Permian Basin), and Davis Canyon and Lavender Canyon site in Utah (Paradox Basin). The remaining sites are: Vacherie Dome, Louisiana; Yucca Mountain, Nevada; and Hanford Reservation, Washington. For compatibility with both the repository system authorized by the NWPA and with the MRS option, two separate scenarios were analyzed. In belief, they are (1) shipment of spent fuel and high-level wastes (HLW) directly from waste generators to a repository (Reference Case) and (2) shipment of spent fuel to a Monitored Retrievable Storage (MRS) facility and then to a repository. Between 17 and 38 truck accident fatalities, between 1.4 and 7.7 rail accident fatalities, and between 0.22 and 12 radiological health effects can be expected to occur as a result of radioactive material transportation during the 26-year operating period of the first repository. During the same period in the United States, about 65,000 total deaths from truck accidents and about 32,000 total deaths from rail accidents would occur; also an estimated 58,300 cancer fatalities are predicted to occur in the United States during a 26-year period from exposure to background radiation alone (not including medical and other manmade sources). The risks reported here are upper limits and are small by comparison with the ''natural background'' of risks of the same type. 3 refs., 6 tabs

  15. The software analysis project for the Office of Human Resources

    Science.gov (United States)

    Tureman, Robert L., Jr.

    1994-01-01

    There were two major sections of the project for the Office of Human Resources (OHR). The first section was to conduct a planning study to analyze software use with the goal of recommending software purchases and determining whether the need exists for a file server. The second section was analysis and distribution planning for retirement planning computer program entitled VISION provided by NASA Headquarters. The software planning study was developed to help OHR analyze the current administrative desktop computing environment and make decisions regarding software acquisition and implementation. There were three major areas addressed by the study: current environment new software requirements, and strategies regarding the implementation of a server in the Office. To gather data on current environment, employees were surveyed and an inventory of computers were produced. The surveys were compiled and analyzed by the ASEE fellow with interpretation help by OHR staff. New software requirements represented a compilation and analysis of the surveyed requests of OHR personnel. Finally, the information on the use of a server represents research done by the ASEE fellow and analysis of survey data to determine software requirements for a server. This included selection of a methodology to estimate the number of copies of each software program required given current use and estimated growth. The report presents the results of the computing survey, a description of the current computing environment, recommenations for changes in the computing environment, current software needs, management advantages of using a server, and management considerations in the implementation of a server. In addition, detailed specifications were presented for the hardware and software recommendations to offer a complete picture to OHR management. The retirement planning computer program available to NASA employees will aid in long-range retirement planning. The intended audience is the NASA civil

  16. Projects at the Western Environmental Technology Office. Quarterly technical progress report, April 1--June 30, 1995

    International Nuclear Information System (INIS)

    1995-01-01

    This report contains brief outlines of the multiple projects under the responsibility of the Western Environmental Technology Office in Butte Montana. These projects include biomass remediation, remediation of contaminated soils, mine waste technology, and several other types of remediation

  17. Crystalline Repository Project: Review and comment of the Leech Lake Reservation Business Committee: Draft area recommendation report

    International Nuclear Information System (INIS)

    1986-09-01

    The Leech Lake Reservation Business Committee (LLRBC) has reviewed five documents related to the US Department of Energy's Crystalline Repository Project (CRP). They are the ''National Survey of Crystalline Rocks,'' ''General Guidelines for the Recommendation of Sites for the Nuclear Waste Repositories;' Final Siting Guidelines (10 CFR Part 960),'' ''Regional Characterization Reports for the North Central Region,'' the ''Region to Area Screening Methodology Document'' (SMD) and the ''Draft Area Recommendation Report'' (DARR). The comments and discussions of issues contained in this review will be considered in the preparation of the Final Area Recommendation Report, which will formally identify potentially acceptable sites for a second national repository for the permanent disposal of high level nuclear waste. Following a review of the above referenced documents, the LLRBC has concluded that the identification of potentially acceptable sites in the Draft Area Recommendation Report is based upon inferior and incomplete technical information being applied to a flawed screening process which, among other deficiencies, pays little attention to the importance of hydrological factors in the siting process. Although the DOE prefers that comments from states and tribes be directed at the Draft Area Recommendation Report alone, the Leech Lake Reservation Business Committee is extremely concerned about inadequacies in the ''National Survey of Crystalline Rocks'' (ORCD-1), which serves as the foundation for all siting work done to date. The national survey was conducted utilizing little of the time or staffing required for this important phase of the Crystalline Repository Program. As a result, the national survey is based upon out-of-date scientific literature, exaggerates certain screening variables that favor the selection of regions in the eastern US and arbitrarily eliminated the few western crystalline rock bodies that passed the questionable screening process utilized

  18. Response to state comments on the revised draft North Central Regional characterization reports for the Crystalline Repository Project

    International Nuclear Information System (INIS)

    1985-08-01

    The purpose of this document is to respond to the comments received from the states of the North Central Region on the revised draft North Central Regional Characterization Reports (RCRs). The responses in this document indicate the manner in which the suggestions or comments received have been considered in modifying the revised draft North Central RCRs. Both general comments related to the overall Crystalline Repository Project (CRP) and comments on specific sections of the RCRs are addressed. This document responds to North Central State comments on both the revised draft North Central Regional Geologic Characterization Report (RGCR) and the revised draft North Central Regional Environmental Characterization Report (RECR)

  19. DECOVALEX III PROJECT. Mathematical Models of Coupled Thermal-Hydro-Mechanical Processes for Nuclear Waste Repositories. Executive Summary

    Energy Technology Data Exchange (ETDEWEB)

    Jing, L.; Stephansson, O. [Royal Inst. of Technology, Stockholm (Sweden). Engineering Geology; Tsang, C.F. [Lawrence Berkely National Laboratory, Berkeley, CA (United States). Earth Science Div.; Mayor, J.C. [ENRESA, Madrid (Spain); Kautzky, F. [Swedish Nuclear Power Inspectorate, Stockholm (Sweden)] (eds.)

    2005-02-15

    DECOVALEX is an international consortium of governmental agencies associated with the disposal of high-level nuclear waste in a number of countries. The consortium's mission is the DEvelopment of COupled models and their VALidation against EXperiments. Hence the acronym/name DECOVALEX. Currently, agencies from Canada, Finland, France, Germany, Japan, Spain, Switzerland, Sweden, United Kingdom, and the United States are in DECOVALEX. Emplacement of nuclear waste in a repository in geologic media causes a number of physical processes to be intensified in the surrounding rock mass due to the decay heat from the waste. The four main processes of concern are thermal, hydrological, mechanical and chemical. Interactions or coupling between these heat-driven processes must be taken into account in modeling the performance of the repository for such modeling to be meaningful and reliable. DECOVALEX III is organized around four tasks. The FEBEX (Full-scale Engineered Barriers EXperiment) in situ experiment being conducted at the Grimsel site in Switzerland is to be simulated and analyzed in Task 1. Task 2, centered around the Drift Scale Test (DST) at Yucca Mountain in Nevada, USA, has several sub-tasks (Task 2A, Task 2B, Task 2C and Task 2D) to investigate a number of the coupled processes in the DST. Task 3 studies three benchmark problems: a) the effects of thermal-hydrologic-mechanical (THM) coupling on the performance of the near-field of a nuclear waste repository (BMT1); b) the effect of upscaling THM processes on the results of performance assessment (BMT2); and c) the effect of glaciation on rock mass behavior (BMT3). Task 4 is on the direct application of THM coupled process modeling in the performance assessment of nuclear waste repositories in geologic media. This executive summary presents the motivation, structure, objectives, approaches, and the highlights of the main achievements and outstanding issues of the tasks studied in the DECOVALEX III project

  20. DECOVALEX III PROJECT. Mathematical Models of Coupled Thermal-Hydro-Mechanical Processes for Nuclear Waste Repositories. Executive Summary

    International Nuclear Information System (INIS)

    Jing, L.; Stephansson, O.; Kautzky, F.

    2005-02-01

    DECOVALEX is an international consortium of governmental agencies associated with the disposal of high-level nuclear waste in a number of countries. The consortium's mission is the DEvelopment of COupled models and their VALidation against EXperiments. Hence the acronym/name DECOVALEX. Currently, agencies from Canada, Finland, France, Germany, Japan, Spain, Switzerland, Sweden, United Kingdom, and the United States are in DECOVALEX. Emplacement of nuclear waste in a repository in geologic media causes a number of physical processes to be intensified in the surrounding rock mass due to the decay heat from the waste. The four main processes of concern are thermal, hydrological, mechanical and chemical. Interactions or coupling between these heat-driven processes must be taken into account in modeling the performance of the repository for such modeling to be meaningful and reliable. DECOVALEX III is organized around four tasks. The FEBEX (Full-scale Engineered Barriers EXperiment) in situ experiment being conducted at the Grimsel site in Switzerland is to be simulated and analyzed in Task 1. Task 2, centered around the Drift Scale Test (DST) at Yucca Mountain in Nevada, USA, has several sub-tasks (Task 2A, Task 2B, Task 2C and Task 2D) to investigate a number of the coupled processes in the DST. Task 3 studies three benchmark problems: a) the effects of thermal-hydrologic-mechanical (THM) coupling on the performance of the near-field of a nuclear waste repository (BMT1); b) the effect of upscaling THM processes on the results of performance assessment (BMT2); and c) the effect of glaciation on rock mass behavior (BMT3). Task 4 is on the direct application of THM coupled process modeling in the performance assessment of nuclear waste repositories in geologic media. This executive summary presents the motivation, structure, objectives, approaches, and the highlights of the main achievements and outstanding issues of the tasks studied in the DECOVALEX III project. The

  1. Response to state comments on the revised draft Southeastern Regional Characterization Reports for the Crystalline Repository Project

    International Nuclear Information System (INIS)

    1985-08-01

    The purpose of this document is to respond to the comments received from the states of the Southeastern Region on the revised draft Southeastern Regional Characterization Reports (RCRs). The responses in this document indicate the manner in which the suggestions or comments received have been considered in modifying the revised draft Southeastern RCRs. Both general comments related to the overall Crystalline Repository Project (CRP) and comments on specific sections of the RCRs are addressed. This document responds to Southeastern State comments on both the revised draft Southeastern Regional Geologic Characterization Report (RGCR) and the revised draft Southeastern Regional Environmental Characterization Report (RECR)

  2. Response to state comments on the revised draft northeastern regional characterization reports for the Crystalline Repository Project

    International Nuclear Information System (INIS)

    1985-08-01

    The purpose of this document is to respond to the comments received from the States of the Northeastern Region on the revised draft Northeastern Regional Characterization Reports (RCRs). The responses in this document indicate the manner in which the suggestions or comments received have been considered in modifying the revised draft Northeastern RCRs. Both general comments related to the overall Crystalline Repository Project (CRP) and comments on specific sections of the RCRs are addressed. This document responds to Northeastern State comments on both the revised draft Northeastern Regional Geologic Characterization Report (RGCR) and the revised draft Northeastern Regional Environmental Characterization Report (RECR)

  3. Modeling gas migration experiments in repository host rocks for the MEGAS project

    International Nuclear Information System (INIS)

    Worgan, K.; Impey, M.; Volckaert, G.; DePreter, P.

    1993-01-01

    In response to concerns over the possibility of hydrogen gas generation within an underground repository for high-level radioactive waste, and its implications for repository safety, a joint European research study (MEGAS) is underway. Its aims are to understand and characterize the behavior of gas migration within an argillacious, host-rock. Laboratory experiments are being carried out by SCK/CEN, BGS and ISMES. SCK/CEN are also conducting in situ experiments at the underground laboratory at Mol, Belgium. Modeling of gas migration is being done in parallel with the experiments, by Intera Information Technologies. A two-phase flow code, TOPAZ, has been developed specifically for this work. In this paper the authors report on the results of some preliminary calculations performed with TOPAZ, in advance of the in situ experiments

  4. Biosphere conceptual model development in the frame of Baita Bihor repository safety project

    International Nuclear Information System (INIS)

    Paunescu, N.; Margineanu, R.; Ene, D.

    2002-01-01

    The topic of this paper is the development of the biosphere model in the frame of the preliminary performance assessment of the Romanian National L and ILW repository, Baita-Bihor. The work presents the actual understanding of the radionuclide pathways through the repository adjacent area and their conceptualization, collection of required data, implementation of model and preliminary calculation results. The model takes into consideration a leaching scenario from the near field and the transport of radionuclides by river water. The critical group is a small community of inhabitants relying on the local resources, which constitutes an agriculture community 'small farm system'. On the basis of the defined specifications (biosphere equations and data), application of model and dose rate estimates were performed by the ABRICOT code. (author)

  5. Configuration management plan. System definition and project development. Repository Based Software Engineering (RBSE) program

    Science.gov (United States)

    Mckay, Charles

    1991-01-01

    This is the configuration management Plan for the AdaNet Repository Based Software Engineering (RBSE) contract. This document establishes the requirements and activities needed to ensure that the products developed for the AdaNet RBSE contract are accurately identified, that proposed changes to the product are systematically evaluated and controlled, that the status of all change activity is known at all times, and that the product achieves its functional performance requirements and is accurately documented.

  6. Comparative simulation study of coupled THM processes near back-filled and open-drift nuclear waste repositories in Task D of the International DECOVALEX Project

    International Nuclear Information System (INIS)

    Rutqvist, J.; Birkholzer, J.T.; Chijimatsu, M.; Kolditz, O.; Liu, Quan-Sheng; Oda, Y.; Wang, Wenqing; Zhang, Cheng-Yuan

    2006-01-01

    As part of the ongoing international DECOVALEX project, four research teams used five different models to simulate coupled thermal, hydrological, and mechanical (THM) processes near underground waste emplacement drifts. The simulations were conducted for two generic repository types, one with open and the other with back-filled repository drifts, under higher and lower post-closure temperature, respectively. In the completed first model inception phase of the project, a good agreement was achieved between the research teams in calculating THM responses for both repository types, although some disagreement in hydrological responses are currently being resolved. Good agreement in the basic thermal-mechanical responses was also achieved for both repository types, even though some teams used relatively simplified thermal-elastic heat-conduction models that neglect complex near-field thermal-hydrological processes. The good agreement between the complex and simplified process models indicates that the basic thermal-mechanical responses can be predicted with a relatively high confidence level

  7. Innovation in health service management: Adoption of project management offices to support major health care transformation.

    Science.gov (United States)

    Lavoie-Tremblay, Mélanie; Aubry, Monique; Cyr, Guylaine; Richer, Marie-Claire; Fortin-Verreault, Jean-François; Fortin, Claude; Marchionni, Caroline

    2017-11-01

    To explore the characteristics that influence project management offices acceptance and adoption in healthcare sector. The creation of project management offices has been suggested as a promising avenue to promote successful organisational change and facilitate evidence-based practice. However, little is known about the characteristics that promote their initial adoption and acceptance in health care sector. This knowledge is important in the context where many organisations are considering implementing project management offices with nurse managers as leaders. A descriptive multiple case study design was used. The unit of analysis was the project management offices. The study was conducted in three university-affiliated teaching hospitals in 2013-14 (Canada). Individual interviews (n = 34) were conducted with senior managers. Results reveal that project management offices dedicated to project and change management constitute an innovation and an added value that addresses tangible needs in the field. Project management offices are an innovation highly compatible with health care managers and their approach has parallels to the process of clinical problem solving and reasoning well-known to adopters. This knowledge is important in a context where many nurses hold various roles in project management offices, such as Director, project manager, clinical expert and knowledge broker. © 2017 John Wiley & Sons Ltd.

  8. Report of the Peer Review Panel on the early site suitability evaluation of the Potential Repository Site at Yucca Mountain, Nevada; Yucca Mountain Site Characterization Project

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1992-01-01

    The US Department of Energy (DOE) Yucca mountain Site Characterization Project Office (YMPO) assigned Science Applications International Corporation (SAIC), the Technical and Management Support Services (T&MSS) contractor to the YmPo, the task of conducting an Early Site Suitability Evaluation (ESSE) of the Yucca mountain site as a potential site for a high-level radioactive waste repository. First, the assignment called for the development of a method to evaluate a single site against the DOE General Guidelines for Recommendation of Sites for Nuclear Waste Repositories, 10 CFR Part 960. Then, using this method, an evaluation team, the ESSE Core Team, of senior YMP scientists, engineers, and technical experts, evaluated new information obtained about the site since publication of the final Environmental Assessment (DOE, 1986) to determine if new suitability/unsuitability findings could be recommended. Finally, the Core Team identified further information and analyses needed to make final determinations for each of the guidelines. As part of the task, an independent peer review of the ESSE report has been conducted. Expertise was solicited that covered the entire spectrum of siting guidelines in 10 CFR Part 960 in order to provide a complete, in-depth critical review of the data evaluated and cited in the ESSE report, the methods used to evaluate the data, and the conclusions and recommendations offered by the report. Fourteen nationally recognized technical experts (Table 2) served on the Peer Review Panel. The comments from the Panel and the responses prepared by the ESSE Core Team, documented on formal Comment Response Forms, constitute the body of this document.

  9. ANALYSIS OF THE POSSIBILITY FOR ESTABLISHING PROJECT MANAGEMENT OFFICE (PMO IN COMPANIES IN SERBIA

    Directory of Open Access Journals (Sweden)

    Dragana Milin

    2012-09-01

    Full Text Available Project Management Office (PMO is an organizational unit established to help project managers, project teams and the various levels of management in carrying out the principles of project management. The research was carried out in Serbia, in 2011, with the aim to establish which methodologies and techniques are used for project m anagement, and which of them are used the most frequently. Furthermore, the need for establishment of PMOs in Serbia is discussed. These offices should help in establishing a standardized methodology (at the organization level and thus overcome the obviou s poor use of any project management methodology at all.

  10. Experiences of unemployed clients with services offered them by the front office of the Bridge project

    OpenAIRE

    Twum, Sampson

    2010-01-01

    The purpose of this study was to examine the experiences of unemployed clients of the Bridge project to the services offered them by the front office. The Bridge project organises programs to ease immigrant’s integration. The project also aid immigrant’s integration with supervision, information and education through front office activity. This study used a qualitative research approach and the method of data collection was in-depth interviews. The participants were selected using snow b...

  11. US Department of Energy Grand Junction Projects Office Remedial Action Project, final report of the decontamination and decommissioning of Building 36 at the Grand Junction Projects Office Facility

    International Nuclear Information System (INIS)

    Widdop, M.R.

    1996-08-01

    The U.S. Department of Energy (DOE) Grand Junction Projects Office (GJPO) occupies a 61.7-acre facility along the Gunnison River near Grand Junction, Colorado. This site was contaminated with uranium ore and mill tailings during uranium refining activities of the Manhattan Engineer District and during pilot milling experiments conducted for the U.S. Atomic Energy Commission's domestic uranium procurement program. The DOE Defense Decontamination and Decommissioning Program established the GJPO Remedial Action Project to clean up and restore the facility lands, improvements, and the underlying aquifer. The site contractor for the facility, Rust Geotech, also is the remedial action contractor. Building 36 was found to be radiologically contaminated and was demolished in 1996. The soil beneath the building was remediated in accordance with identified standards and can be released for unlimited exposure and unrestricted use. This document was prepared in response to a DOE request for an individual final report for each contaminated GJPO building

  12. The Microbiology of Subsurface, Salt-Based Nuclear Waste Repositories: Using Microbial Ecology, Bioenergetics, and Projected Conditions to Help Predict Microbial Effects on Repository Performance

    International Nuclear Information System (INIS)

    Swanson, Juliet S.; Cherkouk, Andrea; Arnold, Thuro; Meleshyn, Artur; Reed, Donald T.

    2016-01-01

    This report summarizes the potential role of microorganisms in salt-based nuclear waste repositories using available information on the microbial ecology of hypersaline environments, the bioenergetics of survival under high ionic strength conditions, and ''repository microbiology'' related studies. In areas where microbial activity is in question, there may be a need to shift the research focus toward feasibility studies rather than studies that generate actual input for performance assessments. In areas where activity is not necessary to affect performance (e.g., biocolloid transport), repository-relevant data should be generated. Both approaches will lend a realistic perspective to a safety case/performance scenario that will most likely underscore the conservative value of that case.

  13. The Microbiology of Subsurface, Salt-Based Nuclear Waste Repositories: Using Microbial Ecology, Bioenergetics, and Projected Conditions to Help Predict Microbial Effects on Repository Performance

    Energy Technology Data Exchange (ETDEWEB)

    Swanson, Juliet S. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Cherkouk, Andrea [Helmholtz-Zentrum Dresden-Rossendorf, Rossendorf (Germany); Arnold, Thuro [Helmholtz-Zentrum Dresden-Rossendorf, Rossendorf (Germany); Meleshyn, Artur [Gesellschaft fur Anlagen und Reaktorsicherheit, Braunschweig (Germany); Reed, Donald T. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2016-11-17

    This report summarizes the potential role of microorganisms in salt-based nuclear waste repositories using available information on the microbial ecology of hypersaline environments, the bioenergetics of survival under high ionic strength conditions, and “repository microbiology” related studies. In areas where microbial activity is in question, there may be a need to shift the research focus toward feasibility studies rather than studies that generate actual input for performance assessments. In areas where activity is not necessary to affect performance (e.g., biocolloid transport), repository-relevant data should be generated. Both approaches will lend a realistic perspective to a safety case/performance scenario that will most likely underscore the conservative value of that case.

  14. 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

  15. Economic and fiscal impacts of large-scale development projects: implications for nuclear waste repositories

    International Nuclear Information System (INIS)

    Leistritz, F.L.; Murdock, S.H.; Texas A and M Univ., College Station)

    1982-01-01

    This paper deals with the local economic and fiscal implications of siting high-level nuclear waste repositories in rural areas. The economic and fiscal effects of repository development fall into two categories: (1) standard impacts similar to those that would be associated with developing any large-scale industrial facility in an isolated area; (2) special impacts that result from the hazardous nature of the nuclear materials stored and from federal ownership of the facility. Standard economic and fiscal impacts include employment effects (direct and secondary), local income changes, alterations in community price structures, effects on community services, and changes in revenues and costs for local jurisdictions. Special impacts include the possibility of diminished activity in other basic economic sectors, negative effects on the area's long-term growth prospects and a consequent dampening of investment in the local trade an service sectors, additional costs for local jurisdictions (e.g., for preparing evacuation plans), and limited local tax revenues resulting from the tax-exempt status of the facility. These special effects are difficult to quantify and require additional analysis. 47 references, 1 figure, 4 tables

  16. Financial Management in the Strategic Systems Project Office.

    Science.gov (United States)

    SSPO, the largest program office in the Navy and in existence for over 20 years, has perfected time tested financial management procedures which may...serve as a model for the student of program management. This report presents an overview of the SSPO financial management concepts and general

  17. The hands-on project office guaranteeing ROI and on-time delivery

    CERN Document Server

    Kesner, Richard M

    2003-01-01

    THE THREE PILLARS OF IT DELIVERY - PROBLEM RESOLUTION, SERVICE REQUESTS, AND PROJECTSIntroduction The Business Context The Internal Economy for Investing in IT Services and ProjectsThe Three Pillars of IT Delivery Managing Service DeliveryManaging Project Commitments IT Metrics and Reporting Tools THE PROJECT MANAGEMENT OFFICE BUSINESS MODELIntroduction: Revisiting the IT Organization IT Service and Project Delivery RolesThe Role of the Project Management Office: Measuring its ROI The PMO Value Proposition: An Initial ROI Estimate ALIGNMENT AND PLANNING - DOING THE RIGHT THINGS Introduction Ge

  18. Grand Junction Projects Office Remedial Action Project Building 2 public dose evaluation. Final report

    International Nuclear Information System (INIS)

    Morris, R.

    1996-05-01

    Building 2 on the U.S. Department of Energy (DOE) Grand Junction Projects Office (GJPO) site, which is operated by Rust Geotech, is part of the GJPO Remedial Action Program. This report describes measurements and modeling efforts to evaluate the radiation dose to members of the public who might someday occupy or tear down Building 2. The assessment of future doses to those occupying or demolishing Building 2 is based on assumptions about future uses of the building, measured data when available, and predictive modeling when necessary. Future use of the building is likely to be as an office facility. The DOE sponsored program, RESRAD-BUILD, Version. 1.5 was chosen for the modeling tool. Releasing the building for unrestricted use instead of demolishing it now could save a substantial amount of money compared with the baseline cost estimate because the site telecommunications system, housed in Building 2, would not be disabled and replaced. The information developed in this analysis may be used as part of an as low as reasonably achievable (ALARA) cost/benefit determination regarding disposition of Building 2

  19. The eDoc-Server Project Building an Institutional Repository for the Max Planck Society

    CERN Document Server

    Beier, Gerhard

    2004-01-01

    With the eDoc-Server the Heinz Nixdorf Center for Information Management in the Max Planck Society (ZIM) provides the research institutes of the Max Planck Society (MPS) with a platform to disseminate, store, and manage their scientific output. Moreover, eDoc serves as a tool to facilitate and promote open access to scientific information and primary sources. Since its introduction in October 2002 eDoc has gained high visibility within the MPS. It has been backed by strong institutional commitment to open access as documented in the 'Berlin Declaration on Open Access to the Data of the Sciences and Humanities', which was initiated by the MPS and found large support among major research organizations in Europe. This paper will outline the concept as well as the current status of the eDoc-Server, providing an example for the development and introduction of an institutional repository in a multi-disciplinary research organization.

  20. Review of Draft Crystalline Repository Project reports [sited on Indian reservation]: Final report

    International Nuclear Information System (INIS)

    Thorson, R.M.

    1988-01-01

    The Mashantucket Pequot Tribal Council was concerned about the possible emplacement of a nuclear waste repository in the crystalline rocks of Eastern Connecticut and Rhode Island. The Tribe was especially concerned with the hydrological problems because the Tribe's lands occur in an area with all of the complications cited above, including one of the highest concentrations of large brittle-fractures in southern New England. We questioned whether the intermediate and(or) regional groundwater systems might intersect the Cedar Swamp - a major groundwater discharge point at the junction of the Mesozoic brittle fractures and the Honey Hill Thrust. If the Cedar Swamp intersected the regional groundwater flow system, and if the groundwater flows were substantial (i.e., 5% of total flow during dry periods), the regional contribution to the surface discharge might possibly be measurable from surface data. 4 refs., 12 figs

  1. Waste handling building design tradeoff studies: Salt Repository Project closeout task report

    International Nuclear Information System (INIS)

    1988-01-01

    The purpose of this closeout study is to capture work done by SRPO contractors and the relevant knowledge and recommendations of Battelle staff regarding design of WHB receiving, storage, hot cell areas, and process logistics. The information and recommendations are based on the latest available studies and prior experience of Battelle personnel at WIPP, INEL, and Hanford facilities. The information is expected to be directly applicable to WHB design work that will be done at Nevada, MRS, or other repository facilities. A perspective showing the various WHB areas and general arrangement is given. This study addresses alternatives associated with the receiving area, the fuel storage areas, the cell arrangements, the failed fuel accommodations, and the process logistics. 16 refs., 2 figs., 5 tabs

  2. Accelerating Project and Process Improvement using Advanced Software Simulation Technology: From the Office to the Enterprise

    Science.gov (United States)

    2010-04-29

    Technology: From the Office Larry Smith Software Technology Support Center to the Enterprise 517 SMXS/MXDEA 6022 Fir Avenue Hill AFB, UT 84056 801...2010 to 00-00-2010 4. TITLE AND SUBTITLE Accelerating Project and Process Improvement using Advanced Software Simulation Technology: From the Office to

  3. Report: EPA Managers Did Not Hold Supervisors and Project Officers Accountable for Grants Management

    Science.gov (United States)

    Report #2005-P-00027, September 27, 2005. Managers did not sufficiently hold supervisors and project officers accountable for grants management because there is no process to measure most grants management activity.

  4. Region 9 Tribal Grant Program - Project Officer and Tribal Contact Information Map Service

    Science.gov (United States)

    This compilation of geospatial data is for the purpose of managing and communicating information about current EPA project officers, tribal contacts, and tribal grants, both internally and with external stakeholders.

  5. L'Arxiu de la Paraula : context i projecte del repositori audiovisual de l'Ateneu Barcelonès

    Directory of Open Access Journals (Sweden)

    Alcaraz Martínez, Rubén

    2014-12-01

    Full Text Available Es presenten els resultats del projecte de digitalització del fons audiovisual de l'Ateneu Barcelonès iniciat per l'Àrea de Biblioteca i Arxiu Històric l'any 2011. S'explica la metodologia de treball fent èmfasi en la gestió dels fitxers analògics i nascuts digitals i en la problemàtica derivada dels drets d'autor. Finalment, es presenta l'Arxiu de la Paraula i l'@teneu hub, nous repositori i web respectivament, l'objectiu dels quals és difondre el patrimoni audiovisual i donar accés centralitzat als diferents continguts generats per l'entitat.Se presentan los resultados del proyecto de digitalización del fondo audiovisual del Ateneu Barcelonès iniciado por el área de Biblioteca y Archivo Histórico en 2011. Se explica la metodología de trabajo haciendo énfasis en la gestión de los ficheros analógicos y nacidos digitales y en la problemática derivada de los derechos de autor. Finalmente, se presenta el Archivo de la Palabra y el @teneo hub, nuevos repositorio y web respectivamente, cuyo objetivo es difundir el patrimonio audiovisual y dar acceso centralizado a los diferentes contenidos generados por la entidad.This paper reports on the project to digitize the audiovisual archives of the Ateneu Barcelonès, which was launched by that institution’s Library and Archive department in 2011. The paper explains the methodology used to create the repository, focusing on the management of analogue files and born-digital materials and the question of author’s rights. Finally, it presents the new repository L’Arxiu de la Paraula (the Word Archive and the new website, @teneu hub, which are designed to disseminate the Ateneu’s audiovisual heritage and provide centralized access to its different contents.

  6. White Paper on Data Repository Reorganization Proposal for the xLPR Project

    Energy Technology Data Exchange (ETDEWEB)

    Klasky, Hilda B [ORNL; Williams, Paul T [ORNL; Bass, Bennett Richard [ORNL

    2012-09-01

    As the xLPR project moves along, it is important to properly manage the knowledge generated by the different groups. We focus specifically on the knowledge and communications written in files, including general documents, source code and executable files. Data generated through the project are different in nature and, for this reason, need to be treated differently. To that end, ORNL put in place a series of tools that facilitate proper storage and management of project data, document and code changes, group collaboration, knowledge transfer, transparency, accountability and auditability. This paper describes the approaches/tools that we recommend for moving the project forward on knowledge management.

  7. Abstraction of information in repository performance assessments. Examples from the SKI project Site-94

    International Nuclear Information System (INIS)

    Dverstorp, B.; Andersson, J.

    1995-01-01

    Performance Assessment of a nuclear waste repository implies an analysis of a complex system with many interacting processes. Even if some of these processes may be known to large detail, problems arise when combining all information, and means of abstracting information from complex detailed models into models that couple different processes are needed. Clearly, one of the major objectives of performance assessment, to calculate doses or other performance indicators, implies an enormous abstraction of information compared to all information that is used as input. Other problems are that the knowledge of different parts or processes is strongly variable and adjustments, interpretations, are needed when combining models from different disciplines. In addition, people as well as computers, even today, always have a limited capacity to process information and choices have to be made. However, because abstraction of information clearly is unavoidable in performance assessment the validity of choices made, always need to be scrutinized and judgements made need to be updated in an iterative process

  8. Project SAFE. Modelling of long-term concrete degradation processes in the Swedish SFR repository

    Energy Technology Data Exchange (ETDEWEB)

    Hoeglund, L.O. [Kemakta Konsult AB, Stockholm (Sweden)

    2001-04-01

    This study concerns the leaching of concrete barriers, in particular the silo construction, in the Swedish SFR repository for low and intermediate level radioactive waste. A conceptual model for the leaching of concrete in a saline groundwater has been proposed based on the increased understanding achieved from research studies presented in the literature. The conceptual model has been used to set up a numerical model for the complex chemical interactions between the cement minerals of the concrete with the groundwater. The calculations show that various chemical reactions are expected to occur in the concrete over time. Different cases have been calculated. The results show that the chemical conditions in the concrete barriers will maintain alkaline for long time. In the most exposed parts of the concrete a high degree of leaching can be expected during the considered 10,000 years, whereas only for the most unfavourable assumptions (initially fractured concrete with groundwater flow-through) the inner parts of the concrete will be degraded to any significant degree.

  9. Project SAFE. Modelling of long-term concrete degradation processes in the Swedish SFR repository

    International Nuclear Information System (INIS)

    Hoeglund, L.O.

    2001-04-01

    This study concerns the leaching of concrete barriers, in particular the silo construction, in the Swedish SFR repository for low and intermediate level radioactive waste. A conceptual model for the leaching of concrete in a saline groundwater has been proposed based on the increased understanding achieved from research studies presented in the literature. The conceptual model has been used to set up a numerical model for the complex chemical interactions between the cement minerals of the concrete with the groundwater. The calculations show that various chemical reactions are expected to occur in the concrete over time. Different cases have been calculated. The results show that the chemical conditions in the concrete barriers will maintain alkaline for long time. In the most exposed parts of the concrete a high degree of leaching can be expected during the considered 10,000 years, whereas only for the most unfavourable assumptions (initially fractured concrete with groundwater flow-through) the inner parts of the concrete will be degraded to any significant degree

  10. Reduction of sulfate by hydrogen in natural systems: A literature review: Salt Repository Project

    International Nuclear Information System (INIS)

    Mahoney, J.J.; Strachan, D.M.

    1988-01-01

    The results of this literature search indicate that the reduction of sulfate by hydrogen gas can occur in nature, but that temperature appears to be a key factor in the rate of this reaction. At temperatures below 200/degree/C, the key factor in the rate of reaction appears to be extremely slow. At low pH the rate of reaction is faster than at high pH. The solution composition also influences the reaction rate; the most recent research available (Yanisagawa 1983) suggests that the concentration of sulfide in solution influences the rate of this reaction. The reduction reaction appears to proceed through a thiosulfate intermediate, so the presence and distribution of other sulfur species will influence the reaction rate. If the reaction mechanism proposed by Yanisagawa is correct, then higher concentrations of sulfide will result in faster rates of sulfate reduction. In conclusion, the reduction of sulfate by hydrogen to form significant amounts of sulfide is a function of temperature, sulfate and sulfide concentrations, pH, and solution composition. The rate of this reaction appears to be very slow under the conditions anticipated in this repository, but given the length of time required to maintain the integrity of the containers (300 to 1000 years) and the unusual solution compositions present, a better understanding of the reaction mechanism is needed. 16 refs., 1 tab

  11. UMTRA project office federal employee occupational safety and health program plan

    International Nuclear Information System (INIS)

    1994-06-01

    This document establishes the Federal Employee Occupational Safety and Health (FEOSH) Program for the US Department of Energy (DOE) Uranium Mill Tailings Remedial Action (UMTRA) Project Office. This program will ensure compliance with applicable requirements of DOE Order 3790.1B and DOE Albuquerque Operations Office (AL) Order 3790.lA. FEOSH Program responsibilities delegated by the DOE-AL to the UMTRA Project Office by AL Order 3790.1A also are assigned. The UMTRA Project Office has developed the UMTRA Project Environmental, Safety, and Health (ES ampersand H) Plan (DOE, 1992), which establishes the basic programmatic ES ampersand H requirements for all participants on the UMTRA Project. The ES ampersand H plan is designed primarily to cover remedial action activities at UMTRA sites and defines the ES ampersand H responsibilities of both the UMTRA Project Office and its contractors. The UMTRA FEOSH Program described herein is a subset of the overall UMTRA ES ampersand H program and covers only federal employees working on the UMTRA Project

  12. US Department of Energy Grand Junction Projects Office Remedial Action Project. Final report of the decontamination and decommissioning of Building 52 at the Grand Junction Projects Office Facility

    International Nuclear Information System (INIS)

    Krabacher, J.E.

    1996-08-01

    The U.S. Department of Energy (DOE) Grand Junction Projects Office (GJPO) occupies a 61.7-acre facility along the Gunnison River near Grand Junction, Colorado. This site was contaminated with uranium ore and mill tailings during uranium refining activities of the Manhattan Engineer District and during pilot milling experiments conducted for the U.S. Atomic Energy Commission's domestic uranium procurement program. The DOE Defense Decontamination and Decommissioning Program established the GJPO Remedial Action Project to clean up and restore the facility lands, improvements, and the underlying aquifer. The site contractor for the facility, Rust Geotech, also was the remedial action contractor. Building 52 was found to be radiologically contaminated and was demolished in 1994. The soil area within the footprint of the building has been remediated in accordance with the identified standards and the area can be released for unlimited exposure and unrestricted use. This document was prepared in response to a DOE request for an individual final report for each contaminated GJPO building

  13. The Aespoe redox investigations in block scale. Project summary and implications for repository performance assessment

    Energy Technology Data Exchange (ETDEWEB)

    Banwart, S [ed.; Bradford Univ. (United Kingdom). Dept. of Civil Engineering

    1995-11-01

    During construction and operation of a deep repository for high level waste, the groundwater environment will be open to oxidizing surface conditions and surface water inflow. Construction of the access tunnel to the Hard Rock Laboratory intersected a vertical fracture zone at a depth of 70 m. Changes in the groundwater chemistry were then monitored for a period of three years. Mass balances for conservative and reactive natural tracers provided a basis for a site model of the fracture zone. Groundwater dilution was the dominant process affecting the geochemistry of the site. There was associated Na-Ca ion-exchange. There is evidence for extensive lateral flow between recharge areas and the discharge point in the access tunnel. There was a significant transport of young organic carbon from the surface to the discharge borehole during recharge. Proposed microbial processes during lateral flow include anaerobic respiration coupled to reduction of iron hydroxide, methanogenesis, precipitation of calcite and secondary ferrous minerals. There is strong evidence to rule out sulfate reduction. Sulfate increased dramatically, possibly by desorption from fracture minerals. Fracture performance is affected by the extensive groundwater dilution and by the microbial processes that occur. Dilution affects aqueous speciation, radionuclide solubility and sorption, and the stability and mobility of colloids. Aerobic respiration provides an effective sink for oxygen. Maintaining anoxia favors low solubility for Tc, Np, Pu and U. Reductive dissolution of iron hydroxide will release sorbed radionuclides, while formation of biogenic Fe(II) minerals can provide an effective reducing migration barrier to radionuclides and to future intrusion of oxygen from the surface. 26 refs, 13 figs, 10 tabs.

  14. The Aespoe redox investigations in block scale. Project summary and implications for repository performance assessment

    International Nuclear Information System (INIS)

    Banwart, S.

    1995-11-01

    During construction and operation of a deep repository for high level waste, the groundwater environment will be open to oxidizing surface conditions and surface water inflow. Construction of the access tunnel to the Hard Rock Laboratory intersected a vertical fracture zone at a depth of 70 m. Changes in the groundwater chemistry were then monitored for a period of three years. Mass balances for conservative and reactive natural tracers provided a basis for a site model of the fracture zone. Groundwater dilution was the dominant process affecting the geochemistry of the site. There was associated Na-Ca ion-exchange. There is evidence for extensive lateral flow between recharge areas and the discharge point in the access tunnel. There was a significant transport of young organic carbon from the surface to the discharge borehole during recharge. Proposed microbial processes during lateral flow include anaerobic respiration coupled to reduction of iron hydroxide, methanogenesis, precipitation of calcite and secondary ferrous minerals. There is strong evidence to rule out sulfate reduction. Sulfate increased dramatically, possibly by desorption from fracture minerals. Fracture performance is affected by the extensive groundwater dilution and by the microbial processes that occur. Dilution affects aqueous speciation, radionuclide solubility and sorption, and the stability and mobility of colloids. Aerobic respiration provides an effective sink for oxygen. Maintaining anoxia favors low solubility for Tc, Np, Pu and U. Reductive dissolution of iron hydroxide will release sorbed radionuclides, while formation of biogenic Fe(II) minerals can provide an effective reducing migration barrier to radionuclides and to future intrusion of oxygen from the surface. 26 refs, 13 figs, 10 tabs

  15. Building Bridges: Using the Office Consultation Project to Connect Students to Theory and Practice

    Science.gov (United States)

    Wawrzynski, Korine Steinke; Jessup-Anger, Jody E.

    2014-01-01

    The Office Consultation Project is an innovative capstone project that partners graduate students in student affairs preparation programs with academic and student affairs practitioners. It provides an opportunity for students to apply research and scholarship to practical settings, while giving practitioners new insight into their units,…

  16. INVENTORY OF ECOSYSTEM RESTORATION PROJECTS - PUBLISHED ON THE OFFICE OF WATER WEB PAGE

    Science.gov (United States)

    USEPA's National Risk Management Research Laboratory working jointly with the Office of Water, has developed an Internet-accessible database of ecosystem restoration projects within the Mid-Atlantic Integrated Assessment (MAIA) region. This article informs project owners of the i...

  17. Report on materials characterization center workshop on stress corrosion cracking for the Salt Repository Project, December 16-17, 1986, Seattle, Washington: Workshop summary

    International Nuclear Information System (INIS)

    Merz, M.D.; Shannon, D.W.

    1986-09-01

    The Materials Characterization Center (MCC) at Pacific Northwest Laboratory (PNL) conducted a Workshop on Stress Corrosion Cracking for the Salt Repository Project on December 16 and 17, 1986 in Seattle, Washington. The workshop was held to formulate recommendations for addressing stress corrosion cracking (SCC) in a salt repository. It was attended by 24 representatives from major laboratories, universities, and industry. This report presents the recommendations of the workshop, along with the agenda, list of participants, questions and comments, summaries of working groups on low-strength steel and alternate materials, and materials handed out by the speakers

  18. Some Materials Degradation Issues in the U.S. High-Level Nuclear Waste Repository Study (The Yucca Mountain Project)

    Energy Technology Data Exchange (ETDEWEB)

    F. Hua; P. Pasupathi; N. Brown; K. Mon

    2005-09-19

    The safe disposal of radioactive waste requires that the waste be isolated from the environment until radioactive decay has reduced its toxicity to innocuous levels for plants, animals, and humans. All of the countries currently studying the options for disposing of high-level nuclear waste (HLW) have selected deep geologic formations to be the primary barrier for accomplishing this isolation. In U.S.A., the Nuclear Waste Policy Act of 1982 (as amended in 1987) designated Yucca Mountain in Nevada as the potential site to be characterized for high-level nuclear waste (HLW) disposal. Long-term containment of waste and subsequent slow release of radionuclides into the geosphere will rely on a system of natural and engineered barriers including a robust waste containment design. The waste package design consists of a highly corrosion resistant Ni-based Alloy 22 cylindrical barrier surrounding a Type 316 stainless steel inner structural vessel. The waste package is covered by a mailbox-shaped drip shield composed primarily of Ti Grade 7 with Ti Grade 24 structural support members. The U.S. Yucca Mountain Project has been studying and modeling the degradation issues of the relevant materials for some 20 years. This paper reviews the state-of-the-art understanding of the degradation processes based on the past 20 years studies on Yucca Mountain Project (YMP) materials degradation issues with focus on interaction between the in-drift environmental conditions and long-term materials degradation of waste packages and drip shields within the repository system during the 10,000 years regulatory period. This paper provides an overview of the current understanding of the likely degradation behavior of the waste package and drip shield in the repository after the permanent closure of the facility. The degradation scenario discussed in this paper include aging and phase instability, dry oxidation, general and localized corrosion, stress corrosion cracking and hydrogen induced

  19. Some Materials Degradation Issues in the U.S. High-Level Nuclear Waste Repository Study (The Yucca Mountain Project)

    International Nuclear Information System (INIS)

    Hua, F.; Pasupathi, P.; Brown, N.; Mon, K.

    2005-01-01

    The safe disposal of radioactive waste requires that the waste be isolated from the environment until radioactive decay has reduced its toxicity to innocuous levels for plants, animals, and humans. All of the countries currently studying the options for disposing of high-level nuclear waste (HLW) have selected deep geologic formations to be the primary barrier for accomplishing this isolation. In U.S.A., the Nuclear Waste Policy Act of 1982 (as amended in 1987) designated Yucca Mountain in Nevada as the potential site to be characterized for high-level nuclear waste (HLW) disposal. Long-term containment of waste and subsequent slow release of radionuclides into the geosphere will rely on a system of natural and engineered barriers including a robust waste containment design. The waste package design consists of a highly corrosion resistant Ni-based Alloy 22 cylindrical barrier surrounding a Type 316 stainless steel inner structural vessel. The waste package is covered by a mailbox-shaped drip shield composed primarily of Ti Grade 7 with Ti Grade 24 structural support members. The U.S. Yucca Mountain Project has been studying and modeling the degradation issues of the relevant materials for some 20 years. This paper reviews the state-of-the-art understanding of the degradation processes based on the past 20 years studies on Yucca Mountain Project (YMP) materials degradation issues with focus on interaction between the in-drift environmental conditions and long-term materials degradation of waste packages and drip shields within the repository system during the 10,000 years regulatory period. This paper provides an overview of the current understanding of the likely degradation behavior of the waste package and drip shield in the repository after the permanent closure of the facility. The degradation scenario discussed in this paper include aging and phase instability, dry oxidation, general and localized corrosion, stress corrosion cracking and hydrogen induced

  20. Project Opalinus Clay: Radionuclide Concentration Limits in the Cementitious Near-Field of an ILW Repository

    International Nuclear Information System (INIS)

    Berner, U.

    2003-05-01

    The disposal feasibility study currently performed by Nagra includes a succession of quantitative models, aiming at describing the fate of radionuclides potentially escaping from the repository system. In this chain of models the present report provides the so called 'solubility limits' (maximum expected concentrations) for safety relevant radionuclides from ILW wastes, disposed of in a chemically reducing, cementitious environment. From a chemical point of view, the pore waters of hydrated cement matrices provide an exceptional environment. Compared with usual ground waters exhibiting pH-values of around 8, cement pore waters are strongly alkaline with pH-values from 12.5 to 13.5 and contain nearly no carbonate and only little sulfate. Oxides and hydroxides mainly determine solubility and speciation of the elements. Solubility and speciation calculations in cementitious pore waters were performed using the very recently updated Nagra/PSI Chemical Thermodynamic Data Base (TDB) for the majority of the 36 elements addressed as potentially relevant. Wherever possible, maximum concentrations compiled in this report were based on geochemical calculations. In order to ensure full traceability, all thermodynamic data not included in the TDB are explicitly specified in the document. For similar reasons the compilation of results (Table 1) clearly distinguishes between calculated and recommended items. The heading 'CALCULATED' lists maximum concentrations based on data fully documented in the TDB; results under the heading 'RECOMMENDED' include data from other sources. The pH sensitivity of the results was examined by performing calculations at pH 13.4, in accordance with the pH of non-altered cement pore water. Solubility increases predominantly for elements that tend to form anionic hydroxide complexes (Sn, Pd, Zr, Ni, Eu, Cd, Mo, Co). Oxidizing conditions around +350 mV might be expected in the environment of nitrate-containing wastes. In this case, significant

  1. Project Opalinus Clay: Radionuclide Concentration Limits in the Cementitious Near-Field of an ILW Repository

    Energy Technology Data Exchange (ETDEWEB)

    Berner, U

    2003-05-01

    The disposal feasibility study currently performed by Nagra includes a succession of quantitative models, aiming at describing the fate of radionuclides potentially escaping from the repository system. In this chain of models the present report provides the so called 'solubility limits' (maximum expected concentrations) for safety relevant radionuclides from ILW wastes, disposed of in a chemically reducing, cementitious environment. From a chemical point of view, the pore waters of hydrated cement matrices provide an exceptional environment. Compared with usual ground waters exhibiting pH-values of around 8, cement pore waters are strongly alkaline with pH-values from 12.5 to 13.5 and contain nearly no carbonate and only little sulfate. Oxides and hydroxides mainly determine solubility and speciation of the elements. Solubility and speciation calculations in cementitious pore waters were performed using the very recently updated Nagra/PSI Chemical Thermodynamic Data Base (TDB) for the majority of the 36 elements addressed as potentially relevant. Wherever possible, maximum concentrations compiled in this report were based on geochemical calculations. In order to ensure full traceability, all thermodynamic data not included in the TDB are explicitly specified in the document. For similar reasons the compilation of results (Table 1) clearly distinguishes between calculated and recommended items. The heading 'CALCULATED' lists maximum concentrations based on data fully documented in the TDB; results under the heading 'RECOMMENDED' include data from other sources. The pH sensitivity of the results was examined by performing calculations at pH 13.4, in accordance with the pH of non-altered cement pore water. Solubility increases predominantly for elements that tend to form anionic hydroxide complexes (Sn, Pd, Zr, Ni, Eu, Cd, Mo, Co). Oxidizing conditions around +350 mV might be expected in the environment of nitrate-containing wastes. In

  2. Center for Leadership Development (CLD) Repository

    Data.gov (United States)

    Office of Personnel Management — The Center for Leadership Development Repository stores various data including policies, procedures, governance, guidance, security, and financial documents of the...

  3. Project officer's perspective: quality assurance as a management tool.

    Science.gov (United States)

    Heiby, J

    1993-06-01

    Advances in the management of health programs in less developed countries (LDC) have not kept pace with the progress of the technology used. The US Agency for International Development mandated the Quality Assurance Project (QAP) to provide quality improvement technical assistance to primary health care systems in LDCs while developing appropriate quality assurance (QA) strategies. The quality of health care in recent years in the US and Europe focused on the introduction of management techniques developed for industry into health systems. The experience of the QAP and its predecessor, the PRICOR Project, shows that quality improvement techniques facilitate measurement of quality of care. A recently developed WHO model for the management of the sick child provides scientifically based standards for actual care. Since 1988, outside investigators measuring how LDC clinicians perform have revealed serious deficiencies in quality compared with the program's own standards. This prompted developed of new QA management initiatives: 1) communicating standards clearly to the program staff; 2) actively monitoring actual performance corresponds to these standards; and 3) taking action to improve performance. QA means that managers are expected to monitor service delivery, undertake problem solving, and set specific targets for quality improvement. Quality improvement methods strengthen supervision as supervisors can objectively assess health worker performance. QA strengthens the management functions that support service delivery, e.g., training, records management, finance, logistics, and supervision. Attention to quality can contribute to improved health worker motivation and effective incentive programs by recognition for a job well done and opportunities for learning new skills. These standards can also address patient satisfaction. QA challenges managers to aim for the optimal level of care attainable.

  4. Implementation of a Project Management Office (PMO)--experiences from year 1.

    Science.gov (United States)

    Isola, Miriam; Polikaitis, Audrius; Laureto, Rose Ann

    2006-01-01

    Recognized as an early leader in clinical information systems, the University of Illinois Medical Center was challenged to meet the ever-increasing demand for information systems. Interviews with key stakeholders revealed unfavorable attitudes toward the Information Services department. Reasons given were that projects often are not aligned with business strategy, projects are delayed, IS itself is a barrier to progress, and a lack of proactive planning precipitates crises. Under the leadership of a new CIO, IS began developing a Project Management Office, or PMO, to better meet medical center business objectives and to more effectively manage technology projects. Successes during the first year included comprehensive IT strategic planning. Collaborative relationships were established with departmental leaders for planning, prioritizing, budgeting, and executing projects. A formal Web-based process for requesting IS projects was implemented, project management training was provided, and elements of standard project management methodology were implemented. While a framework for effective project management was created, significant effort is still required to firmly root these new processes within the organizational culture. Project management office goals for the second year include implementing a project portfolio management tool, refining the benefits methodology, and continuing the advancement of the project management methodology.

  5. PROJECT MANAGEMENT OFFICE – LINK BETWEEN ORGANIZATIONAL STRATEGIC AND OPERATIONAL: A CASE STUDY

    Directory of Open Access Journals (Sweden)

    Mario Manzini Cianfanelli

    2014-12-01

    Full Text Available The objective of this work is to demonstrate the organizational integration achieved through the implementation of a project management office (PMO, created to combat the loss of water distribution in one of the business units of Basic Sanitation Company of the State of São Paulo – Sabesp. The methodology used to achieve this goal was the study of a single case in which the information was obtained through documentary research and semi-structured interviews. The results showed how this integration was achieved with the adoption of a standard methodology in project management, control based on information technology and the spread of the organization's strategy in the sectors below. This work concluded that with this implantation of the project management office it was possible to improve the planning and the control of the activities of the projects through a pattern methodology in managing projects that gave possibilities to create a new culture focusing in solving problems.

  6. MAJOR REPOSITORY DESIGN ISSUES

    International Nuclear Information System (INIS)

    JACK N. BAILEY, DWAYNE CHESTNUT, JAMES COMPTON AND RICHARD D. SNELL

    1997-01-01

    The Yucca Mountain Project is focused on producing a four-part viability assessment in late FY98. Its four components (design, performance assessment, cost estimate, and licensing development plan) must be consistent. As a tool to compare design and performance assessment options, a series of repository pictures were developed for the sequential time phases of a repository. The boundaries of the time phases correspond to evolution in the engineered barrier system (EBS)

  7. Restoration of areas disturbed by site studies for a mined commercial radioactive waste repository: The Basalt Waste Isolation Project [BWIP

    International Nuclear Information System (INIS)

    Brandt, C.A.; Rickard, W.H. Jr.; Biehert, R.W.; Newell, R.L.; Page, T.L.

    1989-01-01

    The Basalt Waste Isolation Project (BWIP) was undertaken to environmentally characterize a portion of the US Department of Energy's Hanford Site in Washington State as a potential host for the nation's first mined commercial nuclear waste repository. Studies were terminated by Congress in 1987. Between 1976 and 1987, 72 areas located across the Hanford Site were disturbed by the BWIP. These areas include borehole pads, a large Exploratory Shaft Facility, and the Near Surface Test Facility. Most boreholes were cleared of vegetation, leveled, and stabilized with a thick layer of compacted pit-run gravel and sand. The Near Surface Test Facility consists of three mined adits, a rock-spoils bench, and numerous support facilities. Restoration began in 1988 with the objective of returning sites to pre-existing conditions using native species. The Hanford Site retains some of the last remnants of the shrub-steppe ecosystem in Washington. The primary constraints to restoring native vegetation at Hanford are low precipitation and the presence of cheatgrass, an extremely capable alien competitor. 5 figs

  8. Progress in evaluation of radionuclide geochemical information developed by DOE high-level nuclear waste repository site projects

    International Nuclear Information System (INIS)

    Meyer, R.E.; Arnold, W.D.; O'Kelley, G.D.; Case, F.I.; Land, J.F.

    1989-08-01

    Information that is being developed by projects within the Department of Energy (DOE) pertinent to the potential geochemical behavior of radionuclides at candidate sites for a high-level radioactive waste repository is being evaluated by Oak Ridge National Laboratory (ORNL) for the Nuclear Regulatory Commission (NRC). During this report period, all experiments were conducted with tuff from the proposed high-level nuclear waste site at Yucca Mountain, Nevada. The principal emphasis in this report period was on column studies of migration of uranium and technetium in water from well J-13 at the Yucca Mountain site. Columns 1 cm in diameter and about 5 cm long were constructed and carefully packed with ground tuff. The characteristics of the columns were tested by determination of elution curves of tritium and TcO 4 - . Elution peaks obtained in past studies with uranium were asymmetrical and the shapes were often complex, observations that suggested irreversibilities in the sorption reaction. To try to understand these observations, the effects of flow rate and temperature on uranium migration were studied in detail. Sorption ratios calculated from the elution peaks became larger as the flow rate decreased and as the temperature increased. These observations support the conclusion that the sorption of uranium is kinetically hindered. To confirm this, batch sorption ratio experiments were completed for uranium as a function of time for a variety of conditions

  9. Statement of John H. Anttonen, Project Manager, Basalt Waste Isolation Project, Richland Operations Office, Department of Energy

    International Nuclear Information System (INIS)

    Anon.

    1987-01-01

    My name is John Anttonen and I am the Project Manager for the Basalt Waste Isolation Project (BWIP) at the Department of Energy Richland Operation Office. The responsibilities of may office are to manage the day-to-day activities of the site suitability investigations of the basalt formations at the Hanford Site, a Department complex that is involved in a variety of national missions, including defense materials production, nuclear energy research, and radioactive waste management. In may prepared comments today I would like to touch upon four specific subject areas relating to the BWIP program and then I would be happy to answer any questions you might have. The topics I will cover are: (1) historical aspects; (2) site specific technical issues and how they will be addressed during site characterization of the basalt site at Hanford; (3) current project status and; (4) institutional interaction. For clarity, I have attached several charts to my statement

  10. Salt Repository Project: Data report on corrosion results obtained from excess-salt corrosion test Matrix 1

    International Nuclear Information System (INIS)

    Haberman, J.H.; Westerman, R.E.

    1987-05-01

    The test discussed in this data report was directed at determining the response of the reference A216 grade WCA steel when it is exposed to anoxic excess-salt conditions at 150 0 C. The environment used in the test was intended to duplicate the intrusion brine scenario (i.e., the formation of brine by the intrusion of water from an outside source into the repository, with the formation of brine through dissolution of salt from the repository horizon). The salt-brine environment used in the test therefore reflected the expected gross salt composition of the repository horizon

  11. Vermont's involvement with the DOE's high-level radioactive waste disposal crystalline repository project. Final technical report, January 1-September 30, 1986

    International Nuclear Information System (INIS)

    1986-09-01

    The US Department of Energy (DOE) is charged with siting a second repository for the disposal of highly radioactive nuclear wastes. Because of this siting process, the DOE has looked to localities in 17 states in the eastern US for possible sites in crystalline rock. During the beginning of the progress report period, crystalline rocks in Vermont were under consideration as sites for further study. Vermont, through the Vermont State Geologist's Office, was closely involved with the DOE program during this period. Our main function has been to review DOE reports; attend DOE workshops and meetings; and inform the Vermont public, with the help of the DOE, about the high-level nuclear waste repository siting process. Nine sites in Vermont were under consideration during the Regional Characterization Phase until January 16, 1986. Because of this fact, there was considerable public interest in this program. Upon release of the Draft Area Recommendation Report, Vermont crystalline rock bodies were dropped from consideration. A site in New Hampshire and two sites in Maine remained on the list. Because of the draft status of the report and the possibility that a site 20 miles from the Vermont border in New Hampshire could remain as a selected site, Vermont has stayed active and interested. Two briefings and hearings were held in the State during the comment period January 16 through April 16, 1986. A thorough review of the Draft Area Recommendation Report was completed using reviewers from our Office, State agencies, outside experts, and citizen groups. With the announcement on May 28, 1986 of the suspension of the second repository siting process in crystalline rocks, our Office has worked toward closing out our active involvement

  12. Radioactive waste repository of high ecological safety

    International Nuclear Information System (INIS)

    Sobolev, I.; Barinov, A.; Prozorov, L.

    2000-01-01

    With the purpose to construct a radioactive waste repository of high ecological safety and reliable containment, MosNPO 'Radon' specialists have developed an advanced type repository - large diameter well (LBD) one. A project is started for the development of a technology for LDW repository construction and pilot operation of the new repository for 25-30 years. The 2 LDW repositories constructed at the 'Radon' site and the developed monitoring system are described

  13. Project Management Series Case Study: The Office of Registration and Records

    Science.gov (United States)

    Burgher, Karl E.; Snyder, Michael

    2012-01-01

    This is the third in a series of eight articles on project management (PM) in the academy. In this article, the authors describe the step-by-step implementation of a structural change to Indiana State University's (ISU's) Office of Registration and Records (ORR). The process described may vary as it is implemented elsewhere, but the authors…

  14. Experimental data obtained by the characterization and leaching of industrially lead contaminated soil projected to the stored in a repository.

    Data.gov (United States)

    U.S. Environmental Protection Agency — The data set contains the elemental composition, pH, and surface area, TOC, IC and bulk density of the soils to be deposited in a repository. Additionally, contains...

  15. Site specific statutory compliance planning for the salt repository project at the Deaf Smith County Site, Texas: Requirements, strategy, and status: Revision 4

    International Nuclear Information System (INIS)

    1986-06-01

    This document and the requirements and actions it presents are addressed to the Deaf Smith County Site, Texas. The proposed actions upon which the plan is based are those described in Chapters 4 and 5 of the final EA for the site. Similarly, the environmental and health and safety requirements covered in the plan are those identified in the EA as being potentially applicable to the salt repository project at the Deaf Smith site. 12 figs., 8 tabs

  16. Project Guarantee 1985. Final repository for low- and intermediate-level radioactive wastes: The system of safety barriers

    International Nuclear Information System (INIS)

    Anon.

    1985-01-01

    The safety barrier system for the type B repository for low- and intermediate-level waste is described. The barrier parameters which are relevant for safety analysis are quantified and associated error limits and data scatter are given. The aim of the report is to give a summary documentation of the safety analysis input data and their scientific background. For secure containment of radioactive waste safety barriers are used which effectively limit the release of radioactive material from the repository (release barriers) and effectively retard the entry of the original radioactive material into the biosphere (time barriers). In the case of low- and intermediate-level waste the technical safety barrier system comprises: waste solidification matrix (cement, bitumen and resin), immobilisation of the waste packages in containers using liquid cement, concrete repository containers, backfilling of remaining vacant storage space with special concrete, concrete lining of the repository caverns, sealing of access tunnels on final closure of the repository. Natural geological safety barriers - host rock and overlying formations - have the following important functions. Because of its stability, the host rock in the repository zone protects the technical safety barrier system from destruction caused by climatic effects and erosion for a sufficient length of time. It also provides for low water flow and favourable chemistry (reducing conditions)

  17. Safety upgrading of Novi Han Repository under IAEA TC Project BUL/4/005 achievements and future plans

    International Nuclear Information System (INIS)

    Stefanova, I.

    2003-01-01

    The report presents the safety upgrading of the Novi Han Repository under the IAEA TC Project BUL/4/005. The Project covers: identification of radionuclide inventory; characterisation of the disposal vaults; site characterisation; safety assessment; upgrading of the monitoring and radiation control; selection of treatment and conditioning processes and a conceptual design for a new waste processing and storage facility and other direct measures for safety improvement. The current inventory is identified and presented in the report. Schemes of the vault for solid wastes and vault for biological wastes are given, demonstrating reinforced concrete, stainless steel lining, and hydro insulation are presented. Several studies for safety assessment are made between 1997 and 2003. The operational safety assessment for disposal in existing facilities gives the annual risk for: spilling of waste package during upload (7.58.10 -9 ); spilling of waste package in transport accident (2.90.10 -9 ); fire scenario (3.50.10 - 1 3 ); radionuclide release due to flooding or earthquake (5.05.10 -4 ). The monitoring radiation control is upgraded according to the regulatory guidance and covered the site, restricted zone (1 km) and supervised zone (5 km). The types of analyses made are: Direct measurement of the dose rate -TLD; Direct measurements of the dose rate - portable surveillance monitors; In situ gamma spectrometry; Gamma spectrometry; Gross beta, gross alpha; Liquid scintillation spectrometry. The analyses show no transfer od radionuclides to the environment. The individual radiation control shows no evidence for specific radiation pathology. The operational radiation control service premises and transport vehicles. The following is measured: gamma dose rate; beta exposure; alpha exposure; neutron radiation; contamination level. Under the development is a detailed technical design supply of equipment for characterization of waste, including hot cell for control over high level

  18. The Role of the Project Management Office on Information Technology Project Success

    Science.gov (United States)

    Stewart, Jacob S.

    2010-01-01

    The rate of failed and challenged Information Technology (IT) projects is too high according to the CHAOS Studies by the Standish Group and the literature on project management (Standish Group, 2008). The CHAOS Studies define project success as meeting the triple constraints of scope, time, and cost. Assessing critical success factors is another…

  19. Towards Interoperable Preservation Repositories: TIPR

    Directory of Open Access Journals (Sweden)

    Priscilla Caplan

    2010-07-01

    Full Text Available Towards Interoperable Preservation Repositories (TIPR is a project funded by the Institute of Museum and Library Services to create and test a Repository eXchange Package (RXP. The package will make it possible to transfer complex digital objects between dissimilar preservation repositories.  For reasons of redundancy, succession planning and software migration, repositories must be able to exchange copies of archival information packages with each other. Every different repository application, however, describes and structures its archival packages differently. Therefore each system produces dissemination packages that are rarely understandable or usable as submission packages by other repositories. The RXP is an answer to that mismatch. Other solutions for transferring packages between repositories focus either on transfers between repositories of the same type, such as DSpace-to-DSpace transfers, or on processes that rely on central translation services.  Rather than build translators between many dissimilar repository types, the TIPR project has defined a standards-based package of metadata files that can act as an intermediary information package, the RXP, a lingua franca all repositories can read and write.

  20. The use of on-site Project Officers by a nuclear regulatory body

    International Nuclear Information System (INIS)

    Beare, J.W.

    1977-01-01

    In Canada consideration of applications for licensing nuclear installations is entrusted to the Reactor Safety Advisory Committee within the Atomic Energy Control Board (AECB). The licensing procedure is conducted in three stages (site approval, construction licence, operating licence). In order to control construction and operation of nuclear installations Project Officers are assigned to each particular installation. The policy of AECB is to send these officers on site several months before the reactor reaches criticality; and during reactor operation. This system clearly provides great practical advantages. (NEA) [fr

  1. Conflict free implementation of strategic project management office at the Entitie level utilizing “Evaporated cloud” diagram

    OpenAIRE

    Oganov, A.; Gogunsky, V.

    2015-01-01

    The analysis of reports on the last researches in area of project management office (PMO) in the organizations is carried out. Comparison of approaches in project management at the entities with PMO of different levels of a maturity and without it is executed. It is shown that the effectiveness of organizations orientation determined by the level of activity on project approaches, implemented with the help of Project Management Office through continuous improvement of design processes and ope...

  2. Repositories; Repositorios

    Energy Technology Data Exchange (ETDEWEB)

    Freire, Carolina Braccini; Tello, Cledola Cassia Oliveira de [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil)]. E-mails: cbf@cdtn.br; tellocc@cdtn.br

    2007-11-15

    The use of the nuclear energy is increasing in all areas. Then the radioactive waste management is in continuous development to comply the national and international established requirements. The final objective is to assure that it will not have any contamination of the public or the environmental, and that the exposition doses will be lower than the radiological protection limits. The multi barrier concept for the repository is internationally recognized. Among the repository types, the most used are: near surface, geological formations and of deposition in rock cavities. This article explains the concept and the types of repository and gives some examples of them. (author)

  3. Spent fuel and high level waste: Chemical durability and performance under simulated repository conditions. Results of a coordinated research project 1998-2004

    International Nuclear Information System (INIS)

    2007-10-01

    This publication contains the results of an IAEA Coordinated Research Project (CRP). It provides a basis for understanding the potential interactions of waste form and repository environment, which is necessary for the development of the design and safety case for deep disposal. Types of high level waste matrices investigated include spent fuel, glasses and ceramics. Of particular interest are the experimental results pertaining to ceramic forms such as SYNROC. This publication also outlines important areas for future work, namely, standardized, collaborative experimental protocols for package-release studies, structured development and calibration of predictive models linking the performance of packaged waste and the repository environment, and studies of the long term behaviour of the wastes, including active waste samples

  4. Progress in evaluation of radionuclide geochemical information developed by DOE high-level nuclear waste repository site projects. Annual report, October 1984-September 1985. Volume 4

    International Nuclear Information System (INIS)

    Meyer, R.E.; Arnold, W.D.; Blencoe, J.G.; Jacobs, G.K.; Kelmers, A.D.; Seeley, F.G.; Whatley, S.K.

    1986-05-01

    Information pertaining to the potential geochemical behavior of radionuclides at candidate sites for a high-level radioactive waste repository, which is being developed by projects within the Department of Energy (DOE), is being evaluated by Oak Ridge National Laboratory for the Nuclear Regulatory Commission (NRC). During this report period, emphasis was placed on the evaluation of information pertinent to the Hanford site in southeastern Washington. Results on the sorption/solubility behavior of technetium, neptunium, and uranium in the basalt/water geochemical system are summarized and compared to the results of DOE. Also, summaries of results are reported from two geochemical modeling studies: (1) an evaluation of the information developed by DOE on the native copper deposits of Michigan as a natural analog for the emplacement of copper canisters in a repository in basalt, and (2) calculation of the solubility and speciation of radionuclides for representative groundwaters from the Yucca Mountain site in Nevada

  5. Office of Civilian Radioactive Waste Management: Annual report to Congress

    International Nuclear Information System (INIS)

    1987-04-01

    This document summarizes the activities of the Office of Civilian Radioactive Waste Management for FY 1986. Topics include public interaction between the states and affected Indian Tribes, planning for a waste management system, site selection and site characterization of potential geologic repositories, participation in international repository projects, proposal development for a monitored retrievable storage system, demonstrations of spent fuel storage, and development of quality assurance and safety plans. 59 refs., 10 figs., 6 tabs

  6. Public health response to radiation emergencies and the role of the Helsinki Project Office

    International Nuclear Information System (INIS)

    Baverstock, Keith F.

    1997-01-01

    This paper focuses on the public health element of nuclear emergency preparedness, defined as the mitigation of the long-term effects of radiation on exposed populations, as opposed to dealing with the health consequences of an exposure in an individual (termed medical aspects). The paper also approaches to the role of the Helsinki Project Office which is concerned with the protection of public health through effective response to nuclear emergencies, and falling into two categories, namely contingency planning or preparedness, and response

  7. Research project for the determination of the suitability of the mine ''Konrad'' as a final repository for radioactive waste products

    International Nuclear Information System (INIS)

    1984-01-01

    A feasibility study of the Konrad mine for its use as a final repository for radioactive waste products was performed in 1978, 1979 and 1980. The report summarizes the most important results gained in the fields of geosciences and technical aspects of disposal operations

  8. DOE hearing on the Draft Area Recommendation Report for the Crystalline Repository Project, Sauk Center, Minnesota: Transcript of proceedings

    International Nuclear Information System (INIS)

    1986-01-01

    This document contains a transcript of the comments of 57 witnesses. Also included is a list of 101 exhibits. These meetings were held to hear public comments regarding the selection of a site for a second high-level nuclear waste repository

  9. Low-ph injection grout for deep repositories. Summary report from a co-operation project between NUMO (Japan), Posiva (Finland) and SKB (Sweden)

    Energy Technology Data Exchange (ETDEWEB)

    Boden, A. (ed.) [SwedPower Ab, Stockholm (Sweden); Sievaenen, U. (ed.) [JP-Suoraplan Oy, Vantaa (Finland)

    2006-02-15

    This report summarises results achieved in the joint SKB, Posiva and NUMO project 'Injection grout for deep repositories'. The work has been carried out in four subprojects with SKB and Posiva as responsible for two sub-projects each. This report summarises the original reporting. Posiva was responsible for the studies on low-pH cementitious grout, while SKB was responsible for the studies on non-cementitious grout. The work was done by literature surveys, laboratory analyses and field tests A result of the project is that there are both low-pH cementitious material for grouting larger fractures ((>-) 100 {mu}m) and non-cementitious material for grouting smaller fractures ((<-) 100 {mu}m) that will, after further optimisation work, be recommended for grouting of deep repositories. This project concentrated on the technical development of properties for the low pH grouts. Long-term safety and environmental aspects and durability of materials were preliminarily considered. Continued evaluations have to be carried out. (orig.)

  10. Low level waste repositories

    International Nuclear Information System (INIS)

    Hill, P.R.H.; Wilson, M.A.

    1983-11-01

    Factors in selecting a site for low-level radioactive waste disposal are discussed. South Australia has used a former tailings dam in a remote, arid location as a llw repository. There are also low-level waste disposal procedures at the Olympic Dam copper/uranium project

  11. PROCESS FOR LICENSE APPLICATION DEVELOPMENT FOR THE GEOLOGIC REPOSITORY

    International Nuclear Information System (INIS)

    DOUGLAS M. FRANKS AND NORMAN C. HENDERSON

    1997-01-01

    The Department of Energy (DOE), specifically the Office of Civilian Radioactive Waste Management (OCRWM) has been charged by the U.S. Congress, through the Nuclear Waste Policy Act (NWPA), with the responsibility for obtaining a license to develop a geologic repository. The NRC is the licensing authority for geologic disposal, and its regulations pertinent to construction authorization and license application are specified in 10 CFR Part 60, Disposal of High-Level Radioactive Wastes in Geologic Repositories, (section)60.21ff and (section)60.31ff. This paper discusses the process the Yucca Mountain Site Site Characterization Project (YMP) will use to identify and apply regulatory and industry guidance to development of the license application (LA) for a geologic repository at Yucca Mountain, Nevada. This guidance will be implemented by the ''Technical Guidance Document for Preparation of the License Application'' (TGD), currently in development

  12. Process for license application development for the geologic repository

    International Nuclear Information System (INIS)

    Franks, D.M.; Henderson, N.C.

    1998-01-01

    The Department of Energy (DOE), specifically the Office of Civilian Radioactive Waste Management (OCRWM) has been charged by the US Congress, through the Nuclear Waste Policy Act (NWPA), with the responsibility for obtaining a license to develop a geologic repository. The NRC is the licensing authority for geologic disposal, and its regulations pertinent to construction authorization and license application are specified in 10 CFR Part 60, Disposal of High-Level Radioactive Wastes in Geologic Repositories, section 60.21ff and section 60.31ff. This paper discusses the process the Yucca Mountain Site Characterization Project (YMP) will use to identify and apply regulatory and industry guidance to development of the license application (LA) for a geologic repository at Yucca Mountain, Nevada. This guidance will be implemented by the Technical Guidance Document for Preparation of the License Application (TGD), currently in development

  13. Influence analysis of Github repositories.

    Science.gov (United States)

    Hu, Yan; Zhang, Jun; Bai, Xiaomei; Yu, Shuo; Yang, Zhuo

    2016-01-01

    With the support of cloud computing techniques, social coding platforms have changed the style of software development. Github is now the most popular social coding platform and project hosting service. Software developers of various levels keep entering Github, and use Github to save their public and private software projects. The large amounts of software developers and software repositories on Github are posing new challenges to the world of software engineering. This paper tries to tackle one of the important problems: analyzing the importance and influence of Github repositories. We proposed a HITS based influence analysis on graphs that represent the star relationship between Github users and repositories. A weighted version of HITS is applied to the overall star graph, and generates a different set of top influential repositories other than the results from standard version of HITS algorithm. We also conduct the influential analysis on per-month star graph, and study the monthly influence ranking of top repositories.

  14. Cigeo. The French deep geological repository for radioactive waste. Excavation techniques and technologies tested in underground laboratory and forecasted for the future construction of the project

    International Nuclear Information System (INIS)

    Chauvet, Francois; Bosgiraud, Jean-Michel

    2015-01-01

    Cigeo is the French project for the repository of the high activity and intermediate long-lived radioactive waste. It will be situated at a depth of 500 m, In a clayish rock formation. An underground laboratory was built in the year 2000 and numerous tests are performed since 15 years, in order to know in detail the behavior of the rock and its ability to confine radioactive elements. In addition, this underground laboratory has brought and will continue to bring many lessons on the excavation methods to be chosen for the construction of Cigeo.

  15. Spent fuel and high level waste: Chemical durability and performance under simulated repository conditions. Results of a coordinated research project 1998-2004. Part 1: Contributions by participants in the co-ordinated research project on chemical durability and performance assessment under simulated repository conditions

    International Nuclear Information System (INIS)

    2007-07-01

    This publication contains the results of an IAEA Coordinated Research Project (CRP). It provides a basis for understanding the potential interactions of waste form and repository environment, which is necessary for the development of the design and safety case for deep disposal. Types of high level waste matrices investigated include spent fuel, glasses and ceramics. Of particular interest are the experimental results pertaining to ceramic forms such as SYNROC. This publication also outlines important areas for future work, namely, standardized, collaborative experimental protocols for package-release studies, structured development and calibration of predictive models linking the performance of packaged waste and the repository environment, and studies of the long term behaviour of the wastes, including active waste samples. It comprises 15 contributions of the participants on the Coordinated Research Project which are indexed individually.

  16. Repository design

    Energy Technology Data Exchange (ETDEWEB)

    John, C M

    1982-01-01

    Various technical issues of radioactive waste design are addressed in this paper. Two approaches to repository design considered herein are: (1) design to minimize the disturbance of the hot rock; and (2) designs that intentionally modify the hot rock to insure better containment of the wastes. The latter designs range from construction of a highly impermeable barrier around a spherical cavern to creating a matrix of tunnels and boreholes to form a cage within which the hydraulic pressure is nearly constant. Examples of these design alternatives are described in some detail. It is concluded that proposed designs for repositories illustrate that performance criteria considered acceptable for such facilities can be met by appropriate site selection and repository engineering. With these technically feasible design concepts, it is also felt that socioeconomic and institutional issues can be better resolved. (BLM)

  17. Characterization of Swelling Clays as Components of the Engineered Barrier System for Geological Repositories. Results of an IAEA Coordinated Research Project 2002-2007

    International Nuclear Information System (INIS)

    2013-11-01

    At the request of the Member States, the IAEA coordinates research into subjects of common interest in the context of the peaceful application of nuclear technology. The coordinated research projects (CRPs) are intended to promote knowledge and technology transfer between Member States and are largely focused on subjects of prime interest to the international nuclear community. This report presents the results of a CRP carried out between 2002 and 2007 on the subject of swelling clays proposed for use as a component in the engineered barrier system (EBS) of the multibarrier concept for disposal of radioactive waste. In 2002, under the auspices of the IAEA, a number of Member States came together to form a Network of Centres of Excellence on Training in and Demonstration of Waste Disposal Technologies in Underground Research Facilities (URF Network). This network identified the general subject of the application of high swelling clays to seal repositories for radioactive waste, with specific emphasis on the isolation of high level radioactive waste from the biosphere, as being suitable for a CRP. Existing concepts for geological repositories for high level radioactive waste and spent nuclear fuel require the use of EBSs to ensure effective isolation of the radioactive waste. There are two major materials proposed for use in the EBS, swelling clay based materials and cementitious/concrete materials. These materials will be placed between the perimeter of the excavation and the waste container to fill the existing gap and ensure isolation of the waste within the canister (also referred to as a container in some EBS concepts) by supporting safety through retardation and confinement. Cementitious materials are industrially manufactured to consistent standards and are readily available in most locations and therefore their evaluation is of less value to Member States than that of swelling clays. There exists a considerable range of programme development regarding

  18. Change of the layout of an office of a metallurgical company: simple projects, big solutions.

    Science.gov (United States)

    Duarte, Luiz Carlos da Silva; Eckhardt, Moacir; da Motta, Giordano Paulo

    2012-01-01

    The posture, a good organization and the proper layout of the environment and workplaces have a positive influence on the income of an employee. To develop the work it is used a methodology that addressed the study phases of the theory involving the subject, description of the current situation, preparation of conceptions, choice of design, implementation and reporting of results. Through the project of "Change of the layout of an office of a metallurgical company" there was an intervention in these reported aspects providing improvements in the office, regarding ergonomic, layout, workplace and lighting issues, bringing welfare to the official, with the intent to improve its performance within the company and facilitating its actions, as the company's customer service. The results provided improvements in layout, in the workplace and especially in comfort for the human resources that perform their activities.

  19. Historical Post Office Directory Parser (POD Parser Software From the AddressingHistory Project

    Directory of Open Access Journals (Sweden)

    Nicola Osborne

    2014-07-01

    Full Text Available The POD Parser is Python software for parsing the OCR’d (optical character recognised text of digitised historical Scottish Post Office Directories (PODs to produce a consistent structured format for the data and for geocoding each address. The software was developed as part of the AddressingHistory project which sought to combine digitised historic directories with digitised and georeferenced historic maps.  The software has potential for reuse in multiple research contexts where historical post office directory data is relevant, and is therefore particularly of use in historical research into social, economic or demographic trends. The POD Parser is currently designed for use with Scottish directories but is extensible, perhaps with some adaptation, to use with other similarly formatted materials such as the English Trade Directories.

  20. The healthy workplace project: Reduced viral exposure in an office setting.

    Science.gov (United States)

    Reynolds, Kelly A; Beamer, Paloma I; Plotkin, Kevin R; Sifuentes, Laura Y; Koenig, David W; Gerba, Charles P

    2016-05-03

    Viral illnesses such as gastroenteritis and the common cold create a substantial burden in the workplace due to reduced productivity, increased absenteeism, and increased health care costs. Behaviors in the workplace contribute to the spread of human viruses via direct contact between hands, contaminated surfaces, and the mouth, eyes, and/or nose. This study assessed whether implementation of the Healthy Workplace Project (HWP) (providing hand sanitizers, disinfecting wipes, facial tissues, and use instructions) would reduce viral loads in an office setting of approximately 80 employees after seeding fomites and the hands of volunteer participants with an MS-2 phage tracer. The HWP significantly reduced viable phage detected on participants' hands, communal fomites, and personal fomites (p ≤ .010) in office environments and presents a cost-effective method for reducing the health and economic burden associated with viral illnesses in the workplace.

  1. Sellafield repository design concept

    International Nuclear Information System (INIS)

    1998-01-01

    Between 1989 and 1997, UK Nirex Ltd carried out a programme of investigations to evaluate the potential of a site adjacent to the BNFL Sellafield works to host a deep repository for the United Kingdom's intermediate-level and certain low-level radioactive waste. The programme of investigations was wound down following the decision in March 1997 to uphold the rejection of the Company's planning application for the Rock Characterisation Facility (RCF), an underground laboratory which would have allowed further investigations to confirm whether or not the site would be suitable. Since that time, the Company's efforts in relation to the Sellafield site have been directed towards documenting and publishing the work carried out. The design concept for a repository at Sellafield was developed in parallel with the site investigations through an iterative process as knowledge of the site and understanding of the repository system performance increased. This report documents the Sellafield repository design concept as it had been developed, from initial design considerations in 1991 up to the point when the RCF planning application was rejected. It shows, from the context of a project at that particular site, how much information and experience has been gained that will be applicable to the development of a deep waste repository at other potential sites

  2. An evaluation of environmental effects of the DOE HLW repository siting and characterization program at Yucca Mountain, Nevada

    International Nuclear Information System (INIS)

    Winsor, M.F.; Ulland, L.M.

    1989-01-01

    This paper presents highlights of the Nevada Nuclear Waste Project Office (NWPO) environmental investigations in progress on the environmental effects of past and proposed activities of the Department of Energy (DOE) at the Yucca Mountain repository. The environmental investigations refer to those studies specifically related to resource evaluation, impact assessment and mitigation planning for the repository program; it is defined to exclude consideration of technical suitability determinations, socioeconomics and transportation. This paper addresses the question of what are the disturbances created by past and proposed DOE activities related to repository siting and characterization at Yucca Mountain. It discusses considerations in linking disturbance to the potential for significant adverse environmental impacts

  3. Energy edge post-occupancy evaluation project: the Hollywood Office Building, Portland, Oregon

    Energy Technology Data Exchange (ETDEWEB)

    1990-06-01

    The Hollywood Office Park Building Survey for the Energy Post- Occupancy Project was administered to nine building occupants. The nine respondents answered the questions which rated building features in the areas of (1) thermal factors; (2) air quality; (3) lighting; (4) acoustics; and, (5) overall workspace satisfaction. In addition to rating these ambient environmental features, these respondents also rated their satisfaction of various functional and aesthetic features and specific kinds of workspaces. Data was also collected on heath characteristics and occupational demographics of the respondents. No analysis is made of the survey findings which are reported in graphic format. 15 figs. (BN)

  4. Repository exploration

    International Nuclear Information System (INIS)

    Pentz, D.L.

    1984-01-01

    This paper discusses exploration objectives and requirements for a nuclear repository in the U.S.A. The importance of designing the exploration program to meet the system performance objectives is emphasized and some examples of the extent of exploration required before the License Application for Construction Authorization is granted are also discussed

  5. Implementing Earned Value Management in the CxP EVA Systems Project Office

    Science.gov (United States)

    Sorge, Les L.

    2009-01-01

    Earned Value Management (EVM), like project management, is as much art as it is science to develop an implementation plan for a project. This presentation will cover issues that were overcome and the implementation strategy to deploy Earned Value Management (EVM) within the Constellation Program (CxP), EVA Systems Project Office (ESPO), as well as discuss additional hurdles that currently prevent the organization from optimizing EVM. Each organization and each project within an organization needs to mold an EVM implementation plan around existing processes and tools, while at the same time revising those existing processes and tools as necessary to make them compatible with EVM. The ESPO EVM implementation covers work breakdown structure, organizational breakdown structure, control account, work/planning package development; integrated master schedule development using an integrated master plan; incorporating reporting requirements for existing funding process such as Planning, Programming, Budgeting, and Execution (PPBE) and JSC Internal Task Agreements (ITA); and interfacing with other software tools such as the Systems Applications and Products (SAP) accounting system and the CxP wInsight EVM analysis tool. However, there are always areas for improvement and EVM is no exception. As EVM continues to mature within the NASA CxP, these areas will continue to be worked to resolution to provide the Program Managers, Project Managers, and Control Account Managers the best EVM data possible to make informed decisions.

  6. A Health Care Project Management Office's Strategies for Continual Change and Continuous Improvement.

    Science.gov (United States)

    Lavoie-Tremblay, Mélanie; Aubry, Monique; Richer, Marie-Claire; Cyr, Guylaine

    Health care organizations need project and change management support in order to achieve successful transformations. A project management office (PMO) helps support the organizations through their transformations along with increasing their capabilities in project and change management. The aim of the present study was to extend understanding of the continuous improvement mechanisms used by PMOs and to describe PMO's strategies for continual change and continuous improvement in the context of major transformation in health care. This study is a descriptive case study design with interviews conducted from October to December 2015 with PMO's members (3 managers and 1 director) and 3 clients working with the PMO after a major redevelopment project ended (transition to the new facility). Participants suggested a number of elements including carefully selecting the members of the PMO, having a clear mandate for the PMO, having a method and a discipline at the same time as allowing openness and flexibility, clearly prioritizing projects, optimizing collaboration, planning for everything the PMO will need, not overlooking organizational culture, and retaining the existing support model. This study presents a number of factors ensuring the sustainability of changes.

  7. SKB WP-cave project. Radionuclide release from the near-field in a WP-cave repository

    International Nuclear Information System (INIS)

    Lindgren, M.; Skagius, K.

    1989-04-01

    The release of radionuclides from the bentonite-sand barrier (near-field) in a WP-cave repository for high level radioactive waste has been studied. Calculations were made for two cases; a Low Flow Through Case and a High Flow Through Case. The difference between the two cases lies in the assumed hydraulic properties of the bentonite-sand barrier and the system inside the barrier. The effect on the nuclide release of solubility limitations, sorption capacity of the barriers, radiolytic fuel oxidation rate as well as the thickness of the bentonite-sand barrier, were also investigated for the Low Flow Through Case. (authors)

  8. Long term behaviour of low and intermediate level waste packages under repository conditions. Results of a co-ordinated research project 1997-2002

    International Nuclear Information System (INIS)

    2004-06-01

    The development and application of approaches and technologies that provide long term safety is an essential issue in the disposal of radioactive waste. For low and intermediate level radioactive waste, engineered barriers play an important role in the overall safety and performance of near surface repositories. Thus, developing a strong technical basis for understanding the behaviour and performance of engineered barriers is an important consideration in the development and establishment of near surface repositories for radioactive waste. In 1993, a Co-ordinated Research Project (CRP) on Performance of Engineered Barrier Materials in Near Surface Disposal Facilities for Radioactive Waste was initiated by the IAEA with the twin goals of addressing some of the gaps in the database on radionuclide isolation and long term performance of a wide variety of materials and components that constitute the engineered barriers system (IAEA-TECDOC-1255 (2001)). However, during the course of the CRP, it was realized that that the scope of the CRP did not include studies of the behaviour of waste packages over time. Given that a waste package represents an important component of the overall near surface disposal system and the fact that many Member States have active R and D programmes related to waste package testing and evaluation, a new CRP was launched, in 1997, on Long Term Behaviour of Low and Intermediate Level Waste Packages Under Repository Conditions. The CRP was intended to promote research activities on the subject area in Member States, share information on the topic among the participating countries, and contribute to advancing technologies for near surface disposal of radioactive waste. Thus, this CRP complements the afore mentioned CRP on studies of engineered barriers. With the active participation and valuable contributions from twenty scientists and engineers from Argentina, Canada, Czech Republic, Egypt, Finland, India, Republic of Korea, Norway, Romania

  9. THE CONTEXT OF ESTABLISHING PROJECT MANAGEMENT OFFICES IN THE IT AREA: TWO CASE STUDIES

    Directory of Open Access Journals (Sweden)

    Andrea Giovanni Spelta

    2010-01-01

    Full Text Available Completing strategic Information Technology (IT projects as planned is certainly an important objective for large firms. One of the measures adopted to reach this goal systematically is to create a Project Management Office in the IT area (PMO-IT. However, many firms consider the possibility of creating a PMO-IT, but decide not to do it. This paper presents the results of an exploratory research about the contextual drivers that determine the decision to create PMO-Its. Through two case studies of large Brazilian firms – one that created the entity and another which believes does not need it –, the drivers of the decision to create or not to create a PMO-IT were identified, and it was possible to confirm some of the drivers mentioned in the literature. This paper increases the undertstanding about this topic, which is important in the Management Information Systems field, as well as indicates paths for future research.

  10. Technology overview of mined repositories

    International Nuclear Information System (INIS)

    Gimera, R.; Thirumalai, K.

    1982-01-01

    Mined repositories present an environmentally viable option for permanent disposal of nuclear waste. This paper reviews the state-of-the-art mining technologies and identifies technological issues and developments necessary to mine a repository in basalt. The thermal loading, isolation, and retrieval requirements of a repository present unique technological challenges unknown to conventional mining practice. The technology issues and developments required in the areas of excavation, roof and ground support, equipment development, instrumentation development, and sealing are presented. Performance assessment methods must be developed to evaluate the adequacies of technologies developed to design, construct, operate, and decommission a repository. A stepwise test-and-development approach is used in the Basalt Waste Isolation Project to develop cost-effective technologies for a repository

  11. Teaching weather and climate science in primary schools - a pilot project from the UK Met Office

    Science.gov (United States)

    Orrell, Richard; Liggins, Felicity; Challenger, Lesley; Lethem, Dom; Campbell, Katy

    2017-04-01

    Wow Schools is a pilot project from the Met Office with an aim to inspire and educate the next generation of scientists and, uniquely, use the data collected by schools to improve weather forecasts and warnings across the UK. Wow Schools was launched in late 2015 with a competition open to primary schools across the UK. 74 schools entered the draw, all hoping to be picked as one of the ten lucky schools taking part in the pilot scheme. Each winning school received a fully automatic weather station (AWS), enabling them to transmit real-time local weather observations to the Met Office's Weather Observation Website (WOW - wow.metoffice.gov.uk), an award winning web portal for uploading and sharing a range of environmental observations. They were also given a package of materials designed to get students out of the classroom to observe the weather, get hands-on with the science underpinning weather forecasting, and analyse the data they are collecting. The curriculum-relevant materials were designed with the age group 7 to 11 in mind, but could be extended to support other age groups. Each school was offered a visit by a Wow Schools Ambassador (a Met Office employee) to bring the students' learning to life, and access to a dedicated forecast for its location generated by our new supercomputer. These forecasts are improved by the school's onsite AWS reinforcing the link between observations and forecast production. The Wow Schools pilot ran throughout 2016. Here, we present the initial findings of the project, examining the potential benefits and challenges of working with schools across the UK to: enrich students' understanding of the science of weather forecasting; to source an ongoing supply of weather observations and discover how these might be used in the forecasting process; and explore what materials and business model(s) would be most useful and affordable if a wider roll-out of the initiative was undertaken.

  12. Monte Carlo simulations for generic granite repository studies

    Energy Technology Data Exchange (ETDEWEB)

    Chu, Shaoping [Los Alamos National Laboratory; Lee, Joon H [SNL; Wang, Yifeng [SNL

    2010-12-08

    In a collaborative study between Los Alamos National Laboratory (LANL) and Sandia National Laboratories (SNL) for the DOE-NE Office of Fuel Cycle Technologies Used Fuel Disposition (UFD) Campaign project, we have conducted preliminary system-level analyses to support the development of a long-term strategy for geologic disposal of high-level radioactive waste. A general modeling framework consisting of a near- and a far-field submodel for a granite GDSE was developed. A representative far-field transport model for a generic granite repository was merged with an integrated systems (GoldSim) near-field model. Integrated Monte Carlo model runs with the combined near- and farfield transport models were performed, and the parameter sensitivities were evaluated for the combined system. In addition, a sub-set of radionuclides that are potentially important to repository performance were identified and evaluated for a series of model runs. The analyses were conducted with different waste inventory scenarios. Analyses were also conducted for different repository radionuelide release scenarios. While the results to date are for a generic granite repository, the work establishes the method to be used in the future to provide guidance on the development of strategy for long-term disposal of high-level radioactive waste in a granite repository.

  13. Long-term safety for KBS-3 repositories at Forsmark and Laxemar - a first evaluation. Main Report of the SR-Can project

    International Nuclear Information System (INIS)

    Hedin, Allan

    2006-10-01

    This document is the main report from the safety assessment project SR-Can. The SR-Can project is a preparatory stage for the SR-Site assessment, the report that will be used in support of SKB's application for a final repository. The purposes of the safety assessment SR-Can are the following: 1. To make a first assessment of the safety of potential KBS-3 repositories at Forsmark and Laxemar to dispose of canisters as specified in the application for the encapsulation plant. 2. To provide feedback to design development, to SKB's RandD programme, to further site investigations and to future safety assessment projects. 3. To foster a dialogue with the authorities that oversee SKB's activities, i.e. the Swedish Nuclear Power Inspectorate, SKI, and the Swedish Radiation Protection Authority, SSI, regarding interpretation of applicable regulations, as a preparation for the SR-Site project. The assessment relates to the KBS-3 disposal concept in which copper canisters with a cast iron insert containing spent nuclear fuel are surrounded by bentonite clay and deposited at approximately 500 m depth in saturated, granitic rock. Preliminary data from the Forsmark and Laxemar sites, presently being investigated by SKB as candidates for a KBS-3 repository are used in the assessment. An important aim of this report is to demonstrate the proper handling of requirements placed on the safety assessment in applicable regulations. Therefore, regulations issued by the Swedish Nuclear Power Inspectorate and the Swedish Radiation Protection Institute are reproduced in an Appendix where references are given to sections in the main text where the handling of the different requirements is discussed. The principal acceptance criterion requires that 'the annual risk of harmful effects after closure does not exceed 10 -6 for a representative individual in the group exposed to the greatest risk'. 'Harmful effects' refer to cancer and hereditary effects. The risk limit corresponds to an

  14. Long-term safety for KBS-3 repositories at Forsmark and Laxemar - a first evaluation. Main Report of the SR-Can project

    Energy Technology Data Exchange (ETDEWEB)

    Hedin, Allan (ed.)

    2006-10-15

    This document is the main report from the safety assessment project SR-Can. The SR-Can project is a preparatory stage for the SR-Site assessment, the report that will be used in support of SKB's application for a final repository. The purposes of the safety assessment SR-Can are the following: 1. To make a first assessment of the safety of potential KBS-3 repositories at Forsmark and Laxemar to dispose of canisters as specified in the application for the encapsulation plant. 2. To provide feedback to design development, to SKB's RandD programme, to further site investigations and to future safety assessment projects. 3. To foster a dialogue with the authorities that oversee SKB's activities, i.e. the Swedish Nuclear Power Inspectorate, SKI, and the Swedish Radiation Protection Authority, SSI, regarding interpretation of applicable regulations, as a preparation for the SR-Site project. The assessment relates to the KBS-3 disposal concept in which copper canisters with a cast iron insert containing spent nuclear fuel are surrounded by bentonite clay and deposited at approximately 500 m depth in saturated, granitic rock. Preliminary data from the Forsmark and Laxemar sites, presently being investigated by SKB as candidates for a KBS-3 repository are used in the assessment. An important aim of this report is to demonstrate the proper handling of requirements placed on the safety assessment in applicable regulations. Therefore, regulations issued by the Swedish Nuclear Power Inspectorate and the Swedish Radiation Protection Institute are reproduced in an Appendix where references are given to sections in the main text where the handling of the different requirements is discussed. The principal acceptance criterion requires that 'the annual risk of harmful effects after closure does not exceed 10{sup -6} for a representative individual in the group exposed to the greatest risk'. 'Harmful effects' refer to cancer and hereditary effects

  15. The Use of Numerical Models in Support of Site Characterization and Performance Assessment Studies of Geological Repositories. Results of an IAEA Coordinated Research Project 2005-2010

    International Nuclear Information System (INIS)

    2013-10-01

    The siting, development and operation of waste disposal facilities, and the related safety issues, have been described in many IAEA publications. The safe management and disposal of radioactive waste from the nuclear fuel cycle remains a necessary condition for future development of nuclear energy. In particular, the disposal of high level waste and spent nuclear fuel in geological repositories, despite having been studied worldwide over the past several decades, still requires full scale demonstration through safe implementation, as planned at the national level in Finland and Sweden by 2020 and 2023, respectively, and in France by 2025. Safety assessment techniques are currently applicable to potential facility location and development through a quite large range of approaches and methodologies. By implementing research activities through coordinated research projects (CRPs), the IAEA enables research institutes in both developing and developed Member States to collaborate on research topics of common interest. In response to requests by several Member States in different networks and platforms dealing with waste disposal, in 2005 a CRP on The Use of Numerical Models in Support of Site Characterization and Performance Assessment Studies of Geological Repositories was proposed and developed to transfer modelling expertise and numerical simulation technology to countries needing them for their national nuclear waste management programmes. All Member States involved in this CRP have acquired the scientific basis for, and expertise in, the site characterization process, including test design, data analysis, model calibration, model validation, predictive modelling, sensitivity analysis and uncertainty propagation analysis. This expertise is documented in this publication, in which numerical modelling is used to address the pertinent issue of site characterization and its impact on safety, using data and information from a potential repository site

  16. Office of Legacy Management Decision Tree for Solar Photovoltaic Projects - 13317

    International Nuclear Information System (INIS)

    Elmer, John; Butherus, Michael; Barr, Deborah L.

    2013-01-01

    To support consideration of renewable energy power development as a land reuse option, the DOE Office of Legacy Management (LM) and the National Renewable Energy Laboratory (NREL) established a partnership to conduct an assessment of wind and solar renewable energy resources on LM lands. From a solar capacity perspective, the larger sites in the western United States present opportunities for constructing solar photovoltaic (PV) projects. A detailed analysis and preliminary plan was developed for three large sites in New Mexico, assessing the costs, the conceptual layout of a PV system, and the electric utility interconnection process. As a result of the study, a 1,214-hectare (3,000-acre) site near Grants, New Mexico, was chosen for further study. The state incentives, utility connection process, and transmission line capacity were key factors in assessing the feasibility of the project. LM's Durango, Colorado, Disposal Site was also chosen for consideration because the uranium mill tailings disposal cell is on a hillside facing south, transmission lines cross the property, and the community was very supportive of the project. LM worked with the regulators to demonstrate that the disposal cell's long-term performance would not be impacted by the installation of a PV solar system. A number of LM-unique issues were resolved in making the site available for a private party to lease a portion of the site for a solar PV project. A lease was awarded in September 2012. Using a solar decision tree that was developed and launched by the EPA and NREL, LM has modified and expanded the decision tree structure to address the unique aspects and challenges faced by LM on its multiple sites. The LM solar decision tree covers factors such as land ownership, usable acreage, financial viability of the project, stakeholder involvement, and transmission line capacity. As additional sites are transferred to LM in the future, the decision tree will assist in determining whether a solar

  17. Experimental studies on the migration of radionuclides of the elements I, Sr, Cs, Co and Pd in the roof rock of the projected waste repository at Gorleben

    International Nuclear Information System (INIS)

    Klotz, D.; Lang, H.; Moser, H.

    1985-07-01

    The studies were intended to provide information on the sorptive properties of 15 samples of fine-grain and medium-grain sands with regard to the radionuclides of I, Sr, Cs, Co, and Pd, and on their hydraulic properties. The samples were taken from the geologic formations in the area surrounding the projected waste repository in the Gorleben salt mine, at depth of up to 250 m down from terrain surface, and were analysed by means of column and batch experiments. Further goals were to determine the radionuclide migration as a function of flow velocity of the groundwater, and of sand compactness, as well as the effects of carrier ions and main groundwater contituents. The margins of retardation factors for the various radionuclides are given. One important result of the studies is that it could be expeimentally verified that there is the process of quasi irreversible sorption, i.e. it could be shown that desorption of radionuclides from natural, unconsolidated rock proceeds very much slowlier than sorption, so that this finding is of great significance to the safety assessment of a radioactive waste repository in geologic formations. (orig./HP) [de

  18. The Curriculum Improvement Project in Business Careers Programs: Business Manager, Officer Administrator, Real Estate Agent, Real Estate Broker.

    Science.gov (United States)

    College of the Mainland, Texas City, TX.

    In 1987, the College of the Mainland undertook a project to update curricula in real estate, business management, and office technology. The project entailed a survey of the labor market to clarify personnel needs in selected fields; the use of the DACUM (Developing a Curriculum) process, which involved expert workers in the creation of task…

  19. Research and Grant Management: The Role of the Project Management Office (PMO) in a European Research Consortium Context

    Science.gov (United States)

    Wedekind, Gerben Kristian; Philbin, Simon Patrick

    2018-01-01

    This paper illustrates how a university-based project management office (PMO) can provide focused support across the entire grant project lifecycle within a European research context. In recent years, EU (European Union) research and innovation grant programs have increasingly shifted to support multidisciplinary consortia composed of industry,…

  20. Preclosure radiological safety analysis for accident conditions of the potential Yucca Mountain Repository: Underground facilities; Yucca Mountain Site Characterization Project

    Energy Technology Data Exchange (ETDEWEB)

    Ma, C.W.; Sit, R.C.; Zavoshy, S.J.; Jardine, L.J. [Bechtel National, Inc., San Francisco, CA (United States); Laub, T.W. [Sandia National Labs., Albuquerque, NM (United States)

    1992-06-01

    This preliminary preclosure radiological safety analysis assesses the scenarios, probabilities, and potential radiological consequences associated with postulated accidents in the underground facility of the potential Yucca Mountain repository. The analysis follows a probabilistic-risk-assessment approach. Twenty-one event trees resulting in 129 accident scenarios are developed. Most of the scenarios have estimated annual probabilities ranging from 10{sup {minus}11}/yr to 10{sup {minus}5}/yr. The study identifies 33 scenarios that could result in offsite doses over 50 mrem and that have annual probabilities greater than 10{sup {minus}9}/yr. The largest offsite dose is calculated to be 220 mrem, which is less than the 500 mrem value used to define items important to safety in 10 CFR 60. The study does not address an estimate of uncertainties, therefore conclusions or decisions made as a result of this report should be made with caution.

  1. Sites and projects for the disposal of radioactive waste and repositories in Russia and other states of the former USSR

    International Nuclear Information System (INIS)

    Schneider, L.; Herzog, C.

    2000-01-01

    The nuclear industry in Russia and other states of the former USSR contents the whole nuclear fuel cycle - Uranium mining, fuel element production, nuclear power and research reactors, nuclear powered ships and reprocessing of nuclear fuel. High amounts of radioactive waste are already disposed at the sites of these industrial centers and further radioactive waste is arising in production, reprocessing and decommissioning processes. Spent fuel elements are reprocessed or stored onsite. Solid and liquid wastes are disposed near surface at the sites of nuclear power plants, radiochemical plants, 'Radon'- and other sites. High volumes of high-, medium- and low-level liquid waste with high radioactivity has been injected into deep geologic formations at the sites of radiochemical plants. In Russia perspective all spent fuel elements shall be reprocessed and dry storage facilities are planned for long term storage until reprocessing. Repositories for solid waste are foreseen in deep geological formations (e.g. salt, granite) at several sites. (author)

  2. RE/SPEC Inc. technical support to the Repository Technology Program

    International Nuclear Information System (INIS)

    Wagner, R.A.

    1992-06-01

    This report presents a summary of all RE/SPEC Inc. technical support activities to the Repository Technology Program (RTP) from September 1, 1988, through June 30, 1992. The RE/SPEC Inc. activities are grouped into the following categories: project management, project quality assurance (QA), performance assessment (PA), support of the Office of Civilian Radioactive Waste Management (OCRWM) through technical reviews and general assistance, participation in the Department of Energy (DOE) International Program, and code evaluation and documentation

  3. Business models for digital repositories

    CERN Document Server

    CERN. Geneva; Bjørnshauge, Lars

    2007-01-01

    Those setting up, or planning to set up, a digital repository may be interested to know more about what has gone before them. What is involved, what is the cost, how many people are needed, how have others made the case to their institution, and how do you get anything into it once it is built? I have recently undertaken a study of European repository business models for the DRIVER project and will present an overview of the findings.

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

    DEFF Research Database (Denmark)

    Landgren, Mathilde; Jensen, Lotte Bjerregaard

    2017-01-01

    process and informing the industry of them. This has led to optimised design processes such as Integrated Energy Design, in which many decisions related to energy consumption and indoor climate are made in the early design stages. The current tendency is to use an expanded notion of sustainability......, derived from the sustainability certification system itself, and to apply it even in the early design process. This perspective emphasises all phases of the life cycle of a building. The goal of the present study was to map how a Danish architectural office approached sustainability in the projects......The context of the study is the very strict regulation of energy consumption for operating buildings in Denmark. It is difficult to meet the requirements by system optimisation in the final design phase, so recent research has focused on ways of meeting the target by adapting the whole design...

  5. Reducing RN Vacancy Rate: A Nursing Recruitment Office Process Improvement Project.

    Science.gov (United States)

    Hisgen, Stephanie A; Page, Nancy E; Thornlow, Deirdre K; Merwin, Elizabeth I

    2018-06-01

    The aim of this study was to reduce the RN vacancy rate at an academic medical center by improving the hiring process in the Nursing Recruitment Office. Inability to fill RN positions can lead to higher vacancy rates and negatively impact staff and patient satisfaction, quality outcomes, and the organization's bottom line. The Model for Improvement was used to design and implement a process improvement project to improve the hiring process from time of interview through the position being filled. Number of days to interview and check references decreased significantly, but no change in overall time to hire and time to fill positions was noted. RN vacancy rate also decreased significantly. Nurse manager satisfaction with the hiring process increased significantly. Redesigning the recruitment process supported operational efficiencies of the organization related to RN recruitment.

  6. Challenges in planning and performing the retrieval of the prototype repository at Aespoe HRL- Project management's reflections and practical experiences from field work

    International Nuclear Information System (INIS)

    Grahm, Paer; Hagman, Patrik; Johannesson, Lars-Erik

    2012-01-01

    Document available in extended abstract form only. Since 2001 the Prototype Repository at Aespoe Hard Rock Laboratory has been carried out as a large-scale experimental installation of the KBS-3 Swedish/Finnish concept for final disposal of spent nuclear fuel. The overall objective of the trial 'Prototype Repository' is to test and demonstrate the integrated function of sub-components in a final repository under realistic full-scale conditions. Data from the experiment shall also be compared to results from modelling based on site conditions. Opening of the outer section for the Prototype Repository was recognized as substantial operation. No trial of this size has been made earlier with regard to removal of buffer and backfilling. Experience was available only from retrieval of the buffer in Canister Retrieval Test at Aespoe HRL where samples of the buffer were taken, down to the mid-height of the canister. It was expected that sampling of the buffer in the deposition holes of the Prototype Repository would be very difficult, especially deep down in the holes. No significant experience regarding the breaching of such a concrete plug or removing backfill was available. The lack of experience together with the size of the project made extensive planning essential before the opening and removal could begin. It was decided that SKB (Sweden) and Posiva Oy (Finland) should run the project in a co-operation, where SKB is responsible for managing the project. In addition, a wide international interest was observed and accordingly waste management organisations were invited by SKB and Posiva to be a party to the Retrieval of the Prototype Repository. Six individual project agreements were signed with Andra (France), NUMO (Japan), NDA (United Kingdom), NAGRA (Switzerland), BMWi (Germany) and NWMO (Canada). The planning of the Retrieval of the Prototype Repository (section II) started at the beginning of 2010. The planning phase was successful meaning that the breaching of

  7. Nye County, Nevada 1992 nuclear waste repository program: Program overview. Final report

    International Nuclear Information System (INIS)

    1998-01-01

    The purpose of this document is to provide an overview of the Nye County FY92 Nuclear Waste Repository Program (Program). Funds to pay for Program costs will come from the Federal Nuclear Waste Fund, which was established under the Nuclear Waste Policy Act of 1982 (NWPA). In early 1983, the Yucca Mountain was identified as a potentially suitable site for the nation's first geologic repository for spent reactor fuel and high-level radioactive waste. Later that year, the Nye County Board of County Commissioners (Board) established the capability to monitor the Federal effort to implement the NWPA and evaluate the potential impacts of repository-related activities on Nye County. Over the last eight years, the County's program has grown in complexity and cost in order to address DOE's evolving site characterization studies, and prepare for the potential for facility construction and operation. Changes were necessary as well, in response to Congress's redirection of the repository program specified in the amendments, to the NWPA approved in 1987. In early FY 1991, the County formally established a project office to plan and implement its program of work. The Repository Project Office's (RPO) mission and functions are provided in Section 2.0. The RPO organization structure is described in Section 3.0

  8. Nuclear waste. DOE has terminated research evaluating crystalline rock for a repository

    International Nuclear Information System (INIS)

    Fultz, Keith O.; Sprague, John W.; Weigel, Dwayne E.; Price, Vincent P.

    1989-05-01

    We found that DOE terminated funding of research projects specifically designed to evaluate the suitability of crystalline rock for a repository. DOE continued other research efforts involving crystalline rock because they will provide information that it considers useful for evaluating the suitability of Yucca Mountain, Nevada, for a potential repository. Such research activities are not prohibited by the amendments. In January 1988, DOE began evaluating both its domestic and international research programs to ensure their compliance with the 1987 amendments. Several DOE offices and contractors were involved in the evaluation. DOE officials believe that the evaluation effectively brought the Office of Civilian Radioactive Waste Management activities into compliance with the amendments while maintaining useful international relations of continuing benefit to the nuclear waste program in general and to DOE's investigation of the Yucca Mountain site in particular. (The 1987 amendments designated Yucca Mountain as the only site that DOE is to investigate for a potential repository.) The approach and results of DOE's evaluation are discussed. Our review of DOE documents indicates that, by June 22, 1988, DOE completed its evaluation of ongoing crystalline rock research projects to ensure compliance with the 1987 amendments, terminated those research activities it identified as being specifically designed to evaluate the suitability of crystalline rock for a repository, continued some research activities involving crystalline rock because these activities would benefit the investigation and development of the Yucca Mountain repository site, and redirected some research activities so that they would contribute to investigating and developing the Yucca Mountain site

  9. Mont Terri Project - Ventilation experiment in Opalinus Clay for the disposal of radioactive waste in underground repositories

    Energy Technology Data Exchange (ETDEWEB)

    Mayor, J. C. [Empresa Nacional de Residuos Radioactivos SA (ENRESA), Madrid (Spain); Garcia-Sineriz, J. [Asociacion para la Investigacion y Desarollo Industrial de los Recursos Naturales (AITEMIN), Madrid (Spain); Velasco, M. [DM Iberia SA, Madrid (Spain); Gomez-Hernandez, J. [Ingenieria Hidraulica y Medio Ambiente, Escuela de Ingenieros de Caminos (UPV), Valencia (Spain); Lloret, A.; Matray, J.-M. [IRSN/DEI/SARG/LETS, Fontenay-aux-Roses (France); Coste, F. [Aradis ESG, Sevres Cedex (France); Giraud, A. [LAEGO-ENSG, Vandoeuvre les Nancy (France); Rothfuchs, T. [Gesellschaft fuer Anlagen und Reaktorsicherheit mbH (GRS), Braunschweig (Germany); Marschall, P. [National Cooperative for the Disposal of Radioactive Waste (Nagra), Wettingen (Switzerland); Roesli, U. [Solexperts AG, Moenchaltorf (Switzerland); Mayer, G. [Colenco Power Engineering Ltd, Baden (Switzerland)

    2007-07-01

    The ventilation of the underground drifts during the construction and operation of a radioactive waste repository could produce the partial desaturation of the rock around the drifts, modifying its thermo-hydro-mechanical properties, especially in clayey rocks. This change of rock properties may have an impact on the design of the repositories (drifts spacing and repository size), which depends on the thermal load that the clay barrier and the rock can accept. To evaluate 'in situ' and better understand the desaturation process of a hard clay formation, the Ventilation Experiment (VE) has been carried out at the Mont Terri underground laboratory (Switzerland), generating a flow of dry air during several months along a section of a microtunnel. Specifically, the VE test has been performed, under practically isothermal conditions (T {approx_equal} 15-16 {sup o}C), in a 10 m long section of a non-lined horizontal microtunnel (diameter = 1.3 m), excavated in 1999 in the shaly facies of the Opalinus Clay of Mont Terri. The microtunnel is oriented perpendicular to the bedding strike direction of the rock (mean value of the bedding dip {approx_equal} 25{sup o}). The VE experiment real data and its modelling have shown that the desaturation of clayey rocks of low hydraulic conductivity (K < 10{sup -12} m/s) due to ventilation is very small. Under real repository conditions, the thermal and hydro-mechanical rock characteristics will not be practically affected by the ventilation. Specifically, the monitoring of the VE test (mainly the hygrometer data, confirmed also by the geoelectrical measurements) indicates that, after about 5 months of ventilation with almost dry air, the rock relative humidity (and then the degree of saturation) was less than 95% only in a ring of thickness less than 40 cm. Nevertheless, a suction state (subatmospheric liquid pressures) developed up to a distance of about 2 m, but it should be kept in mind that a clayey rock such as the

  10. Mont Terri Project - Ventilation experiment in Opalinus Clay for the disposal of radioactive waste in underground repositories

    International Nuclear Information System (INIS)

    Mayor, J. C.; Garcia-Sineriz, J.; Velasco, M.; Gomez-Hernandez, J.; Lloret, A.; Matray, J.-M.; Coste, F.; Giraud, A.; Rothfuchs, T.; Marschall, P.; Roesli, U.; Mayer, G.

    2007-01-01

    The ventilation of the underground drifts during the construction and operation of a radioactive waste repository could produce the partial desaturation of the rock around the drifts, modifying its thermo-hydro-mechanical properties, especially in clayey rocks. This change of rock properties may have an impact on the design of the repositories (drifts spacing and repository size), which depends on the thermal load that the clay barrier and the rock can accept. To evaluate 'in situ' and better understand the desaturation process of a hard clay formation, the Ventilation Experiment (VE) has been carried out at the Mont Terri underground laboratory (Switzerland), generating a flow of dry air during several months along a section of a microtunnel. Specifically, the VE test has been performed, under practically isothermal conditions (T ≅ 15-16 o C), in a 10 m long section of a non-lined horizontal microtunnel (diameter = 1.3 m), excavated in 1999 in the shaly facies of the Opalinus Clay of Mont Terri. The microtunnel is oriented perpendicular to the bedding strike direction of the rock (mean value of the bedding dip ≅ 25 o ). The VE experiment real data and its modelling have shown that the desaturation of clayey rocks of low hydraulic conductivity (K -12 m/s) due to ventilation is very small. Under real repository conditions, the thermal and hydro-mechanical rock characteristics will not be practically affected by the ventilation. Specifically, the monitoring of the VE test (mainly the hygrometer data, confirmed also by the geoelectrical measurements) indicates that, after about 5 months of ventilation with almost dry air, the rock relative humidity (and then the degree of saturation) was less than 95% only in a ring of thickness less than 40 cm. Nevertheless, a suction state (subatmospheric liquid pressures) developed up to a distance of about 2 m, but it should be kept in mind that a clayey rock such as the Opalinus Clay is quasi-saturated for suction values up

  11. Low-pH injection grout for deep repositories. Summary report from a co-operation project between NUMO (Japan), Posiva (Finland) and SKB (Sweden)

    International Nuclear Information System (INIS)

    Boden, Anders; Sievaenen, Ursula

    2005-06-01

    The use of standard cementitious material creates pulses of pH in the magnitude of 12-13 in the leachates and release alkalis. Such a high pH is detrimental and also unnecessarily complicates the safety analysis of the repository. As no reliable pH-plume models exist, the use of products giving a pH below 11 in the leachates facilitates the safety analysis. Also, according to current understanding, the use of low-pH cement (pH = 11) will not disturb the functioning of the bentonite, although limiting the amount of low-pH cement is recommended. A result of the project is that there are both low-pH cementitious material for grouting larger fractures (= 100 μm) and non-cementitious material for grouting smaller fractures (< 100 μm) that will, after further optimisation work, be recommended for grouting of deep repositories. This project concentrated on the technical development of properties for the low pH grouts. Long-term safety and environmental aspects and durability of materials were preliminarily considered. Continued evaluations have to be carried out. Five systems, e.g. material combinations, were studied in the project: 1. Ordinary Portland Cement + Silica Fume. 'OPC+SF' denotes a binder system that is based mainly on OPC+SF. SF was used in a few commercial forms. The OPC used in this system was mainly UF16 and in some cases Rheocem 900 or white cement. 2. Blast furnace slag. 'Slag' denotes an OPC activated slag based system. Alkali and water glass activation were not examined, because of long-term safety reasons. OPC used in this system was rapid hardening Portland cement. 3. Super sulphate cement. 'SSC' is a slag-based system activated with gypsum and OPC. The OPC used was rapid hardening Portland cement and the gypsum was a very fine grained slurry product. 4. Low-Alkali Cement 'LAC' was introduced to the project by NUMO as a product, ground to fixed fineness by the producer. Neither the mineral composition nor fineness, were modified in the present

  12. Low-pH injection grout for deep repositories. Summary report from a co-operation project between NUMO (Japan), Posiva (Finland) and SKB (Sweden)

    Energy Technology Data Exchange (ETDEWEB)

    Boden, Anders [SwedPower AB, Stockholm (Sweden); Sievaenen, Ursula [JP-Suoraplan Oy, Vantaa (Finland)

    2005-06-01

    The use of standard cementitious material creates pulses of pH in the magnitude of 12-13 in the leachates and release alkalis. Such a high pH is detrimental and also unnecessarily complicates the safety analysis of the repository. As no reliable pH-plume models exist, the use of products giving a pH below 11 in the leachates facilitates the safety analysis. Also, according to current understanding, the use of low-pH cement (pH = 11) will not disturb the functioning of the bentonite, although limiting the amount of low-pH cement is recommended. A result of the project is that there are both low-pH cementitious material for grouting larger fractures (= 100 {mu}m) and non-cementitious material for grouting smaller fractures (< 100 {mu}m) that will, after further optimisation work, be recommended for grouting of deep repositories. This project concentrated on the technical development of properties for the low pH grouts. Long-term safety and environmental aspects and durability of materials were preliminarily considered. Continued evaluations have to be carried out. Five systems, e.g. material combinations, were studied in the project: 1. Ordinary Portland Cement + Silica Fume. 'OPC+SF' denotes a binder system that is based mainly on OPC+SF. SF was used in a few commercial forms. The OPC used in this system was mainly UF16 and in some cases Rheocem 900 or white cement. 2. Blast furnace slag. 'Slag' denotes an OPC activated slag based system. Alkali and water glass activation were not examined, because of long-term safety reasons. OPC used in this system was rapid hardening Portland cement. 3. Super sulphate cement. 'SSC' is a slag-based system activated with gypsum and OPC. The OPC used was rapid hardening Portland cement and the gypsum was a very fine grained slurry product. 4. Low-Alkali Cement 'LAC' was introduced to the project by NUMO as a product, ground to fixed fineness by the producer. Neither the mineral composition nor

  13. Office of Legacy Management Decision Tree for Solar Photovoltaic Projects - 13317

    Energy Technology Data Exchange (ETDEWEB)

    Elmer, John; Butherus, Michael [S.M. Stoller Corporation (United States); Barr, Deborah L. [U.S. Department of Energy Office of Legacy Management (United States)

    2013-07-01

    To support consideration of renewable energy power development as a land reuse option, the DOE Office of Legacy Management (LM) and the National Renewable Energy Laboratory (NREL) established a partnership to conduct an assessment of wind and solar renewable energy resources on LM lands. From a solar capacity perspective, the larger sites in the western United States present opportunities for constructing solar photovoltaic (PV) projects. A detailed analysis and preliminary plan was developed for three large sites in New Mexico, assessing the costs, the conceptual layout of a PV system, and the electric utility interconnection process. As a result of the study, a 1,214-hectare (3,000-acre) site near Grants, New Mexico, was chosen for further study. The state incentives, utility connection process, and transmission line capacity were key factors in assessing the feasibility of the project. LM's Durango, Colorado, Disposal Site was also chosen for consideration because the uranium mill tailings disposal cell is on a hillside facing south, transmission lines cross the property, and the community was very supportive of the project. LM worked with the regulators to demonstrate that the disposal cell's long-term performance would not be impacted by the installation of a PV solar system. A number of LM-unique issues were resolved in making the site available for a private party to lease a portion of the site for a solar PV project. A lease was awarded in September 2012. Using a solar decision tree that was developed and launched by the EPA and NREL, LM has modified and expanded the decision tree structure to address the unique aspects and challenges faced by LM on its multiple sites. The LM solar decision tree covers factors such as land ownership, usable acreage, financial viability of the project, stakeholder involvement, and transmission line capacity. As additional sites are transferred to LM in the future, the decision tree will assist in determining

  14. Shared Medical Imaging Repositories.

    Science.gov (United States)

    Lebre, Rui; Bastião, Luís; Costa, Carlos

    2018-01-01

    This article describes the implementation of a solution for the integration of ownership concept and access control over medical imaging resources, making possible the centralization of multiple instances of repositories. The proposed architecture allows the association of permissions to repository resources and delegation of rights to third entities. It includes a programmatic interface for management of proposed services, made available through web services, with the ability to create, read, update and remove all components resulting from the architecture. The resulting work is a role-based access control mechanism that was integrated with Dicoogle Open-Source Project. The solution has several application scenarios like, for instance, collaborative platforms for research and tele-radiology services deployed at Cloud.

  15. Confirmatory radiological survey of the Grand Junction Projects Office Remedial Action Project exterior portions, 1989-1995

    International Nuclear Information System (INIS)

    Forbes, G.H.; Egidi, P.V.

    1997-04-01

    The purpose of this independent assessment was to provide the U.S. Department of Energy (DOE) with an independent verification (IV) that the soil at the Grand Junction Projects Office (GJPO) complies with applicable DOE guidelines. Oak Ridge National Laboratory/ Environmental Technology Section (ORNL/ETS) which is also located at the GJPO, was assigned by DOE as the Independent Verification Contractor (IVC). The assessment included reviews of the decontamination and decommissioning plan, annual environmental monitoring reports, data in the pre- and post-remedial action reports, reassessment reports and IV surveys. Procedures and field methods used during the remediation were reviewed, commented on, and amended as needed. The IV surveys included beta-gamma and gamma radiation scans, soil sampling and analyses. Based on the data presented in the post-remedial action report and the results of the IV surveys, the remediation of the outdoor portions of the GJPO has achieved the objectives. Residual deposits of uranium contamination may exist under asphalt because the original characterization was not designed to identify uranium and subsequent investigations were limited. The IVC recommends that this be addressed with the additional remediation. The IVC is working with the remedial action contractor (RAC) to assure that final documentation WM be sufficient for certification. The IVC will address additional remediation of buildings, associated utilities, and groundwater in separate reports. Therefore, this is considered a partial verification

  16. Investigative study of the underground excavations for a nuclear waste repository in tuff: Nevada Nuclear Waste Storage Investigations Project

    International Nuclear Information System (INIS)

    St John, C.M.

    1987-07-01

    Numerical studies were conducted on the behavior of a tuff rock mass within which emplacement drifts for a nuclear waste repository are excavated. The first study evaluated the effects of rockbolting and excavation-induced damage on the behavior of the rock mass round typical drifts. The second study provided a simple means of assessing the significance of drift shape, drift size, and in-situ state of stress on the deformation and stress in the vicinity of drifts for vertical and horizontal emplacement of waste. Neither study considered the effect of heating of the rock mass after emplacement of the waste so the conclusions pertain only to the conditions immediately after excavation of the underground openings. The results of analyses of the rockbolted excavations indicated that rockbolts do not have a significant influence on the states of deformation or stress within the rock mass, and that the rockbolts are subjected to acceptable levels of stress even if installed as close to the face of the excavation as possible. Accordingly, rockbolts were not considered in the study of drift shape, drift size, and the in-situ state of stress. That study indicated that stable openings of the dimensions investigated can be constructed within a tuff rock mass with the properties assumed. Of the parameters investigated, the in-situ state of stress appeared to be most important. Potentially adverse conditions were predicted if the in-situ horizontal stress is very low, but current indications are that it lies within a range which is consistent with good conditions and a stable roof. 28 refs., 49 figs., 11 tabs

  17. Learning Object Repositories

    Science.gov (United States)

    Lehman, Rosemary

    2007-01-01

    This chapter looks at the development and nature of learning objects, meta-tagging standards and taxonomies, learning object repositories, learning object repository characteristics, and types of learning object repositories, with type examples. (Contains 1 table.)

  18. Project ANSICHT. Final repository concept and backfilling and sealing concept for the final repository site model SUeD; Projekt ANSICHT. Endlagerkonzept sowie Verfuell- und Verschlusskonzept fuer das Endlagerstandortmodell SUeD. Technischer Bericht

    Energy Technology Data Exchange (ETDEWEB)

    Jobmann, Michael; Lommerzheim, Andree

    2015-08-03

    In the frame of ANSICHT the methodology for the demonstration of safe enclosure for high-level heat generating radioactive wastes is described. The report is based on the safety requirements for final repository concepts and shows a first backfilling and sealing concept that was developed for the final repository site model SUeD. The final repository model SUeD is based on a horizontal line storage concept, the Gorleben (VSG) and ERATO container concept and the mine layout were adopted and adapted to the given conditions. The backfill and sealing concept includes migration barriers, line closures and shaft closures in the frame of a redundant and diverse enclosure system. For all technical and geotechnical barrier components the long-term functional requirements were defined. The backfilling concept of underground cavities considers the variety of possible cavities in the line and infrastructure areas.

  19. Project Execution Plan, Waste Management Division, Nevada Operations Office, U.S. Department of Energy, April 2000

    International Nuclear Information System (INIS)

    2000-01-01

    This plan addresses project activities encompassed by the U.S. Department of Energy/Nevada Operations Office Waste Management Division and conforms to the requirements contained in the ''Life Cycle Asset Management,'' U.S. Department of Energy Order O430.1A; the Joint Program Office Policy on Project Management in Support of DOE Order O430.1, and the Project Execution and Engineering Management Planning Guide. The plan also reflects the milestone philosophies of the Federal Facility Agreement and Consent Order, as agreed to by the state of Nevada; and traditional project management philosophies such as the development of life cycle costs, schedules, and work scope; identification of roles and responsibilities; and baseline management and controls

  20. EEI/UWASTE oversight of the DOE Repository Program by the Repository Information Exchange Team

    International Nuclear Information System (INIS)

    Henkel, C.J.; Supko, E.M.; Schwartz, M.H.

    1993-01-01

    The Utility Nuclear Waste and Transportation Program of the Edison Electric Institute (EEI/UWASTE) has conducted reviews of the US DOE's repository program through its Repository Information Exchange Team (RIET or Team). Eight such reviews have been conducted since 1985 covering topics that include repository program management and control; repository schedule; repository budget; quality assurance; site characterization; repository licensing; environmental issues; and institutional and public information activities. The utility industry has used these repository program reviews as a forum for providing DOE's Office of Civilian Radioactive Waste Management (OCRWM) with comments on the direction of the repository program, advice for future actions regarding quality assurance activities and repository licensing, and suggestions for management and control of the Repository Program. The most significant recommendations made by the utility industry through the RIET are discussed along with any subsequent action by OCRWM in response to or subsequent to utility industry recommendations. The process used by the RIET to develop its recommendations to OCRWM regarding the repository program is also discussed

  1. Atmospheric release advisory capability pilot project at two nuclear power plants and associated state offices of emergency preparedness. Final report

    International Nuclear Information System (INIS)

    Rosen, L.C.

    1983-01-01

    A project to demonstrate the feasibility of utilizing Atmospheric Release Advisory Capability (ARAC) limited service with commercial nuclear power plants and their associated state offices of emergency preparedness is discussed. Preliminary planning, installation and testing of the ARAC site facilities at Indian Point Nucler Power Station, New York State; at New York State Office of Emergency Preparedness, Albany, New York; at Rancho Seco Nuclear Generating Station, California; and at the State of California Office of Emergency Services, Sacramento, California, are summarized. ARAC participation in the Robert E. Ginna nuclear generating plant accident in New York on January 25, 1982, is discussed. The ARAC system is evaluated with emphasis on communications, the suite of models contained within the ARAC system, and the staff. The implications of this project in designing the next-generation ARAC system to service federal and state needs are assessed

  2. YUCCA MOUNTAIN PROJECT RECOMMENDATION BY THE SECRETARY OF ENERGY REGARDING THE SUITABILITY OF THE YUCCA MOUNTAIN SITE FOR A REPOSITORY UNDER THE NUCLEAR WASTE POLICY ACT OF 1982

    Energy Technology Data Exchange (ETDEWEB)

    NA

    2002-03-26

    For more than half a century, since nuclear science helped us win World War II and ring in the Atomic Age, scientists have known that !he Nation would need a secure, permanent facility in which to dispose of radioactive wastes. Twenty years ago, when Congress adopted the Nuclear Waste Policy Act of 1982 (NWPA or ''the Act''), it recognized the overwhelming consensus in the scientific community that the best option for such a facility would be a deep underground repository. Fifteen years ago, Congress directed the Secretary of Energy to investigate and recommend to the President whether such a repository could be located safely at Yucca Mountain, Nevada. Since then, our country has spent billions of dollars and millions of hours of research endeavoring to answer this question. I have carefully reviewed the product of this study. In my judgment, it constitutes sound science and shows that a safe repository can be sited there. I also believe that compelling national interests counsel in favor of proceeding with this project. Accordingly, consistent with my responsibilities under the NWPA, today I am recommending that Yucca Mountain be developed as the site for an underground repository for spent fuel and other radioactive wastes. The first consideration in my decision was whether the Yucca Mountain site will safeguard the health and safety of the people, in Nevada and across the country, and will be effective in containing at minimum risk the material it is designed to hold. Substantial evidence shows that it will. Yucca Mountain is far and away the most thoroughly researched site of its kind in the world. It is a geologically stable site, in a closed groundwater basin, isolated on thousands of acres of Federal land, and farther from any metropolitan area than the great majority of less secure, temporary nuclear waste storage sites that exist in the country today. This point bears emphasis. We are not confronting a hypothetical problem. We have a

  3. YUCCA MOUNTAIN PROJECT RECOMMENDATION BY THE SECRETARY OF ENERGY REGARDING THE SUITABILITY OF THE YUCCA MOUNTAIN SITE FOR A REPOSITORY UNDER THE NUCLEAR WASTE POLICY ACT OF 1982

    International Nuclear Information System (INIS)

    2002-01-01

    For more than half a century, since nuclear science helped us win World War II and ring in the Atomic Age, scientists have known that the Nation would need a secure, permanent facility in which to dispose of radioactive wastes. Twenty years ago, when Congress adopted the Nuclear Waste Policy Act of 1982 (NWPA or ''the Act''), it recognized the overwhelming consensus in the scientific community that the best option for such a facility would be a deep underground repository. Fifteen years ago, Congress directed the Secretary of Energy to investigate and recommend to the President whether such a repository could be located safely at Yucca Mountain, Nevada. Since then, our country has spent billions of dollars and millions of hours of research endeavoring to answer this question. I have carefully reviewed the product of this study. In my judgment, it constitutes sound science and shows that a safe repository can be sited there. I also believe that compelling national interests counsel in favor of proceeding with this project. Accordingly, consistent with my responsibilities under the NWPA, today I am recommending that Yucca Mountain be developed as the site for an underground repository for spent fuel and other radioactive wastes. The first consideration in my decision was whether the Yucca Mountain site will safeguard the health and safety of the people, in Nevada and across the country, and will be effective in containing at minimum risk the material it is designed to hold. Substantial evidence shows that it will. Yucca Mountain is far and away the most thoroughly researched site of its kind in the world. It is a geologically stable site, in a closed groundwater basin, isolated on thousands of acres of Federal land, and farther from any metropolitan area than the great majority of less secure, temporary nuclear waste storage sites that exist in the country today. This point bears emphasis. We are not confronting a hypothetical problem. We have a staggering amount of

  4. Organizational Considerations for Implementing Systems Engineering and Integration in the Ares Projects Office

    Science.gov (United States)

    Thomas, LeAnn; Doreswamy, Rajiv N.

    2008-01-01

    Systems Engineering and Integration (SE&I) is a critical discipline in developing new space systems. In 2005, NASA performed an internal study of 24 agency and Department of Defense (DoD) programs to evaluate methods of integrating SE&I practices and determine their effectiveness. The goal of the study was to determine the best SE&I implementation strategy for the Ares Projects Office. The study identified six SE&I organizational structures: 1. Lead systems integrator (LSI) with SE&I responsibility and government technical insight. 2a. Integration contractor with government SE&I responsibility (government insight). 2b. Integration contractor with government SE&I responsibility (government oversight). 3a. Prime contractor with SE&I responsibility (government insight). 3b. Prime contractor with SE&I responsibility (government oversight). 3c. Prime contractor with SE&I responsibility (government/industry partnership). 4a.Prime contractor with government SE&I responsibility (government insight). 4b. Prime contractor with government SE&I responsibility (government oversight). 4d.Prime contractors with total system performance responsibility (TSPR). 5. Prime contractor with government SE&I responsibility and integration products through a Federally Funded Research and Development Center (FFRDC). 6. Government/FFRDC in-house development with SE&I responsibility and function. The organizational structure used most often was number 4, using a prime contractor with government SE&I responsibility and government technical insight. However, data analyses did not establish a positive relationship between program development costs and specific SE&I organizational types, nor did it positively determine the relationship between successful programs or projects and their SE&I structure. The SE&I study reached the following conclusions: (1) Large, long-duration, technically complex programs or projects reach their technical goals, but rarely meet schedule or cost goals. NASA's recent

  5. Mega-conflict project and social complexity - Illustrated by the decision-making on locating a radioactive waste repository in Denmark

    DEFF Research Database (Denmark)

    Kørnøv, Lone; Lyhne, Ivar; Larsen, Sanne Vammen

    2018-01-01

    . The process was formally initiated in 2003 when the Danish Parliament gave consent for the government to start preparing a basis for deciding a final repository for Denmark’s low- and intermediate level radioactive waste. After preliminary studies, proposal for a plan for a final repository – and later also...

  6. Dark Skies Africa: a Prototype Project with the IAU Office of Astronomy for Development

    Science.gov (United States)

    Walker, Constance Elaine; Tellez, Daniel; Pompea, Stephen M.

    2015-08-01

    The IAU’s Office of Astronomy for Development (OAD) awarded the National Optical Astronomy Observatory (NOAO) with a grant to deliver a “Dark Skies Outreach to Sub-Saharan Africa” program to institutions in 12 African countries during 2013: Algeria, Nigeria, Rwanda, Tanzania, Ghana, Zambia, South Africa, Ethiopia, Gabon, Kenya, Namibia and Senegal. The program helped students identify wasteful and inefficient lighting and provided ways to reduce consumption and to keep energy costs in check. The goal was to inspire students to be responsible stewards in helping their community safeguard one of Africa’s natural resources - a dark night sky.Thirteen kits made by the NOAO Education and Public Outreach group were sent to coordinators at university, science center and planetarium-type institutions in the 12 countries and to the IAU OAD. The program’s kit included complete instructional guides and supplies for six hands-on activities (e.g., on the importance of shielding lights and using energy efficient bulbs) and a project on energy conservation and responsible lighting (through energy audits). The activities were taught to the coordinators in a series of six Google+ Hangout sessions scheduled from June to mid-November. The coordinators at the institutions in turn trained local teachers in junior and senior high schools. The Google+ Hangout sessions also included instruction on carrying out evaluations. From the end of November until mid-December students from the different African countries shared final class projects (such as posters or powerpoints) on the program’s website.The entire program was designed to help coordinators and educators work with students, parents and the community to identify dark sky resource, lighting and energy issues and to assess their status, efficiency and effectiveness. The audience will take away from the presentation lessons learned on how well the techniques succeeded in using Google+ Hangout sessions to instruct and

  7. Repository performance confirmation

    International Nuclear Information System (INIS)

    Hansen, Francis D.

    2011-01-01

    Repository performance confirmation links the technical bases of repository science and societal acceptance. This paper explores the myriad aspects of what has been labeled performance confirmation in U.S. programs, which involves monitoring as a collection of distinct activities combining technical and social significance in radioactive waste management. This paper is divided into four parts: (1) A distinction is drawn between performance confirmation monitoring and other testing and monitoring objectives; (2) A case study illustrates confirmation activities integrated within a long-term testing and monitoring strategy for Yucca Mountain; (3) A case study reviews compliance monitoring developed and implemented for the Waste Isolation Pilot Plant; and (4) An approach for developing, evaluating and implementing the next generation of performance confirmation monitoring is presented. International interest in repository monitoring is exhibited by the European Commission Seventh Framework Programme 'Monitoring Developments for Safe Repository Operation and Staged Closure' (MoDeRn) Project. The MoDeRn partners are considering the role of monitoring in a phased approach to the geological disposal of radioactive waste. As repository plans advance in different countries, the need to consider monitoring strategies within a controlled framework has become more apparent. The MoDeRn project pulls together technical and societal experts to assimilate a common understanding of a process that could be followed to develop a monitoring program. A fundamental consideration is the differentiation of confirmation monitoring from the many other testing and monitoring activities. Recently, the license application for Yucca Mountain provided a case study including a technical process for meeting regulatory requirements to confirm repository performance as well as considerations related to the preservation of retrievability. The performance confirmation plan developed as part of the

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

    International Nuclear Information System (INIS)

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

    1991-07-01

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

  9. Simulation approaches for the two-phase flow in saline repositories using the code TOUGH2-GRS. Report in the frame of the project ZIESEL. Two-phase flow in a saline repository using the example ERAM; Ansaetze zur Simulation der Zweiphasenstroemung in salinaren Endlagern mit dem Code TOUGH2-GRS. Bericht im Vorhaben ZIESEL. Zweiphasenfluss in einem salinaren Endlager am Beispiel des ERAM

    Energy Technology Data Exchange (ETDEWEB)

    Navarro, Martin; Fischer, Heidemarie; Seher, Holger; Weyand, Torben

    2016-10-15

    The simulation approaches for the two-phase flow in saline repositories using the code TOUGH2-GRS cover the following issues: simulation of gravitational flows in horizontal galleries without vertical discretization, homogenization approach for the simulation of the two-phase flow in converging partly backfilled galleries, qualification of the convergence approach implemented by GRS into the code TOUGH2-GRS, discretization effects during replacement of liquid by gas, consequences for the system analyses in the frame of the project ZIESEL.

  10. Long-term observations programme on the geological environment of a radioactive waste repository in clayey or related formations, implications on the various phases of the project

    International Nuclear Information System (INIS)

    Manfroy, P.; Raynal, M.; Bonne, A.

    1993-01-01

    The process of emplacing radioactive waste in deep clayey or related formations involves numerous interdependent actions, the common objective of which is to guarantee optimum isolation of the waste for the durations required. Among these actions, observations on the geological environment will have to extend over a very long period of time, from site characterization to repository closure. All the far-field and near-field observations will constitute the basis and confirmation of the models intended to describe the phenomena which take place in the repository and its surrounding host formation and will have to be taken into account in the repository closure procedures. 6 refs

  11. Health Care Transformation Through Collaboration on Open-Source Informatics Projects: Integrating a Medical Applications Platform, Research Data Repository, and Patient Summarization

    Science.gov (United States)

    McCoy, Allison B; Wright, Adam; Wattanasin, Nich; Sittig, Dean F; Murphy, Shawn N

    2013-01-01

    Background The Strategic Health IT Advanced Research Projects (SHARP) program seeks to conquer well-understood challenges in medical informatics through breakthrough research. Two SHARP centers have found alignment in their methodological needs: (1) members of the National Center for Cognitive Informatics and Decision-making (NCCD) have developed knowledge bases to support problem-oriented summarizations of patient data, and (2) Substitutable Medical Apps, Reusable Technologies (SMART), which is a platform for reusable medical apps that can run on participating platforms connected to various electronic health records (EHR). Combining the work of these two centers will ensure wide dissemination of new methods for synthesized views of patient data. Informatics for Integrating Biology and the Bedside (i2b2) is an NIH-funded clinical research data repository platform in use at over 100 sites worldwide. By also working with a co-occurring initiative to SMART-enabling i2b2, we can confidently write one app that can be used extremely broadly. Objective Our goal was to facilitate development of intuitive, problem-oriented views of the patient record using NCCD knowledge bases that would run in any EHR. To do this, we developed a collaboration between the two SHARPs and an NIH center, i2b2. Methods First, we implemented collaborative tools to connect researchers at three institutions. Next, we developed a patient summarization app using the SMART platform and a previously validated NCCD problem-medication linkage knowledge base derived from the National Drug File-Reference Terminology (NDF-RT). Finally, to SMART-enable i2b2, we implemented two new Web service “cells” that expose the SMART application programming interface (API), and we made changes to the Web interface of i2b2 to host a “carousel” of SMART apps. Results We deployed our SMART-based, NDF-RT-derived patient summarization app in this SMART-i2b2 container. It displays a problem-oriented view of

  12. Health care transformation through collaboration on open-source informatics projects: integrating a medical applications platform, research data repository, and patient summarization.

    Science.gov (United States)

    Klann, Jeffrey G; McCoy, Allison B; Wright, Adam; Wattanasin, Nich; Sittig, Dean F; Murphy, Shawn N

    2013-05-30

    The Strategic Health IT Advanced Research Projects (SHARP) program seeks to conquer well-understood challenges in medical informatics through breakthrough research. Two SHARP centers have found alignment in their methodological needs: (1) members of the National Center for Cognitive Informatics and Decision-making (NCCD) have developed knowledge bases to support problem-oriented summarizations of patient data, and (2) Substitutable Medical Apps, Reusable Technologies (SMART), which is a platform for reusable medical apps that can run on participating platforms connected to various electronic health records (EHR). Combining the work of these two centers will ensure wide dissemination of new methods for synthesized views of patient data. Informatics for Integrating Biology and the Bedside (i2b2) is an NIH-funded clinical research data repository platform in use at over 100 sites worldwide. By also working with a co-occurring initiative to SMART-enabling i2b2, we can confidently write one app that can be used extremely broadly. Our goal was to facilitate development of intuitive, problem-oriented views of the patient record using NCCD knowledge bases that would run in any EHR. To do this, we developed a collaboration between the two SHARPs and an NIH center, i2b2. First, we implemented collaborative tools to connect researchers at three institutions. Next, we developed a patient summarization app using the SMART platform and a previously validated NCCD problem-medication linkage knowledge base derived from the National Drug File-Reference Terminology (NDF-RT). Finally, to SMART-enable i2b2, we implemented two new Web service "cells" that expose the SMART application programming interface (API), and we made changes to the Web interface of i2b2 to host a "carousel" of SMART apps. We deployed our SMART-based, NDF-RT-derived patient summarization app in this SMART-i2b2 container. It displays a problem-oriented view of medications and presents a line-graph display of

  13. Mont Terri Project - Engineered barrier emplacement experiment in Opalinus Clay for the disposal of radioactive waste in underground repositories

    International Nuclear Information System (INIS)

    Mayor, J. C.; Garcia-Sineriz, J.; Alonso, E.; Alheid, H.-J.; Bluemling, P.

    2007-01-01

    hydration system removes the reality of this as a true demonstration site but without it, the work could not be conducted in a reasonable experimental time period, so that the suggested technical approach seems a good compromise. The combination of the hydro-mechanical data obtained in this project and the knowledge gained from other projects under a variety of conditions (natural/artificial saturation) have brought very useful information for assessing the performance of this barrier system. The backfilling methodology developed in the project is a promising solution, which is certainly worth considering in the future although some improvements could be made in order to increase the dry density of the GBM and to get a more homogeneous buffer. On the other hand, geoelectric and seismic measurements have proven to be a good complement of the hydraulic testing methodology of the Excavation Disturbed Zone (EDZ) evolution during saturation. The investigations on the time dependent evolution of the EDZ strongly support the hypothesis of EDZ self-sealing in Opalinus Clay, and is thus an excellent completion of the work done in the SELFRAC experiment under contract with the European Commission, as well. Mathematical model calculations have been compared with field measurements. A good estimation of the rock EDZ is derived from calculations. Buffer response was compared with measurements at the position of the monitoring points. A reasonably good agreement was found for suction evolution and swelling pressure development. However, field measurements indicate a marked heterogeneous behaviour which cannot be reproduced by the model. The heterogeneous transient response of the buffer is explained by the irregular hydration of the buffer which is a consequence of the emplacement conditions and the nature of the evolving permeability of the GBM. From December 2003 on, the EB experiment is in a latent monitoring phase and close to a full saturation situation, that is the time when the

  14. Mont Terri Project - Engineered barrier emplacement experiment in Opalinus Clay for the disposal of radioactive waste in underground repositories

    Energy Technology Data Exchange (ETDEWEB)

    Mayor, J. C. [Empresa Nacional de Residuos Radioactivos SA (ENRESA), Madrid (Spain); Garcia-Sineriz, J. [Asociacion para la Investigacion y Desarollo Industrial de los Recursos Naturales (AITEMIN), Madrid (Spain); Alonso, E. [Centre Internacional de Metodos Numerics en Ingenyeria (CIMNE), Barcelona (Spain); Alheid, H.-J. [Bundesanstalt fuer Geowissenschaften und Rohstoffe (BGR), Hannover (Germany); Bluemling, P. [National Cooperative for the Disposal of Radioactive Waste (Nagra), Wettingen (Switzerland)

    2007-07-01

    artificial hydration system removes the reality of this as a true demonstration site but without it, the work could not be conducted in a reasonable experimental time period, so that the suggested technical approach seems a good compromise. The combination of the hydro-mechanical data obtained in this project and the knowledge gained from other projects under a variety of conditions (natural/artificial saturation) have brought very useful information for assessing the performance of this barrier system. The backfilling methodology developed in the project is a promising solution, which is certainly worth considering in the future although some improvements could be made in order to increase the dry density of the GBM and to get a more homogeneous buffer. On the other hand, geoelectric and seismic measurements have proven to be a good complement of the hydraulic testing methodology of the Excavation Disturbed Zone (EDZ) evolution during saturation. The investigations on the time dependent evolution of the EDZ strongly support the hypothesis of EDZ self-sealing in Opalinus Clay, and is thus an excellent completion of the work done in the SELFRAC experiment under contract with the European Commission, as well. Mathematical model calculations have been compared with field measurements. A good estimation of the rock EDZ is derived from calculations. Buffer response was compared with measurements at the position of the monitoring points. A reasonably good agreement was found for suction evolution and swelling pressure development. However, field measurements indicate a marked heterogeneous behaviour which cannot be reproduced by the model. The heterogeneous transient response of the buffer is explained by the irregular hydration of the buffer which is a consequence of the emplacement conditions and the nature of the evolving permeability of the GBM. From December 2003 on, the EB experiment is in a latent monitoring phase and close to a full saturation situation, that is the time

  15. DOE hearing on the draft area recommendation report for the Crystalline Repository Project, Lake Region High School, Bridgton, Maine, April 5, 1986: Volume 5: Transcript of proceedings

    International Nuclear Information System (INIS)

    1986-01-01

    This document contains a transcript of the comments of 15 witnesses. These meetings were held to hear the public's comments regarding the selection of a site for a second high-level radioactive waste repository

  16. DOE hearing on the draft area recommendation report for the Crystalline Repository Project, Ada High School Gymnasium, Ada, Minnesota, April 3, 1986: Transcript of proceedings

    International Nuclear Information System (INIS)

    1986-01-01

    This document contains a transcript of the comments of 64 witnesses. These meetings were held to hear the public's comments regarding the selection of a site for a second high-level radioactive waste repository

  17. DOE hearing on the draft area recommendation report for the Crystalline Repository Project, Penobscot Community Building, Indian Island, Maine: Volume 2, April 1, 1986: Transcript of proceedings

    International Nuclear Information System (INIS)

    1986-01-01

    This document contains a transcript of the comments of 10 witnesses. These meetings were held to hear public comments regarding the selection of a site for a second high-level nuclear waste repository

  18. DOE hearing on the draft area recommendation report for the Crystalline Repository Project, Kennett High School, Conway, New Hampshire, April 14, 1986: Volume 1: Transcript of proceedings

    International Nuclear Information System (INIS)

    1986-01-01

    This document contains a transcript of the comments of 18 witnesses. These meetings were held to hear public comments regarding the selection of a site for a second high-level nuclear waste repository

  19. DOE hearing on the draft area recommendation report for the Crystalline Repository Project, State Museum Auditorium, Trenton, New Jersey, April 10, 1986: Transcript of proceedings

    International Nuclear Information System (INIS)

    1986-01-01

    This document contains a transcript of the comments of a single witness. These meetings were held to hear public comments regarding the selection of a site for a second high-level nuclear waste repository

  20. DOE hearing on the draft area recommendation report for the Crystalline Repository Project, Mattanawcook Academy, Lincoln, Maine: Volume 2, April 4, 1986: Transcript of proceedings

    International Nuclear Information System (INIS)

    1986-01-01

    This document contains a transcript of the comments of 11 witnesses. These meetings were held to hear public comments regarding the selection of a site for a second high-level nuclear waste repository

  1. DOE hearing on the draft area recommendation report for the Crystalline Repository Project, Concord City Auditorium, Concord, New Hampshire: Volume 1, April 4, 1986: Transcript of proceedings

    International Nuclear Information System (INIS)

    1986-01-01

    This document contains a transcript of the comments of 29 witnesses. These meetings were held to hear public comments regarding the selection of a site for a second high-level nuclear waste repository

  2. DOE hearing on the draft area recommendation report for the Crystalline Repository Project, Lake Region High School, Bridgton, Maine: Volume 6, April 6, 1986

    International Nuclear Information System (INIS)

    1986-01-01

    This document contains a transcript of the comments of 10 witnesses. These meetings were held to hear public comments regarding the selection of a site for a second high-level nuclear waste repository

  3. DOE hearing on the draft area recommendation report for the Crystalline Repository Project, Calais High School, Calais, Maine, April 8, 1986: Volume 2: Transcript of proceedings

    International Nuclear Information System (INIS)

    1986-01-01

    This document contains a transcript of the comments of 32 witnesses. These meetings were held to hear the public's comments regarding the selection of a site for a second high-level radioactive waste repository

  4. DOE hearing on the draft area recommendation report for the Crystalline Repository Project, Kennett High School, Conway, New Hampshire: Volume 2, April 14, 1986: Transcript of proceedings

    International Nuclear Information System (INIS)

    1986-01-01

    This document contains a transcript of the comments of 15 witnesses. These meetings were held to hear public comments regarding the selection of a site for a second high-level nuclear waste repository

  5. DOE hearing on the draft area recommendation report for the Crystalline Repository Project, Foley High School, Foley, Minnesota, April 7, 1986: Transcript of proceedings

    International Nuclear Information System (INIS)

    1986-01-01

    This document contains a transcript of the comments of 40 witnesses. These meetings were held to hear public comments regarding the selection of a site for a second high-level nuclear waste repository

  6. DOE hearing on the draft area recommendation report for the Crystalline Repository Project, Portland High School, Portland, Maine: Volume 1, March 25, 1986: Transcript of proceedings

    International Nuclear Information System (INIS)

    1986-01-01

    This document contains a transcript of the comments of 13 witnesses. These meetings were held to hear public comments regarding the selection of a site for a second high-level nuclear waste repository

  7. DOE hearing on the Draft Area Recommendation Report for the Crystalline Repository Project, Ashland High School, Ashland, Wisconsin, Session 1: Transcript of proceedings

    International Nuclear Information System (INIS)

    1986-01-01

    This document contains a transcript of the comments of more than 35 witnesses. These meetings were held to hear public comments regarding the selection of a site for a second high-level nuclear waste repository

  8. DOE hearing on the draft area recommendation report for the Crystalline Repository Project, Concord City Auditorium, Concord, New Hampshire: Volume 2, April 4, 1986: Transcript of proceedings

    International Nuclear Information System (INIS)

    1987-01-01

    This document contains a transcript of the comments of 42 witnesses. These meetings were held to hear public comments regarding the selection of a site for a second high-level nuclear waste repository

  9. DOE hearing on the draft area recommendation report for the Crystalline Repository Project, Loganville High School, Loganville, Georgia, March 25, 1986: Transcript of Proceedings

    International Nuclear Information System (INIS)

    1986-01-01

    This document contains a transcript of the comments of 32 witnesses. These meetings were held to hear public comments regarding the selection of a site for a second high-level nuclear waste repository

  10. DOE hearing on the draft area recommendation report for the Crystalline Repository Project, Concord City Auditorium, Concord, New Hampshire: Volume 1, April 3, 1986

    International Nuclear Information System (INIS)

    1986-01-01

    This document contains a transcript of the comments of 32 witnesses. These meetings were held to hear the public's comments regarding the selection of a site for a second high-level radioactive waste repository

  11. DOE hearing on the draft area recommendation report for the Crystalline Repository project, Waupaca, Wisconsin, April 8, 1986: Transcript of Proceedings

    International Nuclear Information System (INIS)

    1986-01-01

    This document contains a transcript of the comments of 29 witnesses. These meetings were held to hear public comments regarding the selection of a site for a second high-level nuclear waste repository

  12. DOE hearing on the Draft Area Recommendation Report for the Crystalline Repository Project, Lakes Region High School, Bridgton, Maine: Volume 5: Transcript of proceedings

    International Nuclear Information System (INIS)

    1986-01-01

    This document contains a transcript of the comments of 17 witnesses. These meetings were held to hear public comments regarding the selection of a site for a second high-level nuclear waste repository

  13. DOE hearing on the draft area recommendation report for the Crystalline Repository Project, Ironwood Theater, Ironwood, Michigan, April 10, 1986: Transcript of proceedings

    International Nuclear Information System (INIS)

    1986-01-01

    This document contains a transcript of the comments of 22 witnesses. These meetings were held to hear public comments regarding the selection of a site for a second high-level nuclear waste repository. TEM

  14. DOE hearing on the draft area recommendation report for the Crystalline Repository Project, Concord City Auditorium, Concord, New Hampshire: Volume 4, April 3, 1986: Transcript of proceedings

    International Nuclear Information System (INIS)

    1986-01-01

    This document contains a transcript of the comments of 36 witnesses. These meetings were held to hear public comments regarding the selection of a site for a second high-level nuclear waste repository

  15. DOE hearing on the Draft Area Recommendation Report for the Crystalline Repository Project, Capitol Hill Armory, St. Paul, Minnesota: Transcript of proceedings

    International Nuclear Information System (INIS)

    1986-01-01

    This document contains a transcript of the comments of more than 15 witnesses. These meetings were held to hear comments regarding the selection of a site for a second high-level nuclear waste repository

  16. DOE hearing on the draft area recommendation report for the Crystalline Repository Project, Lake Region High School, Bridgton, Maine: Volume 1, April 5, 1986: Transcript of proceedings

    International Nuclear Information System (INIS)

    1986-01-01

    This document contains a transcript of the comments of 26 witnesses. These meetings were held to hear public comments regarding the selection of a site for a second high-level nuclear waste repository

  17. DOE hearing on the Draft Area Recommendation Report for the Crystalline Repository Project, Lakes Region High School, Bridgton, Maine: Volume 4: Transcript of proceedings

    International Nuclear Information System (INIS)

    1986-01-01

    This document contains a transcript of the comments of 16 witnesses. These meetings were held to hear public comments regarding the selection of a site for a second high-level nuclear waste repository

  18. DOE hearing on the draft area recommendation report for the Crystalline Repository Project, Winthrop High School Gymnasium, Winthrop, Minnesota: Session 1, April 8, 1986: Transcript of proceedings

    International Nuclear Information System (INIS)

    1987-01-01

    This document contains a transcript of the comments of witnesses number 1 through 15. These meetings were held to hear comments regarding the selection of a site for a second high-level nuclear waste repository

  19. DOE hearing on the Draft Area Recommendation Report for the Crystalline Repository Project, Lakes Region High School, Bridgton, Maine: Volume 3: Transcript of proceedings

    International Nuclear Information System (INIS)

    1986-01-01

    This document contains a transcript of the comments of 22 witnesses. These meetings were held to hear public comments regarding the selection of a site for a second high-level nuclear waste repository

  20. DOE hearing on the draft area recommendation report for the Crystalline Repository Project, Asheville, North Carolina: Session 2: Transcript of proceedings

    International Nuclear Information System (INIS)

    1986-01-01

    This document contains a transcript of the comments of 79 witnesses. These meetings were held to hear public comments regarding the selection of a site for a second high-level nuclear waste repository

  1. DOE hearing on the draft area recommendation report for the Crystalline Repository Project, State House, Boston, Massachusetts, April 8, 1986: Transcript of proceedings

    International Nuclear Information System (INIS)

    1986-01-01

    This document contains a transcript of the comments of 48 witnesses. These meetings were held to hear public comments regarding the selection of a site for a second high-level nuclear waste repository

  2. DOE hearing on the draft area recommendation report for the Crystalline Repository Project, South Boston, Virginia: Session 1, March 26, 1986: Transcript of proceedings

    International Nuclear Information System (INIS)

    1986-01-01

    This document contains a transcript of the comments of 53 witnesses. These meetings were held to hear public comments regarding the selection of a site for a second high-level nuclear waste repository

  3. DOE hearing on the draft area recommendation report for the Crystalline Repository Project, Patrick Henry High School, Ashland, Virginia: Session 1, April 7, 1986: Transcript of proceedings

    International Nuclear Information System (INIS)

    1986-01-01

    This document contains a transcript of the comments of 35 witnesses. These meetings were held to hear public comments regarding the selection of a site for a second high-level nuclear waste repository

  4. DOE hearing on the draft area recommendation report for the Crystalline Repository Project, Ashland Public High School, Ashland, Wisconsin: Session 2, April 9, 1986: Transcript of proceedings

    International Nuclear Information System (INIS)

    1986-01-01

    This document contains a transcript of the comments of 111 witnesses. These meetings were held to hear the public's comments regarding the selection of a site for a second high-level radioactive waste repository

  5. DOE hearing on the draft area recommendation report for the Crystalline Repository Project, Capitol Hill Armory, St. Paul, Minnesota, April 15, 1986: Transcript of proceedings

    International Nuclear Information System (INIS)

    1986-01-01

    This document contains a transcript of the comments of over 23 witnesses. These meetings were held to hear public comments regarding the selection of a site for a second high-level nuclear waste repository

  6. DOE hearing on the draft area recommendation report for the Crystalline Repository Project, Ada High School Gymnasium, Ada, Minnesota, April 3, 1986: Transcript of proceedings

    International Nuclear Information System (INIS)

    1986-01-01

    This document contains a transcript of the comments of 64 witnesses. These meetings were held to hear public comments regarding the selection of a site for a second high-level nuclear waste repository

  7. DOE hearing on the draft area recommendation report for the Crystalline Repository Project, State House, Boston, Massachusetts, April 8, 1986: Transcript of proceedings

    International Nuclear Information System (INIS)

    1986-01-01

    This document contains a transcript of the comments of 48 witnesses. These meetings were held to hear public comments regarding the selection of a site for a second high-level nuclear waste repository. TAM

  8. DOE hearing on the draft area recommendation report for the Crystalline Repository Project, Providence, Rhode Island, April 10, 1986: Transcript of proceedings

    International Nuclear Information System (INIS)

    1986-01-01

    This document contains a transcript of the comments of 10 witnesses. These meetings were held to hear the public's comments regarding the selection of a site for a second high-level radioactive waste repository

  9. DOE hearing on the draft area recommendation report for the Crystalline Repository Project, Lakes Region High School, Bridgton, Maine: Volume 8, April 5, 1986: Transcript of proceedings

    International Nuclear Information System (INIS)

    1986-01-01

    This document contains a transcript of the comments of 10 witnesses. These meetings were held to hear public comments regarding the selection of a site for a second high-level nuclear waste repository

  10. DOE hearing on the Draft Area Recommendation Report for the Crystalline Repository Project, Lake Region High School, Bridgton, Maine: Volume 6: Transcript of proceedings

    International Nuclear Information System (INIS)

    1986-01-01

    This document contains a transcript of the comments of 18 witnesses. These meetings were held to hear public comments regarding the selection of a site for a second high-level nuclear waste repository

  11. DOE hearing on the draft area recommendation report for the Crystalline Repository Project, South Boston, Virginia: Session 2, March 26, 1986: Transcript of proceedings

    International Nuclear Information System (INIS)

    1986-01-01

    This document contains a transcript of the comments of 15 witnesses. These meetings were held to hear public comments regarding the selection of a site for a second high-level nuclear waste repository

  12. DOE hearing on the Draft Area Recommendation Report for the Crystalline Repository Project, Warren High School, Warren, Minnesota: Transcript of proceedings

    International Nuclear Information System (INIS)

    1986-01-01

    This document contains a transcript of the comments of over 30 witnesses. These meetings were held to hear public comments regarding the selection of a site for a second high-level nuclear waste repository

  13. DOE hearing on the Draft Area Recommendation Report for the Crystalline Repository Project, Liberty High School, Bedford, Virginia, Session 1: Transcript of proceedings

    International Nuclear Information System (INIS)

    1986-01-01

    This document contains a transcript of the comments of 52 witnesses. These meetings were held to hear public comments regarding the selection of a site for a second high-level nuclear waste repository

  14. DOE hearing on the draft area recommendation report for the Crystalline Repository Project, Springfield High School, Springfield, Vermont, April 15, 1986: Transcript of proceedings

    International Nuclear Information System (INIS)

    1986-01-01

    This document contains a transcript of the comments of 13 witnesses. These meetings were held to hear public comments regarding the selection of a site for a second high-level nuclear waste repository

  15. DOE hearing on the draft area recommendation report for the Crystalline Repository Project, Henniker, New Hampshire, April 1, 1986: Transcript of proceedings

    International Nuclear Information System (INIS)

    1986-01-01

    This document contains a transcript of the comments of 95 witnesses. These meetings were held to hear the public's comments regarding the selection of a site for a second high-level radioactive waste repository

  16. DOE hearing on the draft area recommendation report for the Crystalline Repository Project, Mattanawcook Academy, Lincoln, Maine, April 4, 1986: Volume 5: Transcript of proceedings

    International Nuclear Information System (INIS)

    1986-01-01

    This document contains a transcript of the comments of 14 witnesses. These meetings were held to hear public comments regarding the selection of a site for a second high-level nuclear waste repository

  17. DOE hearing on the draft area recommendation report for the Crystalline Repository Project, Lake Region High School, Bridgton, Maine, April 5, 1986: Volume 4: Transcript of proceedings

    International Nuclear Information System (INIS)

    1986-01-01

    This document contains a transcript of the comments of 14 witnesses. These meetings were held to hear public comments regarding the selection of a site for a second high-level nuclear waste repository

  18. DOE hearing on the draft area recommendation report for the Crystalline Repository Project, Concord City Auditorium, Concord, New Hampshire, April 3, 1986: Volume 2: Transcript of proceedings

    International Nuclear Information System (INIS)

    1986-01-01

    This document contains a transcript of the comments of 36 witnesses. These meetings were held to hear the public's comments regarding the selection of a site for a second high-level radioactive waste repository

  19. DOE hearing on the draft area recommendation report for the Crystalline Repository Project, Hilton Hotel, Hartford, Connecticut, April 14, 1986: Transcript of proceedings

    International Nuclear Information System (INIS)

    1986-01-01

    This document contains a transcript of the comments of 22 witnesses. These meetings were held to hear public comments regarding the selection of a site for a second high-level nuclear waste repository

  20. DOE hearing on the draft area recommendation report for the Crystalline Repository Project, Augusta Armory, Augusta, Maine: Volume 2, April 7, 1986: Transcript of proceedings

    International Nuclear Information System (INIS)

    1986-01-01

    This document contains a transcript of the comments of 9 witnesses. These meetings were held to hear the public's comments regarding the selection of a site for a second high-level radioactive waste repository

  1. Agile working as a key for diversity: the Siemens office project

    OpenAIRE

    S. Cuomo; A. Mapelli

    2014-01-01

    Following directives from corporate headquarters in 2011, the Real Estate Division of Siemens Italia faced the challenge of implementing significant changes in work organisation, which arose from the need to consolidate all the Milan-based offices into a single location; a Green Building, characterised by a reduction of the available floor space, compared to the sum of the local offices. However, this reorganisation was perceived as stimulus to think of this change, not only in relation to sp...

  2. Design and construction of a large-scale sand-bentonite seal for controlled gas release from a L/ILW repository - The GAST project at GTS

    International Nuclear Information System (INIS)

    Rueedi, J.; Marschall, P.; Vaissiere, R. de la; Jung, H.; Reinhold, M.; Steiner, P.; Garcia-Sineriz, J.L.

    2012-01-01

    experiments on the real scale are needed for benchmarking the performance of the two-phase flow models. The Gas-Permeable Seal Test (GAST) was initiated in 2010 as a GTS partner project with Andra and KRMC as project partners. The experiment was emplaced at Grimsel Test Site (GTS) in 2011/2012. The S/B seal with a length of 8 m and a diameter of 3m was emplaced to demonstrate the effective functioning of gas permeable seals at realistic scales and under realistic hydraulic boundary conditions ('proof of concept'). The latter condition required the experiment to be emplaced in an existing TBM (tunnel boring machine) drilled tunnel at GTS where the surrounding granite has shown to provide a negligible excavation damaged zone (EDZ) and the stiff rock enables water injection at pressures similar to those expected for a L/ILW repository seal, i.e. 3-5 MPa corresponding to the hydrostatic pressure at 300-500 m depth. The S/B body was compacted manually in horizontal sheets of about 10 cm thickness with a target dry density of 1.7 g/cm 3 . The remaining head space as well as all S/B interfaces (i.e. towards granite and concrete plug) were sealed with granular bentonite and/or with bentonite blocks. The experiment is planned to be saturated until 2014 followed by gas injection from the far end of the tunnel in 2015. The experiment aims at validating and, if necessary, improving current conceptual models for the re-saturation and gas invasion processes into S/B seals and the determination of up-scaled gas / water permeabilities of S/B seals (i.e. two-phase flow parameters for large-scale models). For this reason material saturation, water pressures and earth pressures are monitored continuously by more than 150 sensors distributed among 15 instrumentation cross sections, comprising of piezometers for pore pressure, relative humidity sensors, psychrometers and TDRs for water saturation, total pressure cells for stress state and piezo-crystals for seismic tomography. All instruments and

  3. Interaction of nuclear waste panels with shafts and access ramps for a potential repository at Yucca Mountain: Nevada Nuclear Waste Storage Investigations Project

    International Nuclear Information System (INIS)

    St John, C.M.

    1987-09-01

    A series of two-dimensional and three-dimensional analyses of a potential nuclear waste repository at Yucca Mountain were performed to estimate the thermal stresses that would be experienced at the possible locations of shafts or ramps providing access to the repository horizon. Two alternative assumptions were made for the initial state of stress, and calculations were performed to investigate behavior at repository scale. The computed states of stress were also used as boundary conditions for a series of analyses of the access ramps and vertical shafts. The results of the repository scale analyses indicated that there is a region above the repository horizon where the horizontal stresses are reduced as a consequence of the thermal loads imposed by waste emplacement. If the initial state of stress is relatively low then the total horizontal stresses near the ground surface above the repository may be tensile. An evaluation of the total stress state relative to the strength of the rock matrix and vertical and near vertical joints indicates that there is no potential for development of new fractures in the matrix, but joints near the surface could be activated if the initial stress state is low. 13 refs., 24 figs., 4 tabs

  4. Best in Class Project Management and Contract Management Initiative at the Department of Energy's Office of Environmental Management

    International Nuclear Information System (INIS)

    Van Camp, S.G.; Stevenson, J.S.; Deiters, M.G.

    2009-01-01

    Since its founding in 1989, the U.S. Department of Energy (DOE), Office of Environmental Management (EM) has struggled with a legacy of inadequate project and contract management. This has been manifested in recurring scope changes, cost overruns and schedule delays, and has been documented in multiple internal and external reviews. To address this issue, EM has developed a vision for building a 'Best in Class' Project Management and Contract Management (BICPM) organization. To develop the strategy and implement the process to accomplish this vision, EM contracted with the U.S. Army Corps of Engineers (USACE) and their support contractors. EM and the USACE Team developed a five-phased approach to implement the BICPM Initiative: (I) develop assessment criteria, (II) assess existing project and contract management capabilities, (III) develop an implementation plan, (IV) implement corrective actions, and (V) institutionalize BICPM. Under Phases I and II, the USACE Team assessed the status of project and contract management capabilities at 16 EM offices. These assessments evaluated strengths and weaknesses in 12 key project management capabilities and benchmarks and three contract management benchmarks. Under Phase III, EM and the USACE Team developed the Corporate Implementation Plan which identified the key challenges and provided a road-map to address these challenges and to implement BICPM. These challenges included: Federal staffing shortages; integration of project and contract management; further development of project-oriented culture; project baseline maintenance; consistent implementation of the DOE order for project management, 413.3A; and role of EM Headquarters in BICPM. The shortage of qualified resources dedicated to supporting Federal project and contract management functions was identified as a primary cause for project and contract management difficulties within EM. The Corporate Implementation Plan outlined a set of 18 specific Recommended Priority

  5. Process mining software repositories

    NARCIS (Netherlands)

    Poncin, W.; Serebrenik, A.; Brand, van den M.G.J.

    2011-01-01

    Software developers' activities are in general recorded in software repositories such as version control systems, bug trackers and mail archives. While abundant information is usually present in such repositories, successful information extraction is often challenged by the necessity to

  6. Breast Cancer Tissue Repository

    National Research Council Canada - National Science Library

    Iglehart, J

    1997-01-01

    The Breast Tissue Repository at Duke enters its fourth year of finding. The purpose of the Repository at Duke is to provide substantial quantities of frozen tissue for explorative molecular studies...

  7. Technical program plan, Basalt Waste Isolation Project

    International Nuclear Information System (INIS)

    1979-12-01

    The Basalt Waste Isolation Project (BWIP) program as administered by the DOE's Richland Operations Office and Rockwell Hanford Operations is described. The objectives, scope and scientific technologies are discussed. The work breakdown structure of the project includes: project management and support, systems integration, geosciences, hydrology, engineered barriers, test facility design and construction, engineering testing, repository studies, and schedules. The budget of the program including operating and capital cost control is also included

  8. Cost estimate of the Yucca Mountain repository based on the site characterization plan conceptual design: Nevada Nuclear Waste Storage Investigations Project

    International Nuclear Information System (INIS)

    Gruer, E.R.; Fowler, M.E.; Rocha, G.A.

    1987-06-01

    This report of the life-cycle costs of a mined repository in tuff is based on the site characterization conceptual design and contains estimates of two methods of waste emplacement - vertical and horizontal. The life cycle of the repository progresses from design and construction to emplacement operations that last 25 years. When emplacement has ended, a caretaker period begins and continues until 50 years from emplacement of the first waste. The life of the repository concludes with closure and decommissioning, which includes backfilling and sealing the repository, decontaminating and razing the surface facilities, restoring the land to as near its original condition as possible, and marking the site. The estimates, developed for each phase of the life cycle of the repository, are based on January 1986 constant (unescalated) dollars and include an allowance for contingency. This report mainly comprises explanations of design and operating assumptions, estimating methods, exclusions, definition of cost accounts, calculating procedures, data sources, staffing and other qualifying remarks. Cost estimates are approximations of value and should not be construed as exact. The cost and staffing detail provided in this estimate is commensurate with the detail in the conceptual design

  9. Presentation of safety after closure of the repository for spent nuclear fuel. Main report of the project SR-Site. Part III

    International Nuclear Information System (INIS)

    2011-01-01

    The purpose of the safety assessment SR-Site is to investigate whether a safe repository for spent nuclear fuel by KBS-3 type can be constructed at Forsmark in Oesthammar in Sweden. The location of the Forsmark has been selected based on results of several surveys from surface conditions at depth in Forsmark and in Laxemar in Oskarshamn. The choice of location is not justified in SR-Site Report, but in other attachments to SKB's permit applications. SR-Site Report is an important part of SKB's permit applications to construct and operate a repository for spent nuclear fuel at Forsmark in Oesthammar. The purpose of the report in the applications is to show that a repository at Forsmark is safe after closure

  10. Presentation of safety after closure of the repository for spent nuclear fuel. Main report of the project SR-Site. Part I

    International Nuclear Information System (INIS)

    2011-01-01

    The purpose of the safety assessment SR-Site is to investigate whether a safe repository for spent nuclear fuel by KBS-3 type can be constructed at Forsmark in Oesthammar in Sweden. The location of the Forsmark has been selected based on results of several surveys from surface conditions at depth in Forsmark and in Laxemar in Oskarshamn. The choice of location is not justified in SR-Site Report, but in other attachments to SKB's permit applications. SR-Site Report is an important part of SKB's permit applications to construct and operate a repository for spent nuclear fuel at Forsmark in Oesthammar. The purpose of the report in the applications is to show that a repository at Forsmark is safe after closure

  11. The project ANSICHT. Safety and demonstration methodology for a final repository in clay formations in Germany; Projekt ANSICHT. Sicherheits- und Nachweismethodik fuer ein Endlager im Tongestein in Deutschland. Synthesebericht

    Energy Technology Data Exchange (ETDEWEB)

    Jobmann, Michael; Bebiolka, Anke; Jahn, Steffen; and others

    2017-03-30

    Based on the status of science and technology and under consideration of international repository concepts the fundamental methodology for safety demonstration for a high-level radioactive waste final repository in clay formations Germany was developed. Basic elements of the safety concept are the geological site description and the geo-scientific long-term prognosis on future performance. Another important section is the closure and sealing concept for the mine shafts. In the frame of the project the fundamental elements were developed and documented for model regions in northern and southern Germany. Three independent safety proofs have to be performed: the demonstration of the geological barrier integrity (clay), the demonstration of the geo-technical barrier system integrity - i.e. closure constructions and backfilling of the shafts, and the radiological demonstration that the radionuclide release in the area is lower than the respective limiting value.

  12. Contributing to Tumor Molecular Characterization Projects with a Global Impact | Office of Cancer Genomics

    Science.gov (United States)

    My name is Nicholas Griner and I am the Scientific Program Manager for the Cancer Genome Characterization Initiative (CGCI) in the Office of Cancer Genomics (OCG). Until recently, I spent most of my scientific career working in a cancer research laboratory. In my postdoctoral training, my research focused on identifying novel pathways that contribute to both prostate and breast cancers and studying proteins within these pathways that may be targeted with cancer drugs.

  13. Research in progress: FY 1984. Summaries of projects sponsored by the Office of Health and Environmental Research

    International Nuclear Information System (INIS)

    1983-12-01

    This report provides a compilation of summaries of the research projects supported by the Office of Health and Environmental Research (OHER) during Fiscal Year 1984. OHER is a component of the Office of Energy Research within the US Department of Energy, responsible for developing a comprehensive understanding of the health and environmental effects of energy technology development and use as well as other Departmental operations. The OHER program is broad in scope and diverse in character with substantial commitments to both applied and basic research. The research projects have been organized to reflect the major themes and focus of the OHER program. Each research category is preceeded by a short narrative to provide some perspective of the scope of activities which follow. Within each research category, the summaries are organized by efforts performed in DOE laboratories (onsite laboratories) and those performed elsewhere (offsite contractors) to help characterize their respective role in the program. The compilation of project titles and summaries, despite its volume, is still a relatively superficial source of information. It does not provide a sound basis for considering program quality or even relevance

  14. Final report of the decontamination and decommissioning of the exterior land areas at the Grand Junction Projects Office facility

    Energy Technology Data Exchange (ETDEWEB)

    Widdop, M.R.

    1995-09-01

    The US Department of Energy (DOE) Grand Junction Projects Office (GJPO) facility occupies approximately 56.4 acres (22.8 hectares) along the Gunnison River near Grand Junction, Colorado. The site was contaminated with uranium ore and mill tailings during uranium-refining activities conducted by the Manhattan Engineer District and during pilot-milling experiments conducted for the US Atomic Energy Commission`s (AEC`s) domestic uranium procurement program. The GJPO facility was the collection and assay point for AEC uranium and vanadium oxide purchases until the early 1970s. The DOE Decontamination and Decommissioning Program sponsored the Grand Junction Projects Office Remedial Action Project (GJPORAP) to remediate the facility lands, site improvements, and the underlying aquifer. The site contractor, Rust Geotech, was the Remedial Action Contractor for GJPORAP. The exterior land areas of the facility assessed as contaminated have been remediated in accordance with identified standards and can be released for unrestricted use. Restoration of the aquifer will be accomplished through the natural flushing action of the aquifer during the next 50 to 80 years. The remediation of the DOE-GJPO facility buildings is ongoing and will be described in a separate report.

  15. Final report of the decontamination and decommissioning of Building 44 at the Grand Junction Projects Office Facility

    International Nuclear Information System (INIS)

    Widdop, M.R.

    1996-07-01

    The U.S. Department of Energy (DOE) Junction Projects Office (GJPO) occupies a 61.7 acre facility along the Gunnison River near Grand Junction, Colorado. This site was contaminated with uranium ore and mill tailings during uranium refining activities of the Manhattan Engineer District and during pilot milling experiments conducted for the U.S. Atomic Energy Commission's domestic uranium procurement program. The DOE Defense Decontamination and Decommissioning Program established the Grand Junction Projects Office Remedial Action Project to clean up and restore the facility lands, improvements, and the underlying aquifer. The site contractor for the facility, Rust Geotech, is also the remedial action contractor. Building 44 was radiologically contaminated and the building was demolished in 1994. The soil area within the footprint of the building was not contaminated; it complies with the identified standards and the area can be released for unlimited exposure and unrestricted use. This document was prepared in response to a DOE request for an individual final report for each contaminated GJPO building

  16. Final report of the decontamination and decommissioning of Building 34 at the Grand Junction Projects Office Facility

    International Nuclear Information System (INIS)

    Widdop, M.R.

    1996-08-01

    The U.S. Department of Energy (DOE) Grand Junction Projects Office (GJPO) occupies a 61.7 acre facility along the Gunnison River near Grand Junction, Colorado. This site was contaminated with uranium ore and mill tailings during uranium refining activities of the Manhattan Engineer District and during pilot milling experiments conducted for the U.S. Atomic Energy Commission's domestic uranium procurement program. The DOE Defense Decontamination and Decommissioning Program established the Grand Junction Projects Office Remedial Action Project to clean up and restore the facility lands, improvements, and the underlying aquifer. The site contractor for the facility, Rust Geotech, was also the remedial action contractor. Building 34 was radiologically contaminated and the building was demolished in 1996. The soil area within the footprint of the building was analyzed and found to be not contaminated. The area can be released for unlimited exposure and unrestricted use. This document was prepared in response to a DOE request for an individual closeout report for each contaminated GJPO building

  17. U.S. Department of Energy Grand Junction Projects Office site environmental report for calendar year 1995

    International Nuclear Information System (INIS)

    1996-05-01

    This report presents information pertaining to environmental activities conducted during calendar year 1995 at the US Department of Energy (DOE) Grand Junction Projects Office (GJPO) facility in Grand Junction, Colorado. Environmental activities conducted at the GJPO facility during 1995 were associated with mixed-waste treatment, site remediation, off-site dose modeling, and radiological and nonradiological monitoring. As part of the GJPO Mixed-Waste Treatment Program, on-site treatability studies were conducted in 1995 that made use of pilot-scale evaporative-oxidation and thermal-desorption units and bench-scale stabilization. DOE-GJPO used some of its own mixed-waste as well as samples received from other DOE sites for these treatability studies. These studies are expected to conclude in 1996. Removal of radiologically contaminated materials from GJPO facility buildings was conducted under the provisions of the Grand Junction Projects Office Remedial Action Project. Remediation activities included the removal of 394 metric tons of contaminated material from Buildings 18 and 28 and revegetation activities on the GJPO site; remediation was conducted in compliance with applicable permits

  18. Documenting cost and performance for environmental remediation projects: Department of Energy Office of Environmental Management

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-08-08

    The purpose of this DOE guide is to facilitate the use of consistent procedures to document cost and performance information for projects involving the remediation of media contaminated with hazardous and radioactive wastes. It provides remedial action project managers with a standardized set of data to document completed remediation projects. Standardized reporting of data will broaden the utility of the information, increase confidence in the effectiveness of future remedial technologies, and enhance the organization, storage and retrieval of relevant information for future cleanup projects. The foundation for this guide was laid down by the Federal Remediation Technologies Roundtable (FRTR) in their publication, Guide to Documenting Cost and Performance for Remediation Projects, EPA-542-B- 95-002. Member agencies of the FRTR include the US EPA, the US DOD, the US DOE, and the US DOI. All the member agencies are involved in site remediation projects and anticipate following the guidance provided in the above reference. Therefore, there is much to be gained for DOE to be consistent with the other member agencies as it will be easier to compare projects across different agencies and also to learn from the experiences of a wider spectrum of prior completed projects.

  19. Tribal Grant Program Area Polygons with Project Officer and Tribal Contact Information, US EPA Region 9, 2015, Regional Tribal Operations Committee

    Data.gov (United States)

    U.S. Environmental Protection Agency — This dataset contains information pertaining to EPA Region 9 project officers and their areas of oversight, EPA Region 9 grant program recipients and grant types,...

  20. DOE hearing on the draft area recommendation report for the Crystalline Repository Project, Patrick Henry High School, Ashland, Virginia: Session 2: Transcript of proceedings

    International Nuclear Information System (INIS)

    1986-01-01

    This document contains a transcript of the comments of more than witnesses. Also included is a list of 2 exhibits. These meetings were held to hear public comments regarding the selection of a site for a second high-level nuclear waste repository

  1. DOE hearing on the Draft Area Recommendation Report for the Crystalline Repository Project, Foley Elementary Gymnasium, Foley, Minnesota: Volume 2: Transcript of proceedings

    International Nuclear Information System (INIS)

    1986-01-01

    This document contains a transcript of the comments of witnesses. Also included is a list of exhibits 1 through 310. These meetings were held to hear public comments regarding the selection of a site for a second high-level nuclear waste repository

  2. DOE hearing on the draft area recommendation report for the Crystalline Repository Project, Foley Elementary Gymnasium, Foley, Minnesota: Volume 1, April 7, 1986: Transcript of proceedings

    International Nuclear Information System (INIS)

    1986-01-01

    This document contains a transcript of the comments of 60 witnesses. Also included is a list of 312 exhibits. These meetings were held to hear public comments regarding the selection of a site for a second high-level nuclear waste repository

  3. DOE hearing on the draft area recommendation report for the Crystalline Repository Project, Morris High School, Morris, Minnesota, March 24, 1986: Volume 1: Transcript of proceedings

    International Nuclear Information System (INIS)

    1986-01-01

    This document contains a transcript of the comments of 48 witnesses. Also included is a description of the one exhibit. These meetings were held to hear the public's comments regarding the selection of a site for a second high-level radioactive waste repository

  4. DOE hearing on the draft area recommendation report for the Crystalline Repository Project, Menominee Indian Senior High School, Keshena, Wisconsin, March 22, 1986: Transcript of proceedings

    International Nuclear Information System (INIS)

    1986-01-01

    This document contains a transcript of the comments of 34 witnesses. Also included is a list of 14 exhibits. These meetings were held to hear public comments regarding the selection of a site for a second high-level nuclear waste repository

  5. DOE hearing on the draft area recommendation report for the Crystalline Repository Project, White Lake High School, White Lake, Wisconsin: Transcript of proceedings

    International Nuclear Information System (INIS)

    1986-01-01

    This document contains a transcript of the comments of 33 witnesses. Also included is a list of 18 exhibits. These meetings were held to hear public comments regarding the selection of a site for a second high-level nuclear waste repository

  6. DOE hearing on the draft area recommendation report for the Crystalline Repository Project, Mahnomen High School Gymnasium, Mahnomen, Minnesota, March 31, 1986: Transcript of proceedings

    International Nuclear Information System (INIS)

    1987-01-01

    This document contains a transcript of the comments of 47 witnesses. Also included is a list of over 300 exhibits. These meetings were held to hear public comments regarding the selection of a site for a second high-level nuclear waste repository

  7. Long-term safety for the final repository for spent nuclear fuel at Forsmark. Main report of the SR-Site project

    Energy Technology Data Exchange (ETDEWEB)

    2011-03-15

    The central conclusion of the safety assessment SR-Site is that a KBS-3 repository that fulfils long-term safety requirements can be built at the Forsmark site. This conclusion is reached because the favourable properties of the Forsmark site ensure the required long-term durability of the barriers of the KBS-3 repository. In particular, the copper canisters with their cast iron inserts have been demonstrated to provide a sufficient resistance to the mechanical and chemical loads to which they may be subjected in the repository environment. The conclusion is underpinned by: - The reliance of the KBS-3 repository on i) a geological environment that exhibits long-term stability with respect to properties of importance for long-term safety, i.e. mechanical stability, low groundwater flow rates at repository depth and the absence of high concentrations of detrimental components in the groundwater, and ii) the choice of naturally occurring materials (copper and bentonite clay) for the engineered barriers that are sufficiently durable in the repository environment to provide the barrier longevity required for safety. - The understanding, through decades of research at SKB and in international collaboration, of the phenomena that affect long-term safety, resulting in a mature knowledge base for the safety assessment. - The understanding of the characteristics of the site through several years of surface-based investigations of the conditions at depth and of scientific interpretation of the data emerging from the investigations, resulting in a mature model of the site, adequate for use in the safety assessment. - The detailed specifications of the engineered parts of the repository and the demonstration of how components fulfilling the specifications are to be produced in a quality assured manner, thereby providing a quality assured initial state for the safety assessment. The detailed analyses demonstrate that canister failures in a one million year perspective are rare

  8. Long-term safety for the final repository for spent nuclear fuel at Forsmark. Main report of the SR-Site project

    International Nuclear Information System (INIS)

    2011-03-01

    The central conclusion of the safety assessment SR-Site is that a KBS-3 repository that fulfils long-term safety requirements can be built at the Forsmark site. This conclusion is reached because the favourable properties of the Forsmark site ensure the required long-term durability of the barriers of the KBS-3 repository. In particular, the copper canisters with their cast iron inserts have been demonstrated to provide a sufficient resistance to the mechanical and chemical loads to which they may be subjected in the repository environment. The conclusion is underpinned by: - The reliance of the KBS-3 repository on i) a geological environment that exhibits long-term stability with respect to properties of importance for long-term safety, i.e. mechanical stability, low groundwater flow rates at repository depth and the absence of high concentrations of detrimental components in the groundwater, and ii) the choice of naturally occurring materials (copper and bentonite clay) for the engineered barriers that are sufficiently durable in the repository environment to provide the barrier longevity required for safety. - The understanding, through decades of research at SKB and in international collaboration, of the phenomena that affect long-term safety, resulting in a mature knowledge base for the safety assessment. - The understanding of the characteristics of the site through several years of surface-based investigations of the conditions at depth and of scientific interpretation of the data emerging from the investigations, resulting in a mature model of the site, adequate for use in the safety assessment. - The detailed specifications of the engineered parts of the repository and the demonstration of how components fulfilling the specifications are to be produced in a quality assured manner, thereby providing a quality assured initial state for the safety assessment. The detailed analyses demonstrate that canister failures in a one million year perspective are rare

  9. Linux toys II 9 Cool New Projects for Home, Office, and Entertainment

    CERN Document Server

    Negus, Christopher

    2006-01-01

    Builds on the success of the original Linux Toys (0-7645-2508-5) and adds projects using different Linux distributionsAll-new toys in this edition include a car computer system with built-in entertainment and navigation features, bootable movies, a home surveillance monitor, a LEGO Mindstorms robot, and a weather mapping stationIntroduces small business opportunities with an Internet radio station and Internet caf ̌projectsCompanion Web site features specialized hardware drivers, software interfaces, music and game software, project descriptions, and discussion forumsIncludes a CD-ROM with scr

  10. What do we mean by a cold repository?

    International Nuclear Information System (INIS)

    Halsey, W.G.

    1994-01-01

    The topic of thermal loading of a potential repository at Yucca Mountain in Nevada has been the subject of intense discussion within the project technical community. While terms such as ''Hot Repository'' and ''Cold Repository'' are frequently used, they have not been clearly defined. In particular, the definition of a cold repository has remained the opinion of each individual. This has led to confusion and misunderstanding. In this paper, a number of observed definitions for a cold repository are discussed along with the technical implications, assumptions and inconsistencies. Finally, a common language is suggested

  11. EPA Office of Water (OW): Nonpoint Source Projects NHDPlus Indexed Dataset

    Data.gov (United States)

    U.S. Environmental Protection Agency — GRTS locational data for nonpoint source projects. GRTS locations are coded onto NHDPlus v2.1 flowline features to create point and line events or coded onto NHDPlus...

  12. Final report of the decontamination and decommissioning of Building 1 at the Grand Junction Projects Office Facility

    International Nuclear Information System (INIS)

    Widdop, M.R.

    1996-08-01

    The U.S. Department of Energy (DOE) Grand Junction Projects Office (GJPO) occupies a 61.7-acre facility along the Gunnison River near Grand Junction, Colorado. This site was contaminated with uranium ore and mill tailings during uranium refining activities of the Manhattan Engineer District and during pilot milling experiments conducted for the U.S. Atomic Energy Commission's domestic uranium procurement program. The DOE Defense Decontamination and Decommissioning Program established the GJPO Remedial Action Project to clean up and restore the facility lands, improvements, and the underlying aquifer. The site contractor for the facility, Rust Geotech, also is the remedial action contractor. Building 1 was found to be radiologically contaminated and was demolished in 1996. The soil beneath and adjacent to the building was remediated in accordance with identified standards and can be released for unlimited exposure and unrestricted use. This document was prepared in response to a DOE request for an individual final report for each contaminated GJPO building

  13. Repository Rodeo Redux

    CERN Document Server

    Anez, Melissa; Donohue, Tim; Fyson, Will; Simko, Tibor; Wilcox, David

    2017-01-01

    You’ve got more repository questions and we’ve got more answers! Last year’s Repository Rodeo panel was a huge success, so we’re taking the show on the road to Brisbane for OR2017. Join representatives from the DSpace, Eprints, Fedora, Hydra, and Islandora communities as we (briefly) explain what each of our repositories actually does. We'll also talk about the directions of our respective technical and community developments, and related to the conference theme of Open: Innovation Knowledge Repositories, offer brief observations about the latest, most promising and/or most surprising innovations in our space. This panel will be a great opportunity for newcomers to Open Repositories to get a crash course on the major repository options and meet representatives from each of their communities. After a brief presentation from each representative, we'll open the session up for questions from the audience.

  14. Implementation of the Brazilian national repository

    International Nuclear Information System (INIS)

    Tello, Cledola Cassia Oliveira de

    2013-01-01

    Ionizing radiation in Brazil is used in electricity generation, medicine, industry, agriculture and for research and development purposes. All these activities can generate radioactive waste. At this point, in Brazil, the use of nuclear energy and radioisotopes justifies the construction of a national repository for radioactive wastes of low and intermediate-level. According to Federal Law No. 10308, Brazilian National Commission for Nuclear Energy (CNEN) is responsible for designing and constructing the intermediate and final storages for radioactive wastes. Additionally, a restriction on the construction of Angra 3 is that the repository is under construction until its operation start, attaining some requirements of the Brazilian Environmental Regulator (IBAMA). The RBMN Project (Repository for Low and Intermediate-Level Radioactive Wastes) aims at the implantation of a National Repository for disposal of low and intermediate-level of radiation wastes. This Project has some aspects that are unique in the Brazilian context, especially referring to the time between its construction and the end of its institutional period. This time is about 360 years, when the area will be released for unrestricted uses. It means that the Repository must be safe and secure for more than three hundred years, which is longer than half of the whole of Brazilian history. This aspect is very new for the Brazilian people, bringing a new dimension to public acceptance. Another point is this will be the first repository in South America, bringing a real challenge for the continent. The current status of the Project is summarized. (author)

  15. CAED Document Repository

    Data.gov (United States)

    U.S. Environmental Protection Agency — Compliance Assurance and Enforcement Division Document Repository (CAEDDOCRESP) provides internal and external access of Inspection Records, Enforcement Actions, and...

  16. Administrative Data Repository (ADR)

    Data.gov (United States)

    Department of Veterans Affairs — The Administrative Data Repository (ADR) was established to provide support for the administrative data elements relative to multiple categories of a person entity...

  17. 18 CFR 375.308 - Delegations to the Director of the Office of Energy Projects.

    Science.gov (United States)

    2010-04-01

    ... the Federal Power Act, where no substantive changes in ownership, corporate structure or domicile, or... government dams or other structures billed to licensees each year for contractual payments for the... resources projects submitted by other agencies of the Federal government for Commission review or comment...

  18. The lazy project manager how to be twice as productive and still leave the office early

    CERN Document Server

    Taylor, Peter

    2009-01-01

    Peter Taylor reveals how adopting a more focused approach to life, projects and work can make you twice as productive. The lazy project manager illustrates how anyone can apply the simple techniques of lazy project management in their own activities in order to work more effectively and consequently improve work-life balance. This 'productive laziness' approach builds on the Pareto principle that states that for many phenomena, 80 per cent of consequences stem from 20 per cent of the causes. To put it simply, only 20 per cent of the things people do during their working days really matter. Inside this insightful and informative book you'll discover: * The intelligence of laziness - why smart, lazy people have the edge over others; * Why the Jungle Book's 'Bare Necessities' should be the productive lazy theme tune; * How to get the maximum output for a minimised input; * Quick tips to productive lazy heaven. Everyone wants to achieve more without chaining themselves to their desk. By concentrating your project...

  19. Reducing Plug Loads in Office Spaces: Hawaii and Guam Energy Improvement Technology Demonstration Project

    Energy Technology Data Exchange (ETDEWEB)

    Sheppy, M. [National Renewable Energy Lab. (NREL), Golden, CO (United States); Metzger, I. [National Renewable Energy Lab. (NREL), Golden, CO (United States); Cutler, D. [National Renewable Energy Lab. (NREL), Golden, CO (United States); Holland, G. [National Renewable Energy Lab. (NREL), Golden, CO (United States); Hanada, A. [Naval Facilities Engineering Command, Washington, DC (United States)

    2014-01-01

    As part of its overall strategy to meet its energy goals, the Naval Facilities Engineering Command (NAVFAC) partnered with the Department of Energy's National Renewable Energy Laboratory (NREL) to rapidly demonstrate and deploy cost-effective renewable energy and energy efficiency technologies. This project was one of several demonstrations of new or underutilized commercial energy technologies. The common goal was to demonstrate and measure the performance and economic benefit of the system while monitoring any ancillary impacts to related standards of service and operation and maintenance (O&M) practices. In short, demonstrations at naval facilities simultaneously evaluate the benefits and compatibility of the technology with the U.S. Department of Defense (DOD) mission, and with NAVFAC's design, construction, operations, and maintenance practices, in particular. This project demonstrated the performance of commercially available advanced power strips (APSs) for plug load energy reductions in building A4 at Joint Base Pearl Harbor-Hickam (JBPHH), Hawaii.

  20. Front-office staff can improve clinical tobacco intervention: health coordinator pilot project.

    Science.gov (United States)

    Bass, Frederic; Naish, Brigham; Buwembo, Isaac

    2013-11-01

    To learn whether front-line personnel in primary care practices can increase delivery of clinical tobacco interventions and also help smokers address physical inactivity, at-risk alcohol use, and depression. Uncontrolled before-and-after design. Vancouver, BC, area (4 practices); northern British Columbia (2 practices). Six practices, with 1 staff person per practice serving as a "health coordinator" who tracked and, after the baseline period, delivered preventive interventions to all patients who smoked. To assess delivery of preventive interventions, each practice was to sample 300 consecutive patient records, both at baseline and at follow-up 15 months later. Front-office staff were recruited, trained, paid, and given ongoing support to provide preventive care. Clinicians supplemented this care with advice and guided the use of medication. Effectiveness of the intervention was based on comparison, at baseline and at follow-up, of the proportion of patients with any of the following 6 proven intervention components documented in their medical records: chart reminder, advice received, self-management plan, target quit date, referral, and follow-up date (as they applied to tobacco, physical inactivity, at-risk alcohol use, and depression). A Tobacco Intervention Flow Sheet cued preventive care, and its data were entered into a spreadsheet (which served as a smokers' registry). Qualitative appraisal data were noted. For tobacco, substantial increases occurred after the intervention period in the proportion of patients with each of the intervention components noted in their charts: chart reminder (20% vs 94%); provision of advice (34% vs 79%); self-management plan (14% vs 57%); target quit date (5% vs 11%); referral (6% vs 11%); and follow-up date (7% vs 42%). Interventions for physical inactivity and depression showed some gains, but there were no gains for at-risk alcohol use. Front-line staff, patients, and clinicians were enthusiastic about the services offered

  1. Partial support for the International Global Atmospheric Chemistry Core Project Office

    Energy Technology Data Exchange (ETDEWEB)

    Prinn, Ronald G.

    2001-05-04

    IGAC provides an international framework for the planning, coordination, and execution of atmospheric--biospheric research with emphasis on projects which require resources beyond the capabilities of any single nation. The development of chemical emission inventories by IGAC scientists, the development and intercomparison under IGAC leadership of existing chemical transport models, the analysis of data gathered during IGAC-sponsored field campaigns, etc., has provided new scientific information essential to the development of the discipline.

  2. Project SAFE. Microbial features, events and processes in the Swedish final repository for low-and intermediate-level radioactive waste

    International Nuclear Information System (INIS)

    Pedersen, Karsten

    2001-01-01

    The waste disposed of in the Swedish final repository for low and intermediate radioactive waste (SFR) typically contains large amounts of organic substances. This waste thus constitutes a possible source of energy and nutrients for microorganisms. Microbes can degrade the waste to degradation products, which to a varying degree may create problems if the process is significant. The environment for microbial life in the SFR is, however, unique since it cannot be compared to any environment to which microbes have adapted naturally over millions of years. Most similar to the SFR are waste dumps and landfills. In those, microbes degrade the waste and form degradation products. The experience from such 'analogues' and from research performed under repository-like conditions may provide useful clues about the microbial processes which may occur in the repository. Microbes have the ability to degrade bitumen, used to solidify some wastes, but this degradation is very slow under anaerobic conditions. Bitumen degradation will, therefore, not influence the safety of the SFR. However, some microbes can produce acids that could influence concrete stability, particularly in the presence of oxygen. The future SFR environment is anaerobic, which suggests that acid production is a very unlikely problem. Sulphate-reducing bacteria (SRB) have the ability to produce sulphide, which may act as a corrosive on metals. Under specific conditions, with the local groundwater flow close to a metal surface and with dissolved organic material from the repository, pitting corrosion of metal canisters is a potential threat. This process appears to require conditions fairly atypical of the SFR, however. Large groups of microorganisms can use hydrogen as a source of energy, thereby contributing to the decrease of this gas mainly formed from water during the anaerobic corrosion of metals. Cellulose is an excellent substrate for many microorganisms and it will be the dominating carbon and energy

  3. Project SAFE. Microbial features, events and processes in the Swedish final repository for low-and intermediate-level radioactive waste

    Energy Technology Data Exchange (ETDEWEB)

    Pedersen, Karsten [Goeteborg Univ. (Sweden)

    2001-01-01

    The waste disposed of in the Swedish final repository for low and intermediate radioactive waste (SFR) typically contains large amounts of organic substances. This waste thus constitutes a possible source of energy and nutrients for microorganisms. Microbes can degrade the waste to degradation products, which to a varying degree may create problems if the process is significant. The environment for microbial life in the SFR is, however, unique since it cannot be compared to any environment to which microbes have adapted naturally over millions of years. Most similar to the SFR are waste dumps and landfills. In those, microbes degrade the waste and form degradation products. The experience from such 'analogues' and from research performed under repository-like conditions may provide useful clues about the microbial processes which may occur in the repository. Microbes have the ability to degrade bitumen, used to solidify some wastes, but this degradation is very slow under anaerobic conditions. Bitumen degradation will, therefore, not influence the safety of the SFR. However, some microbes can produce acids that could influence concrete stability, particularly in the presence of oxygen. The future SFR environment is anaerobic, which suggests that acid production is a very unlikely problem. Sulphate-reducing bacteria (SRB) have the ability to produce sulphide, which may act as a corrosive on metals. Under specific conditions, with the local groundwater flow close to a metal surface and with dissolved organic material from the repository, pitting corrosion of metal canisters is a potential threat. This process appears to require conditions fairly atypical of the SFR, however. Large groups of microorganisms can use hydrogen as a source of energy, thereby contributing to the decrease of this gas mainly formed from water during the anaerobic corrosion of metals. Cellulose is an excellent substrate for many microorganisms and it will be the dominating carbon and

  4. Nuclear waste repository siting

    International Nuclear Information System (INIS)

    Soloman, B.D.; Cameron, D.M.

    1987-01-01

    This paper discusses the geopolitics of nuclear waste disposal in the USA. Constitutional choice and social equity perspectives are used to argue for a more open and just repository siting program. The authors assert that every potential repository site inevitably contains geologic, environmental or other imperfections and that the political process is the correct one for determining sites selected

  5. Radioactive waste repository study

    International Nuclear Information System (INIS)

    1978-11-01

    This is the second part of a report of a preliminary study for AECL. It considers the requirements for an underground waste repository for the disposal of wastes produced by the Canadian Nuclear Fuel Program. The following topics are discussed with reference to the repository: 1) geotechnical assessment, 2) hydrogeology and waste containment, 3) thermal loading and 4) rock mechanics. (author)

  6. Numerical study of the THM effects on the near-field safety of a hypothetical nuclear waste repository - BMT1 of the DECOVALEX III project. Part 1: conceptualization and characterization of the problems and summary of results

    International Nuclear Information System (INIS)

    Chijimatsu, M.; Nguyen, T.S.; Jing, L.; De Jonge, J.; Kohlmeier, M.; Millard, A.; Rejeb, A.; Rutqvist, J.; Souley, M.; Sugita, Y.

    2004-01-01

    Geological disposal of the spent nuclear fuel uses often the concept of multiple barrier systems. In order to predict the performance of these barriers, mathematical models have been developed, verified and validated against analytical solutions, laboratory tests and field experiments within the international DECOVALEX III project. These models in general consider the full coupling of thermal (T), hydraulic (H) and mechanical (M) processes that would prevail in the geological media around the repository. For Bench Mark Test no. 1 (BMT1) of the DECOVALEX III project, seven multinational research teams studied the implications of coupled THM processes on the safety of a hypothetical nuclear waste repository at the near-field and are presented in three accompany papers in this issue. This paper is the first of the three companion papers, which provides the conceptualization and characterization of the BMT1 as well as some general conclusions based on the findings of the numerical studies. It also shows the process of building confidence in the mathematical models by calibration with a reference T-H-M experiment with realistic rock mass conditions and bentonite properties and measured outputs of thermal, hydraulic and mechanical variables

  7. Environmental assessment of facility operations at the U.S. Department of Energy Grand Junction Projects Office, Grand Junction, Colorado

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-06-01

    The US Department of Energy (DOE) has prepared a sitewide environmental assessment (EA) of the proposed action to continue and expand present-day activities on the DOE Grand Junction Projects Office (GJPO) facility in Grand Junction, Colorado. Because DOE-GJPO regularly proposes and conducts many different on-site activities, DOE decided to evaluate these activities in one sitewide EA rather than in multiple, activity-specific documents. On the basis of the information and analyses presented in the EA, DOE has determined that the proposed action does not constitute a major Federal action significantly affecting the quality of the human environment, as defined by the National Environmental Policy Act (NEPA) of 1969. Therefore, preparation of an environmental impact statement is not required for facility operations, and DOE is issuing this Finding of No Significant Impact (FONSI).

  8. Environmental assessment of facility operations at the U.S. Department of Energy Grand Junction Projects Office, Grand Junction, Colorado

    International Nuclear Information System (INIS)

    1996-06-01

    The US Department of Energy (DOE) has prepared a sitewide environmental assessment (EA) of the proposed action to continue and expand present-day activities on the DOE Grand Junction Projects Office (GJPO) facility in Grand Junction, Colorado. Because DOE-GJPO regularly proposes and conducts many different on-site activities, DOE decided to evaluate these activities in one sitewide EA rather than in multiple, activity-specific documents. On the basis of the information and analyses presented in the EA, DOE has determined that the proposed action does not constitute a major Federal action significantly affecting the quality of the human environment, as defined by the National Environmental Policy Act (NEPA) of 1969. Therefore, preparation of an environmental impact statement is not required for facility operations, and DOE is issuing this Finding of No Significant Impact (FONSI)

  9. The Challenges of Integrating NASA's Human, Budget, and Data Capital within the Constellation Program's Exploration Launch Projects Office

    Science.gov (United States)

    Kidd, Luanne; Morris, Kenneth B.; Self, Tim

    2006-01-01

    The U.S. Vision for Space Exploration directs NASA to retire the Space Shuttle in 2010 and replace it with safe, reliable, and cost-effective space transportation systems for crew and cargo travel to the Moon, Mars, and beyond. Such emerging space transportation initiatives face massive organizational challenges, including building and nurturing an experienced, dedicated team with the right skills for the required tasks; allocating and tracking the fiscal capital invested in achieving technical progress against an integrated master schedule; and turning generated data into usehl knowledge that equips the team to design and develop superior products for customers and stakeholders. This paper discusses how NASA's Exploration Launch Projects Office, which is responsible for delivering these new launch vehicles, integrates these resources to create an engineering business environment that promotes mission success.

  10. Planning the rad waste repository - Croatian case

    International Nuclear Information System (INIS)

    Kucar Dragicevic, S.; Subasic, D.; Lokner, V.

    1996-01-01

    Radioactive waste is generated in Croatia from various nuclear applications as well as from the Krsko NPP (Slovenian and Croatian joint venture facility). The national programme on radioactive waste management is aimed at straightening existing infrastructure, establishing new (more transparent) system of responsibilities and development of new legislation. The siting of LL/ILW repository is important segments of the whole radioactive waste management cycle. The status and efficiency of the rad waste management infrastructure in the country have the significant influence on all the activities related to the project of repository construction - from the very first phases of preliminary planning and background preparations to advanced phases of the project development. The present status of the Croatian national radioactive waste infrastructure and its influence on the repository project are presented. The role of national legislation and institutional framework are specially discussed. (author)

  11. Planning geological underground repositories - Communicating with society

    International Nuclear Information System (INIS)

    Schenkel, W.; Gallego Carrera, D.; Renn, O.; Dreyer, M.

    2009-06-01

    The project 'Planning geological underground repositories: Communicating with society', financed by the Swiss Federal Office for Energy, aimed at identifying basic principles for an appropriate information and communication strategy in the process of finding an underground site to store radioactive wastes. The topic concerns an issue increasingly discussed in modern societies: How to improve the dialogue between science, infrastructure operators, public authorities, groups in civil society and the population to answer complex problems? Against this background, in the project the following questions were taken into account: (i) How can the dialogue between science, politics, economy, and the (non-)organised public be arranged appropriately? Which principles are to be considered in organising this process? How can distrust within the population be reduced and confidence in authorities and scientific expertise be increased? (ii) How can society be integrated in the process of decision-making so that this process is perceived as comprehensible, acceptable and legitimate? To answer these questions, an analysis method based on scientific theory and methodology was developed, which compares national participation and communication processes in finding underground storage sites in selected countries. Case studies have been carried out in Germany, Sweden, Belgium, and Switzerland. By using specific criteria to evaluate communication processes, the strong points as well as the drawbacks of the country-specific concepts of information, communication and participation have been analysed in a comparing dimension. By taking into account the outcomes, prototypical scenarios have been deduced that can serve as a basis for compiling a reference catalogue of measures, which is meant to support the Swiss communication strategy in the finding of an appropriate site for a nuclear waste repository. Following conclusions can be drawn from the international comparison: (i) Open and

  12. [Psychiatric patients and relatives instruct German police officers - an anti-stigma project of "BASTA - the alliance for mentally ill people"].

    Science.gov (United States)

    Wundsam, Kerstin; Pitschel-Walz, Gabi; Leucht, Stefan; Kissling, Werner

    2007-05-01

    Contact with police officers due to schizophrenia and resort to violence in such interactions is a common occurrence and represents a source for stigmatisation of mentally ill people. Aim of this project was to establish a program for police officers to reduce that stigma. The seminar was developed by a German anti-stigma organisation in cooperation with sociology teachers of the Bavarian police academy. Evaluations focussed on the police officers "social distance" and "negative stereotypes" towards mentally ill people. The personal contact between officers and the referees (patients, relatives, professionals) was the core of the seminar. Results of a debriefing after the pilot-project was overall positive. Evaluations in the renewal years showed significant improvement within the scale "social distance" (p stigma interventions.

  13. Space Telecommunications Radio System (STRS) Application Repository Design and Analysis

    Science.gov (United States)

    Handler, Louis M.

    2013-01-01

    The Space Telecommunications Radio System (STRS) Application Repository Design and Analysis document describes the STRS application repository for software-defined radio (SDR) applications intended to be compliant to the STRS Architecture Standard. The document provides information about the submission of artifacts to the STRS application repository, to provide information to the potential users of that information, and for the systems engineer to understand the requirements, concepts, and approach to the STRS application repository. The STRS application repository is intended to capture knowledge, documents, and other artifacts for each waveform application or other application outside of its project so that when the project ends, the knowledge is retained. The document describes the transmission of technology from mission to mission capturing lessons learned that are used for continuous improvement across projects and supporting NASA Procedural Requirements (NPRs) for performing software engineering projects and NASAs release process.

  14. The Swedish final repository for reactor waste (SFR). A summary of the SFR project with special emphasis on the near-field assessments

    International Nuclear Information System (INIS)

    Carlsson, J.

    1988-01-01

    The first phase of the final repository for reactor waste (SFR) is scheduled for operation in April 1988. The construction work is finished and preoperational tests are in progress. Impact on the environment from SFR is analysed in a final safety report. This paper gives a summary of the design and performance of SFR. Assessments, made for the analysises of the long term safety, are given with special emphasis on the near-field. As a conclusion from the analysises, the dose commitment to the most affected individual during the post-closure period, has proved to constitute only an insignificant contribution to the natural radioactive environment of the area

  15. Multinational/regional repository - an illusion or solution

    International Nuclear Information System (INIS)

    Mele, I.

    2006-01-01

    The concept and current status of multinational and regional repositories are presented in the paper. Particular emphasis is given to the results and findings of the recent EU project SAPIERR, investigating the feasibility of regional repository concepts in Europe. Prospects for further development of multinational repositories are also brought forward and the impact and potential benefits of this approach to our national disposal programme are discussed as well. (author)

  16. Acceptability of the Urban Family Medicine Project among Physicians: A Cross-Sectional Study of Medical Offices, Iran.

    Science.gov (United States)

    Kor, Elham Movahed; Rashidian, Arash; Hosseini, Mostafa; Azar, Farbod Ebadi Fard; Arab, Mohammad

    2016-10-01

    It is essential to organize private physicians in urban areas by developing urban family medicine in Iran. Acceptance of this project is currently low among physicians. The present research determined the factors affecting acceptability of the Urban Family Medicine Project among physicians working in the private sector of Mazandaran and Fars provinces in Iran. This descriptive-analytical and cross-sectional study was conducted in Mazandaran and Fars provinces. The target population was all physicians working in private offices in these regions. The sample size was calculated to be 860. The instrument contained 70 items that were modified in accordance with feedback from eight healthcare managers and a pilot sample of 50 physicians. Data was analyzed using the LISREL 8.80. The response rate was 82.21% and acceptability was almost 50% for all domains. The fit indices of the structural model were the chi-square to degree-of-freedom (2.79), normalized fit index (0.98), non-normalized fit index (0.99), comparative fit index (0.99), and root mean square error of approximation (0.05). Training facilities had no significant direct effect on acceptability; however, workload had a direct negative effect on acceptability. Other factors had direct positive effects on acceptability. Specification of the factors relating to acceptance of the project among private physicians is required to develop the project in urban areas. It is essential to upgrade the payment system, remedy cultural barriers, decrease the workload, improve the scope of practice and working conditions, and improve collaboration between healthcare professionals.

  17. Connecting the pieces: using ORCIDs to improve research impact and repositories

    KAUST Repository

    Baessa, Mohamed A.

    2015-05-19

    Quantitative data are crucial in the assessment of research impact in the academic world. However, as a young university created in 2009, King Abdullah University of Science and Technology (KAUST) needs to aggregate bibliometrics from researchers coming from diverse origins, not necessarily with the proper affiliations. In this context, the University has launched an institutional repository in September 2012 with the objectives of creating a home for the intellectual outputs of KAUST researchers. Later, the university adopted the first mandated institutional open access policy in the Arab region, effective June 31, 2014. Several projects were then initiated in order to accurately identify the research being done by KAUST authors and bring it into the repository in accordance with the open access policy. Integration with ORCID has been a key element in this process and the best way to ensure data quality for researcher’s scientific contributions. It included the systematic inclusion and creation, if necessary, of ORCID identifiers in the existing repository system, an institutional membership in ORCID, and the creation of dedicated integration tools. In addition and in cooperation with the Office of Research Evaluation, the Library worked at implementing a Current Research Information System (CRIS) as a standardized common resource to monitor KAUST research outputs. We will present our findings about the CRIS implementation, the ORCID API, the repository statistics as well as our approach in conducting the assessment of research impact in terms of usage by the global research community.

  18. Connecting the pieces: Using ORCIDs to improve research impact and repositories.

    Science.gov (United States)

    Baessa, Mohamed; Lery, Thibaut; Grenz, Daryl; Vijayakumar, J K

    2015-01-01

    Quantitative data are crucial in the assessment of research impact in the academic world. However, as a young university created in 2009, King Abdullah University of Science and Technology (KAUST) needs to aggregate bibliometrics from researchers coming from diverse origins, not necessarily with the proper affiliations. In this context, the University has launched an institutional repository in September 2012 with the objectives of creating a home for the intellectual outputs of KAUST researchers. Later, the university adopted the first mandated institutional open access policy in the Arab region, effective June 31, 2014. Several projects were then initiated in order to accurately identify the research being done by KAUST authors and bring it into the repository in accordance with the open access policy. Integration with ORCID has been a key element in this process and the best way to ensure data quality for researcher's scientific contributions. It included the systematic inclusion and creation, if necessary, of ORCID identifiers in the existing repository system, an institutional membership in ORCID, and the creation of dedicated integration tools. In addition and in cooperation with the Office of Research Evaluation, the Library worked at implementing a Current Research Information System (CRIS) as a standardized common resource to monitor KAUST research outputs. We will present our findings about the CRIS implementation, the ORCID API, the repository statistics as well as our approach in conducting the assessment of research impact in terms of usage by the global research community.

  19. DECOVALEX-THMC Project. Task A. Influence of near field coupled THM phenomena on the performance of a spent fuel repository. Report of Task A1: Preliminary scoping calculations

    Energy Technology Data Exchange (ETDEWEB)

    Nguyen, Son (ed.) [Canadian Nuclear Safety Commission (Canada); Lanru Jing (ed.) [Royal Institute of Technology, Stockholm (Sweden); Boergesson, Lennart [Clay Technology AB, Lund (Sweden); Chijimatzu, Masakazu [Hazama Corporation (Japan); Jussila, Petri [Helsinki Univ. of Technology, Helsinki (Finland); Rutqvist, Jonny [Lawrence Berkeley National Laboratory CA (United States)

    2007-02-15

    The DECOVALEX-THMC project is an ongoing international co-operative project that was stared in 2004 to support the development of mathematical models of coupled Thermal (T), Hydrological (H), Mechanical (M) and Chemical (C) processes in geological media for siting potential nuclear fuel waste repositories. The general objective is to characterise and evaluate the coupled THMC processes in the near field and far field of a geological repository and to assess their impact on performance assessment: - during the three phases of repository development: excavation phase, operation phase and post-closure phase; - for three different rocks types: crystalline, argillaceous and tuff; - with specific focus on the issues of: Excavation Damaged Zone (EDZ), permanent property changes of rock masses, and glaciation and permafrost phenomena. The project involves a large number of research teams supported by radioactive waste management agencies or governmental regulatory bodies in Canada, China, Finland, France, Germany, Japan, Sweden and USA, who conducted advanced studies and numerical modelling of coupled THMC processes under five tasks. This report presents the definition of the first phase, Task A-1, of the Task A of the project. The task is a working example of how interaction between THMC modelling and SA analysis could be performed. Starting with the technical definition of the Task A, the report presents the results of preliminary THM calculations with a purpose of an initial appreciation of the phenomena and material properties that must be better understood in subsequent phases. Many simplifications and assumptions were introduced and the results should be considered under these assumptions. Based on the evaluation of the multiple teams' results, a few points of concern were identified that may guide the successive phases of Task A studies: 1. The predicted maximum total stress in the MX-80 bentonite could slightly exceed the 15 MPa design pressure for the

  20. DECOVALEX-THMC Project. Task A. Influence of near field coupled THM phenomena on the performance of a spent fuel repository. Report of Task A1: Preliminary scoping calculations

    International Nuclear Information System (INIS)

    Nguyen, Son; Lanru Jing; Boergesson, Lennart; Chijimatzu, Masakazu; Jussila, Petri; Rutqvist, Jonny

    2007-02-01

    The DECOVALEX-THMC project is an ongoing international co-operative project that was stared in 2004 to support the development of mathematical models of coupled Thermal (T), Hydrological (H), Mechanical (M) and Chemical (C) processes in geological media for siting potential nuclear fuel waste repositories. The general objective is to characterise and evaluate the coupled THMC processes in the near field and far field of a geological repository and to assess their impact on performance assessment: - during the three phases of repository development: excavation phase, operation phase and post-closure phase; - for three different rocks types: crystalline, argillaceous and tuff; - with specific focus on the issues of: Excavation Damaged Zone (EDZ), permanent property changes of rock masses, and glaciation and permafrost phenomena. The project involves a large number of research teams supported by radioactive waste management agencies or governmental regulatory bodies in Canada, China, Finland, France, Germany, Japan, Sweden and USA, who conducted advanced studies and numerical modelling of coupled THMC processes under five tasks. This report presents the definition of the first phase, Task A-1, of the Task A of the project. The task is a working example of how interaction between THMC modelling and SA analysis could be performed. Starting with the technical definition of the Task A, the report presents the results of preliminary THM calculations with a purpose of an initial appreciation of the phenomena and material properties that must be better understood in subsequent phases. Many simplifications and assumptions were introduced and the results should be considered under these assumptions. Based on the evaluation of the multiple teams' results, a few points of concern were identified that may guide the successive phases of Task A studies: 1. The predicted maximum total stress in the MX-80 bentonite could slightly exceed the 15 MPa design pressure for the container

  1. Final report of the decontamination and decommissioning of Building 39 at the Grand Junction Projects Office Facility

    International Nuclear Information System (INIS)

    Widdop, M.R.

    1996-07-01

    The U.S. Department of Energy (DOE) Grand Junction Projects Office (GJPO) occupies a 61.7-acre facility along the Gunnison River near Grand Junction, Colorado. This site was contaminated with uranium ore and mill tailings during uranium refining activities of the Manhattan Engineer District and during pilot milling experiments conducted for the U.S. Atomic Energy Commission's domestic uranium procurement program. The DOE Defense Decontamination and Decommissioning Program established the GJPO Remedial Action Project to clean up and restore the facility lands, improvements, and the underlying aquifer. The site contractor for the facility, Rust Geotech, is also the remedial action contractor. The soil beneath Building 39 was radiologically contaminated and the building was demolished in 1992. The soil area within the footprint of the building has been remediated in accordance with the identified standards and the area can be released for unlimited exposure and unrestricted use. This document was prepared in response to a DOE request for an individual final report for each contaminated GJPO building

  2. Final report of the decontamination and decommission of Building 31 at the Grand Junction Projects Office Facility

    International Nuclear Information System (INIS)

    Krabacher, J.E.

    1996-07-01

    The U.S. Department of Energy (DOE) Grand Junction Projects Office (GJPO) occupies a 61.7-acre facility along the Gunnison River near Grand Junction, Colorado. This site was contaminated with uranium ore and mill tailings during uranium refining activities of the Manhattan Engineer District and during pilot milling experiments conducted for the domestic uranium procurement program funded by the U.S. Atomic Energy Commission. The DOE Defense Decontamination and Decommissioning Program established the GJPO Remedial Action Project to clean up and restore the facility lands, improvements, and the underlying aquifer. The site contractor for the facility, Rust Geotech, also was the remedial action contractor. Radiological contamination was identified in Building 31 and the building was demolished in 1992. The soil area within the footprint of the building has been remediated in accordance with the identified standards and the area can be released for unlimited exposure and unrestricted use. This area was addressed in the summary final report of the remediation of the exterior areas of the GJPO facility. This document was prepared in response to a DOE request for an individual final report for each contaminated GJPO building

  3. Final report of the decontamination and decommissioning of Building 6 at the Grand Junction Projects Office Facility

    International Nuclear Information System (INIS)

    Widdop, M.R.

    1996-07-01

    The U.S. Department of Energy (DOE) Grand Junction Projects Office (GJPO) occupies a 61.7-acre facility along the Gunnison River near Grand Junction, Colorado. This site was contaminated with uranium ore and mill tailings during uranium refining activities of the Manhattan Engineer District and during pilot milling experiments conducted for the domestic uranium procurement program funded by the U.S. Atomic Energy Commission. The DOE Defense Decontamination and Decommissioning Program established the GJPO Remedial Action Project to clean up and restore the facility lands, improvements, and the underlying aquifer. The site contractor for the facility, Rust Geotech, is also the remedial action contractor. Radiological contamination was identified in Building 6, and the building was demolished in 1992. The soil area within the footprint of the building has been remediated in accordance with the identified standards and the area can be released for unlimited exposure and unrestricted use. This document was prepared in response to a DOE request for an individual final report for each contaminated GJPO building

  4. Gas generation in repositories

    International Nuclear Information System (INIS)

    Biddle, P.; Rees, J.H.; McGahan, D.; Rushbrook, P.E.

    1987-09-01

    The nature and quantities of gases likely to be produced by various processes in repositories for low level and intermediate level radioactive wastes are examined in this preliminary study. Many simplifying assumptions are made where published or experimental data is unavailable. The corrosion of the canisters and metallic components in wastes is likely to be the major gas production process in both types of repository. A significant contribution from microbiological activity is expected to occur in low level repositories, predominantly where no cement grouting of the cans has been carried out. A number of areas for further research, required before a more comprehensive study could be carried out, have been identified. (author)

  5. Centralized mouse repositories.

    Science.gov (United States)

    Donahue, Leah Rae; Hrabe de Angelis, Martin; Hagn, Michael; Franklin, Craig; Lloyd, K C Kent; Magnuson, Terry; McKerlie, Colin; Nakagata, Naomi; Obata, Yuichi; Read, Stuart; Wurst, Wolfgang; Hörlein, Andreas; Davisson, Muriel T

    2012-10-01

    Because the mouse is used so widely for biomedical research and the number of mouse models being generated is increasing rapidly, centralized repositories are essential if the valuable mouse strains and models that have been developed are to be securely preserved and fully exploited. Ensuring the ongoing availability of these mouse strains preserves the investment made in creating and characterizing them and creates a global resource of enormous value. The establishment of centralized mouse repositories around the world for distributing and archiving these resources has provided critical access to and preservation of these strains. This article describes the common and specialized activities provided by major mouse repositories around the world.

  6. National Radwaste Repository Mochovce

    International Nuclear Information System (INIS)

    2000-01-01

    In this leaflet the National Radioactive Waste Repository in Mochovce (Repository) is described. The Mochovce National Radioactive Waste Repository is a surface multi-barrier type storage facility for solid and treated solidified radioactive wastes generated from the Slovak Republic nuclear power plants operation and decommissioning, research institutes, laboratories and hospitals. The Repository comprises a system of single- and double-row storage boxes. The first double-row is enclosed by a steel-structure building. The 18 x 6 x 5.5 m storage boxes are made of reinforced concrete. The wall thickness is 600 mm. Two-double-rows, i.e. 80 storage boxes were built as part of Stage I (1 row = 20 storage boxes). Each storage box has a storage capacity of 90 fibre concrete containers of 3.1 m 3 volume. The total storage capacity is 7200 containers with the overall storage volume of 22320 m 3

  7. NIA Aging Cell Repository

    Data.gov (United States)

    Federal Laboratory Consortium — To facilitate aging research on cells in culture, the NIA provides support for the NIA Aging Cell Repository, located at the Coriell Institute for Medical Research...

  8. NIDDK Central Repository

    Data.gov (United States)

    U.S. Department of Health & Human Services — The NIDDK Central Repository stores biosamples, genetic and other data collected in designated NIDDK-funded clinical studies. The purpose of the NIDDK Central...

  9. Design aspects of the Alpha Repository. VII. Summary of results for the conceptual facility layout, room stability analysis, and equipment selection. Project summary report RSI-0033

    Energy Technology Data Exchange (ETDEWEB)

    Gnirk, P.F.; Grams, W.H.; Zeller, T.J.

    1978-11-03

    In 1975, RE/SPEC Inc. analyzed various design engineering aspects of an Alpha Repository for the disposal and isolation of packages of low-level solid waste and sealed metal canisters of spent fuel cladding waste. The proposed site was located in southeastern New Mexico, with candidate disposal horizons situated in massive bedded salt at depths of 580 to 825 m. The canisters would be emplaced in vertical drillholes in the floors of disposal rooms, and the packages of solid waste subsequently stacked on the floors. Consideration was given to various conceptual facility layouts, the structural stability of the disposal rooms, appropriate excavation/haulage systems, and equipment availability for drilling the canister emplacement holes. This report summarizes the results of the entire study.

  10. PASS - Project on Alternative Systems Study. Performance assessment of bentonite clay barrier in three repository concepts: VDH, KBS-3 and VLH

    International Nuclear Information System (INIS)

    Pusch, R.; Boergesson, L.

    1992-12-01

    The three repository concepts VDH, KBS3 and VLH have been investigated with respect to their functions in short- and long-term perspectives. The study shows that while KBS3 does not require development of new techniques for excavation and application of buffers and canisters, such development is needed for VLH and VDH. The various physical processes in the deployment part of VDH are more critical and less understood than those in KBS3 and VLH, but the sealing effect of the plugged 'low-temperature' part is sufficiently good to make the concept qualify as a candidate. VLH has the highest and KBS3 the lowest temperature and the latter has the highest potential for good long-term function. (59 refs.)

  11. Managing and Evaluating Digital Repositories

    Science.gov (United States)

    Zuccala, Alesia; Oppenheim, Charles; Dhiensa, Rajveen

    2008-01-01

    Introduction: We examine the role of the digital repository manager, discuss the future of repository management and evaluation and suggest that library and information science schools develop new repository management curricula. Method: Face-to-face interviews were carried out with managers of five different types of repositories and a Web-based…

  12. Radioactive waste repository study

    International Nuclear Information System (INIS)

    1978-11-01

    This is the first part of a report of a preliminary study for Atomic Energy of Canada Limited. It considers the requirements for an underground waste repository for the disposal of wastes produced by the Canadian Nuclear Fuel Program. The following topics are discussed with reference to the repository: 1) underground layout, 2) cost estimates, 3) waste handling, 4) retrievability, decommissioning, sealing and monitoring, and 5) research and design engineering requirements. (author)

  13. Repository simulation tests

    International Nuclear Information System (INIS)

    Wicks, G.G.; Bibler, N.E.; Jantzen, C.M.; Plodinec, M.J.

    1984-01-01

    The repository simulation experiments described in this paper are designed to assess the performance of SRP waste glass under the most realistic repository conditions that can be obtained in the laboratory. These tests simulate the repository environment as closely as possible and introduce systematically the variability of the geology, groundwater chemistry, and waste package components during the leaching of the waste glass. The tests evaluate waste form performance under site-specific conditions, which differ for each of the geologic repositories under consideration. Data from these experiments will aid in the development of a realistic source term that can describe the release of radionuclides from SRP waste glass as a component of proposed waste packages. Hence, this information can be useful to optimize waste package design for SRP waste glass and to provide data for predicting long-term performance and subsequent conformance to regulations. The repository simulation tests also help to bridge the gap in interpreting results derived from tests performed under the control of the laboratory to the uncertainity and variability of field tests. In these experiments, site-specific repository components and conditions are emphasized and only the site specific materials contact the waste forms. An important feature of these tests is that both actual and simulated waste glasses are tested identically. 7 figures, 2 tables

  14. Repository operational criteria analysis

    International Nuclear Information System (INIS)

    Hageman, J.P.; Chowdhury, A.H.

    1992-08-01

    The objective of the ''Repository Operational Criteria (ROC) Feasibility Studies'' (or ROC task) was to conduct comprehensive and integrated analyses of repository design, construction, and operations criteria in 10 CFR Part 60 regulations, considering the interfaces and impacts of any potential changes to those regulations. The study addresses regulatory criteria related to the preclosure aspects of the geologic repository. The study task developed regulatory concepts or potential repository operational criteria (PROC) based on analysis of a repository's safety functions and other regulations for similar facilities. These regulatory concepts or PROC were used as a basis to assess the sufficiency and adequacy of the current criteria in 10 CFR Part 60. Where the regulatory concepts were same as current operational criteria, these criteria were referenced. The operations criteria referenced or the PROC developed are given in this report. Detailed analyses used to develop the regulatory concepts and any necessary PROC for those regulations that may require a minor change are also presented. The results of the ROC task showed a need for further analysis and possible major rule change related to the design bases of a geologic repository operations area, siting, and radiological emergency planning

  15. Characteristics of potential repository wastes

    International Nuclear Information System (INIS)

    Notz, K.J.

    1989-01-01

    The Office of Civilian Radioactive Waste Management (OCRWM) is responsible for the spent fuels and other wastes that will be disposed of in a geologic repository. The two major sources of these materials are commercial light-water reactor (LWR) spent fuel and immobilized high-level waste (HLW). Other wastes that may require long-term isolation include non-LWR spent fuels and miscellaneous sources such as activated metals. Detailed characterizations are required for all of these potential repository wastes. These characterizations include physical, chemical, and radiological properties. The latter must take into account decay as a function of time. This information has been extracted from primary data sources, evaluated, and assembled in a Characteristics Data Base which provides data in four formats: hard copy standard reports, menu-driven personal computer (PC) data bases, program-level PC data bases, and mainframe computer files. The Characteristics Data Base provides a standard set of self-consistent data to the various areas of responsibility including systems integration and waste stream analysis, storage, transportation, and geologic disposal. The data will be used for design studies, evaluation of alternatives, and system optimization by OCRWM and supporting contractors. 7 refs., 5 figs., 7 tabs

  16. Salt Repository emplacement mode evaluation and selection: Final report

    International Nuclear Information System (INIS)

    1988-03-01

    This document describes the decision analysis performed to evaluate and compare the emplacement mode for the Salt Repository. The study was commissioned to recommend one emplacement mode to the Salt Repository Project Office using multi-attribute decision analysis. The nature of the decision required analysis of uncertain outcomes and conflicting attributes and offers a high degree of objectivity for these types of decisions since the decision model is structured to allow only the facts to enter into the final decision. The analysis requires an explicit definition of the attributes used to evaluate the alternative (e.g., cost, safety, environmental impact), the definition of a utility function over the attributes which incorporated both risk attitudes and trade-offs between attributes, and the probability distribution over the outcomes that would result from the selection of one alternative over the other. The decision process is described and results are given. A simulation model was developed to evaluate the probability distributions over the attributes. This report documents logic, inputs and results of this model. Final ranking of alternatives is given. Extensive technical backup documentation is included in the appendices to provide the quantitative basis for this decision. 5 refs., 2 figs., 8 tabs

  17. Findings and recommendations of the ONWI peer review of the SocioEconomic Analysis of Repository Siting (SEARS) modeling system

    International Nuclear Information System (INIS)

    Cluett, C.; Bjornstad, D.; DeVeny, G.; Ellis, C.B.; Goldstone, S.E.; Ritchey, P.N.; Winter, R.

    1985-12-01

    A Peer Review Group was convened by the Office of Nuclear Waste Isolation (ONWI) of the Battelle Project Management Division (BPMD) to provide an outside professional assessment of the SocioEconomic Analysis of Repository Siting (SEARS) modeling system. The SEARS model is intended to provide detailed, site-specific projections by jurisdiction and political subdivision of the economic, demographic, infrastructure, and fiscal effects of constructing, operating, and decommissioning a geologic repository for the isolation of nuclear waste in one or more locations. In addition, it is expected to aid in the indentification of appropriate local correction actions and to aid in monitoring socioeconomic changes. The SEARS model will address program-related issues, local concerns, and statutory requirements relating to economic-demographic impacts; employ technically defensible methods and procedures; be adequately and appropriately documented, verified, and validated; and provide results that are consistent and replicable

  18. Characteristics of potential repository wastes

    International Nuclear Information System (INIS)

    Cowart, C.G.; Notz, K.J.

    1992-10-01

    This report presents the results of a fully documented peer review of DOE/RW-0184, Rev. 1, ''Characteristics of Potential Repository Wastes''. The peer review was chaired and administered by oak Ridge National Laboratory (ORNL) for the Department of Energy (DOE), Office of Civilian Radioactive Waste Management (OCRWM) and was conducted in accordance with OCRWM QA procedure QAAP 3.3 ''Peer Review'' for the purpose of quailing the document for use in OCRWM quality-affecting work. The peer reviewers selected represent a wide range of experience and knowledge particularly suitable for evaluating the subject matter. A total of 596 formal comments were documented by the seven peer review panels, and all were successfully resolved. The peers reached the conclusion that DOE/RW-0184, Rev. 1, is quality determined and suitable for use in quality-affecting work

  19. Progress and Failure of Repository Projects for Radioactive Waste - a Comparative Analysis of Turning Points, Deadlock and Ways to get out

    Energy Technology Data Exchange (ETDEWEB)

    Barth, Regine; Kallenbach-Herbert, Beate (Environmental Law and Nuclear Engineering and Governance Div., Facility Safety Div., Oeko-Institut e.V. Darmstadt (Germany)), e-mail: r.barth@oeko.de

    2009-12-15

    The examples of factors that may support or obstruct a disposal process give an overview of results from empirical studies with regard to the selected issues in site selection and approval procedure and public participation. They reveal how experience from disposal projects in different countries and from other large infrastructure projects may contribute to the shaping of national disposal projects. As was to be expected project specific features limit the level of detail with which factors of success or failure can be described. On the other hand a relatively large number of factors on a generic level can be identified. They give a clear indication as to which issues are important for the successful implementation of a disposal project for high active waste. The project specific implementation of generic success factors on the national level requires an additional step of analysis. In that step a detailed adaption under consideration of the specific situation and circumstances of a project can be performed

  20. Progress and Failure of Repository Projects for Radioactive Waste - a Comparative Analysis of Turning Points, Deadlock and Ways to get out

    International Nuclear Information System (INIS)

    Barth, Regine; Kallenbach-Herbert, Beate

    2009-12-01

    The examples of factors that may support or obstruct a disposal process give an overview of results from empirical studies with regard to the selected issues in site selection and approval procedure and public participation. They reveal how experience from disposal projects in different countries and from other large infrastructure projects may contribute to the shaping of national disposal projects. As was to be expected project specific features limit the level of detail with which factors of success or failure can be described. On the other hand a relatively large number of factors on a generic level can be identified. They give a clear indication as to which issues are important for the successful implementation of a disposal project for high active waste. The project specific implementation of generic success factors on the national level requires an additional step of analysis. In that step a detailed adaption under consideration of the specific situation and circumstances of a project can be performed

  1. Determination of the spatial structure of vegetation on the repository of the mine “Fryderyk” in Tarnowskie Góry, based on airborne laser scanning from the ISOK project and digital orthophotomaps

    Directory of Open Access Journals (Sweden)

    Szostak Marta

    2015-06-01

    Full Text Available The purpose of this study was to determine the spatial structure of vegetation on the repository of the mine “Fryderyk” in Tarnowskie Góry. Tested area was located in the Upper Silesian Industrial Region (a large industrial region in Poland. It was a unique refuge habitat – Natura2000; PLH240008. The main aspect of this elaboration was to investigate the possible use of geotechniques and generally available geodata for mapping LULC changes and determining the spatial structure of vegetation. The presented study focuses on the analysis of a spatial structure of vegetation in the research area. This exploration was based on aerial images and orthophotomaps from 1947, 1998, 2003, 2009, 2011 and airborne laser scanning data (2011, ISOK project. Forest succession changes which occurred between 1947 and 2011 were analysed. The selected features of vegetation overgrowing spoil heap “Fryderyk” was determined.

  2. Grey Guide Repository: presentation and demo

    OpenAIRE

    Biagioni, Stefania; Carlesi, Carlo; Schopfel, Joachim; Farace, Dominic; Frantzen, Jerry

    2013-01-01

    The goal of this project is to develop an open source repository of good practices in the field of grey literature. That which originated in monographic form will now open and expand to include content from the global grey literature community. Such practices will range from the production and processing of grey literature through to its distribution, uses, and preservation.

  3. Office of the Chief Financial Officer Annual Report 2009

    Energy Technology Data Exchange (ETDEWEB)

    Fernandez, Jeffrey

    2009-12-15

    Presented is the 2009 Chief Financial Officer's Annual Report. The data included in this report has been compiled from the Budget Office, the Controller, Procurement and Property Management and the Sponsored Projects Office.

  4. Trust in Digital Repositories

    Directory of Open Access Journals (Sweden)

    Elizabeth Yakel

    2013-06-01

    Full Text Available ISO 16363:2012, Space Data and Information Transfer Systems - Audit and Certification of Trustworthy Digital Repositories (ISO TRAC, outlines actions a repository can take to be considered trustworthy, but research examining whether the repository’s designated community of users associates such actions with trustworthiness has been limited. Drawing from this ISO document and the management and information systems literatures, this paper discusses findings from interviews with 66 archaeologists and quantitative social scientists. We found similarities and differences across the disciplines and among the social scientists. Both disciplinary communities associated trust with a repository’s transparency. However, archaeologists mentioned guarantees of preservation and sustainability more frequently than the social scientists, who talked about institutional reputation. Repository processes were also linked to trust, with archaeologists more frequently citing metadata issues and social scientists discussing data selection and cleaning processes. Among the social scientists, novices mentioned the influence of colleagues on their trust in repositories almost twice as much as the experts. We discuss the implications our findings have for identifying trustworthy repositories and how they extend the models presented in the management and information systems literatures.

  5. Spent fuel and high level waste: Chemical durability and performance under simulated repository conditions. Results of a coordinated research project 1998-2004. Part 2: Results of a previously unpublished CRP: Performance of high level waste forms and packages under repository conditions. Results of a co-ordinated research project 1991-1998

    International Nuclear Information System (INIS)

    2007-07-01

    The objective of the CRP (Coordinated Research Projekt) on the 'Performance of High Level Waste Forms and Packages under Repository Conditions' was to contribute to the development and implementation of proper and sound technologies for HLW and spent fuel management. Special emphasis was given to the identification of various waste form properties and the study of their long term durability in simulated repository conditions. Another objective was to promote the co-operation and exchange of information between Member States on experimental concerning behaviour of the waste form. The CRP was composed of research contracts and agreements with Argentina, Australia, Belgium, Canada, China, Czech Republic, Finland, France, Germany, India, Japan, Russia, and the United States of America. The publication includes 14 individual contributions of the participants to the CRP, which are indexed separately.

  6. FEBEX project: full-scale engineered barriers experiment for a deep geological repository for high level radioactive waste in crystalline host rock. Final report

    International Nuclear Information System (INIS)

    Alberdi, J.; Barcala, J. M.; Campos, R.; Cuevas, A. M.; Fernandez, E.

    2000-01-01

    FEBEX has the multiple objective of demonstrating the feasibility of manufacturing, handling and constructing the engineered barriers and of developing codes for the thermo-hydro-mechanical and thermo-hydro-geochemical performance assessment of a deep geological repository for high level radioactive wastes. These objectives require integrated theoretical and experimental development work. The experimental work consists of three parts: an in situ test, a mock-up test and a series of laboratory tests. The experiments is based on the Spanish reference concept for crystalline rock, in which the waste capsules are placed horizontally in drifts surround by high density compacted bentonite blocks. In the two large-scale tests, the thermal effects of the wastes were simulated by means of heaters; hydration was natural in the in situ test and controlled in the mock-up test. The large-scale tests, with their monitoring systems, have been in operation for more than two years. the demonstration has been achieved in the in situ test and there are great expectation that numerical models sufficiently validated for the near-field performance assessment will be achieved. (Author)

  7. FEBEX project: full-scale engineered barriers experiment for a deep geological repository for high level radioactive waste in crystalline host rock

    Energy Technology Data Exchange (ETDEWEB)

    Alberid, J; Barcala, J M; Campos, R; Cuevas, A M; Fernandez, E [Ciemat. Madrid (Spain)

    2000-07-01

    FEBEX has the multiple objective of demonstrating the feasibility of manufacturing, handling and constructing the engineered barriers and of developing codes for the thermo-hydro-mechanical and thermo-hydro-geochemical performance assessment of a deep geological repository for high level radioactive wastes. These objectives require integrated theoretical and experimental development work. The experimental work consists of three parts: an in situ test, a mock-up test and a series of laboratory tests. The experiments is based on the Spanish reference concept for crystalline rock, in which the waste capsules are placed horizontally in drifts surround by high density compacted bentonite blocks. In the two large-scale tests, the thermal effects of the wastes were simulated by means of heaters; hydration was natural in the in situ test and controlled in the mock-up test. The large-scale tests, with their monitoring systems, have been in operation for more than two years. the demonstration has been achieved in the in situ test and there are great expectation that numerical models sufficiently validated for the near-field performance assessment will be achieved. (Author)

  8. DECOVALEX III/BENCHPAR PROJECTS. Implications of Thermal-Hydro-Mechanical Coupling on the Near-Field Safety of a Nuclear Waste Repository in a Homogeneous Rock Mass. Report of BMT1B/WP2

    International Nuclear Information System (INIS)

    Jing, L.

    2005-02-01

    This report presents the works performed for the second phase (BMT1B) of BMT1 of the DECOVALEX III project for the period of 1999-2002. The works of BMT1 is divided into three phases: BMT1A, BMT1B and BMT1C. The BMT1A concerns with calibration of the computer codes with a reference T-H-M experiment at Kamaishi Mine, Japan. The objective is to validate the numerical approaches, computer codes and material models, so that the teams simulating tools are at a comparable level of maturity and sophistication. The BMT1B uses the calibrated codes to perform scoping calculations, considering varying degrees of THM coupling and varying permeability values of the surrounding rock for a reference generic repository design without fractures. The aim is to identify the coupling mechanisms of importance for construction, performance and safety of the repository. The chosen measures for evaluating the long term safety and performance of the repository are the maximal temperature created by the thermal loading from the emplaced wastes, the time for re-saturation of the buffer, the maximal swelling stress developed in the buffer, the structural integrity of the rock mass and the permeability evolution in the rock mass. Six teams participated in BMT1B: IRSN/CEA (France), CNSC (Canada), ANDRA/INERIS (France), JNC (Japan), BGR/ISEB-ZAG (Germany) and SKI/KTH (Sweden). All teams used FEM approach except the ANDRA/INERIS team who used the FDM approach, with different codes. All research teams except ISEB/ZAG used models with full THM coupling capabilities. The governing equations in these models were derived within the framework of Biot's theory of consolidation and have for primary unknown variables: temperature, pore fluid pressure and displacements of the solid skeleton. Since the original Biot's theory of consolidation is applicable to saturated materials and isothermal conditions, the research teams have to extend Biot's theory in order to deal with thermal effects and the variably

  9. DECOVALEX III/BENCHPAR PROJECTS. Implications of Thermal-Hydro-Mechanical Coupling on the Near-Field Safety of a Nuclear Waste Repository in a Homogeneous Rock Mass. Report of BMT1B/WP2

    Energy Technology Data Exchange (ETDEWEB)

    Jing, L. [Royal Inst. of Technology, Stockholm (Sweden). Engineering Geology; Nguyen, T.S. [Canadian Nuclear Safety Commission, Ottawa, ON (Canada)] (eds.)

    2005-02-15

    This report presents the works performed for the second phase (BMT1B) of BMT1 of the DECOVALEX III project for the period of 1999-2002. The works of BMT1 is divided into three phases: BMT1A, BMT1B and BMT1C. The BMT1A concerns with calibration of the computer codes with a reference T-H-M experiment at Kamaishi Mine, Japan. The objective is to validate the numerical approaches, computer codes and material models, so that the teams simulating tools are at a comparable level of maturity and sophistication. The BMT1B uses the calibrated codes to perform scoping calculations, considering varying degrees of THM coupling and varying permeability values of the surrounding rock for a reference generic repository design without fractures. The aim is to identify the coupling mechanisms of importance for construction, performance and safety of the repository. The chosen measures for evaluating the long term safety and performance of the repository are the maximal temperature created by the thermal loading from the emplaced wastes, the time for re-saturation of the buffer, the maximal swelling stress developed in the buffer, the structural integrity of the rock mass and the permeability evolution in the rock mass. Six teams participated in BMT1B: IRSN/CEA (France), CNSC (Canada), ANDRA/INERIS (France), JNC (Japan), BGR/ISEB-ZAG (Germany) and SKI/KTH (Sweden). All teams used FEM approach except the ANDRA/INERIS team who used the FDM approach, with different codes. All research teams except ISEB/ZAG used models with full THM coupling capabilities. The governing equations in these models were derived within the framework of Biot's theory of consolidation and have for primary unknown variables: temperature, pore fluid pressure and displacements of the solid skeleton. Since the original Biot's theory of consolidation is applicable to saturated materials and isothermal conditions, the research teams have to extend Biot's theory in order to deal with thermal effects and

  10. Environmental issues of repository licensing: an evaluation of a hypothetical high-level radioactive waste repository

    International Nuclear Information System (INIS)

    Owen, J.L.; McGinnis, J.T.; Harper, C.M.; Battelle Columbus Labs., OH)

    1982-01-01

    This paper presents results of an environmental assessment conducted under the direction of the Office of Nuclear Waste Isolation as part of the National Waste Terminal Storage program. The study defined a range of potential environmental effects of constructing, operating, decommissioning, and long-term isolation of a nuclear waste repository. The analytical methodology used to determine potential environmental effects required definition of a hypothetical environmental setting and repository. Potentially applicable regulatory requirements were identified and were used as guidelines to evaluate permitting feasibility. The environmental effects of repository development were analyzed for the two major time periods of concern: short term (the period of construction, operation, and decommissioning) and long term (the isolation period after decommissioning). As a result of this analysis, major environmental uncertainties and issues were identified. 11 references, 5 figures

  11. The industrial organization of the repository. Pitfall or logical?

    International Nuclear Information System (INIS)

    Frostenson, Magnus

    2010-11-01

    From a systems perspective the organization of the Swedish final repository project for nuclear waste is studied. Different aspects of organization are identified in the report, covering dimensions of geographical, operative, structural, responsibility and contextual organization. Following SKB's site selection for the applications for the final repository for spent nuclear system and the closing of the surplus value agreement, issues concerning operative, structural and contextual organization tend to become particularly pressing, which is reflected in three research questions: - How will the final repository project be organized operatively and structurally over time? - Why is the final repository project organized in this way by SKB? - What kind of contextual organization takes place in the final repository project and what are the consequences of these activities? How the different industrial units of the final repository project should be run and within which structure, for example concerning ownership and integration of units, is established in the report. SKB's reasons for choosing this kind of organization are also highlighted. Apart from legal and safety-related demands that must be met together with the demands of the owners, SKB's strategic preference for insourcing conditions organizational choices. The traditional task centred operative and structural organization of SKB is also reflected in the organizational choices for the present and future units of the final depository system. Contextual organization implies deepened actor relationships between SKB's owners and SKB on the one side and the municipalities Oesthammar and Oskarshamn on the other. Through active organizing, the final repository arena 'narrows down' and the final repository issue turns into an in many respects local issue. There is a clear tendency that the roles of SKB are multiplied in order to handle the demands that central stakeholders - in particular the municipalities - place on

  12. Socioeconomic impacts of repositories

    International Nuclear Information System (INIS)

    Thomas, J.K.; Hamm, R.R.; Murdock, S.H.

    1983-01-01

    Federal and state decision makers, community leaders, and residents must know how communities will be changed by the impacts of a high-level nuclear waste repository. This chapter identifies the factors affecting an assessment of socioeconomic impacts and the types of impacts (economic, demographic, fiscal, community service, and social) likely to occur as a result of repository development. Each of these types can be divided into standard (those which typically results from any large-scale development) and special impact categories (those which result from the fact that radioactive materials will be handled). 3 tables

  13. Safeguards for geological repositories

    International Nuclear Information System (INIS)

    Fattah, A.

    2000-01-01

    Direct disposal of spent nuclear fuel in geological repositories is a recognised option for closing nuclear fuel cycles. Geological repositories are at present in stages of development in a number of countries and are expected to be built and operated early next century. A State usually has an obligation to safely store any nuclear material, which is considered unsuitable to re-enter the nuclear fuel cycle, isolated from the biosphere. In conjunction with this, physical protection has to be accounted for to prevent inadvertent access to such material. In addition to these two criteria - which are fully under the State's jurisdiction - a third criterion reflecting international non-proliferation commitments needs to be addressed. Under comprehensive safeguards agreements a State concedes verification of nuclear material for safeguards purposes to the IAEA. The Agency can thus provide assurance to the international community that such nuclear material has been used for peaceful purposes only as declared by the State. It must be emphasised that all three criteria mentioned constitute a 'unit'. None can be sacrificed for the sake of the other, but compromises may have to be sought in order to make their combination as effective as possible. Based on comprehensive safeguards agreements signed and ratified by the State, safeguards can be terminated only when the material has been consumed or diluted in such a way that it can no longer be utilised for any nuclear activities or has become practicably irrecoverable. As such safeguards for nuclear material in geological repositories have to be continued even after the repository has been back-filled and sealed. The effective application of safeguards must assure continuity-of-knowledge that the nuclear material in the repository has not been diverted for an unknown purpose. The nuclear material disposed in a geological repository may eventually have a higher and long term proliferation risk because the inventory is

  14. Shaft barriers for underground waste repositories in abandoned salt mines. Preparatory project. Vol. 2. Annex; Schachtverschluesse fuer untertaegige Deponien in Salzbergwerken. Vorprojekt. Bd. 2. Anhang

    Energy Technology Data Exchange (ETDEWEB)

    Schmidt, M W [GSF - Forschungszentrum fuer Umwelt und Gesundheit, Remlingen (Germany). Forschungsbergwerk Asse; Fruth, R [GSF - Forschungszentrum fuer Umwelt und Gesundheit, Remlingen (Germany). Forschungsbergwerk Asse; Stockmann, N [GSF - Forschungszentrum fuer Umwelt und Gesundheit, Remlingen (Germany). Forschungsbergwerk Asse; Birthler, H [Gesellschaft fuer Anlagen- und Reaktorsicherheit mbH Greece, Braunschweig (Germany). Fachbereich Endlagersicherheitsforschung; Boese, B [Gesellschaft fuer Anlagen- und Reaktorsicherheit mbH Greece, Braunschweig (Germany). Fachbereich Endlagersicherheitsforschung; Storck, R [Gesellschaft fuer Anlagen- und Reaktorsicherheit mbH Greece, Braunschweig (Germany). Fachbereich Endlagersicherheitsforschung; Sitz, P [Technische Univ. Bergakademie Freiberg (Germany). Inst. fuer Bergbau; Krausse, A [Technische Univ. Bergakademie Freiberg (Germany). Inst. fuer Bergbau; Eulenberger, K H [Technische Univ. Bergakademie Freiberg (Germany). Inst. fuer Bergbau; Schleinig, J P [Technische Univ. Bergakademie Freiberg (Germany). Inst. fuer Bergbau; Duddeck, H [Technische Univ. Braunschweig (Germany). Inst. fuer Statik; Ahrens, H [Technische Univ. Braunschweig (Germany). Inst. fuer Statik; Menzel, W [IfG Inst. fuer Gebirgsmechanik GmbH, Leipzig (Germany); Salzer, K [IfG Inst. fuer Gebirgsmechanik GmbH, Leipzig (Germany); Minkley, W [IfG Inst. fuer Gebirgsmechanik GmbH, Leipzig (Germany); Busche, H [Kali und Salz AG, Kassel (Germany); Lindloff, U [Kali und Salz AG, Kassel (Germany); Gierenz, S [Kali und Salz AG, Kassel (Germany)

    1996-12-31

    This preparatory study, ``Shaft barriers for underground waste repositories in abandoned salt mines``, was to demonstrate the current scientific and technological know-how based on a comprehensive analysis of the barrier design concepts or established structures intended to serve as barriers in abandoned shafts of potash or rock salt mines. Taking as a basis the current regulatory regime and the available know-how on barrier systems in underground waste repositories taken into account so far in plan approval and licensing procedures, as well as the state of the art, concepts are developed as technical guides and models of barrier systems for mine shafts. The required research work for the various components of a shaft barrier is shown, particularly relating to aspects such as materials suitability and technical realisation. Immediate demand for research activities is shown with regard to the available potentials of mathematic and numeric geotechnical and hydrogeologic calculation models required in order to give proof of the long-term workability of shaft barriers. The authors are of the opinion that the following activities are required in order to meet the research demand quantified: (1) Laboratory and bench-scale experiments for determination of the efficiency of various sealing materials and backfilling materials, and (2) an in-situ, large-scale experiment in order to demonstrate the suitability of low-consolidation shotter columns, or constructional technologies. The laboratory work can be done in the facilities of the GSF research mine of Asse, the Freiburg Mining Academy, and the Institut fuer Gebirgsmechanik in Leipzig, and the benchmark experiments also at the Asse site in the research mine. The Kali und Salz Beteiligungs AG is prepared to offer its mine Salzdetfurth II as a site for the large-scale experiment. (orig.) [Deutsch] Im Rahmen der Vorstudie ``Schachtverschluesse fuer Untertagedeponien in Salzbergwerken`` wird ausgehend von einer umfangreichen

  15. Shaft barriers for underground waste repositories in abandoned salt mines. Preparatory project. Vol. 2. Annex; Schachtverschluesse fuer untertaegige Deponien in Salzbergwerken. Vorprojekt. Bd. 2. Anhang

    Energy Technology Data Exchange (ETDEWEB)

    Schmidt, M.W. [GSF - Forschungszentrum fuer Umwelt und Gesundheit, Remlingen (Germany). Forschungsbergwerk Asse; Fruth, R. [GSF - Forschungszentrum fuer Umwelt und Gesundheit, Remlingen (Germany). Forschungsbergwerk Asse; Stockmann, N. [GSF - Forschungszentrum fuer Umwelt und Gesundheit, Remlingen (Germany). Forschungsbergwerk Asse; Birthler, H. [Gesellschaft fuer Anlagen- und Reaktorsicherheit mbH Greece, Braunschweig (Germany). Fachbereich Endlagersicherheitsforschung; Boese, B. [Gesellschaft fuer Anlagen- und Reaktorsicherheit mbH Greece, Braunschweig (Germany). Fachbereich Endlagersicherheitsforschung; Storck, R. [Gesellschaft fuer Anlagen- und Reaktorsicherheit mbH Greece, Braunschweig (Germany). Fachbereich Endlagersicherheitsforschung; Sitz, P. [Technische Univ. Bergakademie Freiberg (Germany). Inst. fuer Bergbau; Krausse, A. [Technische Univ. Bergakademie Freiberg (Germany). Inst. fuer Bergbau; Eulenberger, K.H. [Technische Univ. Bergakademie Freiberg (Germany). Inst. fuer Bergbau; Schleinig, J.P. [Technische Univ. Bergakademie Freiberg (Germany). Inst. fuer Bergbau; Duddeck, H. [Technische Univ. Braunschweig (Germany). Inst. fuer Statik; Ahrens, H. [Technische Univ. Braunschweig (Germany). Inst. fuer Statik; Menzel, W. [IfG Inst. fuer Gebirgsmechanik GmbH, Leipzig (Germany); Salzer, K. [IfG Inst. fuer Gebirgsmechanik GmbH, Leipzig (Germany); Minkley, W. [IfG Inst. fuer Gebirgsmechanik GmbH, Leipzig (Germany); Busche, H. [Kali und Salz AG, Kassel (Germany); Lindloff, U. [Kali und Salz AG, Kassel (Germany); Gierenz, S. [Kali und Salz AG, Kassel (Germany)

    1995-12-31

    This preparatory study, ``Shaft barriers for underground waste repositories in abandoned salt mines``, was to demonstrate the current scientific and technological know-how based on a comprehensive analysis of the barrier design concepts or established structures intended to serve as barriers in abandoned shafts of potash or rock salt mines. Taking as a basis the current regulatory regime and the available know-how on barrier systems in underground waste repositories taken into account so far in plan approval and licensing procedures, as well as the state of the art, concepts are developed as technical guides and models of barrier systems for mine shafts. The required research work for the various components of a shaft barrier is shown, particularly relating to aspects such as materials suitability and technical realisation. Immediate demand for research activities is shown with regard to the available potentials of mathematic and numeric geotechnical and hydrogeologic calculation models required in order to give proof of the long-term workability of shaft barriers. The authors are of the opinion that the following activities are required in order to meet the research demand quantified: (1) Laboratory and bench-scale experiments for determination of the efficiency of various sealing materials and backfilling materials, and (2) an in-situ, large-scale experiment in order to demonstrate the suitability of low-consolidation shotter columns, or constructional technologies. The laboratory work can be done in the facilities of the GSF research mine of Asse, the Freiburg Mining Academy, and the Institut fuer Gebirgsmechanik in Leipzig, and the benchmark experiments also at the Asse site in the research mine. The Kali und Salz Beteiligungs AG is prepared to offer its mine Salzdetfurth II as a site for the large-scale experiment. (orig.) [Deutsch] Im Rahmen der Vorstudie ``Schachtverschluesse fuer Untertagedeponien in Salzbergwerken`` wird ausgehend von einer umfangreichen

  16. Progress in evaluation of radionuclide geochemical information developed by DOE high-level nuclear waste repository site projects: Report for April 1986-September 1987

    International Nuclear Information System (INIS)

    Meyer, R.E.; Arnold, W.D.; Blencoe, J.G.; O'Kelley, G.D.; Land, J.F.

    1988-02-01

    Experiments were conducted with tuff from the proposed high-level nuclear waste site at Yucca Mountain, Nevada. Batch sorption ratio determinations were conducted for strontium, cesium, uranium, and technetium onto samples of tuff using real and synthetic groundwater J-13. There were no significant differences in sorption ratios in experiments with real and synthetic groundwater. Columns 1 cm in diameter and about 5 cm long were constructed, and experiments were conducted with the objective of correlating the results of batch and the column experiments. The characteristics of the columns were tested by determination of elution curves in J-13 containing tritium and technetium as the TcO 4 - ion. For strontium and cesium, fairly good correlation between values of the sorption ratio obtained by the two methods was observed. Little or no technetium sorption was observed with either method. The elution peaks obtained with neptunium and uranium were asymmetrical and the shapes were often complex, observations which suggest irreversibilities in the sorption reaction. An experiment was performed to provide information on the compositions of the first groundwaters that will contact waste canisters in a tuff-hosted repository after very near field temperatures have cooled to below 100/degree/C. Synthetic groundwater J-13 was slowly dripped onto a slab of tuff maintained at 95-100/degree/C, and the result was a thin encrustation of solids on the slab as the water evaporated. Fresh J-13 groundwater was then allowed to contact the encrustation in a vessel maintained at 90/degree/C. The principal result of the experiment was a significant loss of calcium and magnesium from the fresh J-13 groundwater

  17. The Challenges of Integrating NASA's Human, Budget, and Data Capital within the Constellation Program's Exploration Launch Projects Office

    Science.gov (United States)

    Kidd, Luanne; Morris, Kenneth B.; Self, Timothy A.

    2007-01-01

    The U.S. Vision for Space Exploration directs NASA to retire the Space Shuttle in 2010 and replace it with safe, reliable, and cost-effective space transportation systems for crew and cargo travel to the Moon, Mars, and beyond. Such emerging space transportation initiatives face massive organizational challenges, including building and nurturing an experienced, dedicated team with the right skills for the required tasks; allocating and tracking the fiscal capital invested in achieving technical progress against an integrated master schedule; and turning generated data into useful knowledge that equips the team to design and develop superior products for customers and stakeholders. It has been more than 30 years since the Space Shuttle was designed; therefore, the current aerospace workforce has limited experience with developing new designs for human-rated spaceflight hardware. To accomplish these activities, NASA is using a wide range of state-of-the-art information technology tools that connect its diverse, decentralized teams and provide timely, accurate information for decision makers. In addition, business professionals are assisting technical managers with planning, tracking, and forecasting resource use against an integrated master schedule that horizontally and vertically interlinks hardware elements and milestone events. Furthermore, NASA is employing a wide variety of strategies to ensure that it has the motivated and qualified staff it needs for the tasks ahead. This paper discusses how NASA's Exploration Launch Projects Office, which is responsible for delivering these new launch vehicles, integrates its resources to create an engineering business environment that promotes mission success, which is defined by replacing the Space Shuttle by 2014 and returning to the Moon by 2020.

  18. Investigation on waste disposal in big boreholes. Project 'Second phase of the assessment of the repository at Novaya Zemlya'. Final report - short version

    International Nuclear Information System (INIS)

    2003-12-01

    This report contains the independent view of experts from SKB (Sweden), DBE TECHNOLOGY (Germany) and Institute for Energy Technology (Norway) and is the result of a project performed under a contract funded by the Norwegian Royal Ministry of Foreign Affairs, Swedish International Projects, the Project Unit for radioactive waste disposal of the German Federal Ministry of Economics and Employment and the German Federal Ministry of Ecology, Nature Preservation and Reactor Safety. The work has been carried out in cooperation with VNIPI PT (Russian Federation). The authors of this report accept no liability that arises from the use of material in this report, relating either to nuclear or civil issues. Any publishing or copying of the report in whole or in part requires the explicit approval of the mentioned funding parties. This report has been approved for issue according to the requirements of the project QA procedure. (orig.)

  19. DigitalHub: A Repository Focused on the Future.

    Science.gov (United States)

    Ilik, Violeta; Hebal, Piotr; Olson, Anton; Wishnetsky, Susan; Pastva, Joelen; Kubilius, Ramune; Shank, Jonathan; Gutzman, Karen; Chung, Margarita; Holmes, Kristi

    2018-01-01

    The DigitalHub scholarly repository was developed and launched at the Galter Health Sciences Library for the Feinberg School of Medicine and the greater Northwestern Medicine community. The repository was designed to allow scholars the ability to create, share, and preserve a range of citable digital outputs. This article traces the evolution of DigitalHub's development and engagement activities, highlighting project challenges, innovations, success stories, and the team-based approach that was employed to successfully achieve project goals.

  20. Process model repositories and PNML

    NARCIS (Netherlands)

    Hee, van K.M.; Post, R.D.J.; Somers, L.J.A.M.; Werf, van der J.M.E.M.; Kindler, E.

    2004-01-01

    Bringing system and process models together in repositories facilitates the interchange of model information between modelling tools, and allows the combination and interlinking of complementary models. Petriweb is a web application for managing such repositories. It supports hierarchical process

  1. CRIS and Institutional Repositories

    Directory of Open Access Journals (Sweden)

    A Asserson

    2010-04-01

    Full Text Available CRIS (Current Research Information Systems provide researchers, research managers, innovators, and others with a view over the research activity of a domain. IRs (institutional repositories provide a mechanism for an organisation to showcase through OA (open access its intellectual property. Increasingly, organizations are mandating that their employed researchers deposit peer-reviewed published material in the IR. Research funders are increasingly mandating that publications be deposited in an open access repository: some mandate a central (or subject-based repository, some an IR. In parallel, publishers are offering OA but replacing subscription-based access with author (or author institution payment for publishing. However, many OA repositories have metadata based on DC (Dublin Core which is inadequate; a CERIF (Common-European Research Information Format CRIS provides metadata describing publications with formal syntax and declared semantics thus facilitating interoperation or homogeneous access over heterogeneous sources. The formality is essential for research output metrics, which are increasingly being used to determine future funding for research organizations.

  2. Salt repository design approach

    International Nuclear Information System (INIS)

    Matthews, S.C.

    1983-01-01

    This paper presents a summary discussion of the approaches that have been and will be taken in design of repository facilities for use with disposal of radioactive wastes in salt formations. Since specific sites have yet to be identified, the discussion is at a general level, supplemented with illustrative examples where appropriate. 5 references, 1 figure

  3. Repository site characterization

    International Nuclear Information System (INIS)

    Voss, J.W.; Pentz, D.L.

    1987-01-01

    The characterization of candidate repository sites has a number of programmatic objectives. Principal among these is the acquisition of data: a) to determine the suitability of a site relative to the DOE repository siting guidelines, b) to support model development and calculations to determine the suitability of a site relative to the post closure criteria of the NRC and EPA, c) to support the design of a disposal system, including the waste package and the engineered barrier system, as well as the shafts and underground openings of the repository. In meeting the gaols of site characterization, the authors have an obligation to conduct their investigations within an appropriate budget and schedule. This mandates that a well-constructed and systematic plan for field investigations be developed. Such a plan must fully account for the mechanisms which will control the radiologic performance in the repository. The plan must also flexibly and dynamically respond to the results of each step of field investigation, responding to the spatial variability of earth as well as to enhanced understandings of the performance of the disposal system. Such a plan must ensure that sufficient data are available to support the necessary probabilistic calculations of performance. This paper explores the planning for field data acquisition with specific reference to requirements for demonstrations of the acceptable performance for disposal systems

  4. Radioactive waste repository study

    International Nuclear Information System (INIS)

    1978-11-01

    This is the third part of a report of a preliminary study for AECL. It summarizes the topics considered in reports AECL-6188-1 and AECL-6188-2 as requirements for an undergpound repository for disposal of wastes produced by the Canadian Nuclear Fuel Program. (author)

  5. Computational Materials Repository

    DEFF Research Database (Denmark)

    Landis, David

    , different abstraction levels and enables users to analyze their own results, and allows to share data with collaborators. The approach of the Computational Materials Repository (CMR) is to convert data to an internal format that maintains the original variable names without insisting on any semantics...

  6. The Computational Materials Repository

    DEFF Research Database (Denmark)

    Landis, David D.; Hummelshøj, Jens S.; Nestorov, Svetlozar

    2012-01-01

    The possibilities for designing new materials based on quantum physics calculations are rapidly growing, but these design efforts lead to a significant increase in the amount of computational data created. The Computational Materials Repository (CMR) addresses this data challenge and provides...

  7. Can an ethics officer role reduce delays in research ethics approval? A mixed-method evaluation of an improvement project

    Science.gov (United States)

    Dixon-Woods, Mary; Foy, Chris; Hayden, Charlotte; Al-Shahi Salman, Rustam; Tebbutt, Stephen; Schroter, Sara

    2016-01-01

    Objective Frustration continues to be directed at delays in gaining approvals for undertaking health research in the UK. We aimed to evaluate the impact of an ethics officer intervention on rates of favourable opinions (approval) and provisional opinions (requiring revision and resubmission) and on the time taken to reach a final opinion by research ethics committees (RECs), to characterise how the role operated in practice, and to investigate applicants' views. Design Mixed-method study involving (i) a 2-group, non-randomised before-and-after intervention study of RECs assigned an ethics officer and a matched comparator group; (ii) a process evaluation involving a survey of applicants and documentary analysis. Participants 6 RECs and 3 associated ethics officers; 18 comparator RECs; REC applicants. Results Rates of provisional and favourable opinions between ethics officer and comparator RECs did not show a statistically significant effect of the intervention (logistic regression, p=0.26 for favourable opinions and p=0.31 for provisional opinions). Mean time to reach a decision showed a non-significant reduction (ANOVA, p=0.22) from 33.3 to 32.0 days in the ethics officer RECs compared with the comparator RECs (32.6 to 32.9 days). The survey (30% response rate) indicated applicant satisfaction and also suggested that ethics officer support might be more useful before submission. Ethics officers were successful in identifying many issues with applications, but the intervention did not function exactly as designed: in 31% of applicants, no contact between the applicants and the ethics officer took place before REC review. Limitations This study was a non-randomised comparison cohort study. Some data were missing. Conclusions An ethics officer intervention, as designed and implemented in this study, did not increase the proportion of applications to RECs that were approved on first review and did not reduce the time to a committee decision. PMID:27580832

  8. Consortial routes to effective repositories

    OpenAIRE

    Moyle, M.; Proudfoot, R.

    2009-01-01

    A consortial approach to the establishment of repository services can help a group of Higher Education Institutions (HEIs) to share costs, share technology and share expertise. Consortial repository work can tap into existing structures, or it can involve new groupings of institutions with a common interest in exploring repository development. This Briefing Paper outlines some of the potential benefits of collaborative repository activity, and highlights some of the technical and organisation...

  9. Repository Technology Program: Technical progress report for the period May 29, 1986--June 30, 1987

    International Nuclear Information System (INIS)

    1988-10-01

    This document reports the progress made in the 13-month period from May 29, 1986--June 30, 1987, on the development of a second geologic repository in rocks other than those being considered for a first repository. Subsequent periods will be covered in reports to be issued on a semiannual basis. The reporting elements are arranged by the work breakdown structure so that related studies are presented together. The studies are reported by the Office of Waste Technology Development (OWTD), a prime contractor of the US. Department of Energy (DOE) Repository Technology Program (RTP) Office in the Repository Technology and Transportation Division (RTTD) of the Office of Geologic Repositories (OGR). The studies include work by other DOE prime contractors and by contractors to the OWTD. 50 refs

  10. Scotts Valley Energy Office and Human Capacity Building that will provide energy-efficiency services and develop sustainable renewable energy projects.

    Energy Technology Data Exchange (ETDEWEB)

    Anderson, Temashio [Scotts Valley Band of Pomo Indians

    2013-06-28

    The primary goal of this project is to develop a Scotts Valley Energy Development Office (SVEDO). This office will further support the mission of the Tribe's existing leadership position as the DOE Tribal Multi-County Weatherization Energy Program (TMCWEP) in creating jobs and providing tribal homes and buildings with weatherization assistance to increase energy efficiency, occupant comfort and improved indoor air quality. This office will also spearhead efforts to move the Tribe towards its further strategic energy goals of implementing renewable energy systems through specific training, resource evaluation, feasibility planning, and implementation. Human capacity building and continuing operations are two key elements of the SVEDO objectives. Therefore, the project will 1) train and employ additional Tribal members in energy efficiency, conservation and renewable resource analyses and implementation; 2) purchase materials and equipment required to implement the strategic priorities as developed by the Scotts Valley Tribe which specifically include implementing energy conservation measures and alternative energy strategies to reduce energy costs for the Tribe and its members; and 3) obtain a dedicated office and storage space for ongoing SVEDO operations.

  11. Secured web-based video repository for multicenter studies.

    Science.gov (United States)

    Yan, Ling; Hicks, Matt; Winslow, Korey; Comella, Cynthia; Ludlow, Christy; Jinnah, H A; Rosen, Ami R; Wright, Laura; Galpern, Wendy R; Perlmutter, Joel S

    2015-04-01

    We developed a novel secured web-based dystonia video repository for the Dystonia Coalition, part of the Rare Disease Clinical Research network funded by the Office of Rare Diseases Research and the National Institute of Neurological Disorders and Stroke. A critical component of phenotypic data collection for all projects of the Dystonia Coalition includes a standardized video of each participant. We now describe our method for collecting, serving and securing these videos that is widely applicable to other studies. Each recruiting site uploads standardized videos to a centralized secured server for processing to permit website posting. The streaming technology used to view the videos from the website does not allow downloading of video files. With appropriate institutional review board approval and agreement with the hosting institution, users can search and view selected videos on the website using customizable, permissions-based access that maintains security yet facilitates research and quality control. This approach provides a convenient platform for researchers across institutions to evaluate and analyze shared video data. We have applied this methodology for quality control, confirmation of diagnoses, validation of rating scales, and implementation of new research projects. We believe our system can be a model for similar projects that require access to common video resources. Copyright © 2015 Elsevier Ltd. All rights reserved.

  12. The German quality system for waste repositories

    International Nuclear Information System (INIS)

    Beckmerhagen, I.; Berg, H.P.; Brennecke, P.

    1993-01-01

    The Bundesamt fuer Strahlenschutz (BfS)--Federal Office for Radiation protection--has to guarantee that the requirements resulting from different regulations concerning planning, design, construction, operation and decommissioning of a waste repository are fulfilled. In addition, the results of the safety assessments lead to nuclear-specific requirements on the design of the plant as well as to requirements on the radioactive waste packages intended to be disposed of. Therefore, the implementation of a quality assurance (QA) and quality control (QC) system is an essential task in order to ensure that the designed quality is achieved so that the necessary precaution against damage is taken. In this paper, a detailed description of QA and QC to be applied to the planned Konrad repository as well as the basic principles and the present status of the waste package QC are indicated and discussed

  13. Industrial complementarities between interim storage and reversible geological repository - 59237

    International Nuclear Information System (INIS)

    Hoorelbeke, Jean-Michel

    2012-01-01

    The French Act voted in 2006 made the choice of deep geological disposal as the reference option for the long term management of high level (HLW) and intermediate level long-lived waste. The CIGEO repository project aims at avoiding or limiting burden to future generations, which could not be achieved by the extension in time of interim storage. The reversibility as provided by the Act will maintain a liberty of choice for waste management on a duration which is comparable to new storage facility. Interim storage is required to accommodate waste as long as the repository is not available. The commissioning of the repository in 2025 will not suppress needs for interim storage. The paper describes the complementarities between existing and future interim storage facilities and the repository project: repository operational issues and planning, HLW thermal decay, support for the reversibility, etc. It shows opportunities to prepare a global optimization of waste management including the utilization at best of storage capacities and the planning of waste emplacement in the repository in such a way to facilitate operational conditions and to limit cost. Preliminary simulations of storage-disposal scenarios are presented. Thanks to an optimal use of the waste management system, provision can be made for a progressive increase of waste emplacement flow during the first operation phase of the repository. It is then possible to stabilize the industrial activity level of the repository site. An optimal utilization of interim storage can also limit the diversity of waste packages emplaced simultaneously, which facilitates the operation of the repository. 60 years minimum interim storage duration is generally required with respect to HLW thermal output. Extending this interim storage period may reduce the underground footprint of the repository. Regarding reversibility, the capability to manage waste packages potentially retrieved from the repository should be analyzed. The

  14. Physics and chemistry of the transition of glass to authigenic minerals: State of Nevada, agency for nuclear projects/nuclear waste project office

    International Nuclear Information System (INIS)

    Morgenstein, M.E.

    1984-11-01

    The purpose of this paper is to provide a basic review of the topic of volcanic-glass hydration and the diagenetic formation of authigenic minerals from the hydrated-glass products. The Yucca Mountain Draft Environmental Assessment (DEA) of December 1984 indicates that: most of the available glass in the proximity of the repository horizon has been already hydrated and authigenic minerals which could form have already done so, zeolites could form from as yet unreacted glass during transport of water exiting from the repository, and the zeolites and other authigenic minerals provide sorptive barriers to radionuclide migration. This document surveys the available literature and concludes that the topic appears more complex than as it is treated in the DEA. It is concluded that an insufficient quantity of raw data exists. This paucity of information does not allow the determination of which authigenic minerals (if any) may form from the alteration of volcanic glass in Yucca Mountain; and consequently, radionuclide retardation leading from this reaction process is undeterminable. Appendix A and B contain a critical review of this publication. 29 refs., 6 tabs

  15. Preliminary postclosure risk assessment: Yucca Mountain, Nevada, candidate repository site

    International Nuclear Information System (INIS)

    Eslinger, P.W.; Elwood, D.M.; Freshley, M.D.; Reimus, P.W.; Tanner, J.E.; Doctor, P.G.; Engel, D.W.; Liebetrau, A.M.; Strenge, D.L.; Van Luik, A.E.

    1989-10-01

    A study was conducted by the Pacific Northwest Laboratory for the US Department of Energy, Office of Civilian Radioactive Waste Management, to estimate the postclosure risk, in terms of population health effects, of a proposed high-level nuclear waste repository at Yucca Mountain, Nevada. The risk estimates cover a time span of 1 million years following repository closure. Representative disruptive and intrusive events were selected and evaluated in addition to expected conditions. The estimates were generated assuming spent fuel as the waste form and included all important nuclides from inventory, half-life and dose perspectives. The base case results yield an estimate of 36 health effects over the first million years of repository operation. The doses attributed to the repository corresponds to about 0.1 percent of the doses received from natural background radiation. 16 refs., 1 fig

  16. Building the repositories to serve

    International Nuclear Information System (INIS)

    Lersch, D.

    1994-01-01

    The project to design and build the Superconducting Super Collider (SSC) Laboratory also includes the exciting opportunity to implement client/server information systems. Lab technologists were eager to take advantage of the cost savings inherent in the open systems and a distributed, client server environment and, at the same time, conscious of the need to provide secure repositories for sensitive data as well as a schedule sensitive acquisition strategy for mission critical software. During the first year of project activity, micro-based project management and business support systems were acquired and implemented to support a small study project of less than 400 people allocating contracts of less than $1 million. The transition to modern business systems capable of supporting more than 10,000 participants (world wide) who would be researching and developing the new technologies that would support the world's largest scientific instrument, a 42 Tevatron, superconducting, super collider became a mission critical event. This paper will present the SSC Laboratory's strategy to balance its commitment to open systems, structured query language (SQL) standards and its success with acquiring commercial off the shelf software to support immediate goals. Included will be an outline of the vital roles played by other labs (Livermore, CERN, Brookhaven, Fermi and others) and a discussion of future collaboration potentials to leverage the information activities of all Department of Energy funded labs

  17. Building the repositories to serve

    International Nuclear Information System (INIS)

    Lersch, D.

    1993-04-01

    The project to design and build the Superconducting Super Collider (SSC) Laboratory also includes the exciting opportunity to implement client/server information systems. Lab technologists were eager to take advantage of the cost savings inherent in the open systems and a distributed, client server environment and, at the same time, conscious of the need to provide secure repositories for sensitive data as well as a schedule sensitive acquisition strategy for mission critical software. During the first year of project activity, micro-based project management and business support systems were acquired and implemented to support a small study project of less than 400 people allocating contracts of less than $1 million. The transition to modern business systems capable of supporting more than 10,000 participants (world wide) who would be researching and developing the new technologies that would support the world's largest scientific instrument, a 42 Tevatron, superconducting, super collider became a mission critical event. This paper will present the SSC Laboratory's strategy to balance our commitment to open systems, structured query language (SQL) standards and our success with acquiring commercial off the shelf software (COTS) to support our immediate goals. Included will be an outline of the vital roles played by other labs (Livermore, CERN, Brookhaven, Fermi and others) and a discussion of future collaboration potentials to leverage the information activities of all Department of Energy (DOE) funded labs

  18. Project Opalinus Clay: Radionuclide Concentration Limits in the Near-Field of a Repository for Spent Fuel and Vitrified High-Level Waste

    Energy Technology Data Exchange (ETDEWEB)

    Berner, U

    2002-10-01

    The disposal feasibility study currently performed by Nagra includes a succession of quantitative models, aiming at describing the fate of radionuclides potentially escaping from the repository system. In this chain of models the present report provides the so called 'solubility limits' (maximum expected concentrations) for safety relevant radionuclides from SF/HLW wastes, disposed of in a reducing clay (Opalinus Clay, bentonite) environment. Solubility and speciation calculations in bentonite pore waters were performed using the very recently updated Nagra/PSI Chemical Thermodynamic Data Base (TDB) for the majority of the 37 elements addressed as potentially relevant. Particularly for the most relevant actinides, the straightforward applications with this updated TDB yielded results in contradiction to chemical analogy considerations. This was a consequence of incomplete data and called for problem specific TDB extensions, which were evaluated in a separate study. However, a summary of these problem specific extensions is provided in section 4.1. The results presented in this report solely depend on geochemical model calculations. Thus, it is of utmost importance that the underlying data and assumptions are made clear to the reader. In order to ensure traceability, all thermodynamic data not included in the Nagra/PSI TDB are explicitly specified in the report, in order to provide complete documentation for quality assurance and for comprehensibility. In order to clearly distinguish between results derived from data carefully reviewed in the Nagra/PSI TDB and those calculated from 'other' data, the summary of expected maximum concentrations provided in Table 1 includes two columns. The heading CALCULATED provides maximum concentrations based on data fully documented in the updated TDB, whereas maximum concentrations, which include additional problem specific data and/or data from other sources, are given under the heading RECOMMENDED. The

  19. Project Opalinus Clay: Radionuclide Concentration Limits in the Near-Field of a Repository for Spent Fuel and Vitrified High-Level Waste

    International Nuclear Information System (INIS)

    Berner, U.

    2002-10-01

    The disposal feasibility study currently performed by Nagra includes a succession of quantitative models, aiming at describing the fate of radionuclides potentially escaping from the repository system. In this chain of models the present report provides the so called 'solubility limits' (maximum expected concentrations) for safety relevant radionuclides from SF/HLW wastes, disposed of in a reducing clay (Opalinus Clay, bentonite) environment. Solubility and speciation calculations in bentonite pore waters were performed using the very recently updated Nagra/PSI Chemical Thermodynamic Data Base (TDB) for the majority of the 37 elements addressed as potentially relevant. Particularly for the most relevant actinides, the straightforward applications with this updated TDB yielded results in contradiction to chemical analogy considerations. This was a consequence of incomplete data and called for problem specific TDB extensions, which were evaluated in a separate study. However, a summary of these problem specific extensions is provided in section 4.1. The results presented in this report solely depend on geochemical model calculations. Thus, it is of utmost importance that the underlying data and assumptions are made clear to the reader. In order to ensure traceability, all thermodynamic data not included in the Nagra/PSI TDB are explicitly specified in the report, in order to provide complete documentation for quality assurance and for comprehensibility. In order to clearly distinguish between results derived from data carefully reviewed in the Nagra/PSI TDB and those calculated from 'other' data, the summary of expected maximum concentrations provided in Table 1 includes two columns. The heading CALCULATED provides maximum concentrations based on data fully documented in the updated TDB, whereas maximum concentrations, which include additional problem specific data and/or data from other sources, are given under the heading RECOMMENDED. The present study also pays

  20. Archaeological survey and monitoring of initial excavations within the basalt waste isolation project reference repository location and associated drill borehole site locations

    International Nuclear Information System (INIS)

    McCarthy, M.M.

    1984-01-01

    This letter report concerns cultural resources studies undertaken in November 1982 for the exploratory shaft starter hole and surface facilities for the Basalt Waste Isolation Project (BWIP). These studies were carried out under the provisions of the National Environmental Policy Act, the amended National Historic Preservation Act, and the Archaeological Resources Act. This report concludes that neither cultural nor palentological resources are being affected by the BWIP during the present phase of construction work and test drilling. 4 refs., 10 figs

  1. Geochemical modeling (EQ3/6) plan: Office of Civilian Radioactive Waste Management Program

    International Nuclear Information System (INIS)

    McKenzie, W.F.; Wolery, T.J.; Delany, J.M.; Silva, R.J.; Jackson, K.J.; Bourcier, W.L.; Emerson, D.O.

    1986-01-01

    This plan replaces an earlier plan for the Nevada Nuclear Waste Storage Investigations (NNWSI) Project. It includes activities for all repository projects in the Office of Geologic Repositories: NNWSI, the Basalt Waste Isolation Project, the Salt Repository Project, and the Crystalline Project. Each of these projects is part of the Office of Civilian Radioactive Waste Management (OCRWM) Program. The scope of work for fiscal years 1986 to 1992 includes the work required to upgrade the geochemical codes and supporting data bases, to permit modeling of chemical processes associated with nuclear waste repositories in four geological environments: tuff, salt, basalt, and crystalline rock. Planned tasks include theoretical studies and code development to take account of the effects of precipitation kinetics, sorption, solid solutions, glass/water interactions, variable gas fugacities, and simple mass transport. Recent progress has been made in the ability of the codes to account for precipitation kinetics, highly-saline solutions, and solid solutions. Transition state theory was re-examined resulting in new insights that will provide the foundation for further improvements necessary to model chemical kinetics. Currently there is an increased effort that is concentrated on the supporting data base. For aqueous species and solid phases, specific to nuclear waste, requisite thermodynamic values reported in the literature are being evaluated and for cases where essential data is lacking, laboratory measurements will be carried out. Significant modifications and expansions have been made to the data base. During FY86, the total number of species in the data base has almost doubled and many improvements have been made with regard to consistency, organization, user applications, and documentation. Two Ridge computers using a RISC implementation of UNIX were installed; they are completely dedicated EQ3/6 machines

  2. Geochemical modeling (EQ3/6) plan: Office of Civilian Radioactive Waste Management Program

    Energy Technology Data Exchange (ETDEWEB)

    McKenzie, W.F.; Wolery, T.J.; Delany, J.M.; Silva, R.J.; Jackson, K.J.; Bourcier, W.L.; Emerson, D.O.

    1986-08-28

    This plan replaces an earlier plan for the Nevada Nuclear Waste Storage Investigations (NNWSI) Project. It includes activities for all repository projects in the Office of Geologic Repositories: NNWSI, the Basalt Waste Isolation Project, the Salt Repository Project, and the Crystalline Project. Each of these projects is part of the Office of Civilian Radioactive Waste Management (OCRWM) Program. The scope of work for fiscal years 1986 to 1992 includes the work required to upgrade the geochemical codes and supporting data bases, to permit modeling of chemical processes associated with nuclear waste repositories in four geological environments: tuff, salt, basalt, and crystalline rock. Planned tasks include theoretical studies and code development to take account of the effects of precipitation kinetics, sorption, solid solutions, glass/water interactions, variable gas fugacities, and simple mass transport. Recent progress has been made in the ability of the codes to account for precipitation kinetics, highly-saline solutions, and solid solutions. Transition state theory was re-examined resulting in new insights that will provide the foundation for further improvements necessary to model chemical kinetics. Currently there is an increased effort that is concentrated on the supporting data base. For aqueous species and solid phases, specific to nuclear waste, requisite thermodynamic values reported in the literature are being evaluated and for cases where essential data is lacking, laboratory measurements will be carried out. Significant modifications and expansions have been made to the data base. During FY86, the total number of species in the data base has almost doubled and many improvements have been made with regard to consistency, organization, user applications, and documentation. Two Ridge computers using a RISC implementation of UNIX were installed; they are completely dedicated EQ3/6 machines.

  3. Continuing Science and Technology at the Proposed Yucca Mountain Repository

    International Nuclear Information System (INIS)

    Finch, R.J.

    2005-01-01

    Yucca Mountain, Nevada, was designated in 2002 to be the site for the nation's first permanent geological repository for spent nuclear fuel and high-level radioactive waste. The process of selecting a site for the repository began nearly 25 years ago with passage of the Nuclear Waste Policy Act in 1982. The Department of Energy (DOE) is responsible for submitting a license application to the Nuclear Regulatory Commission for constructing and operating the repository, and DOE's Office of Civilian Radioactive Waste Management (OCRWM) is charged with carrying out this action. The use of multiple natural and engineered barriers in the current repository design are considered by OCRWM to be sufficiently robust to warrant license approval; however, potential design enhancements and increased understanding of both natural and engineered barriers, especially over the long time frames during which the waste is to remain isolated from human contact continue to be examined. The Office of Science and Technology and International (OST andI) was created within OCRWM to help explore novel technologies that might lower overall costs and to develop a greater understanding of processes relevant to the long-term performance of the repository. A brief overview of Yucca Mountain, and the role that OST andI has in identifying technological or scientific advances that could make repository operations more efficient or performance more robust, will be presented. It is important to note, however, that adopting any of OST andI's technological or scientific developments will be at the discretion of OCRWM's Office of Repository Development (ORD)

  4. DECOVALEX III/BENCHPAR PROJECTS. Approaches to Upscaling Thermal-Hydro-Mechanical Processes in a Fractured Rock. Mass and its Significance for Large-Scale Repository Performance Assessment. Summary of Findings. Report of BMT2/WP3

    International Nuclear Information System (INIS)

    Andersson, Johan; Staub, Isabelle; Knight, Les

    2005-02-01

    The Benchmark Test 2 of DECOVALEX III and Work Package 3 of BENCHPAR concerns the upscaling Thermal (T), Hydrological (H) and Mechanical (M) processes in a fractured rock mass and its significance for large-scale repository performance assessment. The work is primarily concerned with the extent to which various thermo-hydro-mechanical couplings in a fractured rock mass adjacent to a repository are significant in terms of solute transport typically calculated in large-scale repository performance assessments. Since the presence of even quite small fractures may control the hydraulic, mechanical and coupled hydromechanical behaviour of the rock mass, a key of the work has been to explore the extent to which these can be upscaled and represented by 'equivalent' continuum properties appropriate PA calculations. From these general aims the BMT was set-up as a numerical study of a large scale reference problem. Analysing this reference problem should: help explore how different means of simplifying the geometrical detail of a site, with its implications on model parameters, ('upscaling') impacts model predictions of relevance to repository performance, explore to what extent the THM-coupling needs to be considered in relation to PA-measures, compare the uncertainties in upscaling (both to uncertainty on how to upscale or uncertainty that arises due to the upscaling processes) and consideration of THM couplings with the inherent uncertainty and spatial variability of the site specific data. Furthermore, it has been an essential component of the work that individual teams not only produce numerical results but are forced to make their own judgements and to provide the proper justification for their conclusions based on their analysis. It should also be understood that conclusions drawn will partly be specific to the problem analysed, in particular as it mainly concerns a 2D application. This means that specific conclusions may have limited applicability to real problems in

  5. DECOVALEX III III/BENCHPAR PROJECTS. Approaches to Upscaling Thermal-Hydro-Mechanical Processes in a Fractured Rock. Mass and its Significance for Large-Scale Repository Performance Assessment. Summary of Findings. Report of BMT2/WP3

    Energy Technology Data Exchange (ETDEWEB)

    Andersson, Johan (comp.) [JA Streamflow AB, Aelvsjoe (Sweden); Staub, Isabelle (comp.) [Golder Associates AB, Stockholm (Sweden); Knight, Les (comp.) [Nirex UK Ltd, Oxon (United Kingdom)

    2005-02-15

    The Benchmark Test 2 of DECOVALEX III and Work Package 3 of BENCHPAR concerns the upscaling Thermal (T), Hydrological (H) and Mechanical (M) processes in a fractured rock mass and its significance for large-scale repository performance assessment. The work is primarily concerned with the extent to which various thermo-hydro-mechanical couplings in a fractured rock mass adjacent to a repository are significant in terms of solute transport typically calculated in large-scale repository performance assessments. Since the presence of even quite small fractures may control the hydraulic, mechanical and coupled hydromechanical behaviour of the rock mass, a key of the work has been to explore the extent to which these can be upscaled and represented by 'equivalent' continuum properties appropriate PA calculations. From these general aims the BMT was set-up as a numerical study of a large scale reference problem. Analysing this reference problem should: help explore how different means of simplifying the geometrical detail of a site, with its implications on model parameters, ('upscaling') impacts model predictions of relevance to repository performance, explore to what extent the THM-coupling needs to be considered in relation to PA-measures, compare the uncertainties in upscaling (both to uncertainty on how to upscale or uncertainty that arises due to the upscaling processes) and consideration of THM couplings with the inherent uncertainty and spatial variability of the site specific data. Furthermore, it has been an essential component of the work that individual teams not only produce numerical results but are forced to make their own judgements and to provide the proper justification for their conclusions based on their analysis. It should also be understood that conclusions drawn will partly be specific to the problem analysed, in particular as it mainly concerns a 2D application. This means that specific conclusions may have limited applicability

  6. Can an ethics officer role reduce delays in research ethics approval? A mixed-method evaluation of an improvement project.

    Science.gov (United States)

    Dixon-Woods, Mary; Foy, Chris; Hayden, Charlotte; Al-Shahi Salman, Rustam; Tebbutt, Stephen; Schroter, Sara

    2016-08-31

    Frustration continues to be directed at delays in gaining approvals for undertaking health research in the UK. We aimed to evaluate the impact of an ethics officer intervention on rates of favourable opinions (approval) and provisional opinions (requiring revision and resubmission) and on the time taken to reach a final opinion by research ethics committees (RECs), to characterise how the role operated in practice, and to investigate applicants' views. Mixed-method study involving (i) a 2-group, non-randomised before-and-after intervention study of RECs assigned an ethics officer and a matched comparator group; (ii) a process evaluation involving a survey of applicants and documentary analysis. 6 RECs and 3 associated ethics officers; 18 comparator RECs; REC applicants. Rates of provisional and favourable opinions between ethics officer and comparator RECs did not show a statistically significant effect of the intervention (logistic regression, p=0.26 for favourable opinions and p=0.31 for provisional opinions). Mean time to reach a decision showed a non-significant reduction (ANOVA, p=0.22) from 33.3 to 32.0 days in the ethics officer RECs compared with the comparator RECs (32.6 to 32.9 days). The survey (30% response rate) indicated applicant satisfaction and also suggested that ethics officer support might be more useful before submission. Ethics officers were successful in identifying many issues with applications, but the intervention did not function exactly as designed: in 31% of applicants, no contact between the applicants and the ethics officer took place before REC review. This study was a non-randomised comparison cohort study. Some data were missing. An ethics officer intervention, as designed and implemented in this study, did not increase the proportion of applications to RECs that were approved on first review and did not reduce the time to a committee decision. Published by the BMJ Publishing Group Limited. For permission to use (where not

  7. Management of radioactive waste at Novi Han Repository

    International Nuclear Information System (INIS)

    Stefanova, I.G.; Mateeva, M.D.; Milanov, M.V.

    2002-01-01

    The Novi Han Repository is the only existing repository in Bulgaria for the disposal of radioactive waste from nuclear applications in industry, medicine and research. The repository was constructed in the early sixties according to the existing requirements. It was operated by the Institute for Nuclear Research and Nuclear Energy for more than thirty years without any accident or release of radioactivity to the environment, but without any investment for upgrading. As a consequence, the Bulgarian Nuclear Safety Authority temporarily stopped the operation of the repository in 1994. The measures for upgrading the Novi Han Repository, supported by the IAEA under TC Project BUL/4/005 'Increasing Safety of Novi Han Repository', are presented in this paper. They comprise: assessment of radionuclide inventory and future waste arisings, characterisation of disposal vaults, characterisation of the site, safety assessment, upgrading of the monitoring system, option study for the selection of treatment and conditioning processes and the development of a conceptual design for low and intermediate level waste processing and storage facility, immediate measures for improvement of the existing disposal vaults and infrastructure, construction of above-ground temporary storage structures, and resuming the operation of the Novi Han Repository. The necessary activities for re-licensing of the Novi Han Repository, construction of a waste processing and storage facility and a disposal facility for spent sealed sources are discussed. (author)

  8. Upgrading of radon's type near surface repository in Latvia

    International Nuclear Information System (INIS)

    Abramenkovs, A.

    2006-01-01

    In 1959, the Soviet government decided to construct the near surface radioactive wastes repository 'Radons' near the Baldone city. It was put in operation in 1962. The changes in the development of the repository were induced by the necessarily to upgrade it for disposal of radioactive wastes from the decommissioning of the Salaspils Research Reactor (SRR). The safety assessment of repository was performed during 2000-2001 under the PHARE project for necessary upgrades of repository. The outline design for new vaults and interim storage for long lived radioactive wastes was elaborated during 2003-2004 years. The Environmental Impact Assessment (EIA) for upgrade of Baldone repository was performed during 2004-2005 years. It was found, that additional efforts must be devoted for solution of social aspects o for successful operation and upgrade of repository. It was shown by EIA, that the local population has a negative opinion against the upgrade of repository in Latvia. The main recommendations for upgrades were connected with increasing the safety of repository, increasing of PR activities for education of society and developing of compensation mechanism for local municipality. (author)

  9. Publishers and repositories

    CERN Multimedia

    CERN. Geneva

    2007-01-01

    The impact of self-archiving on journals and publishers is an important topic for all those involved in scholarly communication. There is some evidence that the physics arXiv has had no impact on physics journals, while 'economic common sense' suggests that some impact is inevitable. I shall review recent studies of librarian attitudes towards repositories and journals, and place this in the context of IOP Publishing's experiences with arXiv. I shall offer some possible reasons for the mis-match between these perspectives and then discuss how IOP has linked with arXiv and experimented with OA publishing. As well as launching OA journals we have co-operated with Cornell and the arXiv on Eprintweb.org, a platform that offers new features to repository users. View Andrew Wray's biography

  10. Distributed Web Service Repository

    Directory of Open Access Journals (Sweden)

    Piotr Nawrocki

    2015-01-01

    Full Text Available The increasing availability and popularity of computer systems has resulted in a demand for new, language- and platform-independent ways of data exchange. That demand has in turn led to a significant growth in the importance of systems based on Web services. Alongside the growing number of systems accessible via Web services came the need for specialized data repositories that could offer effective means of searching of available services. The development of mobile systems and wireless data transmission technologies has allowed the use of distributed devices and computer systems on a greater scale. The accelerating growth of distributed systems might be a good reason to consider the development of distributed Web service repositories with built-in mechanisms for data migration and synchronization.

  11. Czech Republic. Dukovany repository

    International Nuclear Information System (INIS)

    2001-01-01

    Full text: The repository at the Dukovany site is a structure located above the land surface. It consists of two double-rows of reinforced concrete vaults. Each double-row has dimensions 38x160x6 meters and contains 2x28 vaults. The internal dimensions of each vault are 18x6x5.4 meters. The repository serves for reactor wastes from the Dukovany and Temelin nuclear power plants (NPPs). Its capacity is 55,000 m 3 or 130,000 drums. The repository is a fully engineered facility with multiple barriers. The first engineered barrier is the waste form (in the case of waste from the Dukovany NPP, the waste form is mainly bitumen, but concrete and glass are also considered as suitable solidification products). The second barrier is the container (a 200 litre steel drum or a HIC container), whereas the third consists of cut-off reinforced concrete walls with asphalt-based hydro-insulation. The fourth barrier is a cap which should protect the vaults against infiltration of rainwater and should serve also as an intrusion and erosion barrier. The fifth barrier is a drainage system around the repository which is composed of layers of gravel and sand. The void space in drums around the waste is filled with specially composed grout. Such waste packages are emplaced into the disposal vault, which is covered by pre-fabricated panels. Thereafter, joints between the panels are sealed and a provisional coverage added; the final cover, however, will be constructed only over the whole row of 28 vaults, until all vaults are filled with waste. The final cover will encompass the following components: reinforced concrete pre-fabricated panels (500 mm); cement overcoat (30 mm); insulation foil; concrete layer for cap levelling (5-150 mm); layer of asphalto-propylene concrete (150 mm); soil (450 mm); geotextile foil with topsoil (top surface vegetation). (author)

  12. 'Swapping wastes' planned by nuclear power plant operators in order to exert an influence on the government's radwaste repository project Konrad

    International Nuclear Information System (INIS)

    Harries, K.; Stroetmann, C.

    1992-01-01

    An 'exchange of waste', which would involve taking back high-level radioactive, heat-generating waste in place of low-level radioactive waste from reprocessing, whereby the amount of high-level radioactive waste would be smaller, corresponding in the degree of radioactivity to that of the low-level radioactive waste, is not provided for in the reprocessing contracts with BNFL and is also not approved by the federal government. There is still an urgent need for waste disposal facilities for radioactive waste with negligible generation of heat. Thus the waste disposal project Konrad is not superfluous, but rather should be accelerated quickly. (orig./HSCH) [de

  13. Digital Repository of Research Institutes – RCIN

    Directory of Open Access Journals (Sweden)

    Kamila Kaczyńska

    2014-03-01

    Full Text Available The paper describes the project of Digital Repository of Scientific Institutes RCIN and presents opportunities for promoting science by digitization and sharing them on the Internet. The Repository has been created by the 16 Scientific Institutes in Warsaw, Krakow and Bialowieza to modernize the science-research and IT infrastructure, to increase digital resources of mathematical, technical, natural and medical sciences, and to popularize and promote of Polish science. That dissemination and popularization of science affects its development and competitiveness in the international arena and it allows transfer of research results to the economy. In addition, Institutes of RCIN providing contemporary and archival materials of science, support the intellectual capital of Polish science and raise awareness of professional literature of search on the Internet. Project RCIN is implemented in the years 2010–2014 and financing is provided by the funds of the European Fund of Regional Development.

  14. Staged Repository Development Programmes

    International Nuclear Information System (INIS)

    Isaacs, T

    2003-01-01

    Programs to manage and ultimately dispose of high-level radioactive wastes are unique from scientific and technological as well as socio-political aspects. From a scientific and technological perspective, high-level radioactive wastes remain potentially hazardous for geological time periods-many millennia-and scientific and technological programs must be put in place that result in a system that provides high confidence that the wastes will be isolated from the accessible environment for these many thousands of years. Of course, ''proof'' in the classical sense is not possible at the outset, since the performance of the system can only be known with assurance, if ever, after the waste has been emplaced for those geological time periods. Adding to this challenge, many uncertainties exist in both the natural and engineered systems that are intended to isolate the wastes, and some of the uncertainties will remain regardless of the time and expense in attempting to characterize the system and assess its performance. What was perhaps underappreciated in the early days of waste management and repository program development were the unique and intense reactions that the institutional, political, and public bodies would have to repository program development, particularly in programs attempting to identify and then select sites for characterization, design, licensing, and ultimate development. Reactions in most nations were strong, focused, unrelenting, and often successful in hindering, derailing, and even stopping national repository programs. The reasons for such reactions and the measures to successfully respond to them are still evolving and continue to be the focus of many national program and political leaders. Adaptive Staging suggests an approach to repository program development that reflects the unique challenges associated with the disposal of high-level radioactive waste. The step-wise, incremental, learn-as-you-go approach is intended to maximize the

  15. Geoscience Digital Data Resource and Repository Service

    Science.gov (United States)

    Mayernik, M. S.; Schuster, D.; Hou, C. Y.

    2017-12-01

    The open availability and wide accessibility of digital data sets is becoming the norm for geoscience research. The National Science Foundation (NSF) instituted a data management planning requirement in 2011, and many scientific publishers, including the American Geophysical Union and the American Meteorological Society, have recently implemented data archiving and citation policies. Many disciplinary data facilities exist around the community to provide a high level of technical support and expertise for archiving data of particular kinds, or for particular projects. However, a significant number of geoscience research projects do not have the same level of data facility support due to a combination of several factors, including the research project's size, funding limitations, or topic scope that does not have a clear facility match. These projects typically manage data on an ad hoc basis without limited long-term management and preservation procedures. The NSF is supporting a workshop to be held in Summer of 2018 to develop requirements and expectations for a Geoscience Digital Data Resource and Repository Service (GeoDaRRS). The vision for the prospective GeoDaRRS is to complement existing NSF-funded data facilities by providing: 1) data management planning support resources for the general community, and 2) repository services for researchers who have data that do not fit in any existing repository. Functionally, the GeoDaRRS would support NSF-funded researchers in meeting data archiving requirements set by the NSF and publishers for geosciences, thereby ensuring the availability of digital data for use and reuse in scientific research going forward. This presentation will engage the AGU community in discussion about the needs for a new digital data repository service, specifically to inform the forthcoming GeoDaRRS workshop.

  16. Waste repository planned for Bruce Site

    International Nuclear Information System (INIS)

    King, F.

    2004-01-01

    Ontario Power Generation (OPG) and Kincardine, the municipality nearest the Bruce site, have agreed in principal to the construction of a deep geologic repository for low and medium level radioactive waste on the site. The two parties signed the 'Kincardine Hosting Agreement' on October 13, 2004 to proceed with planning, seek regulatory approval and further public consultation of the proposed project. A construction Licence is not expected before 2013. (author)

  17. Evaluation of repository safety

    Energy Technology Data Exchange (ETDEWEB)

    Sagar, B.; Patrick, W.; Dasgupta, B.; Mohanty, S. [Center for Nuclear Waste Regulatory Analyses, San Antonio (United States)

    2002-07-01

    The United States high-level waste program requires evaluation of radiological safety during two distinct time intervals. The first interval, commonly referred to as the preclosure period, deals with receipt of waste at the site, transfer into disposal containers, if needed, emplacement in the underground openings, monitoring and maintenance activities, backfill and closure of the underground openings, and decontamination and decommissioning of the surface facilities of the geologic repository. The preclosure period may extend from a few tens of years to as long as a few hundred of years, depending on repository design and societal norms regarding a final decision to permanently seal the repository. During the preclosure or operational period, performance confirmation studies are conducted to provide a basis for updating and reevaluating estimates of postclosure performance and, finally, to provide a basis for a closure decision. The postclosure period during which expected repository performance must meet certain standards may range from ten thousands years, as it does in the United States, to millions of years, as it does in some European nations. Waste handling operations in the preclosure period are to be evaluated in relation to their potential effect on workers, members of general public, and the general environment. During this period, releases of radioactivity are to be monitored and appropriate actions taken whenever established limits are approached or exceeded. Preclosure safety is highly dependent on facility design, operational hardware and automated systems, operational sequences, and reliability of humans involved in operations. Preclosure safety analyses conducted before operations begin play a major role in the design process, selection of equipment, and development of operational procedures. Because of the complexity, duration, and spatial scales of the operations, analyses are conducted using mathematical models implemented in computer codes

  18. Evaluation of repository safety

    International Nuclear Information System (INIS)

    Sagar, B.; Patrick, W.; Dasgupta, B.; Mohanty, S.

    2002-01-01

    The United States high-level waste program requires evaluation of radiological safety during two distinct time intervals. The first interval, commonly referred to as the preclosure period, deals with receipt of waste at the site, transfer into disposal containers, if needed, emplacement in the underground openings, monitoring and maintenance activities, backfill and closure of the underground openings, and decontamination and decommissioning of the surface facilities of the geologic repository. The preclosure period may extend from a few tens of years to as long as a few hundred of years, depending on repository design and societal norms regarding a final decision to permanently seal the repository. During the preclosure or operational period, performance confirmation studies are conducted to provide a basis for updating and reevaluating estimates of postclosure performance and, finally, to provide a basis for a closure decision. The postclosure period during which expected repository performance must meet certain standards may range from ten thousands years, as it does in the United States, to millions of years, as it does in some European nations. Waste handling operations in the preclosure period are to be evaluated in relation to their potential effect on workers, members of general public, and the general environment. During this period, releases of radioactivity are to be monitored and appropriate actions taken whenever established limits are approached or exceeded. Preclosure safety is highly dependent on facility design, operational hardware and automated systems, operational sequences, and reliability of humans involved in operations. Preclosure safety analyses conducted before operations begin play a major role in the design process, selection of equipment, and development of operational procedures. Because of the complexity, duration, and spatial scales of the operations, analyses are conducted using mathematical models implemented in computer codes

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

    International Nuclear Information System (INIS)

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

    1986-12-01

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

  20. Operational safety of geological disposal: IRSN project 'EXREV' for developing a safety assessment strategy for the operation and reversibility of a geological repository

    International Nuclear Information System (INIS)

    Tichauer, M.; Pellegrini, D.; Serres, C.; Besnus, F.

    2014-01-01

    A high-level waste geological disposal facility is envisioned by the legislator in the French Planning Act no. 2006-739 of 28 June 2006. This act sets major milestones for the operator (Andra) in 2013 (public debate), 2015 (licensing) and 2025 (operation). In the framework of the regulatory review process, IRSN's mission is to conduct an assessment of the safety case provided by Andra at every stage of the process for the French regulator, namely the Nuclear Safety Authority (ASN). In 2005, IRSN gathered more than twenty years of research and expertise in order to provide a comprehensive appraisal of the 'Dossier 2005' prepared by Andra, related to the feasibility of a geological disposal in the Callovo-Oxfordian clay formation. At this time, the description of the operational phase was only at a preliminary stage, but this step paved the way for developing an assessment strategy of the operational phase. In this perspective, IRSN set up the EXREV project in 2008 in order to build up a doctrine and to identify key safety issues to be dealt with. (authors)

  1. WORKSHOP ON DEVELOPMENT OF RADIONUCLIDE GETTERS FOR THE YUCCA MOUNTAIN WASTE REPOSITORY: PROCEEDINGS

    International Nuclear Information System (INIS)

    K.C. Holt

    2006-01-01

    One of the important that the U.S. Department of Energy (DOE) is currently undertaking is the development of a high-level nuclear waste repository to be located at Yucca Mountain, Nevada. Concern is generated by the Yucca Mountain Project (YMP) is due to potential releases as groundwater contamination, as described in the Total System Performance Assessment (TSPA). The dose to an off-site individual using this groundwater for drinking and irrigation is dominated by four radionuclides: Tc-99, I-127, Np-237, and U-238. Ideally, this dose would be limited to a single radionuclide, U-238; in other words, YMP would resemble a uranium ore body, a common geologic feature in the Western U.S. For this reason and because of uncertainties in the behavior of Tc-99, I-127, and Np-237, it would be helpful to limit the amount of Tc, I, and Np leaving the repository, which would greatly increase the confidence in the long-term performance of YMP. An approach to limiting the migration of Tc, I, and Np that is complementary to the existing YMP repository design plans is to employ sequestering agents or ''getters'' for these radionuclides such that their migration is greatly hindered, thus decreasing the amount of radionuclide leaving the repository. Development of such getters presents a number of significant challenges. The getter must have a high affinity and high selectivity for the radionuclide in question since there is approximately a 20- to 50-fold excess of other fission products and a 1000-fold excess of uranium in addition to the ions present in the groundwater. An even greater challenge is that the getters must function over a period greater than the half-life of the radionuclide (greater than 5 half-lives would be ideal). Typically, materials with a high affinity for Tc, I, or Np are not sufficiently durable. For example, strong-base ion exchange resins have a very high affinity for TcO 4 - but are not expected to be durable. On the other hand, durable materials, such as

  2. WORKSHOP ON DEVELOPMENT OF RADIONUCLIDE GETTERS FOR THE YUCCA MOUNTAIN WASTE REPOSITORY

    Energy Technology Data Exchange (ETDEWEB)

    K.C. Holt

    2006-03-13

    One of the important that the U.S. Department of Energy (DOE) is currently undertaking is the development of a high-level nuclear waste repository to be located at Yucca Mountain, Nevada. Concern is generated by the Yucca Mountain Project (YMP) is due to potential releases as groundwater contamination, as described in the Total System Performance Assessment (TSPA). The dose to an off-site individual using this groundwater for drinking and irrigation is dominated by four radionuclides: Tc-99, I-127, Np-237, and U-238. Ideally, this dose would be limited to a single radionuclide, U-238; in other words, YMP would resemble a uranium ore body, a common geologic feature in the Western U.S. For this reason and because of uncertainties in the behavior of Tc-99, I-127, and Np-237, it would be helpful to limit the amount of Tc, I, and Np leaving the repository, which would greatly increase the confidence in the long-term performance of YMP. An approach to limiting the migration of Tc, I, and Np that is complementary to the existing YMP repository design plans is to employ sequestering agents or ''getters'' for these radionuclides such that their migration is greatly hindered, thus decreasing the amount of radionuclide leaving the repository. Development of such getters presents a number of significant challenges. The getter must have a high affinity and high selectivity for the radionuclide in question since there is approximately a 20- to 50-fold excess of other fission products and a 1000-fold excess of uranium in addition to the ions present in the groundwater. An even greater challenge is that the getters must function over a period greater than the half-life of the radionuclide (greater than 5 half-lives would be ideal). Typically, materials with a high affinity for Tc, I, or Np are not sufficiently durable. For example, strong-base ion exchange resins have a very high affinity for TcO{sub 4}{sup -} but are not expected to be durable. On the other

  3. CATSIUS CLAY PROJECT: Calculation and testing of behaviour of unsaturated clay as barrier in radioactive waste repositories: stage 3: validation exercises at a large in situ scale

    Energy Technology Data Exchange (ETDEWEB)

    Alonso, E E; Alcoverro, J

    1999-07-01

    Stage 3 of CATSIUS CLAY Project: Validation Exercises at a Large in situ Scale includes two Benchmarks: Benchmark 3.1: In situ Hydration of Boom Clay Pellets (BACCHUS 2) and Benchmark 3.2: FEBEX Mock-up Test. The BACCHUS 2 in situ test was performed in the HADES underground laboratory (Mol, Belgium) to demonstrate and optimize an installation procedure for a clay based material and to study its hydration process. After drilling a vertical shaft (540 mm in diameter, 3.0 m in length) in the host Boom clay, a central filter (90 mm in diameter) was placed, the remaining space was filled with a mixture of clay pellets and clay powder and the assembly was sealed at the upper end by a resin plug (0.20 m in thickness) over which concrete was poured. The test was instrumented so that it could be used as a validation experiment. Total stress, pore water pressure and water content measurements were performed both in the backfill material and in the surrounding clay massif. Once the installation was complete, the natural hydration of the backfill material began (day 0). To accelerate the hydration process, on day 516 water was injected through the central filter. On day 624, after the saturation of the backfill was reached, the hydraulic circuit was closed and the undrained response of the system backfill-host clay was monitored until an overall steady state was reached. Partners were asked to provide predictions for the evolution of the pore water pressure and total pressure of various points where appropriate sensors are installed. This benchmark addresses the Hydro-Mechanical response of an unsaturated low density clay barrier under natural and artificial hydration. (Author)

  4. CATSIUS CLAY PROJECT: Calculation and testing of behaviour of unsaturated clay as barrier in radioactive waste repositories: stage 3: validation exercises at a large in situ scale

    International Nuclear Information System (INIS)

    Alonso, E. E.; Alcoverro, J.

    1999-01-01

    Stage 3 of CATSIUS CLAY Project: Validation Exercises at a Large in situ Scale includes two Benchmarks: Benchmark 3.1: In situ Hydration of Boom Clay Pellets (BACCHUS 2) and Benchmark 3.2: FEBEX Mock-up Test. The BACCHUS 2 in situ test was performed in the HADES underground laboratory (Mol, Belgium) to demonstrate and optimize an installation procedure for a clay based material and to study its hydration process. After drilling a vertical shaft (540 mm in diameter, 3.0 m in length) in the host Boom clay, a central filter (90 mm in diameter) was placed, the remaining space was filled with a mixture of clay pellets and clay powder and the assembly was sealed at the upper end by a resin plug (0.20 m in thickness) over which concrete was poured. The test was instrumented so that it could be used as a validation experiment. Total stress, pore water pressure and water content measurements were performed both in the backfill material and in the surrounding clay massif. Once the installation was complete, the natural hydration of the backfill material began (day 0). To accelerate the hydration process, on day 516 water was injected through the central filter. On day 624, after the saturation of the backfill was reached, the hydraulic circuit was closed and the undrained response of the system backfill-host clay was monitored until an overall steady state was reached. Partners were asked to provide predictions for the evolution of the pore water pressure and total pressure of various points where appropriate sensors are installed. This benchmark addresses the Hydro-Mechanical response of an unsaturated low density clay barrier under natural and artificial hydration. (Author)

  5. Multi-office engineering

    International Nuclear Information System (INIS)

    Cowle, E.S.; Hall, L.D.; Koss, P.; Saheb, E.; Setrakian, V.

    1995-01-01

    This paper addresses the viability of multi-office project engineering as has been made possible in a large part by the computer age. Brief discussions are provided on two past projects describing the authors' initial efforts at multi-office engineering, and an in-depth discussion is provided on a current Bechtel project that demonstrates their multi-office engineering capabilities. Efficiencies and cost savings associated with executing an engineering project from multiple office locations was identified as a viable and cost-effective execution approach. The paper also discusses how the need for multi-office engineering came about, what is required to succeed, and where they are going from here. Furthermore, it summarizes the benefits to their clients and to Bechtel

  6. NASA Biological Specimen Repository

    Science.gov (United States)

    McMonigal, K. A.; Pietrzyk, R. A.; Sams, C. F.; Johnson, M. A.

    2010-01-01

    The NASA Biological Specimen Repository (NBSR) was established in 2006 to collect, process, preserve and distribute spaceflight-related biological specimens from long duration ISS astronauts. This repository provides unique opportunities to study longitudinal changes in human physiology spanning may missions. The NBSR collects blood and urine samples from all participating ISS crewmembers who have provided informed consent. These biological samples are collected once before flight, during flight scheduled on flight days 15, 30, 60, 120 and within 2 weeks of landing. Postflight sessions are conducted 3 and 30 days after landing. The number of in-flight sessions is dependent on the duration of the mission. Specimens are maintained under optimal storage conditions in a manner that will maximize their integrity and viability for future research The repository operates under the authority of the NASA/JSC Committee for the Protection of Human Subjects to support scientific discovery that contributes to our fundamental knowledge in the area of human physiological changes and adaptation to a microgravity environment. The NBSR will institute guidelines for the solicitation, review and sample distribution process through establishment of the NBSR Advisory Board. The Advisory Board will be composed of representatives of all participating space agencies to evaluate each request from investigators for use of the samples. This process will be consistent with ethical principles, protection of crewmember confidentiality, prevailing laws and regulations, intellectual property policies, and consent form language. Operations supporting the NBSR are scheduled to continue until the end of U.S. presence on the ISS. Sample distribution is proposed to begin with selections on investigations beginning in 2017. The availability of the NBSR will contribute to the body of knowledge about the diverse factors of spaceflight on human physiology.

  7. Safety-relevant assessment concerning the proposals for investigations in proposed locations for stage 3 of the deep geological repositories project; Sicherheitstechnisches Gutachten zum Vorschlag der in Etappe 3 SGT weiter zu untersuchenden geologischen Standortgebiete - Sachplan geologische Tiefenlager, Etappe 2

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2017-04-15

    This comprehensive report published by the Swiss Federal Nuclear Safety Inspectorate ENSI examines the proposals made by the Swiss National Cooperative for the disposal of Radioactive Waste (NAGRA) concerning proposed locations for deep waste repositories. Important basic considerations to be made when narrowing down the choice of host rock types and the selection of possible locations are discussed. These include, amongst others, safety concepts for the repositories, geological models and technical feasibility of repositories in Opalinus Clay, Brown Dogger layers and marl. The properties of various host rocks are discussed. Methods to be used in choosing at least two possible sites for repositories are considered. Also, the radioactive dosage to be expected at the various sites proposed is discussed. A safety-relevant comparison of the sites is made and an overall assessment is presented. The locations proposed for surface facilities at three proposed locations are discussed. The report is completed with an appendix containing tables and a list of relevant expert reports.

  8. DOE hearing on the draft area recommendation report for the Crystalline Repository Project, Civic Center Arena, Asheville, North Carolina: Session 1, Volume 4, April 4, 1986: Transcript of proceedings

    International Nuclear Information System (INIS)

    1986-01-01

    This document contains a transcript of the comments of 15 witnesses. These meetings were held to hear public comments regarding the selection of a site for a second high-level nuclear waste repository

  9. Memorandum concerning further information on the constructional feasibility of proposed locations for stage 2 of the deep geological repositories project; Nachforderung zum Indikator „Tiefenlage im Hinblick auf bautechnische Machbarkeit“ in Etappe 2 SGT

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2015-11-15

    This memorandum published by the Swiss Federal Nuclear Safety Inspectorate ENSI examines proposals made by the Swiss National Cooperative for the disposal of Radioactive Waste (NAGRA). Further information concerning the technical feasibility of deep repositories for nuclear wastes and their maximum depth is requested. ENSI requests from NAGRA that the minimum geotechnical requirements on the repositories and an assessment on their maximum depth be stated. Five main areas where more information is required are listed. Provisional assessment results on maximum repository depth are quoted and the associated requirements on supplementary data required are listed. Data on basic rock mechanics are requested and requirements on the evaluation of maximum repository depth are discussed. The document is completed with a comprehensive list of relevant references.

  10. Catsius Clay Project. Calculation and Testing of Behaviour of Unsaturated Clay as Barrier in Radioactive Waste Repositories. Stage 2: Validation Exercises at Laboratory scale

    International Nuclear Information System (INIS)

    Alonso, E. E.; Alcoverro, J.

    1999-01-01

    Stage 2 of CATSIUS CLAY Project: Validation Exercises at Laboratory Scale includes two Benchmarks, Benchmark 2.1: Oedometer Suction Controlled Tests on Samples of compacted Boom Clay and Benchmark 2.2: Small Scale Weltting-Heating Test on Compacted Bentonite. BM 2.1 had two parts: BM 2.1A (volumetric deformation upon wetting-drying cycles) and BM 2.1 B (swelling pressure test). In BM 2.1A, participants were asked to model the results of a series of five tests on samples of compacted Boom clay. In BM 2.1B, a swelling pressure test in which suction, vertical and horizontal stresses were monitored, was proposed as a blind exercise. Participants were asked to use, without further changes, the models calibrated in BM 2.1A. This exercise provides an evaluation of the capabilities of current mechanical constitutive models for unsaturated clay behaviour. It was found that, even if a calibration exercise on the basis of known experimental data is satisfactory, blind predictions of tests involving different paths may prove difficult. The test set up for BM 2.2 consisted of a stainless stell cell filled with highly expansive compacted bentonite (S2 clay from Almeria, Spain). The clay was subjected to a simultaneous central heating and a progressive water inflow through the botton plate. Temperature at various locations within the sample and the boundary radial stress were monitored throughout the test. Water content distribution was also measured at the end of the experiment. Predictions for this benchmark required the solution of field equations for flow, temperature distribution and mechanical analysis. Model parameters were derived from the extensive set of available experiments on this clay. Comparison between model predictions and measurements revealed the significance of water transport in vapour phase, the difficulties to predict boundary stresses and the general good agreement between measured and calculated temperatures. The report provides a detailed accojnt of the

  11. Catsius Clay Project. Calculation and Testing of Behaviour of Unsaturated Clay as Barrier in Radioactive Waste Repositories. Stage 2: Validation Exercises at Laboratory scale

    Energy Technology Data Exchange (ETDEWEB)

    Alonso, E E; Alcoverro, J

    1999-07-01

    Stage 2 of CATSIUS CLAY Project: Validation Exercises at Laboratory Scale includes two Benchmarks, Benchmark 2.1: Oedometer Suction Controlled Tests on Samples of compacted Boom Clay and Benchmark 2.2: Small Scale Weltting-Heating Test on Compacted Bentonite. BM 2.1 had two parts: BM 2.1A (volumetric deformation upon wetting-drying cycles) and BM 2.1 B (swelling pressure test). In BM 2.1A, participants were asked to model the results of a series of five tests on samples of compacted Boom clay. In BM 2.1B, a swelling pressure test in which suction, vertical and horizontal stresses were monitored, was proposed as a blind exercise. Participants were asked to use, without further changes, the models calibrated in BM 2.1A. This exercise provides an evaluation of the capabilities of current mechanical constitutive models for unsaturated clay behaviour. It was found that, even if a calibration exercise on the basis of known experimental data is satisfactory, blind predictions of tests involving different paths may prove difficult. The test set up for BM 2.2 consisted of a stainless stell cell filled with highly expansive compacted bentonite (S2 clay from Almeria, Spain). The clay was subjected to a simultaneous central heating and a progressive water inflow through the botton plate. Temperature at various locations within the sample and the boundary radial stress were monitored throughout the test. Water content distribution was also measured at the end of the experiment. Predictions for this benchmark required the solution of field equations for flow, temperature distribution and mechanical analysis. Model parameters were derived from the extensive set of available experiments on this clay. Comparison between model predictions and measurements revealed the significance of water transport in vapour phase, the difficulties to predict boundary stresses and the general good agreement between measured and calculated temperatures. The report provides a detailed accojnt of the

  12. INSTITUTIONAL REPOSITORY: EMPLOYMENT IN EDUCATION

    Directory of Open Access Journals (Sweden)

    Vasyl P. Oleksyuk

    2012-11-01

    Full Text Available The article investigated the concept of «institutional repository» and determined the aspects of institutional repositories in higher education. Institutional Repositories are information systems that allow preserving, storing and disseminating scientific knowledge produced in higher education and scientific research institutions. This study presented the main aspects using institutional repositories in educational process (such as storage of scientific and educational information, means of organization activity of students, object of studying. This article produced the structure of communities and collections of the institutional. It is described the experience of implementing of DSpace in the learning process.

  13. Site environmental report for the Yucca Mountain Project. Calendar Year 2005

    Energy Technology Data Exchange (ETDEWEB)

    None, None

    2006-10-01

    This site environmental report describes the environmental program conducted during 2005 by the U.S. Department of Energy, Office of Repository Development. The report describes the environmental laws and regulations that were applicable to the Yucca Mountain Project in 2005, the actions taken to comply with those laws and regulations, and the Project’s environmental program. The report also summarizes the data collected to monitor potential impacts of the Project on the environment.

  14. Object linking in repositories

    Science.gov (United States)

    Eichmann, David (Editor); Beck, Jon; Atkins, John; Bailey, Bill

    1992-01-01

    This topic is covered in three sections. The first section explores some of the architectural ramifications of extending the Eichmann/Atkins lattice-based classification scheme to encompass the assets of the full life cycle of software development. A model is considered that provides explicit links between objects in addition to the edges connecting classification vertices in the standard lattice. The second section gives a description of the efforts to implement the repository architecture using a commercially available object-oriented database management system. Some of the features of this implementation are described, and some of the next steps to be taken to produce a working prototype of the repository are pointed out. In the final section, it is argued that design and instantiation of reusable components have competing criteria (design-for-reuse strives for generality, design-with-reuse strives for specificity) and that providing mechanisms for each can be complementary rather than antagonistic. In particular, it is demonstrated how program slicing techniques can be applied to customization of reusable components.

  15. Malaysian Education Index (MEI): An Online Indexing and Repository System

    Science.gov (United States)

    Kabilan, Muhammad Kamarul; Ismail, Hairul Nizam; Yaakub, Rohizani; Yusof, Najeemah Mohd; Idros, Sharifah Noraidah Syed; Umar, Irfan Naufal; Arshad, Muhammad Rafie Mohd.; Idrus, Rosnah; Rahman, Habsah Abdul

    2010-01-01

    This "Project Sheet" describes an on-going project that is being carried out by a group of educational researchers, computer science researchers and librarians from Universiti Sains Malaysia, Penang. The Malaysian Education Index (MEI) has two main functions--(1) Online Indexing System, and (2) Online Repository System. In this brief…

  16. Preservation Health Check: Monitoring Threats to Digital Repository Content

    Science.gov (United States)

    Kool, Wouter; van der Werf, Titia; Lavoie, Brian

    2014-01-01

    The Preservation Health Check (PHC) project, undertaken as a joint effort by Open Planets Foundation (OPF) and OCLC Research, aims to evaluate the usefulness of the preservation metadata created and maintained by operational repositories for assessing basic preservation properties. The PHC project seeks to develop an implementable logic to support…

  17. Job task and functional analysis of the Division of Reactor Projects, office of Nuclear Reactor Regulation. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Morzinski, J.A.; Gilmore, W.; Hahn, H.A.

    1998-07-10

    A job task and functional analysis was recently completed for the positions that make up the regional Divisions of Reactor Projects. Among the conclusions of that analysis was a recommendation to clarify roles and responsibilities among site, regional, and headquarters personnel. As that analysis did not cover headquarters personnel, a similar analysis was undertaken of three headquarters positions within the Division of Reactor Projects: Licensing Assistants, Project Managers, and Project Directors. The goals of this analysis were to systematically evaluate the tasks performed by these headquarters personnel to determine job training requirements, to account for variations due to division/regional assignment or differences in several experience categories, and to determine how, and by which positions, certain functions are best performed. The results of this analysis include recommendations for training and for job design. Data to support this analysis was collected by a survey instrument and through several sets of focus group meetings with representatives from each position.

  18. THM large spatial-temporal model to simulate the past 2 Ma hydrogeological evolution of Paris Basin including natural tracer transport as part of site characterization for radwaste repository project Cigéo - France

    Science.gov (United States)

    Benabderrahmane, A., Sr.

    2017-12-01

    Hydrogeological site characterization for deep geological high level and intermediate level long lived radioactive waste repository cover a large time scale needed for safety analysis and calculation. Hydrogeological performance of a site relies also on the effects of geodynamic evolution as tectonic uplift, erosion/sedimentation and climate including glaciation on the groundwater flow and solute and heat transfer. Thermo-Hydro-Mechanical model of multilayered aquifer system of Paris Basin is developed to reproduce the present time flow and the natural tracer (Helium) concentration profiles based on the last 2 Ma of geodynamic evolution. Present time geological conceptual model consist of 27 layers at Paris Basin (Triassic-Tertiary) with refinement at project site scale (29 layers from Triassic to Portlandian). Target layers are the clay host formation of Callovo-Oxfrodian age (160 Ma) and the surrounding aquifer layers of Oxfordian and Dogger. Modelled processes are: groundwater flow, heat and solutes (natural tracers) transport, freezing and thawing of groundwater (expansion and retreat of permafrost), deformation of the multilayered aquifer system induced by differential tectonic uplift and the hydro-mechanical stress effect as caused by erosion of the outcropping layers. Numerical simulation considers a period from 2 Ma BP and up to the present. Transient boundary conditions are governed by geodynamic processes: (i) modification of the geometry of the basin and (ii) temperatures along the topography will change according to a series of 15 identical climate cycles with multiple permafrost (glaciation) periods. Numerical model contains 71 layers and 18 million cells. The solution procedure solves three coupled systems of equations, head, temperature and concentrations, by the use of a finite difference method, and by applying extensive parallel processing. The major modelling results related to the processes of importance for site characterization as hydraulic

  19. Summary of computational support and general documentation for computer code (GENTREE) used in Office of Nuclear Waste Isolation Pilot Salt Site Selection Project

    International Nuclear Information System (INIS)

    Beatty, J.A.; Younker, J.L.; Rousseau, W.F.; Elayat, H.A.

    1983-01-01

    A Decision Tree Computer Model was adapted for the purposes of a Pilot Salt Site Selection Project conducted by the Office of Nuclear Waste Isolation (ONWI). A deterministic computer model was developed to structure the site selection problem with submodels reflecting the five major outcome categories (Cost, Safety, Delay, Environment, Community Impact) to be evaluated in the decision process. Time-saving modifications were made in the tree code as part of the effort. In addition, format changes allowed retention of information items which are valuable in directing future research and in isolation of key variabilities in the Site Selection Decision Model. The deterministic code was linked to the modified tree code and the entire program was transferred to the ONWI-VAX computer for future use by the ONWI project

  20. Accelerator Physics Code Web Repository

    CERN Document Server

    Zimmermann, Frank; Bellodi, G; Benedetto, E; Dorda, U; Giovannozzi, Massimo; Papaphilippou, Y; Pieloni, T; Ruggiero, F; Rumolo, G; Schmidt, F; Todesco, E; Zotter, Bruno W; Payet, J; Bartolini, R; Farvacque, L; Sen, T; Chin, Y H; Ohmi, K; Oide, K; Furman, M; Qiang, J; Sabbi, G L; Seidl, P A; Vay, J L; Friedman, A; Grote, D P; Cousineau, S M; Danilov, V; Holmes, J A; Shishlo, A; Kim, E S; Cai, Y; Pivi, M; Kaltchev, D I; Abell, D T; Katsouleas, Thomas C; Boine-Frankenheim, O; Franchetti, G; Hofmann, I; Machida, S; Wei, J

    2006-01-01

    In the framework of the CARE HHH European Network, we have developed a web-based dynamic acceleratorphysics code repository. We describe the design, structure and contents of this repository, illustrate its usage, and discuss our future plans, with emphasis on code benchmarking.